ML20082Q814
| ML20082Q814 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, McGuire  |
| Issue date: | 12/31/1994 |
| From: | Mcmeekin T DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9505010101 | |
| Download: ML20082Q814 (200) | |
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DukeIbwer Company , ,, T.C Matkrns
' McGuire Nuclear Generanon Department Vice President 12700Hagers FerryRoad(MG01kP) (704)8754800 Hunterscille NC2807885 (104)8754809 Fat DUKEPOWER April 18,1995 U. S. Nuclear Regulatory Commission 1 Attention: Docurnent Control Desk Washington, D.C. 20555
Subject:
McGuire Nuclear S:ation Docket Nos. 50-369 and 50-370 Annual Radiological Environmental Operating Report Please find attached the McGuire Nuclear Station Annual Radiological Environmental Operating Report for 1994 pursuant to McGuire Technical Specification 6.9.1.6.
Questions or problems with respect to this report should be directed to Kay Crane, at (704) 875-4306.
Very truly yours,
, fYKK e T. C. McMeekin, Vice President j McGuire Nuclear Station l 1
I cc: Mr. Victor Nerses, Project Manager Mr. Dayne Brown ,
Office of Nuclear Reactor Regulation Division of Radiation Protection l U. S. Nucleur Regulatory Commission P. O. Box 27687 Washington D. C. 20555 Raleigh, N. C. 27611-7687.
Mr. S. D. Ebneter, Regional Administrator ANI Library .
U. S. Nuclear Regulatory Commission Town Center, Suite 300S l
Region Il 29 South Main Street 101 Marietta Street, NW - Suite 2900 West Hartford, CT.
Atlanta, Georgia 30323 06107-2445
)
Mr. George Maxwell Senior Resident Inspector McGuire Nuclear Site
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U. S. Nuclear Regulatory Commission April 18,1995 Page 2 cc: W. F. Byrum J. S. Pope J. E. Snyder EC050-ELL D. E. Holden C. D. Martir.ec
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ANNUAL: RADIOLOGICAL; ENVIRONMENTAL OPERATING REPORT for i
DUKE POWER COMPANY McGuire Nuclear Station l Units 1 and 2 l i
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l January 1 - December 31 l l
1994 l l
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TABLE OF CONTENTS TITLE PAGE List of Figures . . . . . . . . . . iv List of Tables . . . . . . . . . . v ,
- 1. Executive Summary . . . . . . . . . 1-1
- 2. Introduction . . . . . . . . . 2-1 2.1 Site Description and Sample Locations . . . . 2-1 2.2 Scope and Requirements of Environmental Monitoring Program . . . . . . . . . . 2-2 2.3 Statistical and Calculational Methodology . . . . 2-10 2.3.1 Estimation of the Mean Value . . . . 2-10 2.3.2 Lower Level of Detection and Minimum Detectable Activity . . . . . . . . 2-10 2.3.3 Trend Identification . . . . . 2-11 2.3.4 Test Statistic . . . . . . . 2-14
- 3. Radiological Environmental Monitoring Program - Discussion, Interpretation, and Trending of Results . . . . . 3-1 3.1 Airborne Radiolodines and Particulates . . . . 3-2 3.1.1 Radiolodines . . . . . . 3-2 3.1.L Particulates . . . . . . . 3-5 3.2 Drinking Water . . . . . . . . . 3-8
- 3. ',. Surface Water . . . . . . . . . 3-13 3.4 Milk . . . . . . . . . . . 3-18 3.5 Broadleaf Vegetation . . . . . . . . 3-21 3.6 Shoreline Sediment . . . . . . . . 3-24 3.7 Fish. . . . . . . . . . . 3-27 ,
3.8 Direct Gamma Radiation . . . . . . . 3-32 l 3.9 Food Product . . . . . . . . . 3-35 3.10 Land Use Census . . . . . . . . 3-38 I
TABLE OF CONTENTS (Continued)
TITLE PAGE
- 4. Evaluation of Dose from Environmental Measurements Versus Estimated Dose from Releases . . . . . . . 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 4.4 Pathway Dose Calculations . . . . . 4-4
- 5. Quality Assurance . . . . . . . . . 5-1 5.1 Duke Power Company's Environmental Laboratories . 5-1 5.2 Contractor Laboratory . . . . . . 5-4
- 6. References . . . . . . . . . . 6-1 Appendix A: Environmental Sample and Analysis Procedures - Summary A-2 I. Change of Sampling Procedures . . . . . A-2 II. Change of Analysis Procedures . . . . . A-2 III. Sampling and Analysis Procedures . . . . . A-2 A.1 Airborne Radioiodines and Particulates . . . A-2 A.2 Drinking Water . . . . . . . . A-3 A.3 Surface Water . . . . . . . . A-3 A.4 Milk . . . . . . . . . . A-3 A.5 Broadleaf Vegetation . . . . . . A-4 A.6 Shoreline Sediment . . . . . . . A-4 A.7 Fish . . . . . . . . . . A-4 l A.8 Direct Gamma Radiation . . . . . . A-4 A.9 Food Products . . . . . . . . A-5 A.10 Land Use Census . . . . . . . A-5 IV. Sampling and Analysis Improvements . . . . A-6 i
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TABLE OF CONTENTS (Continued)
TITLE PAGE Appendix B: Radiological Environmental Monitoring Program -
Summary of Results . . . . . . . B-1 B.1 Radiolodines . . . . . . . . . B-2 B.2 Particulates . . . . . . . . . B-3 B .3 Drinking Water . . . . . . . . . B -4 B .4 Surface Water . . . . . . . . . B-6 B.5 Milk . . . . . . . . . . . B-8 B.6 Broadleaf Vegetation . . . . . . . B-9 B.7 Shoreline Sediment . . . . . . . . B-10 B.8 Fish . . . . . . . . . . . B-11 B.9 Direct Gamma Radiation . . . . . . . B-12 B.10 Food Products . . . . . . . . . B-13 Appendix C: Sampling Deviations and Unavailable Analyses . . C-1 Appendix D: Analytical Deviations - Lower Limits of Detection . D-1 Appendix E: Radiological Environmental Monitoring Program Results E-1 l
111
LIST OF FIGURES FIGURE TIT LE PAGE 1 Sampling Locations Map (2500 ft. radius) . . . . 2-5 2 Sampling Locations Map (ten-mile radius) . . . . 2-6 3 Concentration of Radionuclides in Drinking Water . . 3-8 4 Concentration of Radionuclides in Shoreline Sediment . 3-24 5 Concentration of Radionuclides in Fish . . . . 3-31 6 TLD Exposure from Direction Radiation . . . . 3-33 7 Land Use Census Map . . . . . . . 3-41 1
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LIST OF TABLES FIGURE TITLE PAGE 2.1-A McGuire Radiological Monitoring Program Sampling Locations . . . . . . . . . . 2-3 2.1-B McGuire Radiological Monitoring Program TLD Locations . 2-4 2.2-A Maximum Values for the Lower Limits of Detection . . 2-7
- 2. 2-B Reporting Levels for Radioactivity Concentration in Environmental Samples . . . . . . . 2-8
- 2. 2-C McGuire Radiological Monitoring Program Analyses . . 2-9 3.1.1 - A Concentration of Radionuclides in Airborne Radioiodines . 3-3 3.1.1 -B Percentages of Reporting Levels for Radioiodines . . 3-4 3.1. 2- A Concentration of Radionuclides in Airborne Particulates . 3-6 3 .1. 2-B Percentages of Reporting Levels for Particulates . . 3-7 3.2-A Concentration of Radionuclides in Drinking Water . . 3-9 3.2-B Percentages of Reporting Levels for Drinking Water . . 3-12 3.3- A Concentration of Radionuclides in Surface Water . . 3-14 3.3-B Percentages of Reporting Levels for Surface Water . . 3-17 3.4-A Concentration of Radionuclides in Milk . . . . 3-19 3.4-B Percentages of Reporting Levels for Milk . . . . 3-20 3.5-A Concentration of Radionuclides in Broadleaf Vegetation . 3-22 3.5-B Percentage of Reporting Levels for Broadleaf Vegetation . 3-23 3.6-A Concentration of Radionuclides in Shoreline Sediment . 3-25
- 3. 6-B Percentages of Reporting Levels for Shoreline Sediment . 3-26 3.7-A Concentration of Radior.uclides in Fish . . . . 3-28 3.7-B Percentages of Reporting Levels for Fish . . . . 3-30 3.8-A TLD Exposure from Direct Radiation . . . . . 3-32 3.8-B Comparison of Inner Ring / Outer Ring TLD Results . . 3-34 3.9-A Concentration of Radionuclides in Food Products . . 3-36 3.9-B Percentages of Reporting Levels for Food Products . . 3-37 3.10 Land Use Census Results . . . . . . . 3-39 4.1 1994 Environmental and Effluent Doses . . . . 4-2 5.1 U.S. E.P. A. Interlaboratory Comparison Program - 1994 Cross Check Results for the RE&S Lab. . . . . 5-5 5.2 North Carolina Department of Environmental Health and Natural Resources-Environmental Dosimeter Crosscheck-1994. 5-8 v
l 1.0 EXECUTIVE
SUMMARY
This Annual Radiological Environmental Operating Report describes the McGuire Nuclear Station Radiological Environmental Program and the results of the program for the calendar year 1994.
Included in the report are identification of sampling locations, descriptions of environmental sampling and analysis procedures, comparisons of present environmental radioactivity levels and preoperational environmental data, analysis of trends in the environmental radioactivity levels since the beginning of station operation, comparisons of doses calculated from environmental measurements and doses calculated from effluent data, a summary of the results of the 1994 program, discussion of the results, and discussion of the quality assurance activities associated with the program.
Deviations from program requirements are also included.
Sampling activities were conducted as prescribed by Selected Licensee Commitments. Required analyses were performed and detection capabilities met Selected Licensee Commitments Manual requirements. Supplemental samples also were taken in addition to the required sampling locations.
Concentrations observed in the environment in 1994 for station related radionuclides were within the ranges of concentrations observed in the past. All positive indications of radioactivity due to plant operations were less than the reporting levels specified by the Nuclear Regulatory Commission (NRC) and given in Selected Licensee Commitments. The environmental doses also were well below specified limits.
Statistical analysis of data indicates that there are no radionuclides demonstrating high to moderate increasing trends. All possible increasing trends showed moderate to no probability. It can be concluded that the contribution of McGuire to the radioactivity in the environment is slight.
1-1
2.0 INTRODUCTION
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l 2.1 SITE DESCRIPTION AND SAMPLE LOCATIONS McGuire Nuclear Station is located geographically near the center of the highly industrialized region of the Carolinas. The land is predominantly rural non-farm with a small amount of land 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 the 32,510 acre Lake Norman. Lake Norman is impounded by Duke Power Company's Cowans Ford Dam Ilydroelectric 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 Coal Station is located on the western shore of Lake Norman, approximately 16 miles upstream from the site (reference 6.2 and 6.3). The sites 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 1 and 2 illustrate these locations as compared to McGuire Nuclear Station.
2-1
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2.2 SCOPE AND REQUIREMENTS OF ENVIRONMENTAL MONITORING PROGRAM An environmental monitoring program has been in effect at McGuire Nuclear Station since 1977, four years prior to the Unit No.1 startup in 1981. The preoperational program provided 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 Selected Licensee Commitments Manual Section 16.11-13 with regard to sample media, sampling locations , sampling frequency, and analytical sensitivity requirements . Tables 2.2-A and 2.2-B show the maximum values for LLD and the reporting levels , respectively, from Selected Licensee Commitments. Table 2.2-C shows the analysis schedule for each medium and the type of analysis required. 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 provides surveillance of all appropriate critical exposure pathways to man and satisfies vitalinterests of the company, public, and state and federal agencies concerned with the environment.
2-2
TABLE 2.1-A McGuire Radiological Monitoring Program Sampling Locations Code:
W-Weekly BW-BlWeekly SM-Semimonthly M Monthly 0-Quarterly C-Control SA-Semlannually 1 and surface Drirddng Shorefine Fand Broadiesf Sampling Location Description m wm m %m rm a wm 120 Site Boundary (0.4 mi NNE) W M(b) 121 Site Boundary (0.5 mi NE) W 125 Site Boundary (0.4 mi SW) W M(b) 128 Discharge Canal Bridge (0.4 mi ENE) BW 129 Discharge Canal Er. trance to Lake Norman (0.6 mi ENE) SA S.".
130 Hwy 73 Bridge Downstream (0.6 mi SW) SA 131 Cowans Form Dam (0.7 mi W) BW 132 Charlotte Municipal Water Supply (11.2 mi SSE) BW 133 Cornelius (6.2 mi NE) W
'f" 134C East Lincoln Jr. High School (8.7 mi WNW) W M(b) 135C Plant Marshall intake Canal (12.0 mi N) BW 136C Mooresville Municipal Water Supply (12.5 mi NNE) BW 137C Pinnacle Access Area (12.0 mi N) SA SA 138 Henry Cook Dairy (2.75 mi ESE) SM 139 William Cook Dairy (2.6 mi E) SM 140 Kidd Dairy-Cows (2.8 mi SSE) SM 141C Lynch Dairy-Cows (14.8 mi WNW) SM 142 Davidson Municipal Water Supply (7.5 mi NE) BW 158 4-5 mile radius (5.0 mi NNE) M(b) 184 5 mile radius Gardens (2.5 mi ENE) M(a) 188 5 mile radius Gardens (2.8 mi N) - Special Interest M(a) 192 Peninsula Community (2.8 mi NNE) W 193 Site Boundary (0.3 mi N) M(b) 194 Lincoln County Water Supply (6.88 mi NNW) BW 195 Site Boundary (0.3 mi N) W (a) during harvest season (b) when available
Ttble 2.1-B MCGUIRE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS (TLD LOCATIONS)
SAMPLING LOCATION DESCRIPTION
- SAMPLING LOCATION DESCRIPTION
- 143 SITE BOUNDARY (0.3 MILES NW) 167 4-5 MILE RADIUS (4.9 MILES SW) 144 SITE BOUNDARY (0.4 MILES NNE) 168 4-5 MILE RADIUS - (4.7 MILES WSW) 145 SITE BOUNDARY (0.5 MILES NE) 169 4-5 MILE RADIUS (4.4 MlWS W) 146 SITE BOUNDARY (0.5 MILES ENE) 170 4-5 MILE RADIUS (4.5 MILES WNW; 147 SITE BOUNDARY (0.4 MILES E) 171 405 MILE RADIUS (4.5 MILES NW) 148 SITE BOUNDARY (0.5 MlWS ESE) 172 4-5 MILE RADIUS (5.2 MILES NNW) 149 SITE BOUNDARY (0.6 MILES SE) 173 SPECIAL INTEREST (8.5 MILES NNW) 151 SITE BOUNDARY (0.4 MILES S) 174 SPECIAL INTEREST (8.7 MILES WNW) 7 152 SITE BOUNDARY (0.5 MILES SSW) 175 CONTROL (12.7 MILES WNW) 153 SITE BOUNDARY (0.5 MlWS SW) 176 SPECIAL INTEREST (11.0 MILES SW) .
154 SITE BOUNDARY (0.5 MILES W) 177 SPECIAL INTEREST (8.6 MILES S) 156 SITE BOUNDARY (0.5 MILES WNW) 178 SPECIAL INTEREST (92 MILES SE) 189 SITE BOUNDARY (0.4 MILES SSE) 179 SPECIAL INTEREST (10.4 MILES ESE) 190 SITE BOUNDARY (0.5 MILES WSW) 180 SPECIAL INTEREST (11.5 MILES NNE) 157 4-5 MILE RADIUS (4.8 MILES N) 181 SPECIAL INTEREST (6.7 MILES NC 158 4-5 MILE RADIUS (4.4 MILES NNE) 182 SPECIAL INTEREST (6.0 MILES NE) 159 4-5 MILE RADIUS (5.0 MlWS NE) 183 SPECIAL INTEREST (5.5 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 (0.3 MILES N) 162 4-5 MILE RADIUS (4.6 MILES ESE) 191 SPECIAL INTEREST (2.8 MILES NNE) 163 4-5 MILE RADIUS (5.0 MILES SE) 196 SPECIAL INTEREST (1.0 MILES S) 164 4-5 MILE RADIUS (4.5 MILES SSE) 197 SPECIAL INTEREST (1.1 MILES S) 165 4-5 MILE RADIUS (5.0 MILES S) 198 SPECIAL INTEREST (1.4 MILES S) 166 4-5 MILE RADIUS (5.2 MILES SSW) 199 SPECIAL INTEREST (1.5 MILES S)
All TLD samples are collectM quarterly.
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g e TLD LOCATIONS MCGUIRE NUCLEAR STATION f A ALL OTHER SAMPLING LOCATIONS MON!TORING PROGRAM LOCATIONS Figure 2 Map of REMP Sampling Locations LOTTE WATER WORKS Pg. 2 - 6
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Tcble 2.2-A MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)
WATER AI" ^ '
FISH MILK BROAD LEAF SEDIMENT ANALYSIS G '
( Cl/I) ,a (pCilkg, wet) (pCl/l) pC g e (pCi/kg, dry)
Gross beta 4 N.A. N.A. N.A. N.A. N.A.
H-3 2000* N.A. N.A. N.A. N.A. N.A.
Mn-54 15 N.A. 130 N.A. N.A. N.A.
Fe-59 30 N.A. 260 N.A. N.A. N.A.
" Co-58,60 15 N.A. 130 N.A. N.A. N.A.
4 Zn-65 30 N.A. 260 N.A. N.A. N.A.
1 Zr-95 15 N.A. N.A. N.A. N.A. N.A.
Nb-95 15 N.A. N.A. N.A. N.A. N.A.
1-131 1 7 x 10-2 N.A. 1 60 N.A.
Cs-134 15 5 x 10-2 130 15 60 150 Cs-137 18 6 x 10 150 18 80 180 Ba-140 15 N.A. N.A. 15 N.A. N.A.
La-140 15 N.A. N.A. 15 N.A. N.A.
- If no drinking water pathway exists, a value of 3000 pCi/l may be used.
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Tcble 2.2-B REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS AIRBORN PARTICULATE BROAD LEAF-ANALYSIS OR GAS VEGETATION pCi ) (pCl/ma)
(C g wet) ( 17 )
(pCilkg, wet)
H-3 2 x 10* N.A. N.A. N.A. N.A.
3 4 Mn-54 1 x 10 N.A. 3 x 10 N.A. N.A.
2 4 Fe-59 4 x 10 N.A. 1 x 10 N.A. N.A.
3 4
? Co-58 1 x 10 N.A. 3 x 10 N.A. N.A.
oo 2 4 Co-60 3 x 10 N.A. 1 x 10 N.A. N.A.
2 #
Zn-65 3 x 10 N.A. 2 x 10 N.A. N.A.
2 Zr-Nb-95 4 x 10 N.A. N.A. N.A. N.A.
1-131 2 1 N.A. 3 1 x 10 2 3
Cs-134 30 10 1 x 10 60 1 x 10 8
Cs-137 50 20 2 x 10 70 2 x 10
- 2 2 Ba-La-140 2 x 10 N.A. N.A. 3 x 10 N.A.
- 4 For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 3 x 10 pCi/l may be used.
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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 Environmental Monitoring Program. The following equation was used to estimate the mean:
N Di 7_i=1 N
Where:
ic = estimate of the mean, i = individual sample, N = total number of samples with a net activity (or concentration) x i = 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 l included in the calculation of the mean.
2.3.2 LOWER LEVEL OF DETECTION, MINIMUM DETECTABLE ACTIVITY, AND CRITICAL LEVEL The Lower Level of Detection (LLD), Minimum Detectable Activity (MDA), !
and Critical Level (CL) are used throughout the Environmental Monitoring Program, both in the Selected Licensee Commitments.
LLD - The LLD, as defined in the Selected Licensee Commitments Manual '
is the smallest concentration of radioactive material in a sample that will yield a net count, above the system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. The LLD is an a priori lower limit of detection. The actual LLD is dependent upon the standard deviation of the background counting rate, the counting efficiency, the sample size (mass or volume), the radiochemical yield, and the radioactive decay of the sample between sample collection and counting. The " required" LLD's for each sample medium and selected radionuclides are given in the Selected l Licensee Commitments and are listed in Table 2.2-A.
2-10 l
l
MDA - The MDA may be thought of as an " actual" LLD for a particular l sample measurement remembering that the MDA is calculated using a sample background instead of a system background.
CL - The CL is defined as the net count rate which must be exceeded before a sample is considered to contain any measurable activity above the background.
2.3.3 TREND IDENTIFICATION One of the purposes of an environmental monitoring program is to determine if there is a buildup of radionuclides in the environment due to the operation of the nuclear station. This is traditionally done by looking at historical data (including preoperational data) and determining if a trend exists.
Trends, if they exist, may be either positive or negative. Since nuclear reactor operations do not normally remove radioactivity from the surrounding environment, a negative trend 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 hifluencing the concentration.
2-11
In some cases, visual inspection of tabular or graphical presentations of data may be sufficient to determine if a trend exists. In other cases, it may not be so obvious. Therefore, it is desirable to obtain a single numerical value from the data which will permit a meaningful interpretation of the relationship existing between the variations in the data. If it is assumed that a linear relationship exists between the time after startup of the reactor and the amount of radionuclides in a particular environmental medium, the least squares regression method may be used to define the linear relationship. To determine if the data actually correlate to the straight line assumption, the theoretical variance is compared to the actual variance.
The numerical value that summarizes this comparison is known as the correlation coefficient. This correlation coefficient, symbolized by "r", is a determination of how closely the data fit a straight line and may be calculated from the following equation:
NEXY-EXE Y r =
[(NEX2 _(3y)2)(y3y2_(3y)2)j i Where:
r = correlation coefficient for the data set of X and Y, X = the year or point in time, Y = the radionuclide concentration associated with X, N = number of observations.
The range of values as calculated by the correlation coefficient lies between positive on (+1) and negative on (-1). The absolute value of the correlation coefficient represents the probability of a trend. Zero (0) represents no indication of either a positive or negative trend. A positive (+) correlation coefficient indicates an increasing trend, and conversely, a negative (-)
correlation coefficient indicates a decreasing trend. The ranges of a correlation coefficient may be summarized as following:
1> lrl > 0.7 High to moderate probability of a trend.
0.7 >, lrl > 0.3 Moderate to poor probability of a trend.
- 0. 3 > lrl > 0 Poor to no probability of trend.
2-12
Identifying a trend by using the correlation coefficient is only useful for the time periods where the discharge from the nuclear plant is relatively stable and no other sources of radioactivity are present. Substantialincreases or decreases in the amount of a particular radionuclide's release from the nuclear plant will greatly affect the resulting environmental levels; therefore, a knowledge of the release of a radionuclide from the nuclear plant is necessary to completely interpret the trends, or lack of trends, determined from the environmental data. Other factors that may affect environmentallevels of radionuclides include prevailing weather conditions (periods of drought or heavier than normal precipitation), construction in or around either the nuclear plant or the sampling location, addition or deletion of other sources of radioactive materials (such as the Chernobyl accident), etc. . Some of these factors may be obvious while others are sometimes unknown to the plant personnel.
The recent change in the method of calculating the mean (using only net positive results) will also affect the apparent trends.
- Because of the above considerations, how trends are identified will depend 4
not only on the least squares regression method, but will include some judgement by plant personnel on the factors affecting environmental levels.
I 2-13
l l
l 2.3.4 TEST STATISTIC In some cases, we would not expect to observe a buildup of radionuclides in the environment, but instead would expect to see a measurable increase in levels over a short duration. This is the case for direct radiation measurements, where the radiation level is measured over a finite period and is dependent upon whether plant discharges were occurring at that time or not. In this case, the correlation coefficient is not a sufficient indicator of whether effluents are having an impact on the environment, since there is no bioaccumulation. Another test is needed to give us a meaningful interpretation of the data. If we assume that the naturally occurring radiation levels around the plant are normally distributed and that the effluents are not affecting the environment outside of this normal distribution, then we can compare the values of two sets of measurements taken at different times around the plant. One measurement can be taken when we are certain no effect is occurring and one when an effect map be occurring, to determine if they are statistically different from one another.
The stathtic that compares the means from two sets of measurements to determine if there is a statistically significant difference is called the test statistic, or t-statistic, and is calculated as follows:
X~X 1 2 sp /1/n, + 1/n2 Where:
[ = the mean value of the first set of measurements K = the mean value of the second set of measurements Sp = the average standard deviation of the two sets of measurements Where:
2 _
(8 - 1) S 1 + (n2 - I) 32 1
Sp -
n 1 + n2 - 2 n3 = the number of measurements in the first set n2
= the number of measurements in the second set 2-14
,. - . .. -. . ..- . - - - - - - - . ~_ =
The calculated value of the test statistic is then compared to expected values of the test statistic tabulated based on the number of measurements taken and the degree of confidence required for the results. For our purposes, the expected value of the test statistic will always be chosen to
- give a 95% confidence level that a positive result is truly positive with only a 5% probability that a positive result is truly negative. This confidence level is chosen since it is consistent with the standard confidence levels
. specified for similar measurements.
Due to the existence of naturally occurring differences in background radiation levels over . time (as a result of solar cycles and other meteorological phenomena) and systematic errors due to instrument variability, ratios of measurements can be used to calculate the t-statistic instead of individual measurements. By using ratios, biases associated with the measurement process are minimized and allow us to more accurately compare results from one year to the next. Specifically, in the case of TLD measurements, the inner. ring of TLD results is raticed with the outer ring of TLD measurements in a given year and the ratio for one year is compared to the ratio for another year.
As with other environmental samples, outside factors may affect the results observed and the resulting trends identified. Therefore, the significance of trends will be based in part on judgment of plant personnel familiar with the factors affecting environmentallevels, as well as the statistical results.
3 l
2-15
y l 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MONITORING PROGRAM - DISCUSSION, INTERPRETATION AND TRENDING OF RESULTS The radionuclides with Selected Licensee Commitments reporting levels in the environmental media samples that indicated detectable activity since the change of analysis techniques in 1988 have been historically trended over a sixteen-year period from 1979 - 1994. Analyses from 1977 - 1978 have been excluded since these results were much higher than the other preoperational years due to outside influence such as weapons testing.
Including these results would have produced correlation coefficients and averages that were not representative. The highest annual mean concentration of each Selected Licensee Commitments radionuclide from the indicator and control locations for each media type was used for the estimation of the mean value and correlation coefficient. The preoperational analyses from 1981 were combined with the operational analyses from the latter part of 1981 and averaged to give one cor; centration for each radionuclide for that year. However, when preoperational comparisons were necessary, only the preoperational report was used.
Sixteen annual means were used to determine trends and occasionally the average concentrations reported were negative. Negative values were obtained using reported activities that were less than the assumed ;
background. All negative values (concentrations) were replaced with a zero ;
to properly represent environmental conditions. Any zero concentrations )
used in tables or graphs represent activity measurements less than detectable levels. Figures 3 through 6 provide a graphical presentation of the annual mean concentrations for drinldng water, shoreline sediment, fish, and TLD data. Some of these figures show both indicators and i controls for significant radionuclides, while others show only indicators for I clarity purposes. These media were chosen for graphical representation for special interest purposes or because they consistently show detectable activity for a few radionuclides. In addition, the percentages of Selected Licensee Commitments reporting levels were calculated for each reportable radionuclide in each media type.
No Selected Licensee Commitments reporting levels were exceeded in 1994 due to plant effluents.
l Only the radionuclides with Selected Licensee Commitments reporting levels were historically trended and compared with the fourteen-year average and control levels. All other radionuclides demonstrated no detectable activity or decreasing trends. It is important to note that while historical trends are l helpful in determining radioactivity buildup, environmental radionuclide '
levels could be aff( cted without exhibiting increasing or decreasing trends .
3-1
3.1 AIRBORNE RADIOIODINES AND PARTICULATES 4
3.1.1 RADIOIODINES In 1994, 345 radiciodine samples were analyzed, 294 at seven indicator locations and 51 at the control location.
The I-131 concentration did not significantly differ from the average, preoperational data, or control location levels for the fifteen-year period.
The historical trend based on highest annual mean for indicator and control location for I-131, showed decreasing trends as illustrated in Table 3 .1.1 - A .
Table 3.1.1-B shows the percentages of environmental concentrations to the Selected Licensee Commitments reporting levels for the indicators at the locations with the highest annual trean for 1994.
3-2
Table 3.1.1-A Concentration of Radionuclides in Airborne Radiolodines Concentration (pCi/m3)
YEAR I-131 Indicator Control 1979
- 3.28E-3 1.04E-3 1980
- 2.01E-3 1.10E-3 1981
- 4.17E-3 6.27E-4 1982
- 1.42E-3 2.48E-3 1983
- 1.99E-3 2.01E-4 1984 3.17E-3 -1.15E-3 1985 3.15E-3 1.04E-3 1
1986 1.27E-2 6.10E-3 1987 1.07E-2 6.60E-3 1988 0.00E0 0.00E0 1989 2.18E-2 0.00E0 1990 0.00E0 0.00E0 1991 0.00E0 0.00E0 1992 0.00E0 0.00E0 1993 0.00E0 0.00E0 15 YEAR AVERAGE 4.29E-3 1.28E-3 1994 0.00E0 0.00E0 l
l CORRELATION COEFFICIENT - 0.077 - 0.021 l
- Radiciodines and Particulates analyzed together.
j NOTE: All negative values were replaced with "zero's" for calculational purposes.
1 3-3 i
' .i; b
(
1 Table 3.'!.1-B l Radionuclide Concentration Reporting Percentage ,
(pCi/m') Level (pCi/m') )
I-131 0.00E0 1.00E0 0.00%
?
e 5
4 4
.l e
s 4
l 3-4
3.1.2 PARTICULATES In 1994, 345 particulate samples were analyzed, 294 at the seven indicator locations and 51 at the control location.
Since no detectable activity was found, all radionuclide concentrations did not significantly differ from the fifteen-year average, preoperational data, and control location levels. The historical trends for the indicator and couttol locations with the highest annual mean for I-131, Cs-134, and Cs-137 continued to r now decreasing trends since the change of analysis reporting in 1988.
. Tr.ble 3.1.2-B shows the percentages of environmental concentrations to the S slected Licensee Commitments reporting levels for the indicator locations with ti e highest annual mean for 1994. No activity was detected and therefore no reporting levels were approached.
8 3-5
Table 3.1.2-A Concentration of Radionuclides in Airborne Particulates l l
Concentration (pCi/m3) j YEAR I-131 Cs-134 Cs-137 1
Indicator Control Indicator Control Indicator Control 1 1979
- 3.28E-3 1.04E-3 1.19E-3 -7.64E-4 4.40E-3 1.47E-3 1980
- 2.04E-3 1.10E-3 -5.89E-5 -2.45 E-4 6.70E-3 4.53E-3 1981
- 4.17E-3 6.27E-4 1.15E-3 2.99E-4 6.16E-3 5.32E-3 1982
- 1.42E-3 2.48E-3 4.85E-4 2.27E-3 3.82E-3 2.29E-3 1983
- 1.99E-3 2.01E-4 6.80E-4 4.98E-4 2.93E-3 3.21E-3 1984 2.72E-3 2.08E-3 9.90E-4 8.83E-4 1.74E-3 8.29E-4 1985 1.57E-3 2.05E-3 1.38E-3 1.05E-3 1.86E-3 1.32E-3 1986 4.42E-3 3.36E-3 2.76E-3 8.90E-4 4.98E-3 3.03E-3 1987 9.73E-3 0.00E0 7.25E-3 0.00E0 1.07E-2 7.91E-3 1988 0.00E0 9.15E-3 0.00E0 0.00E0 0.00E0 0.00E0 1989 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 l'?90 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1991 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1992 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1993 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 15 YEAR AVERAGE 2.09E-3 1.47E-3 1.05E-3 3.93E-4 2.85E-3 1.99E-3 1993 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 CORRELATION COEFFICIENT -0.44 -0.16 -0.17 -0.39 -0.64 -0.55
- Radiciodines and Particulates analyzed together.
NOTE: All negative values were replaced with "zero's" for calculational purposes.
3-6
Table 3.1.2-B Radionuclide Concentration Reporting Percentage (pCi/m3 ) Level (pCi/m3 )
1-131 0.00E0 1.00E0 0.00 %
Cs-134 0.00E0 1.00El 0.00 %
Cs-137 0.00E0 2.00El 0.00 %
3-7
3.2 DRINKING WATER In 1994, 37 drinking water samples were analyzed for I-131/LL, 26 at the two indicator locations and 13 at the control location. Tritium (H-3) analyses were performed on 16 composite samples, twelve at indicator locations and four at the control location. Sixty-three samples were analyzed for other gamma emitting radionuclides, 50 at indicator locations, and 13 at the controllocation. Analyses showed zero ranges for all indicator locations, which means no detectable activity was measured. All radionuclides did not significantly differ from the fifteen-year average or from preoperational data.
A moderate to poor probability of an increasinr, trend was seen for H-3 at the indicator locations. All other radionuclide indicators and controls exhibited decreasing or no trends. Table 3.2-A and Figure 3 illustrate these trends.
FIGURE 3 pci/L m?Im w nITIm a mnatruo nTma 2500 7 1M OF BSPOk7 Dita LavEL 2000 1500
/ , ,
l
.00 f /\ ;
b- 7 '
I i 1*ts 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 YMZ 3-8
Table 3.2-A Concentration of Radionuclides in Drinkina Water (Page 1 of 3)
Concentration (pCi/ liter)
Year H-3 Mn-54 Fe-59 Co-58 Indicator Control Indicator Control Indicator Control Indicator Control 1979 1.65E2 1.50E2 1.46E0 4.27E-1 1.29E0 5.%E-1 1.14E0 2.01E0 1980 1.63E2 2.05E2 6.20E-1 -4.29E-1 1.77E0 5.20E-1 5.62E-1 -3.72E-1 .
l 1981 1.88E2 1.78E2 1.40E-1 -1.%E0 4.58E0 1.13E0 9.36E-1 4.33E-1 1982 2.43E2 1.45E2 8.63E-1 7.05 E-2 3.50E0 -7.39E-1 7.71E-1 6.26E-1 1983 2.65E2 1.45E2 4.18E-1 -3.06E-2 1.44E0 7.93E-1 6.78E-1 -2.60E-1 1984 5.77E2 2.45E2 1.05E0 1.42E-1 2.15E0 1.60E-1 8.89E-1 -2.57E-1 1985 5.93E2 4.00E2 7.14E-2 9.49E-2 7.73E-1 -4.73E-1 3.39E-1 6.16E-1 1986 1.14E3 4.37E2 9.76E-1 -4.59E-2 2.16E0 -4.92E-1 3.82E-1 1.04E-2 1987 1.35E3 7.75E2 4.80E0 0.00E0 6.60E0 0.00E0 4.20E0 0.00E0 1988 9.92E2 7.1 IE2 0.00E0 2.50E0 0.00E0 0.00E0 0.00E0 0.00E0 1989 5.62E2 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1990 7.32E2 6.1 IE2 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1991 5.22E2 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1992 6.73E2 0.NE0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1993 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 15 Yr.
Avg. 6.3'E.2 2.67E2 6.93E-1 2.16E-1 1.62E0 2.13E-1 6.60E-1 2.46E-1 1994 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 Corr.
Coef 0.42 -0.13 -0.26 -0.01 -0.52 -0.68 -0.32 -0.57 NOTEI All negative values were replaced with "zero's" for calculational purposes.
3-9
Table 3.2-A Concentration of Radionuclides in Drinkina Water (Page 2 of 3)
Concentration (pCi/ liter)
Year Co-60 Zn-65 Nb-95 Zr-95 Indicator Control Indicator Control Indicator Control Indicator Control 1979 2.30E0 2.01E0 1.10E-1 2.56E-1 2.52E0* -3.74E-2* 2.52E0* -3.74E-2
- 1980 2.26E0 1.80E0 1.18E0 -7.44E-1 1.71E0* 6.52E-l
- 1.71E0* 6.52E-l
- 1981 1.43E0 1.34E-1 1.76E0 1.29E0 2.30E0 1.47E0 2.42E0 1.81E0 1982 8.25E-1 5.98E-l 1.16E-1 9.43E-1 1.35E0 1.42E0 2.49E0 2.02E0 1983 1.26E0 1.22E0 -6.05E-2 -2.48 E0 -3.99E-1 2.32E-1 1.82E0 1.05E0 1984 7.22E-1 -2.81 E-1 5.03E-1 1.29E-1 7.47E-1 1.91E-1 2.70E0 -1.06E0 1985 8.44E-1 7.09E-1 -3.43E-1 -7.20E-2 9.32E-1 4.63E-1 1.09E0 5.70E-1 1986 2.33E-1 -3.46E-1 2.44E-1 7.25E-2 9.87E-1 1.06E0 5.17E-1 -4.43E-1 1987 0.00E0 0.00E0 0.00E0 0.00E0 5.30E0 0.00E0 0.00E0 7.10E0 1988 0.00E0 4.50E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1989 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1990 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1991 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1992 0.00E0 0.00E0 0.00F0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1993 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 15 Yr.
Avg. 6.58E-1 7.31 E-1 2.61E-1 1.79E-1 1.06E0 3.66E-1 1.02E0 8.74E-1 1994 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 Corr.
Coef -0.88 -0.33 -0.55 -0.50 -0.48 -0.57 -0.87 -0.19 0 Nb-95 and Zr-95 analyzed as Nb/Zr-95 NOTE: All negative values were replaced with "zero's" for calculational purposes.
3-10
1 Tpble 3.2-A Concentration of Radionuclides in Drinking Water (Page 3 of 3)
Concentration (pCi/ liter)
Year I-f % Cs-134 Cs-137 Ba/La-140 Indicator Control Indicator Control Indicator Control Indicator Control 1979 4.95E0 6.97E-1 -1.09E0 -4.12E-1 2.55E0 2.86E-1 1.62E0 1.54E-2 1980 7.39E-1 8.96E-1 -3.54E-1 -6.24E-l 9.53E-1 1.73E0 8.53E-2 2.06E-1 1981 1.83E0 1.0$E0 1.46E0 4.77E-1 1.13E0 1.16E0 1.09E0 -8.20E-1 1982 2.45E0 7.79E-2 5.38E-1 2.64E0 1.08E0 3.50E0 8.28E-1 -6.73E-1 1983 4.34E-! -5.57E-1 6.29E-1 1.54E0 8.91E-1 5.31E-1 4.26E-1 1.13E0 1984 9.46E-2* -8.65 E-2
- 6.16E-1 -2.01E- 1 2.80E0 6.07E-1 1.16E0 -7.66E-1 1985 -1.84 E-l * -1.27E-l
- 1.00E0 5.55E-1 1.43E0 -1.79E-1 5.15E-1 7.75E-1 1986 3.07E-2* 5.63E-2* 8.18E-1 -1.45E-2 2.58E-1 2.83E-1 7.53E-1 -1.11E-1 1987 4.10E-1 0.00E0 0.00E0 5.90E0 4.20E0 2.80E0 0.00E0 4.00E0 1988 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1989 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1990 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1991 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1992 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1993 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 15 Yr.
Avg. 7.02E-1 1.85E-1 3.37E-1 7.41 E-1 1.02E0 7.26E-1 4.32E-1 4.08E-1 1994 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 Corr.
Coef -0.67 -0.67 -0.48 -0.16 -0.52 -0.48 -0.73 -0.06 0 I-131/LL analysis data used.
NOTE: All negative values were replaced with "zero's" for calculational purposes.
3-11
Table 3.2-B shows the percentages of environmental concentrations to the Selected Licensee Commitments reporting levels for the indicators at the locations with the highest annual mean for 1994.
Table 3.2-B i
Radionuclide Concentration (pCi/1) Reporting Level (pCi/1) Percentage j H-3 0.00E0 2.00E4 0.00 % l Mn-54 0.00E0 1.00E3 0.00 %
Fe-59 0.00E0 4.00E2 0.00 % I Co-58 0.00E0 1.00E3 0.00 %
Co-60 0.00E0 3.00E2 0.00%
Zn-65 0.00E0 3.00E2 0.00%
Nb-95 0.00E0 4.00E2 0.00%
Zr-95 0.00E0 4.00E2 0.00 %
I-131/LL 0.00E0 2.00E0 0.00 %
Cs-134 0.00E0 3.00El 0.00%
Cs-137 0.00E0 5.00El 0.00 %
Ba/La-140 0.00E0 2.00E2 0.00 %
1 3-12
l 1
3.3 SURFACE WATER In 1994, 39 surface water samples were analyzed for I-131/LL, 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. Thirty-nine samples were analyzed for other radionuclides, 26 at indicator locations and 13 at the control location.
All Selected Licensee Commitments radionuclides showed zero ranges indicating that no detectable activity was measured. All radionuclides, except H-3, were not significantly different from preoperational data and the controllocation levels. All radionuclides except H-3 control did not differ significantly from the fifteen-year average.
There is a poo; to no probability of an increasing trend for H-3 indicator. All other radionuclide indicators and controls exhibited decreasing trends. Table 3.3-A illustrates these trends.
l 3-13 i
1 Table 3.3-A Concentration of Radionuclides in Surface Water j (Page 1 of 3)
Concentration (pCi/ liter)
Year H-3 Mn-54 Fe-59 Co-58 1
Indicator Control Indicator Control Indicator Control Indicator Control 1979 1.85E2 1.66E2 8.95E-1 6.35E-1 1.69E0 2.55E0 1.47E0 1.90E-1 1980 2.13E2 1.93E2 2.17E0 5.81E-1 5.21E-1 9.48E-1 1.17E0 -5.16E-2 1981 1.75E2 1.70E2 4.95E-2 -1.10E0 1.79E0 3.40E0 9.74E-1 -1.35E-1 1982 3.30E2 1.23E2 1.02E0 -1.22E-1 1.97E0 -3.99E-2 1.63E-1 5.10E-1 1983 5.75E2 3.67E2 -2.30E-1 9.74E-1 1.76E0 -7.08E-1 6.14E-1 5.08E-2 1984 4.10E2 2.65E2 -7.56E-2 -4.19E-1 -4.88E-1 9.15E-1 3.30E-1 4.24E-1 1985 7.33E2
- 1.01E0 -4.75E-1 3.91E-1 1.04E0 7.61E-1 1.65E-1 1986 2.33E3 6.13E2 5.13E-1 3.97E-1 -1.67E-1 4.36E-2 -2.95 E-3 3.31E-1 1987 9.20E2 7.70E2 0.00E0 0.00E0 1.10El 0.00E0 0,00E0 0.00E0 1988 9.40E2 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1989 8.22E2 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1990 6.77E2 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1991 7.53E2 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1992 8.13E2 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1993 6.85E2 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 15 Yr.
Avg. 7.04E2 1.91E2 4.04E-1 1.85E-1 1.37E0 6.35E-1 3.92E-1 1.19E-1 1994 0.00E0 0.00E0 0.00E0 0.00E0 0.C'E0 0.00E0 0.00E0 0.00E0 Corr.
Coef 0.21 -0.35 -0.62 -0.55 -0.19 -0.65 -0.81 -0.44
- No sample analyzed.
NOTE: All negative values were replaced with "zero's" for calculational purposes.
3-14
Table 3.3-A Concentration of Radionuclides in Surface Water (Page 2 of 3)
Concentration (pCi/ liter)
Year Co.-60 Zn-65 Nb-95 Zr-95 Indicator Control Indicator Control Indicator Control Indicator Control 1979 2.45E0 2.60E0 8.62E-1 -5.33E-1 -2.53 E-l
- 5.77E-l* -2.53 E-l
- 5.77E-l*
1980 1.36E0 1.12E0 7.70E-1 1.80E0 1.00E0* -2.54E-l
- 1.00E0* -2.54E-l
- 1981 2.47E-1 1.54EO -6.29E-1 6.93E-1 -2.92E-1 3.50E-2 1.98E0 9.04E-1 1982 1.14E0 6.02E-1 6.28E-1 -3.93E-1 2.16E0 8.89E-1 2.23E0 8.92E-1 1983 1.66E0 2.01E0 -1.20E0 4.71E-1 3.22E-1 1.15E0 3.27E-2 1.41E0 1984 1.47E0 3.38E-1 -9.79E-2 5.91E-1 8.59E-1 2.66E-2 1.67E0 -1.45E-1 1985 3.86E-1 9.97E-1 1.22E0 -2.43E-2 6.10E-1 4.17E-1 1.16E0 1.74E0 1986 -1.36E-1 2.24E-2 -1.24E0 -1.65E0 1.05E0 1.19E0 1.33E0 -3.91E-1 1987 5.20E0 0.00E0 0.00E0 0.00E0 4.50E0 0.00E0 1.20E1 0.00E0 )
1988 0.00E0 0.00E0 2.70E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1989 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1990 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1991 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 .
l 0.00E0 0.00E0 0.00E0 l 1992 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1993 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 15 Yr.
Avg. 9.28E-1 6.15E-1 4.12E-1 2.37E-1 7.00E-1 2.86E-1 1.43E0 3.68E-1 l l
1994 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 Corr.
Coef -0.41 -0.80 -0.23 -0.54 -0.22 --0.44 -0.13 -0.50
- Nb-95 and Zr-95 analyzed as Nb/Zr-95 NOTE: All negative values were replaced with "zero's" for calculational purposes.
l 3-15
Table 3.3-A Concentration of Radionuclides in Surface Water (Page 3 of 3)
Concentration (pCi/ liter)
Year I-131 Cs-134 Cs-137 Ba/La-140 Irxlicator Control Indicator Control Indicator Control Indicator Cutrol 1979 2.66E0 -8.27E-1 -3.62E-1 -1.00E-1 2.63E0 -2.21E-1 2.26E-1 -4.25E-1 1980 1.13E0 1.20E0 -2.60E-1 -9.98E-1 1.97E0 1.27E0 9.70E-1 -3.20E-1 1981 2.32E0 -6.85E-1 2.10E-2 1.88E-1 1.05E0 2.45E0 6.98E-1 8.66E-1 1982 -3. l lE-1 -9.19E-1 -5.68E-1 8.34E-1 1.23E-1 1.65E0 4.30E-1 -4.11E-1 1983 1.89E0 2.88E0 7.87E-1 2.50E-1 8.43E-1 2.39E-1 1.38E0 2.89E-1 1984 3.02E-2* 1.58E-l
- 7.36E-1 1.70E0 9.4E-1 3.30E-2 -2.84E-1 -6.81E-3 1985 -8.69 E-2* -7.90E-2
- 1.72E0 1.25E0 1.3E0 3.26E-1 3.79E-1 4.53E-1 1986 8.94 E-2* 2.13 E-2* 7.54E-1 1.13E-1 5.61E-1 1.97E-1 8.72E-1 8.29E-1 1987 0.00E0 0.00E0 4.40E0 0.00E0 4.70E0 0.00E0 0.00E0 0.00E0 1988 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1989 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1990 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1991 0.00EO 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1992 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1993 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 15 Yr.
Avg. 5.41 E-1 2.84E-1 5.61E-l 2.89E-1 9.37E-1 4.41E-1 3.30E-1 1.62E-1 1994 0.00E0 0.00EO 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 Corr. l Coef -0.70 -0.34 -0.07 -0.32 -0.48 -0.58 -0.62 -0.32
- I-131/LL analysis data used.
NOTE: All negative values were replaced with "zero's" for calculational purposes.
3-16
1 Toble 3.3-B shows the percentages of environmental concentrations to the Selected Licensee Commitments reporting levels for the indicators a*. the location with the highest annual mean for 1994. .
1 1
Table 3.3-B Radionuclide Concentration (pCi/1) Reporting Level (pCi/1) Percentage H-3 0.00E0 2.00E4 0.00 %
Mn-54 0.00E0 1.00E3 0.00 %
Fe-59 0.00E0 4.00E2 0.00 %
Co-58 0.00E0 1.00E3 0.00 %
Co-60 0.00E0 3.00E2 0.00 %
Zn-65 0.00E0 3.00E2 0.00 %
Nb-95 0.00E0 4.00E2 0.00 %
Zr-95 0.00E0 4.00E2 0.00 %
I-131/LL 0.00E0 2.00E0 0.00 %
Cs-134 0.00E0 3.00E1 0.00 %
Cs-137 0.00E0 5.00El 0.00 %
Ba/La-140 0.00E0 2.00E2 0.00 %
1
\
3-17
3.4 MILK In 1994, 104 milk samples were analyzed, 78 at the three indicator locations and 26 at the controllocation.
All Selected Licensee Commitments radionuclides showed a zero range indicating no detectable activity was measured in 1994. The I-131/LL, Cs-134, Cs-137, and Ba/La-140 concentrations did not significantly differ from the fifteen-year average, preoperational data, and control levels.
All radionuclide indicators and controls exhibited decreasing or no
.robability of a trend. These trends are illustrated in Table 3.4-A.
Table 3.4-B shows the percentages of environmental concentrations to the Selected Licensee Commitments reporting levels for the indicators at the location with the highest annual mean for 1994.
3-18
Table 3.4-A Concentration of Radionuclides in Milk Concentration (pCi/ liter)
Year 1-131 Cs-134 Cs-137 Ba/La-140 Indicator Control Indicator Control Indicator Control Indicator Control 1979 6.87E-3 -6.13E-2 -7.05E-1 7.63E-l 2.48El 6.04E0 0.00E0 -6.15E-1 1980 1.ME0 3.22E-2 -7.94 E-2 -6.12E-1 1.72El 4.13E0 1.29E0 1.33E-1 1981 -3.70E-3 -6.54E-2 1.37E0 -2.88E-1 2.04El 4.15E0 3.77E-1 -7.95E-2 1982 -3.22E-2 -8.49E-2 9.44E-1 -4.38E-2 1.21El 5.20E0 2.31E-1 -4.l lE-1 1983 1.23E-2 -4.57E-2 1.26E0 1.55E0 2.02El 2.82E0 4.44E-1 2.35E-1 1984 1.78E-2 -4.30E-2 1.08E0 1.80E0 1.48El 2.56E0 4.79E-1 1.43E-1 1985 2.00E-2 -5.80E-2 9.32E-1 1.99E-1 1.42El 2.72E0 5.78E-1 5.97E-1 1986 8.30E-1 7.55E-1 2.36E0 9.38E-1 3.74E0 3.45E0 2.95 E-1 1.08E-1 1987 4.80E-1 0.00E0 5.10E0 3.60E0 5.20E0 8.60E0 0.00E0 4.40E0 1988 0.00E0 0.00E0 0.00E0 0.00E0 3.40E0 2.90E0 0.00E0 0.00E0 1989 0.00E0 0.00E0 0.00E0 0.00E0 6.00E0 5.60E0 0.00E0 0.00E0 1990 0.00E0 0.00E0 0.00E0 0.00E0 5.30E0 2.60E0 0.00E0 0.00E0 1991 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1992 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 l
1993 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1 1
15 Yr.
Avg. 1.62E-1 5.25E-2 8.70E-1 5.90E-1 9.82E0 3.38E0 2.46E-1 3.74E-1 1994 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 Corr.
Coef -0.33 -0.04 -0.20 -0.20 -0.92 -0.62 -0.61 0.01 1
NOTE: All negative values were replaced with "zero's" for calculational purposes.
3-19
Table 3.4-B Radionuclide Concentration Reporting Percentage (pCill) Level (pCi/l) 1-131/LL 0.00E0 3.00E0 0.00 %
Cs-134 0.00E0 6.00E1 0.00 %
Cs-137 0.00E0 7.00E1 0.00 %
Ba/La-140 0.00E0 3.00E2 0.00 %
1 l
l 3-20
)
3.5 BROADLEAF VEGETATION In 1994, 42 broadleaf vegetation samples were analyed, 31 at the three indicator locations and 11 at the control location. The 1986 data is higher than the other years due to the Chernobyl accident.
All Selected Licensee Commitments radionuclides showed zero ranges indicating that no detectable activity was measured.
The correlation coefficients for the location with the highest annual mean indicated a poor to no probability of an increasing trend for Cs-137 indicator. Since there were anomalous results in 1984 for Cs-134 and Cs-137, new concentrations for these radionuclides were calculated using the location with the highest annual mean excluding these anomalies. All other radionuclide indicators and controls exhibited decreasing trends.
These trends are illustrated in Table 3.5-A.
Table 3.5-B shows the percentage of environmental concentrations to the Selected Licensee Commitments reporting levels for the indicators at the locations with the highest annual mean for 1994.
l 3-21
1 Table 3.5-A Concentration of Radionuclides in Broadleaf Veaetation Concentration (pCi/kg-wet)
YEAR l-131 Cs-134 Cs-137 Indicator Control Indicator Control Indicator Control 1979 -5.82E0 7.30E-1 -1.00El -1.%El 2.19El 1.93El 1980 1.91El 6.15E0 -2.59E0 -1.25El 2.30El 1.92El 1981 -1.87E0 3.16E0 1.24El 5.%E0 3.04El 2.02El 1982 1.41El 6.59E0 1.50El -6.31E-1 2.46El 1.22El 1983 1.13El 7.19E0 4.13E0 1.24E0 9.07E0 7.85E0 1984 6.06E0 5.99E0 8.46E0 2.80E0 1.02El 1.05El 1985 5.67E0 7.98E-1 9.77E0 1.66El 8.05E0 2.37E-2 1986 2.85El 1.76El 2.53El 2.07El 4.03El 1.27El 1987 0.00E0 1.10El 1.70El 2.50El 2.20El 1.70El 1988 0.00E0 0.00E0 0.00E0 0.00E0 3.90E1 3.40El 1989 0.00E0 0.00E0 0.00E0 0.00E0 9.60El 0.00E0 1990 0.00E0 0.00E0 0.00E0 0.00E0 4.00El 0.00E0 1991 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1992 0.00E0 0.00E0 0.00E0 0.00E0 3.30E1 0.00E0 1993 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 15 YEAR AVERAGE 5.65E0 3.95E0 6.14E0 4.82E0 3.08El 1.02El 1994 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 CORRELATION COEFFICIENT -0.43 -0.38 -0.33 -0.01 0.18 -0.59 NOTE: All negative values were replaced with "zero's" for calculational purposes.
3-22
i l
Table _3.5-B Radionuclide Concentration Reporting Percentage (pCi/kg) Level (pCi/kg)
I-131 0.00E0 1.00E2 0.00%
Cs-134 0.00E0 1.00E3 0.00%
Cs-137 0.00E0 2.00E3 0.00%
i 1
l 1
l 1
I I
l 3-23
1 I
i' 3.6 SHORELINE SEDIMENT 1
In 1994, six shoreline sediment samples were analyzed, four from two indicator locations and two at the controllocation. '
The correlation coefficient for the location with the highest annual mean indicated a moderate to poor probability of an increasing trend for Cs-137 indicator. Ilowever, the Cs-137 concentration only corresponds to a small percentage of the Selected Licensee Commitments reporting level as shown in Table 3.6-B. All other indicators and controls exhibited decreasing trends. These trends are illustrated in Table 3.6-A and Figure 4.
FIGURE 4 gg CONCENTRATION OF RADIONUCUDES IN SHOREUNE SEDIMENT 300 2M m
150 L
100 50 - l
' ! ! i 0 2 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 ,
Year l l =e-Cs 137 indkator -*-Cs-137 Control j l
l
)
3-24
Table 3.6-A Concentration of Radionuclides in Shoreline Sediment Concentration (pCi/kg-dry)
Year Cs-134 Cs-137 Indicator Control Indicator Control 1979 0.00E0 1.20El 1.20El -1.77El 1980 -3.53E0 -1.85El 1.44El 6.88El 1981 3.97El 6.08E0 3.36El 1.65E0 1982 7.67El 4.61El 4.40El 2.13El 1983 7.65El 2.78El 8.02El 3.28E1 1984 3.34El 1.32El 9.13El 3.65El 1985 2.02El 1.03El 1.61E2 1.70El 1986 6.35El 3.67El 1.53E2 1.95El 1987 4.20El 2.40El 1.65E2 0.00E0 1988 9.10E0 0.00E0 2.66E2 1.70El 1989 5.30El 0.00E0 6.50El 1.40El 1990 0.00E0 0.00E0 6.10El 2.10El 1991 0.00E0 0.00E0 0.00E0 0.00E0 1992 9.20E0 0.00E0 8.60El 0.00E0 1993 0.00E0 0.00E0 9.30El 0.00E0 15 Year Average 2.82El 1.17El 9.52El 1.66El 1994 0.00E0 0.00E0 6.2El 0.00E0 Correlation Coefficient -0.37 -0.45 0.32 -0.49 NOTE: All negative values were replumd with "zero's" for calculational purposes.
3-25
d Table 3.6-B I
Radionuclide Concentration Reporting Percentage (pCi/kg) Level (pCi/kg)
Cs-134 0.00E0 3.00E3 0.00 %
Cs-137 6.2El 3.00E3 2.07 % ,
3-26
3.7 FISH In 1994,12 fish samples were analyzed, six at the indicator locations and ;
six at the control location. All radionuclides were not significantly 1 different from the fifteen-year average.
Cs-137 concentrations 1 correspond to a small percentage of the Selected Licensee Commitments j reporting level as shown in Table 3.7-B . The correlation coefficients for the location with the highest annual mean indicated a moderate to poor I probability of an increasing trend for the indicator concentrations of j Mn-54, Co-58, Co-60, Cs-134, and Cs-137. All other radionuclide I indicators and controls exhibited decreasing trends. Figure 5 illustrates Co-60 indicator trends.
1 i
3 a
I t
3-27
Table 3.7-A Concentration of Radionucli. des in Fish (Page 1 of 2)
Concentration (pCi/kg-wet)
Year Mn-54 Fe-59 Co-58 Co-60 Indicator Control Indicator Control Indicator Control Indicator Control 1979
- 0.00E-0
- 3.71El *
-2.78E-1
- 9.86E0 1980 -1.97El 1.14El ~1.95El 4.74E1 S.36E0 8.60E0 -2.25El 1.14El 1981 -2.71E0 2.74E0 3.70E0 2.97El -2.98E0 4.25E0 -2.65E0 -2.36E0 1982 -3.83E0 1.28El 0.00E0 8.47El 8.16E0 2.65E0 -4.34E-1 2.95E0 1983 -2.60E0 -1.84E0 -8.68E0 8.28E0 2.60El -5.31E0 1.llEl 2.42E0 1984 3.61E0 3.87E0 -1.23El 2.21El 1.45E2 4.15E0 2.82El 2.83E0 1985 2.53E-1 -1.75E0 4.25E0 4.49E0 7.19E0 1.32El 1.72El 1.55El 1986 1.03E0 -1.91 E0 -1.21 E0 3.77E0 3.17El -1.79E0 2.96El 5.13E0 1987 0.00E0 0.00E0 0.00E0 0.00E0 2.71E2 0.00E0 1.25E2 0.00E0 1988 1.20El 0.00E0 0.00E0 0.00E0 7.70El 0.00E0 0.00E0 0.00E0 1989 9.00El 5.40E0 0.00E0 0.00E0 4.05E2 0.00E0 2.99E2 0.00E0 1990 0.00E0 0.00E0 0.00E0 0.00E0 5.60E1 0.00E0 4.10E1 0.00E0 1991 6.20E0 0.00EO 0.00E0 0.00E0 1.40El 0.00E0 6.50E1 0.00E0 1992 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0F:" 0.00E0 0.00E0 1993 0.00E0 0.00E0 0.00E0 0.00E0 8.20E1 0.00E0 1.30El 0.00E0 15 Yr.
Avg. 8.08E0 2.41E0 5.68E-1 1.58El 8.08El 2.19E0 4.49El 3.34E0 1994 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 Corr.
Coef 0.I6 -0.48 -038 -0.71 0.I8 -0.44 0.22 -0.58 o No sampic analyzed.
NOTE: All negative values were replaced with "zero's" for calculational purposes.
3-28
I Table 3.7-A Concentration of Radionuclides in Fish (Page 2 of 2)
Concentration (pCi/k8 -we0 YEAR Zn-65 Cs-134 Cs-137 Indicator Control Indicator Control Indicator Control .,
1979
- 1.73E0 *
-4.17E0 2.20El 1980 -3.22El -2.26El -2.70El -2.10E0 -4.13 E0 8.07E0 1981 4.62E0 1.16E0 -1.99E0 9.09E0 1.80El 2.77El 1982 -1.39El -9.21 E0 -8.22E-1 3.57E-1 2.69El 9.52E0 1983 -1.07E0 4.86E0 -1.32E0 -2.57E0 6.03El 2.08E1 1984 -2.87E0 -3.26E0 3.llEl -7.09E-1 4.38El 8.18E0 198.5 --2.55 E0 3.17E0 -1.56E0 5.22E0 1.86El 1.48El 1986 -8.09E0 -1.40El I.67El 1.56E0 3.49El 8.64E0 1987 0.00E0 0.00E0 2.60E1 0.(MJ 5.10El 2.90El 1988 0.00E0 0.00E0 2.70El 0.00E0 3.60El 2.30E1 1989 0.00E0 0.00E0 1.10El 0.00E0 3.50El 1.50El 1990 0.00E0 0.00E0 0.00E0 0.00E0 3.30El L60El 1991 0.00E0 0.00E0 5.90E0 0.00E0 2.60El 0.00E0 1992 0.00E0 0.00E0 0.00E0 0.00E0 2.90El 1.10El 1993 0.00E0 0.00E0 0.00E0 0.00E0 1.60El 1.90El 15 Year Average 3.30E- 1 7.28E-1 8.41E0 1.08E0 3.06El 1.46El 1994 0.00E0 0.00E0 0.00E0 0.00E0 3.10El 0.00E0 CORRELATION COEFFICIENT -0.31 -0.40 0.03 -0.33 0.31 -0.45 0 No sample analyzed.
NOTE: All negative values were replaced with "zero's" for calculational purposes.
3-29
Table 3.7-B Radionuclide Concentration (pCi/kg) F.eporting Level (pCi/kg) Percentage Mn-54 0.00E0 3.00E4 0.00 %
Fe-59 0.00E0 1.00E4 0.00 %
Co-58 0.00E0 3.00E4 0.00 %
Co-60 0.00E0 1.00E4 0.00 %
Zn-65 0.00E0 2.00E4 0.00 %
Cs-134 0.00E0 1.00E3 0.00 %
l l
l l
l 3-30
FIGURE 5 PCi/kg wet CONCENTRATION OF CO-60 IN FISH 8m 5'A REPORTING LEVEL, l l
.im 300 200 100 -
/
i ' l 0
1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1902 1993 1994 Year i
l l
l 3-31
3.8 DIRECT GAMMA RADIATION In 1994,181 TLD's were analyzed,177 at indicator locations and four at the cor. trol location. The 1994 exposure rate at the indicator location with the highest annual mean did not significantly differ from the preoperational data or fourteen-year average. Table 3.8-A and Figure 6 illustrate this summary.
Table 3.8-A TLD Exposure from Direct Radiation Exposure (mrem /yr)
, YEAR 1rkhcator Control 1979 8.76El 8.32El 1980 1.16E2 1.05E2 1981 1.45E2 1.05E2 1982 1.36E2 1.10E2 1983 1.75E2 1.30E2 1984 1.20E2 9.02El 1985 1.52E2 1.27E2 1986 1.40E2 1.10E2 1987 1.43E2 1.23E2 1988 1.08E2 5.48El 1989 9.77El 7.55El 1990 8.30El 6.23El 1991 9.60E1 6.80El 1992 1.12E2 7.60El 1993 1.00E2 7.20El 15 Year Average 1.20E2 9.28El 1994 1.09E2 9.55El NOTE: The. expected background for North Cardina is 120 mrem per year from FSAR 11.6.1.
3-32
FIGURE 6 TLD EXPOSURE "M FROM DIRECT RADIATION 200 ilO ~~
32n b. }% x
! I
,, : /
N/*
40 0
l 1979 1980 1961 1982 1963 1964 1985 1986 1987 1968 1989 1990 1991 1992 1993 1994 l Year
-*-TLD Control
[ -*-TLDindicator l l
The test statistic, or t-test, was used to compare the TLD measurements during preoperation to those taken during 1994. In this case, ratios of results from I
the 1-2 mile radius and the 4-5 mile radius were compared from one year to the next. Since the inner ring of TLD's are n40st likely to be affected by plant operations, the hypothesis was used that a significant change in the ratio from one year to another would be indicative of an environmental effect or some other phenomena requiringinvestigation. A statistically significant change in the ratio was determined by comparing the calculated t-value to the expected value of the test statistic based on the number of measurements and the desired accuracy of the results.
The value of the t-statistic was calculated by comparing preoperational results to 1994. .As shown in Table 3.8-B, the t-value was 0.18. This is well within
- the expected value of 2.074, based on 26 degrees of freedom and 95%
l confidence in the result (a = 0.025, n = 24). As a result, it can be concluded l that the dose . ates measured around McGuire in 1994 do not differ significantly I from those fcund during preoperation.
1 3-33 l
Table 3.8-B Comparison of Inner Ring / Outer Ring TLD Results 1994 (mr/yr) Preop (mr/yr)
Inner Ring 64.02 79.14 Outer Ring 69.33 88.16 Ratio 0.92 0.90 Variance 0.026 0.02 t-value +0.18 t-table (95%) i .074 2
l l
3-34
7 a
3.9- FOOD PRODUCTS
- In 1994, 16 food products (crops) samples were analyzed, all at the two indicator locations. All Selected Licensee Commitments radionuclides exhibited a zero range indicating no measurable activity present. All indicators exhibited decreasing trends. Table 3.9-A illustrates this summary.
Table 3.9-B shows the percentages of environmental concentrations to the Selected Licensee Commitments reporting levels for the indicators at the location with the highest annual mean for 1994. No activity was detected and therefore no reporting levels were approached.
i
\
l e
w 3 :
11 1 3-35
1 1
Table 3.9-A Concentration of Radionuclides in Food Products l l
Concentration (pCi/kg-wet)
YEAR I-131 Cs-134 Cs-137 Indicator Control Indicator Control Indicator Control 1979* -5.82E0 7.30E-1 -1.00E1 -1.06El 2.19El 1.93El 1980* 1.91El 6.15E0 -2.59E0 -1.25El 2.30El 1.92El 1981* -1.87E0 3.16E0 1.24E1 5.96E0 3.04El 2.02E1 1982* 1.41 El 6.59E0 1.50E1 -6.31E-1 2.46El 1.22El 1983* 1.13El 7.19E0 4.13E0 1.24E0 9.07E0 7.85E0
- ** 8.45E0 **
1984 -5.08E-1 4.49E-1 1985 1.02E-l -2.48E0 7.99E0
- ** 2.15El **
1986 1.52El 1.74E0
- ** 2.90El **
1987 . ,;.: 0.00E0 0.00E0
- ** 0.00E0 **
1988 0.00E0 0.00E0
- ** 0.00E0 **
1989 0.00E0 0.00E0 1990 0.00E0 0.00E0 0.00E0
- ** 0.00E0 **
1991 0.00E0 0.00E0 1992 0.00E0 0.00E0 0.00E0
- ** 0.00E0 **
1993 0.00E0 0.00E0 15 YEAR AVERAGE 3.99E0 3.40E0 2.25E0 1.03E0 1.17El 1.13El 1994 0.00E0 0.00E0 0.00E0 CORRELATION COEFFICIENT -0.48 -
-0.46 -
-0.77 -
- Broadleaf vegetation samples used for food products media.
- No control site available.
--- Insufficient data to calculate a representative correlation coefficient.
NOTE: All negative values were replaced with "zero's" for calculational purposes.
3-36
l l Table 3.9-B l- ,
1 !
Radionuclide Concentration (pCi/kg) Reporting Level (pCi/kg) Percentage t
I-131 0.00E0 1.00E2 0.00%
Cs-134 0.00E0 1.00E3 0.00 %
Cs-137 0.00E0 2.00E3 0.00 %
l 3-37
3.10 LAND USE CENSUS The land use census was completed June 15, 1994 and the results are shown in Table 3.10 and Figure 7. Currently, two irrigated gardens are being sampled. During the 1994 census, eleven additional irrigated i gardens were identified. These gardens were reviewed with respect to amount of irrigation, size, willingness to participate, crop types, and location. One garden will be evaluated during the 1995 growing season to determine reliability compared to current sites. The census also revealed five milk animal locations that were not included in the 1993 sampling program. However, four of the locations do not produce sufficient volume to be added to the program and the fifth is outside the five kilometer area of participation. The nearest residence is located in the East sector at 0.46 miles.
t h
i I
3-38
Table 3.10 Land Use Census Results Page 1 of 2 SECTOR DISTANCE N Nearest Residence 2.5 miles Nearest Meat Animal None in 5 miles Nearest Garden 2.56 miles Nearest Cow None in 5 miles Nearest Goat None in 5 miles NNE Nearest Residence 1.29 miles Nearest Meat Animal None in 5 miles Nearest Garden 2.37 miles Nearest Cow None in 5 m!b Nearest Goat None in 5 miles NE Nearest Residence 1.2 miles Nearest Meat Animal None in 5 miles Nearest Garden 2.1 miles Nearest Cow None in 5 miles Nearest Goat None in 5 miles ENE Nearest Residence 0.56 miles Nearest Meat Animal 3.81 miles Nearest Garden 2.55 miles Nearest Cow 3.86 miles Nearest Goat None in 5 miles E Nearest Residence 0.46 miles Nearest Meat Animal 4.08 miles Nearest Garden 0.47 miles !
I' Nearest Cow 2.46 miles Nearest Goat None in 5 miles ESE Nearest Residence 0.67 miles Nearest Meat Animal 1.3 miles Nearest Garden 0.85 miles Nearest Cow 3.07 miles Nearest Goat 1.4 miles SE Nearest Residence 1.17 miles Nearest Meat Animal 1.6 miles Nearest Garden 1.21 miles Nearest Cow None in 5 rmlos Nearest Goat 1.9 mib SSE Nearest Residence 1.06 miles l Nearest Meat Animal 1.48 miles Nearest Garden 1.26 miles Nearest Cow 2.76 miles Nearest Goat 2.09 miles 3-39 l
g, 4 -a-.s -a m .a . - a m <.>..e z, ..
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. 1 H
Table 3.10 Land Use Census Results i- Page 2 of 2 l
SECTOR DISTANCE ,
S Nearest Residence 1.82 miles .
Nearest Meat Animal 3.01 miles ,
Nearest Garden 1.49 miles Nearest Cow None in 5 miles ;
Nearest Goat None in 5 miles SSW Nearest Residence 2.57 miles r Nearest Meat Animal 2.75 miles Nearest Garden 2.95 miles Nearest Cow None in Smiles .
. Nearest Goat None in 5 miles i SW Nearest Residence 1.8 miles ,
Nearest Meat Animal 2.58 miles
- Nearest Garden 1.8 miles Nearest Cow None in 5 miles Nearest Goat 2.58 miles )
WSW Nearest Residence 1.01 miles I Nearest Meat Animal 3.72 miles :
Nearest Garden 1.18 miles Nearest Cow None in 5 miles Nearest Goat 3.97 miles W Nearest Residence 0.82 miles Nearest Meat Animal 3.53 miles Nearest Garden 0.90 miles <
Nearest Cow None in 5 miles Nearest Goat None in 5 miles WNW Nearest Residence 0.91 miles Nearest Meat Animal None in 5 miles i Nearest Garden 2.15 miles I Nearest Cow Nonein 5 miles l Nearest Goat None in 5 miles i Nil Nearest Residence 0.93 miles ,
t Nearest Meat Animal None in 5 miles 1 Nearest Garden 1.37 miles .
Nearest Cow None in 5 miles i Nearest Goat None in 5 miles NNW Nearest Residence 1.53 miles Nearest Meat Animal None in 5 miles Nearest Garden 1.69 miles Nearest Cow None in 5 miles Nearest Goat None in 5 miles '
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4.0 EVALUATION OF DOSE FROM ENVIRONMENTAL MEASUREMENTS VERSUS ESTIMATED DOSE FROM RELEASES 4.1 DOSE FROM ENVIRONMENTAL MEASUREMENTS Doses were estimated for measured concentrations of radionuclides in direct pathways to man using NRC Regulatory Guide 1.109 methodology.
The highest annual mean values for each sample type and radionuclide were used after the background concentrations, as measured at the controllocation, had been subtracted. The maximum exposed individual doses are summarized in Table 4.1.
4.2 ESTIMATED DOSE FROM RELEASES Doses were estimated for release concentrations tF radionuclides in direct pathways to man using NRC Regulatory Guide 2.109 methodology.
The doses were calculated using GASPAR and LADTAP computer programs . The maximum exposed individual's doses are summarized in Table 4.1.
4.3 COMPARISOI4 OF DOSES Comparisons of environmental and effluent doses are shown in Table 4.1.
In general, estimated doses from releases are higher than calculated environmental doses. This comparison demonstrates the conservative methodology used in projecting effluent doses.
In the liquid pathway, no environmental doses were evaluated for the bone, thyroid, kidney, and lung due to the dose factors not available for the media which indicated activity in 1994. .
No environmental doses resulted in the gaseous pathway in 1994.
Broadleaf Vegetation samples indicated no activity.
The doses, as calculated using the environmental sample results, are well below the limits specified in Selected Licensee Commitments Manual Section 16.11-12.
4-1
i l
l TABLE 4.1 (Page 1 of 2) 1993 ENVIRONMENTAL AND EFFLUENT DOSES Liould Release Pathway Environmental I"*
Critical Organ or Effluent Critical Pathway Dose Data #9' (mrem /yr)
Skin Environ. Teen Shoreline Sediment 2.10E-4 Skin Effluent Teen Shoreline Sediment 2.12E-3 Bone Environ. - -
0.00E0 Bone Effluent Child Fish 7.86E-2 Liver Environ. Adult Fish 7.12E-2 Liver Effluent Child Drinking Water 4.37E-2 T. Body Environ. Teen Fish 2.57E-2 T. Body Effluent Adult Drinking Water 2.31 E-2 Thyroid Environ. - - 0.00E0 Thyroid Effluent infant Drinking Water 5.08E-1 Kidney Environ. - - 0.00E0 Kidney Effluent Child Drinking Water 6.58E-2 Lung Environ. - - 0.00E0 Lung Effluent Child Drinking Water 4.5CE-2 GI-LLI Environ. Adult Fish 1.37E-3 GI-LLI Effluent Adult Drinking Water 3.88E-2 4
l l
4-2
i l
TABLE 4.1 (Page 2 of 2) 1993 ENVIRONMENTAL AND EFFLUENT DOSES Gaseous Release Pathway Noble Gas Exposure Environmental Maximum
'IU"I Organ or Effluent Critical Pathway Dose Age Data (mrom/yr)
Skin Environ. - - Noble Gas Not Sampled Skin Effluent N/A Noble Gas Exposure 1.06E0 T. Body Environ. - -
Noble Gas Not Sampled T. Body Effluent N/A Noble Gas Exposure 4.12E-1 lodine. Particulate, and Tritium Exposure Environmental Maximum Cridcal Organ or Effluent Critical Pathway Dose Data #9' (mrom/yr)
Bone Environ. - - 0.00E0 Liver Enn on. - -
0.00E0 T. Body Environ. - -
0.00E0 Thyroid Environ. - - 0.00E0 Thyroid Effluent Infant Goat Milk 7.26E-2 Kidney Environ. Child Broadleaf Vegetation 0.00E0 Lung Environ. Child Broadicat Vegetation 0.00E0 GI-LLI Environ. Adult Broadleaf Vegetation 0.00E0 l
4-3
1 1
4.4 PATHWAY DOSE CALCULATIONS Dose calculations for each age and pathway can be found on the following pages.
4-4
t I
l Dose from Air Radiolodine Inhalation Pathway for 1994 Data Maximum Exposed Infant treathing rate = 1400 m3/yr Highest AnnualMean Concentration INFANT Inhalation Dose Factor (mrom per pClinhaled) Air Dose (mrem /yr)
Radionuclide Bone Liver T. Body Thyrold Kidney Lung GI-LLI Location (pCl/m3) Bone Liver T. Body Thyroid Kidney Lung Gl-LLI Mn-54 NO DATA 1.81E-05 3.56E-06 NO DATA 3.56E-06 7.14E-04 5.04E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 8.71E-07 1.30E-06 NO DATA NO DATA 5.55E-04 T.95E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 9.69E-06 1.68E-OS 6.77E-06 NO DATA NO DATA 7.25E-04 1.77E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+0C 0.00E+00 0.00E+00 0.00E+00 Co.60 NO DATA 5.73E-06 8.41E-06 NO DATA NO DATA 3.22E-03 2.28E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 1.38E-05 4.47E-05 2.22E-05 NO DATA 2.32E-05 4.62E-04 3.67E 05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E400 0.00E+00 0.00E+00 0.00E+00 Nb-95 1.12E45 4.59E-06 2.70E-06 NO DATA 3.37E46 3.42E44 9.05E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 8.24E-05 1.99E-05 1.45E-05 NO DATA 2.22E-05 1.25E-03 1.55E45 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 NO DATA 7.56E-07 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0JDOE+00 0.00E+00 0.00E+00 0.00E+00 Co-134 2.83E 04 5.02E-04 5.32E-05 NO DATA 1.36E-04 5.69E-05 9.53E-07 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 3.92E-04 4.37E-04 3.25E-05 NO DATA 1.23E-04 5.09E-05 9.53E-07 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Bala-140 4.00E-05 4.00E-08 2.07E-06 NO DATA 9.59E-09 1.14E-u3 2.74E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Dose Equivalent (mrom/yr)= 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Dose from Air Particulate inhalation Pathway for 1994 Data Maximum ExposedInfant Treathing rate = 1400 m3/yr Highest AnnualMean Concentration INFANT Inhalation Dose Factor (mrem per pCIinholed) led) Indicator Air Does (mrom/yr)
Radionuctide Bone Liver T. Body Thyroid Kidney Lung Gi4.Lt Location (pC1/m^3) Bone Uver T. Body Thyroid Kidney Lung Gl.Lt.l Mn-54 NO DATA 1.81E-05 3.56E-06 NODATA 3.56E46 7.14E-04 5.04E-06 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ;
Co-58 NO DATA 8.71E-37 1.30E.06 NO DATA NO DATA 5.55E44 7.95E-06 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 g Fs-59 9.69E-06 1.68E45 6.77E-06 NO DATA NO DATA 7.25E-04 1.77E45 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 NO DATA 5.73E-06 8.41E-06 NO DATA NO DATA 3.22E-03 2.28E 05 ALL 0.L1E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 1.38E-05 4.47E45 2.22E-05 NO DATA 2.32E-05 4.62E44 3.67E.05 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 1.12E-05 4.59E-06 2.70E-06 NO DATA 3.37E-06 3.42E-04 9.05EC ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 8.24E-05 1.99E-05 1.45E45 NO DATA 2.22E-05 1.25E43 1.55E45 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-131 2.71E-05 3.17E45 1.40E-05 1.06E-02 3.70E-05 NO DATA 7.56E-07 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-134 2.83E-04 5.02E44 5.32E-05 NO DATA 1.36E44 5.69E-05 9.53E-07 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-137 3.92E-04 4.37E-04 3.25E-05 NO DATA 1.23E44 5.09E-05 9.53E 07 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BaLa-140 4.00E-05 4.00E-08 2.07E-06 NO DATA 9.59E-09 1.14E-03 2.74E-05 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Totel Dose Equivalent (mrom/yr)= 0.00E+00 0.002+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
L Dose from Drinking Water Pathway for 1994 Data Maximum ExposedInfant uange (intake rate)- 330 i.sr Highest AnnualMean Concentration
!NFANT Ingestion Dose Factor (mrom per pClingested) Indicator Water Dose (mrom%r)
Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Locetion (pCitL) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 1.99E-05 4.51E-06 NO DATA 4.41E-06 NO DATA 7.31E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 3.60E-06 8.98E46 NO DATA NO DATA NO DATA 8.97E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E MO 0.00E+00 0.00E+00 I
N Fe-59 3.08E-05 5.38E-05 2.12E45 NO DATA NO DATA 1.59E 05 2.57E45 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co40 NO DATA 1.08E45 2.55E-05 NO DATA NO DATA NO DATA 2.57E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn45 1.84E-05 6.31E-05 2.91E-05 NO DATA 3.06E-05 NO DATA 5.33E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i
Nt>95 4.20E-08 1.73E-08 1.00E-08 NO DATA 1.24E48 NO DATA 1.46E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 !
Zr-95 2.06E-07 5.02E-08 3.56E48 NO DATA 5.41E-08 NO DATA 2.50E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-131 3.59E-05 4.23E-05 1.86E45 1.39E-02 4.94E45 NO DATA 1.51E-06 ALL 0.00 0.00E+0L 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.05E+00 0.00E+00 Co-134 3.77E-04 7.03E-04 7.10E-05 NO DATA 1.81E-04 7.42E45 1.91E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-137 5.22E-04 6.11E44 4.33E45 NO DATA 1.64E-04 8.64E 05 1.91E46 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BeLo-140 1.71E-04 1.71E-07 8.81E46 NO DATA 4.06E-08 1.05E-07 4.20E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 NO DATA 3.08E-07 3.00E-07 3.08E-07 3.00E-07 3.08E47 3.00E-07 ALL 0.00 0.00E+00 0.00E+eo 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Totot Dose Equivalent (mromfyr) = 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- ----------__--_--_s
- s' - ' T a a u -
Dose from Milk Pathway for 1994 Data .
Maximum ExposedInfant usage Datake rate)- 330 vyr Highest AnnualMean Concentration ewANT Ingestion Does Factor (wom por pClingested) Indicator tillIt Does(mromhr)
Radionuclide Bone . Liver T. Body Thyroid Kidney Lung GS-LLI Location (pCIIL) Bone Lhrer T. Body Thyroid Indney Lung GI-LLI .
10n-54 NO DATA 1.90E-05 4.51E-05 NO DATA 4.41E-06 NO DATA 7.31E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ' O.00E+00 Co-50 NO DATA 3.00E-06 0.90E46 NO DATA NO DATA NO DATA 0.07E4s ALL 0.00 0.00E+00 0.0CE+00 0.00E+00 0.00E+00 OADE+00 0.00E+00 0.00E+00 I
=
Fe-59 3.00E-05 5.30E-05 2.12E45 NO DATA NODATA 1.50E-05 2.57E-05 ALL 0.00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co40 NO DATA 1.00E45 2.55E45 NO DATA NO DATA NO DATA 2 N E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn45 1.04E45 8.31E-05 2.91E-05 NO DATA 3.00E45 NO DATA 5.33E45 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nt>05 4.20E-08 1.73E-00 1.00E-OS NO DATA 1.24E48 NO DATA 1.40E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 000E+00 ' O.00E+00 Zr-95 2.00E-07 5.02E-00 3.50E-00 NO DATA 5.41E4s NO DATA 2.50E45 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-131 3.50E-05 4.23E45 1.00E45 1.30E42 4.94E45 NO DATA 1.51E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-134 3.77E-04 7A3E44 7.10E-05 NO DATA 1.01E-04 7.42E45 1.91E-OS ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 OJ00E+00 0.00E+00 ,
Co-137 5.22E44 8.11E44 4.33E-05 NO DATA 1.84E44 S.64E-05 1.91E40 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BeLa-140 1.71E44 1.71E47 0.01E46 NODATA 4.00E40 1.00E-07 4.20E-05 ALL 0.00 - 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 OJ00E+00 0.00E+00 Total Does Equivalent (awom%r) = 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
, _ . _ . _ _. . . - _ , _ _ . _. .___~____ ____-._____ ____
i 1
l l
l Dose from Inhalation Air Radioiodines Pathway for 1994 Data i
Maximum Exposed Child Breathing rate = 3700 m3/yr l Highest AnnualMean Concentration CHILD Inhalation Dose Factor (mrem per pClinhaled) Indicator Air Dose (mromfyr)
Radionuclide Bone Liver T. Body Thyrold Kidney Lung GI-LLI Location (pCl/m3) Bone Uver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 1.16E45 2.57E-06 NO DATA 2.71E-06 4.26E-04 6.19E-06 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 4.79E47 6.55E-07 NO DATA NO DATA 2.99E44 9.29E46 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 A Fe-59 5.59E-06 9.04E-06 4.51E-06 NO DATA NO DATA 3.43E-04 1.91E-05 ALL 9.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co40 NO DATA 3.55E46 6.12E-06 NO DATA NO DATA 1.91E-03 2.60E-05 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+ 00 0.00E+00 0.00E+00 0.00E+00 Zn-65 1.15E 05 3.06E-05 1.90E-05 NO DATA 1.93E-05 2.69E-04 4.41E-06 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 6.35E-06 2.48E-06 1.77E-06 NO DATA 2.33E-06 1.66E44 1.00E-05 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 5.13E-05 1.13E-05 1.00E-05 NO DATA 1.61E-05 6.03E44 1.65E-05 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-131 1.30E45 1.30E-05 7.37E-06 4.39E-03 2.13E 85 NO DATA 7.68E 07 ALL 0.00E+00 0.00E+30 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-134 1.76E44 2.74E44 6.07E-05 NO DATA 8.93E45 3.27E 05 1.04E46 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 2.45E-04 2.23E-04 3.47E-05 NO DATA 7.63E45 2.01E45 9.78E47 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Bala-140 2.00E45 1.75E-08 1.17E46 NO DATA 5.71E-09 4.71E44 2.75E45 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Dose Equtvalent(mromtyr)= 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Dose from Inhalation Air Particulate Pathway for 1994 Data Maximum Exposed Child Deathing rate = 3700 (m3fyr)
Highest AnnualMean Concentration CHILD inhalation Does Factor (mrom per pClinhaled) Indicator A!r Does (mromtyr)
Radionuclide Bone Live- T. Body Thyroid Kidney Lung GI-LLI Location (pClhn3) Bone Liver T. Body Thyroid Kidney Lung GlLLI Mn-54 NO DATA 1.16E-05 2.57E-06 NO DATA 2.71E-06 4.26E44 6.19E-06 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 4.79E47 8 55E47 NO DATA NO DATA 2.99E-04 9.29E-06 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 5.59E-06 9.04E-06 4.51E-06 NO DATA NO DATA 3.43E-04 1.91E-05 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0 C&40 NO DATA 3.55E-06 6.12E-06 NO DATA NO DATA 1.91E-03 2.60E-05 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn45 1.15E-05 3.06E45 1.90E-05 NO DATA 1.93E-05 2.69E-04 4.41E-06 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 6.35E46 2.48E-06 1.77E-06 NO DATA 2.33E46 1.66E-04 1.00E45 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 5.13E-05 1.13E-05 1.00E-05 NO DATA 1.61E-05 6.03E44 1.65E45 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 - - 0.00E+00 1131 1.30E45 1.30E45 7.37E-06 4.39E-03 2.13E-05 NO DATA 7.6eE-07 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-134 1.76E-04 2.74E44 6.07E-05 NO DATA 8.93E-05 3.27E-05 1.04E-06 ALL- 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-137 2.,5E44 2.23E-04 3.47E45 NO DATA 7.63E-05 2.81E-05 9.78E-07 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Bala-140 2.00E45 1.75E-06 1.17E-06 NO DATA 5.71E49 4.71E-04 2.75E-05 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
! Total Does Eqdvalent (mrom/yr) = - 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
,,__ w _ . _ _ , , _ _ _ _ _ __ _ _ _ _ _ _ _ - - - - - - - _ _ _ _ _ _ - - _ _ _ _ _ - - - - - - --- = - - - -
Dose from Drinking Water Pathway for 1994 Data Usage (Intake rate) = 510 (Vyr) Maximum Exposed Child CHn D Highest AnnualMean Concentration Ingestion Dose Factor (mrom per pClIngested) Indicator Water Dose (mromfyr)
Radionucilde Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCl/t) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 1.07E45 2.85E-06 NO DATA 3.00E46 NO DA1 A 8.90E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 1.80E-06 5.51E-06 NO DATA NO DATA NO DATA 1.05E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 A Fe-59 1.65E-05 2.67E-05 1.33E-05 NO DATA NO DATA 7.74E-06 2.78E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CO-60 NO DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.33E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E400 0.00E+00 0.00E+00 ZrHi5 1.37E-05 3.65E-05 2.27E-05 NO DATA 2.30E45 NO DATA 6.41E46 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 2.25E48 8.76E49 6.26E49 NODATA 8.23E-09 NO DATA 1.62E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 1.16E-07 2.55E-08 2.27E-08 NO DATA 3.65E48 NO DATA 2.66E45 ALL O.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-131 1.72E45 1.73E45 9.83E-06 5.72E-03 2.84E.05 NO DATA 1.54E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 2.34E44 3.84E44 8.10E-05 NO DATA 1.19E44 4.27E-05 2.07E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 3.27E44 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E45 1.96E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BeLa-140 8.31E 05 7.28E-08 4.85E-06 NO DATA 2.37E-08 4.34E-08 4.21E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 NO DATA 2.03E47 2.03E47 2.03E-07 2.03E47 2.03E-07 2.03E47 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Dooe Equivalent (mromfyr) = 0.00E+00 0.00EA0 0.00E+C9 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Dose from Milk Pathway for 1994 Data Usage (Intake rate) = 330.00 Wr) Maximum Exposed Child i
l CHn.D Highest AnnualMean Concentration Ingestion Dose Factor (rnrem per pCIIngested) Indicator. Milk Dose (mrenVyr)
Radionuctide Bone Uver T. Body Thyrold Kidney Lung G1.LU Location (pC1/1) Bone Uver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 1.07E-05 2.85E-06 NO DATA 3.00E-06 NO DATA 8.90E46 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 1.80E-06 5.51E-06 NO DATA NO DATA NO DATA 1.05E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 g Fe-59 1.65E-05 2.67E 05 1.33E45 NO DATA NO DATA 7.74E-06 2.78E-05 ALL O.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C040 NO DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 1.37E-05 3.65E45 2.27E 05 NO DATA 2.30E45 NO DATA 6.41E-06 ALL O.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00 E - 0.00E+00 0.00E+00 Nb-95 2.25E-08 8.76E-09 6.26E-09 NO DATA 8.23E-09 NO DATA 1.62E45 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 1.16E-07 2.55E48 2.27E 08 NO DATA 3.65E48 NO DATA 2.66E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5-131 1.72E-05 1.73E-05 9.83E-06 5.72E43 2.84E-05 NO DATA 1.54E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 2.34E-04 3.84E 04 8.10E-05 NO DATA 1.19E44 4.27E-05 2.07E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-137 3.27E-04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E45 1.96E 06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Bala-140 8.31E-05 7.28E 08 4.85E-06 NO DATA 2.37E-05 4.34E 08 4.21E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Dome Equivalent (mrenVyr) = 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
w Dose from Broadleaf Vegetation Pathway for 1994 Data us.o. ons.n. r.1.) . 2s ,avyr Maximum Exposed Child CmtD Highest AnnualMean Concentration Ingestion Dooo Factor (nom per pCIIngested Indicator Food Does (snrerWyr)
RadionucHde Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCinig) Bone Liver ' T. Body Thyroid Kidney Lung 04 LLI Mn-54 NO DATA 1.07E-05 2.05E-06 NO DATA 3.00E-06 NO DATA 0.90E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 1.00E-06 5.51E-Os NO DATA NO DATA NO DATA 1.05E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 b
b W
Fe-59 1.85E-05 2.87E45 1.33E-05 NO DATA NO DATA 7.74E-06 2.70E-05 ALL 0.00 0.00E+00 C.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 t C040 NO DATA 5.29E-08 1.56E45 NO DATA NO DATA NO DATA 2.93E45 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 1.37E-05 3.85E45 2.27E-05 NO DATA 2.30E45 NO DATA 4.41E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 - 0.00E+00 0.00E+00 Nb-95 2.25E-00 8.70E-09 6.26E-09 NO DATA 8.23E49 NO DATA 1.82E45 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 1.18E47 2.55E-08 2.27E-00 NO DATA 3.85E45 NO DATA 2.00E45 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-131 1.72E-05 1.73E45 9.83E-05 5.72E-03 2.04E-05 NO DATA 1.54E-08 ALL 0.00 0.00E+00 ' O.00E+00 0.00E+00 0.00E+00 0 00E+00 0.00E+00 0.00E+00 Co-134 2.34E44 3.04E44 0.10E-05 NO DATA 1.19E44 4.27E45 2.07E-08 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4
Co.137 3.27E44 3.13E-04 4.82E-05 NO DATA 1.02E-04 3.87E-05 1.98E-08 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Beta-140 0.31E-05 7.20E48 4.05E-06 NO DATA 2.37E-08 4.34E45 4.21E45 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ' O.00E+00 0.00E+00 0.00E+00 ToteI Dose Equivalent (snresWyr)= 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
. . . _ . ._ . _ _. _ _ , , . _ . , . . _ , . _ .. . . ._~ _ _ _
Dose from Shoreline Sediment Pathway for 1994 Data Maximum Exposed Child i
Shoreline Recreation = 12 hr/yr Chore Width Factor = 0.s (take shore-location 129)
Shore Width Factor = 0.2 (rtver shoreline -location 130)
Extemal Dose Factor for Standing on Highest Annual Mean Concentration Contaminated Ground Dose (mromfyr)
(mrom/hr per pCl/m2) Indicator Sediment Radlonucilde T. Body Skin Location (pCIAig) T. Body Skin Mn-54 5.80E-09 8.80E-09 ALL 0.0 0.00E+00 0.00E+00 A Co-58 7.00E49 8.20E-09 ALL 0.0 0.00E+00 0.00E+00 Fe-59 8.00E-09 9.40E#3 AR 0.0 0.00E+00 0.00E+00 Co-60 170E-08 2.00E-08 All 0.0 0.00E+00 0.00E+00 Zn-65 4.00E-09 4.80E49 ALL 0.0 0.00E+00 0.00E+00 Nb-95 5.10E49 8.00E-09 ALL 0.0 0.00E+00 0.00E+00 Zr45 5.00E49 5.80E 09 ALL 0.0 0.00E+00 0.00E+00 b131 2.80E-09 3.40E-09 ALL 0.0 0.00E+00 0.00E+00 Cs-134 1.20E-08 1.40E48 ALL 0.0 0.00E+00 0.00E+00 Cs-137 4.20E-09 4.90E49 130 82.0 2.92E-05 3.40E45 Beta-140 2.10E-09 2.40E49 ALL 0.0 0.00E+00 0.00E+00 Total Dose (mromfyr) = 2.92E-05 3.40E45
. _ _ . . _ _ = .. - _. _. -. -_ _. . - - . .
0 Dose from Fish Pathway for 1994 Data ut.e om0u0 reet)- 8 u0hr Maximum Exposed Child CNetD Highest Annualnieen Concentration Ingestion Does Factor (awom per PCIIngested) Indicator Feh Does(Grornhr) .
RedlonucHde Bone Liver T.pody Thyroid 10dney Lung GI.LLI Location (pCng) Bone Liver T. Body Thyroid IGdney Lung 06.LLt -
Mn-54 NO DATA 1.07E-05 2.85E48 NO DATA 3.00E-06 NO DATA S. tee 06 ALL 0 00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-50 NO DATA 1.00E-08 5.51E48 NO DATA NO DATA NO DATA 1.05E.05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
~>
A Fe-50 1ASE-05 2.87E45 1.33E-05 NO DATA NO DATA 7.74E48 2.78E45 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9
$ CO.00 NO DATA 5.29E-06 1.58E45 NO DATA NO DATA ' NO DATA 2.93E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+0e ' O.00E+00 2n-65 1.37E45 3.85E45 2.27E45 NO DATA - 2.30E-05 NO DATA 5.41E48 ALL 0.00 0.00E+00 0.00E+00 OA0E+00 0.00E+00 0.00E+00 OASE+00 0.00E+00 Nb-95 2.25E4e 8 76E-09 6.2EE49 NODATA S.23E-09 NO DATA 1.5pE45 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr45 1.18E-07 2.55E48 2.27E40 NO DATA 3.05E-08 NO DATA 2.SSE-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 ' O.00E+00 0.00E+0D 0.00E*00 0.00E+00 M31 1.72E-05 1.73E.05 S.83E46 5.72E43 2.04E-05 NO DATA 1.54E48 ALL 0.00 O M +00 0.00E+00 0.00E+00 OADE+00 0.00E+00 0.00E+00 0.00E+00 Co-134 2.34E-04 3.84E44 8.10E 05 NO DATA 1.19E44 4.27E45 - 2.07E-06 ALL 0.00 0.00E+00 0.0nE+00 0.00E+00 0.00E+00 0.00E+00 SA0E+00 0.00E+00 Co 1*7 3.27E44 3.13E44 4.82E45 ' NODATA 1A2E44 3.87E45 1.90E-08 129 31A0 6.90E42 S.70E42 9.OSE-03 0.00E+00 2.10E 02 ' 7.05E43 4.15E-04 i
Beta-140 8.31E45 7.2eE-08 4.05E48 NO DATA 2.37E45 4.34E48 4.21E45 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+0e 0.00E+00 Total Dose Equivalent (nwom%r) = 5.70E42 8.70E42 9.00E-03 0.00E+00 2.18E42 7.05E43 4.10E44 t
.. . -m, . ~ . , - , . . - , _ ~_ ,. , , - - . . . . _
Dose from Food Pathway (Crops) for 1994 Data Usege (Intake rate) = 520 kgtyr Maximum Exposed Child CHLD Highest AnnualMean Concentration Ingestion Dose Factor (mrem per pCIingested) Indicator Food Does (mromfyr)
Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCilkg) Bone Liver T. Body Thyrold 10dney Lung GkLLI Mn-54 NO DATA 1.07E-05 2.85E-06 NO DATA 3.00E-06 NO DATA 8.98E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 1.80E-06 5.51E-06 NO DATA NO DATA NO DATA 1.05E45 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 A Fe-59 1.65E45 2.67E-05 1.33E-05 NO DATA NO DATA 7.74E-06 2.78E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0 00E+00 0.00E+00 0.00E+00 CO-60 NO DATA 5.29E46 1.56E-05 NO DATA NO DATA NO DATA 2.93E45 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 1.37E45 3.85E-05 2 27E-05 NO DATA 2.30E-05 NO DATA 6.41E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+C? 0.00E+00 0.00E+00 0.00E+00 Hb-95 2.25E48 8.76E-09 6.26E-09 NO DATA 8.23E-09 NO DATA 1.62E-05 ALL 0.00 0.00E4 00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 1.16E-07 2.55E-08 2.27E-08 NO DATA 3.65E-08 NO DATA 2.66E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l.131 1.72E-05 1.73E45 9.83E-06 5.72E-03 2.84E-03 NO DATA 1.54E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ca-134 2.34E-04 3.84E 04 8.10E 05 NO DATA 1.19E44 4.27E45 2.07E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-137 3.27E44 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E45 1.96E 06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Bala-140 8.31E-05 7.28E-06 4.85E-06 NO DATA 2,37E-08 4.34E-08 4.21E-05 ALL O.00 0.00E+00 ' O.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Dose Equivaient(mrom/yr)= 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Doce from Air Radioiodine Inhalation Pathway for 1994 Data Maximum Exposed Teen Usage (Intake rate) = 804,J (maryr)
Highest Annual Mean Co.. ation TEEN Inhalation dose factor (mrom per pClinhaled) Air Dose (mromfyr)
Radionuclide Bone Liver T. Body Thyrold Kidney Lung GI-LLJ Location (pCl/m3) Bone Liver T. Body Thyroid Kidnei Lung G14.r !
Mn-54 NO DATA 6.39E-06 1.05E-06 NO DATA 1.59E-06 2.48E.04 8.35E-06 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 2.59E-07 3.47E-07 NO DATA NO DATA 1.66E44 1.19E-05 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.0f s'9 0.00E+00 h
d
-4 Fe-59 1.09E46 4.62E-06 1.79E-06 NO DATA NO DATA 1.91E44 2.23E.05 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 NO DATA 1.89E-06 2.48E46 NO DATA NO DATA 1.09E43 3.24E-05 ALL 0.00E+00 0.00E+00 0.00E+00 0.006+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 4.82E-06 1.67E.05 7.80E-06 NO DATA 1.08E-05 1.55E-04 5.83E-06 AL*. 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 2.32E-06 1.29E-06 7.00E47 NO DATA 1.25E-06 9.39E-05 1.21E45 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 G.00E+00 0.00E+00 Zr-95 1.82E-05 5.73E46 3.04E46 NO DATA 8.42E-06 3.36E-04 1.86E45 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 NO DATA 8.11E-G7 ALL 0.00E+00 0.00E+C3 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 6.28E C5 1.41E-04 6.86E-05 NO DATA 4.69E.05 1.83E-05 1.22E-06 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 8.38E45 1.06E44 3.89E45 NO DATA 3.90E-05 1.51E-05 1.06E-06 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Bala-140 6.54E.06 8.38E49 4.40E-07 NO DATA 2.85E-09 2.54E44 2.86E 05 ALL O.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Dose Equivalent (mromfyr):= 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Dose from Air Particulate inhalation Pathway for 1994 Data Maximum Exposed Teen Usage (Intake rate) = 8000 (m3/yr)
Highest AnnualMean Concentration TEEN Inhalation dose factor (mrom per pCIinhaled) Indicator Air Dose (mromfrr)
Radionuclide Bone Uver T. Body Thyro!d Kidney Lung GB-LLI Location (pCl/m3) Bone Liver T. Body Tryroid Kidney Lung GB.tLI Mn-54 NO DATA 6.39E-06 1.05E-06 NO DATA 1.59E46 2.48E44 8.35E-06 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+#) 0.00E+00 0.00E+00 0 00E+00 Co-58 NO DATA 2.59E-07 3.47E-07 NO DATA NO DATA 1.68E-04 1.19E-05 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 b
b 00 Fe-59 1.09E-06 4.62E-06 1.79E-06 NO DATA NO DATA 1.91E44 2.23E 05 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co40 NO DATA 1.89E-06 2.48E-06 NO DATA NO DATA 1.09E-03 3.24E-05 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn45 4.82E-06 1.67E-05 7.80E-06 NO DATA 1.08E-05 1.55E-04 5.83E46 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 2.32E.06 1.29E46 7.08E-07 NO DATA 1.25E-06 9.39E-05 1.21E-05 ALL O.00E+00 0.00E+00 0.00E+00 0.GOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-05 1.82E45 6.73E-06 3.94E-06 NO DATA 8.42E-06 3.36E-04 1.86E45 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-131 4.43E46 6.14E-06 3.30E-06 1.83E-03 1.05E-05 NO DATA 8.11E-07 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 6.28E-05 1.41E44 6.86E-05 NO DATA 4.69E45 1.83E-05 1.22E-06 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 040E+00 0.00E+00 0.00E+00 Co-137 8.38E 05 1.06E 04 3.89E-05 NO DATA 3.00E-05 1.51E-05 1.06E 06 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Beta-140 6.84E-06 8.38E-09 4.40E-07 NO DATA 2.85E-09 2.54E-04 2.86E-05 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Dose Equivalent (mromtyr)= 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
1 I
4 1
Dose from Drinking Water Pathway for 1994 Data l u one. r.n.) . m up, Maximum Exposed Teen rn Highest Annualnieen Concentration 2
ine nonD r.eior D+*ine t
( r 0.rOCiine d) inee.ior wr D <n ryr)
, R.dlonuclid. Bon. Liv.r T.Sody Thyroid Kidn.y Lung GI-LLI Loc.tlon (pCIA) Son. Liv.r T. Body Thymid Kidn.y Lung OS-LLI Mn-54 NO DATA 5.90E45 1.17E-00 NO DATA 1.70E46 NO DATA 1.21E45 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-50 NO DATA 0.72E47 2.24E-06 NO DATA NO DATA NO DATA 1.34E45 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6
g F.-50 5.07E-08 1.37E45 5.20E48 NO DATA NO DATA 4.32E45 3.24E45 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
, to Co-00 NO DATA 2.01E46 6.33E46 NO DATA NO DATA W CATA 3.00E45 ALL 0.0 0.00E+00 0.00E+00 0 00E+00 0.00E+00 0.00E+00 - 0.00E+00 0.00E+00 Zn45 5.76E.06 2.00E45 0.33E 06 NO DATA 1.20E45 NO DATA 0.47E-06 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nt>05 0.22E40 4.50E-00 2.51E40 NO DATA 4.42E-00 NO DATA 1.05E45 - ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-05 4.12E.00 1.30E40 0.04E40 NO DATA 1.01E-00 NO DATA 3.00E45 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 M31 5.05E46 0.10E-08 4.40E46 2.30E43 1.4tE-05 NO DATA 1A?E-06 ALL 0.0 0.00E+00 0.00E+00 . 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 e C.-134 0.37E45 1.07E44 0.14E45 NO DATA 6.28E-05 2.30E45 2.45E-t4 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C.-137 1.12E44 1.40E44 5.10E45 NO DATA 4.07E45 1.07E-05 2.12E46 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i l 8.L.-140 2.04E-05 3.40E-00 1.03E40 NO DATA 1.10E40 2.34E40 4.:50E45 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 OJDOE+00 i
H-3 NO DATA 1.00E-07 1.0$E47 1.00E-07 1.00E47 1.00E47 1.00E-07 ALL 0.0 0.00E+00 0.00E+M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 j Toi.I Do Equiv.l.nt (=r lyr)= 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.Or . 4 0.00E+00 0.00E+00
. ,_ _ . . - - . . ~ _ ._- ~ _. , , _ __
Dose from Milk Pathway for 1994 Data u,.e. <\nt.u. r.n.) . 400 uyr Maximum Exposed Teen Teen Highest AnnualMean Concentration ingestion Dose Factor (mrom per pCI Ingested) Indicator MRk Dose (mromfyr)
RadionucHde Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pC1/L) Bone Uver T. Body Thyroid Kkiney Lung Gl4.U -
Mn-54 NO DATA 5.90E-06 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21E-05 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 9.72E47 2.24E46 NO DATA NO DATA NO DATA 1.34E-05 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 p Fe-59 5.87E46 1.37E-05 5.29E 06 NO DATA NO DATA 4.32E-06 3.24E45 ALL 0.0 0.00E+00 0.00Ee40 0.00E+00 0.00E+f)0 0.00E+00 0.00E+00 0.00E+00 w
O Co40 NO DATA 2.81E-06 6.33E-06 NO DATA NO DATA NO DATA 3.66E.05 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn45 5.76E46 2.00E45 9.33E-06 NO DATA 1.29E-05 NO DATA 8.47E46 ALL O.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.nE+00 0.00E+00 Nb-95 8.22E-09 4.56E-09 2,51E49 NO DATA 4.42E-09 NO DATA 1.95E-05 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2r-95 4.12E-08 1.30E-06 S.94E49 NO DATA 1.01E-06 NO DATA 3.00E-05 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 M31 5.85E46 8.19E-06 4.40E-06 2.39E-03 1.41E-05 NO DATA L62E 06 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-134 8.37E-05 1.97E44 9.14E45 NO DATA 4.2SE-05 2.39E-05 2.45E46 ALL O.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+03 0.00E+00 0.00E+00 Co-137 1.12E-04 1.49E e4 5.19E45 NO DATA 5.07E-05 1.97E45 2.12E-06 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BeLa-140 2.94E45 3.48E48 1.83E-06 NO DATA 1.18E48 2.34E 08 4.38E45 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 d.00E+00 0.00E+00 0.00E+00 i
Total Dose Equivalent (mromfyr)= 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
l l
l D3se from Broadleaf Vegetation Pathway for 1994 Data l Usage (Intake rate) = 42 (kgryr) Maximum Exposed Teen Teen Highest AnnualMean Concentration Ingestion Dose Factor (mram per PCIIngested) indicator Food Dose (mrom4r)
Radionuclide 3one Uver T. Body Thyrold Kltney Lung GbLLI Location (kgyr) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 5.90E-06 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21E-05 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA 1.34E45 ALL 0.0 0_00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i
A Fe-59 5.87E46 1.37E45 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E-05 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ' O.00E+00 9.00E+00 e
tQ w Co-60 NO DATA 2.81E-06 6.33E-06 NO DATA NO DATA NO DATA 3.66E45 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn.65 5.76E-06 2.00E-05 9.33E-06 NO DATA 1.28E-05 NO DATA 8.47E.06 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 G.00E+00 0.00E+00 0.00E+00 Nb-95 8.22E49 4.56E-09 2.51E49 NO DATA 4.42E49 NO DATA 1.95E 05 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 4.12E-08 1.30E-08 8.94E49 NO DATA 1.01E-08 NO DATA 3.00E-05 ALL 0.0 0.00E+00 C.00E+00 0.00E+00 . 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-131 5.85E-06 6.19E.06 4.40E-06 2.39E43 1.41E45 NO DATA 1.62E-04 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 8.37E-05 1.97E44 9.14E 05 NO DATA 6.26E-05 2 39E45 2.4SE-06 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-137 1.12E-04 1.49E44 5.19E45 NO DATA 5.07E45 1.97E45 2.12E-06 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BeLa-140 2.84E-05 3.48E-08 1.83E-06 NO DATA 1.18E48 2.34E-08 4.38E45 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Dose Equivalent (mrom4r)= 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Oose from Shoreline Sediment Pathway for 1994 Data Maximum Exposed Teen i Shoreline Recreations 67 hrfyr Shore Width Factor = 0.3 (take shore -location 129)
Shore Width Factor = 0.2 (rivershorenne-location 130) !
External Does Factor for Steneng on Highest Annual Resen Concentration Contaminated Ground Dose (mrom%r)
(mrommr per pCihn2) Indicator Sediment Redlonuclide T. Body Skin cellon (pCWhg) 7. Body Skin ten 44 5.80E4e 8.80E-09 ALL 0.0 0.00E+00 0.00E+00 Co-58 7.00E49 8.20E-09 ALL 0.0 0.00E+00 0.00E+00
$ Fe-59 8.00E-09 9.,40E-03 ALL 0.0 ' O.00E+00 0.00E+00 Co-GO 1.70E48 2.00E45 ALL' O.0 0.00E+00 0.00E+00 t
Zn45 4.00E45 4.SOE-09 ALL 0.0 0.00E+00 0.00E+00 Nb-95 5.10E49 ti.00E49 ALL 0.0 0.00E+00 0.00E+00 Zr-95 5.00E-09 5.00E49 ALL 0.0 0.00E+00 0.00E+00 14 31 2.00E4e 3.40E4e ALL 0.0 0.00E+00 OJO0E+00
~
, Co-134 1.20E48 1.40E-06 ALL 0.0 0.00E+00 0.00E+00 Co-137 4.20E49 4.90E49 130 82.0 1.40E44 1.43E44 pels-140 2.10E49 2.40E 00 ALL 0.0 0JDOE+00 OJDOE+00 Total Dose Esgulvelent (mromhr)= 1.40E44 1.83E44 t
l 1
l Dose from Fish Pathway for 1994 Data u o,m eres.>. ,8 m Maximum Exposed Teen l.
Teen Highest AnnualMean Concentration ingeeHon Does Factor)
(nwom por pClIncested) Indicator Floh - Does(nwomyr)
RadionocWde Bone Liver T. Body Thyroid Kidney Lung GI.LLI Lacedon (kgryr) Bone Liver T. Body Thyroid Midney Lung: GM.Ll l Mn-54 NO DATA 5.90E-06 1.17E-06 NO DATA 1.78E-06 MODATA 1.21E45 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-54 NO DATA 9.72E47 2.24E46 NO DATA NO DMA NO DATA 1.34E-05 129 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ' O.00E+00 0.00E+00 A Fe-59 5.07E-05 1.37E-05 5.29E.06 NO DATA NO DATA 4.32E-08 3.24E-05 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 e
U Co.40 NO DATA 2.01E-05 6.33E.06 NO DATA NO DATA NO DATA 3.SSE-05 129 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn45 5.70E-06 2.00E-05 9.33E-06 NO DATA 1.20E-05 NO DATA S 47E46 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb95 0.22E49 4.50E-09 2.51E-Os MO DATA 4.42E49 NODATA 1.954 05 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 4.12E48 1.30E-08 8.94E4e NO DATA 1.01E48 NO DATA 3.00E45 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E,00 I.131 5.85E46 8.19E-08 4.40E-06 2.39E43 1.41E45 NO DATA 1.82E46 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 OJ00E+00 0.00E+00 Co-134 0.37E-05 1.97E-04 9.14E45 NO DATA 6.2SE45 . 2.39E.05 2.45E46 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-137 1'.12E44 1.40E44 5.19E45 NO DATA SPE45 1.97E45 2.12E-OS ALL 31.0 5.50E-02 7.30E42 2.57E-02 0.00E+00 2.51E42 9.77E43 1.05E43 BeLo.140 2.84E45 ' 3.40E40 1.83E-06 NO DATA 1.10E48 2.34E-Os 4.30E45 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 - 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Does Equivalent (nwomhr)= 5.50E42 7.30E-02 2.57E42 0J00E+00 2.51E42 9.77E43 ' IJ05E43
_. - . _ _ __ ____ -_=_._ - _ - _ _ - _ _ _ _ _ - _ _ _ _ _ _
Dose from Food Products Pathway (Crops) for 1994 Data u g. cini.w. rot.) . 630 (uou,) Maximum Exposed Teen re.n Highest AnnualMean Concentration Ingestion Dose Factor (mrom per pCI Ingested) Indicator Food Dose (mromfyr)
Radionuclide Bone Uver T. Body Thyroid Kidney Lung Gl4Li Location (pCl/wkg) Bone Uver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 5.90E-06 1.17E-06 NO DATA 1.76E46 NO DATA 1.21E-05 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA 1.34E-05 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 p Fe-59 5.87E-06 1.37E-05 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E45 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E,00 0.00E+00 w
A Co40 NO DATA 2.81E-06 6.33E-06 NO DATA NO DATA NO DATA 3.66E-05 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn45 5.76E-06 2.00E45 9.33E-06 NO DATA 1.28E45 NO DATA 8.47E-06 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 8.22E-09 4.56E-09 2.51E-09 NO DATA 4.42E-09 NO DATA 1.95E-05 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 4.12E-08 1.30E-08 8.94E-09 NO DATA 1.01E-08 NO DATA 3.00E-05 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-131 5.85E-06 8.19E46 4.40E-06 2.39E-03 1.41E-05 NO DATA 1.62E-06 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 8.37E E 1.97E-04 9.14E-05 NO DATA 6.26E-05 2.39E45 2.45E-06 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 1.12E-04 1.49E-04 5.19E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Bala-140 2.84E-05 3.48E-08 1.83E-06 NO DATA 1.18E 08 2.34E-08 4.38E-05 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Dose Equivalent (mromfyr)= 0.00E+00 0.00E+00 0.00E+00 0.0un00 0.00E+00 0.00E+00 0.00E+00 waf
1 Dose from Air Radiolodines Inhalation Pathway for 1994 Data Maximum Exposed Adult uenge (intake rate). socom (mwyr)
Highest AnnualMean Concentration Adun ,
In% does factor
('nreen per pClinhaled) Air Does(snreen%r) j Radionucikle Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCthn3) Bone Liver T. Body Thyroid Kidney Lung G84.LI l RSn 64 NO DATA 4.95E46 7.07E-07 NO DATA 1.23E 08 1.74E-04 9.87E-08 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-50 NO DATA 1.00E-07 2.50E-07 NO DATA NO DATA 1.18E-04 1.33E45 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 1.47E-08 3.47E48 1.32E-06 NO DATA NO DATA 1.2FE44 2.35E-05 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 b
b Un Co40 NO DATA 1.44E.06 1.05E48 NO DATA NO DATA 7.48E-04 3.56E-05 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn45 4.05E-08 1.20E45 5.20E-06 NO DATA 0.82E-08 1.00E44 6.60E46 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.0cE+00 0.00E+00 0.00E+00 0.00E+00 NW 1.78E46 9.77E-07 5.20E 07 NO DATA 9.67E 07 6.31E45 1.30E-05 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 .. 0.00E+00 s Zr-05 1.34E-05 4.30E-05 2.91E46 NO DATA 6.77E-06 2.21E44 1.00E45 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I 1131 3.15E45 4.47E-OS 2.58E-OS 1.40E-03 7.00E46 NO DATA 7.05E-07 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-134 4.SSE-05 1.06E-04 9.10E45 NODATA 3.50E-06 1.22E45 1.30E45 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-137 5.95E45 7.70E45 5.35E-05 NO DATA 2.70E45 9.40E-05 1.05E46 ALL 0.00E+00 0.00E+00 0.00E+00 . 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sale-140 4.00E45 8.13E40 3.20E47 - NO DATA 2.00E-00 1.50E-04 2.73E-05 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Does Equivalent (nween4r)= 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i
'f i
I t
Dose from Air Particulate Inhalation Pathway for 1994 Data Maximum Exposed Adult Usage (intake rate) = 8000 (m3/yr)
Highest AnnualMean Concentration Adult inhalation dose factor (mrom per pClInhaled) Air Dose (mromfyr)
Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCl/m3) Bone Liver T. Body Thyroid 10dney Lung Cl.LLI Mn-54 NO DATA 4.95E-06 7.87E-07 NO DATA 1.23E-06 1.74E-04 9.67E-06 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 1.98E47 2.59E47 NO DATA NO DATA 1.16E-04 1.33E45 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 A Fe-59 1.47E-06 3.47E-06 1.32E46 NO DATA NO DATA 1.27E-04 2.35E-05 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 e
$ Co40 NO DATA 1.44E-06 1.85E-06 NO DATA NO DATA 7.46E44 3.56E-05 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 4.05E-06 1.29E45 5.28E46 NO DATA 6.62E46 1.00E-04 6.68E46 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nt>95 1.76E-06 9.77E-07 5.26E-07 NO DATA 9.67E-07 8.31E-05 1.30E45 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 1.34E-05 4.30E-06 2.91E-06 NO DATA 6.77E-06 2.21E44 1.88E-05 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3-131 3.15E-06 4.47E46 2.56E-06 1.49E43 7.66E-06 NO DATA 7.85E47 ALL 0.00E+00 0.00E+00 0.00E+00 0.002+00 0.00E+00 0JD0E+00 0.00E+00 0.00E+00 Cs-134 4.66E-05 1;06E44 9.10E-05 NO DATA 3.59E-05 1.22E-05 1.30E-06 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 5.95E-05 7.78E45 5.35E45 NO DATA 2.78E-05 9.40E46 1.05E46 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BaLa-140 4.0 ;E46 6.13E49 3.20E47 NO DATA 2.09E.09 1.59E-04 2.73E-05 ALL 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Dose Equivalent (mremfyr)= 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.0GE+00 0.00E+00 0.00E+00
Dose from Drinking Water Pathway for 1994 Data Maximum Exposed Adult Usage (Intake rate) = 730 (flyr)
Highest AnnualMean Concentration Adult Ingestion Dose Factor (mrom per pClIngested) Indicator Water Dose (mrem /yr)
Radionuclide Bone Liver T. Body Thyrold Kidney Lung Gl.LLI Location (pCit!) Bone Liver T. Body Thyroid Kidney Lung GI t.LI Mn.54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E46 NO DATA 1.40E45 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 7.45E-07 1.67E46 NO DATA' NO DATA NO DATA 1.51E-05 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 b
a Fe-59 4.34E-06 1.02E-C5 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 4.84E46 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E46 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 6.22E 09 3.46E-09 1.86E-09 NO DATA 3.42E.09 NO DATA 2.10E45 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 000E+00 G.00E+00 Zr-95 3.04E 08 9.75E-09 6.60E-09 NO DATA 1.53E-06 NO DATA 3.09E-05 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 c.00E+00 0.00E+00 l-131 4.16E-06 5.95E-08 3.41E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ca-134 6.22E-05 1.48E-04 1.21E44 NO DATA 4.79E-05 1.59E-05 2.59E-06 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-137 7.97E-05 1.09E-04 7.14E45 NO DATA 3.70E-05 1.23E-05 2.11E-06 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BaLa-140 2.03E-05 2.55E-08 1.33E46 NO DATA 8.67E-09 1.46E-08 4.18E-05 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 NO DATA 1.05E-07 1.05E-07 1.05E47 1.05E 07 1.05E 07 1.05E-07 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Dose Equivalent (mrom/yr):= 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0A0E4 0.00E+00 0.00E+00
_ - _ _ _ . _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ = _ _ _ _ _ - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _
Dose from Milk Pathway for 1994 Data u geanten ret ). 3,0 vyr Maximum Exposed Adult Adult Highest AnnualMean Concentration Ingestion Doea Factor (mrom per pClingested) Indicato Milk Dose (mremfyr)
Radionuctide Bone Uver T. Body Thyroid Kidney Lung GI-LLI Location (pCIIL) Bone Uver T. Body Thyroid 10dney Lung Gl-LU Mn-54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 ALL 0.0 6.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E45 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+GO 0.00E+00 0.00E+00 0.00E+00 A Fe-59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E45 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E*00 0.00E+00 0.00E+00 0.00E+00 s
M 00 Co-60 NO DATA 2.14E46 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 ALL 0.0 0.00E+00 0.00E+00 0.bOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 4.84E-06 1.54E-05 8.96E-06 NO DATA 1.03E45 NO DATA 9.70E-06 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NtNIS 6.22E-09 3.46E-09 1.86E-09 NO DATA 3.42E-09 NO DATA 2.10E-05 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr45 3.04E.06 9.75E-09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E45 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0A0E+00 0.00E+00 0.00E+00 0.00E+00 l-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-134 6.22E-05 1.48E-04 1.21E44 NO DATA 4.79E-05 1.59E-05 2.59E 06 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 7.97E45 1.09E-04 7.14E45 NO DATA 3.70E-05 1.23E-05 2.11E-06 ALL 0.0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Bala-140 2.03E-05 2.55E-08 1.33E-06 NODATA 8.67E-09 1.46E-08 9.25E45 ALL 0,0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Dose Equivalent (mromtyr)= 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Dose from Broadleaf Vegetation Pathway for 1994 Data Maximum Exposed Adult Usage (Intake rate) = 64 kg/yr Highest AnnualMean Concentration Adult ingestion Dose Factor (mrom per pCIIngested) Indicator Food Dose (mrom4r)
Radionuclide Bone Liver T. Body Thyroid Kidney Lung GN.La Location (pCllkg) Bone Liver T. Body Thymid Kidney Lung Gt4.LI Mn-54 NO DATA 4.57E46 8.72E-07 NO DATA 1.36E46 NO DATA 1.40E-05 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 7.45E47 1.67E46 NO DATA NO DATA NO DATA 1.51E-05 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 A
I Fe-59 4.34E-06 1.02E-05 3.91E46 NO DATA NO DATA 2.85E-06 3.40E45 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
$ Co40 NO DATA 2.14E-06 4.72E46 NO DATA NO DATA NO DATA 4.02E45 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn45 4.84E 06 1.54E45 6.96E46 NO DATA 1.03E45 NO DATA 9.70E-06 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 6.22E49 3.46E49 1.86E 09 NO DATA 3.42E-09 NO DATA 2.10E-05 ALL 0 0.00E+00 0.00E+00 040E+00 0.00E+00 0.0CE+00 0.00E+00 0.00E+00 Zr-95 3.04E48 9.75E-09 6.60E-09 NO DATA 1.53E48 NO DATA 3.09E-05 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 f 5131 4.16E-06 5.95E46 3.41E46 1.95E-03 1.02E 05 NO DATA 1.57E-06 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
l Ca-134 6.22E-05 1.4sE-04 1.21E-04 NO DATA 4.79E-05 1.59E45 2.59E-06 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I
j Co-137 7.97E-05 1.09E44 7.14E45 NO DATA 3.70E45 1.23E 05 2.11E 06 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1
BaLa-140 2.03E45 2.55E-08 1.33E-06 NO DATA 8.67E-09 1.46E-08 4.18E-05 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Dose Equivalent (mromhr)= 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
l . _ - _ . -_
Dose from Shoreline Sediment Pathway for 1994 Data Maximum Exposed Adult Shoreline Recreation = 12 hrtyr Shore Width Factor = 0.3 (lake shore -location 129)
Shore Width Factor = 0.2 (river shoreline -location 130)
External Dose Factor for Standing Highest Annual Mean Concentration on Contaminated Ground Dose (meem/yt)
(mrom/hr per pCl/m2) Indicator Sediment A Radionuclide T. Body Sktn Location (pCilkg) T. Body Skin W
O M 54 5.80E-09 6 80E49 ALL 0.0 0.00E+00 0.00E+00 CM8 7.00E49 8.20E49 ALL 02 0.00E+0u u.00E+00 Fe-59 8.00E49 9.40E49 ALL 0.0 0.00E+00 0.00E+00 Co40 1.70E48 2.00E-06 ALL 0.0 0.00E+00 0.00E+00 Zn45 4.00E-09 4.80E49 ALL 0.0 0.00E+00 0.00E+00 Nb-95 5.10E-09 6.00E49 ALL 0.0 0.00E+00 0.00E+00 Zr45 5.00E-09 5.80E-09 ALL 0.0 0.00E+00 OA0E+00 1-131 2.80E49 3.40E 09 ALL 0.0 0.00E+00 0.00E+00 Co-134 1.20E-08 1.40E-08 ALL 0.0 0.00E+00 0.00E+00 Co-137 4.20E49 4.90E49 130 62.0 2.50E45 2.92E-05 Bala-140 2.10E-09 2.40E-09 ALL 0.0 0.00E+00 0.00E+00 Total Dose (mromtyr) = 2.50E45 2.92E-05
l l Dose from Fish Pathway for 1994 Data l
Maximum Exposed Adult Usage (Intake rate) = 21 kglyr
! Highest AnnualMean Concentration Adult ingestion Dose Factor (mrem per pClingested) Indicator Floh Dose (mrenVyr)
Redlonue!!de Bone L' w T. Body Thyroid Kldney Lung GI-LU Location (pCilkg) Bone Liver T. Body Thyroid Kidney Lung Gl.LU Mn-54 NO DATA 4.57E46 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 4.34E-06 1.02E45 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E45 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4
C4 Co-60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E45 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn45 4.84E-06 1.54E45 6.96E46 NO DATA 1.03E-05 NO DATA 9.70E-06 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 6.22E-09 3.46E-09 1.86E49 NO DATA 3.42E49 NO DATA 2.10E-05 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E.08 NO DATA 3.09E-05 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l-131 4.16E.06 5.95E-06 3.41E46 1.95E43 1.02E-05 NO DATA 1.57E-06 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-134 6.22E-05 1.4eE-04 1.21E44 NO DATA 4.79E45 1.59E45 2.59E-06 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-137 7.97E-05 1.09E 04 7.14E-05 NO DATA 3.70E45 1.23E45 2.11E-06 129 31 5.19E-02 7.10E-02 4.65E-02 0.00E+00 2.41E-02 8.01E-03 1.37E43 BeLe-140 2.03E-05 2.55E48 1.33E-06 NO DATA 8.67E-09 1.46E-08 4.18E45 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Dose Equivalent (mrerrlyr)= 5.19E42 7.10E-02 4.65E-02 0.00E+00 2.41E-02 8.01E-03 1.37E-03
Dose from Food Products (Crops) Pathway for 1994 Data Maximum Exposed Adult usage (intake rate)- 520 kg/yr Highest AnnualMean Concentration Adult Ingestion Dose Factor (mrom per pCIIngested) Indicator Food Dose (mromlyr) fledtonuclide Bone Uver T. Body Thyroid Kidney Lung GI-LLI Location (pC1/kg) Bone Liver T. Body Thyroid Kidney Lung GI-LU Mn-54 NO DATA 4.57E46 8.72E47 NO DATA 1.36E-06 NO DATA 1.40E-05 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 y Co-56 NO DATA 7.45E47 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.0GE+00 0.00E+00 ta 20 Fe-59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co40 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn45 4.84E-06 1.54E-05 6.96E46 NO DATA 1.03E45 NO DATA 9.70E-06 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+0S Nb-95 6.22E-09 3.46E-09 1.86E-09 NO DATA 3.42E-09 NO DATA 2.10E45 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 3.04E-08 9.75E-09 6.60E49 NO DATA 1.53E-08 NO DATA 3.00E-05 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+0D OJD0E+00 0.00E+00 B.131 4.16E46 5.95E-06 3.41E-06 1.95E 03 1.02E-05 NO DATA 1.57E-06 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79E-05 1.50E-05 2.59E-06 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 7.97E45 1.09E-04 7.14E45 NO DATA 3.70E-05 1.23E45 2.11E 06 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Bala-140 2.03E-05 2.55E-08 1.33E-06 NO DATA 8.67E-09 1.46E-08 4.18E45 ALL 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Doce Equivalent (mromfyr)= 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
5.0 QUALITY ASSURANCE i
I 5.1 Dur(E POWER COMPANY'S RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l l
5.1.1 SAMPLE COLLECTION l
Radiological and Emironmental Senices, Fisheries, and Aquatic Ecology performed the environmental sample collecdons as specified by approved sample collection procedures.
5.1.2 SAMPLE ANALY91S He Radiological and Emironmental Senices Group performed the emironmental sample analyses as specified by approved analysis procedures.
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 QUALITY ASSURANCE Radiological and Environmental Senices 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. He frequency is dependent upon instrument use and performance. Investigations are performed and documented should calibration verification data fall out oflimits.
5.1.5 INTERLABORATORY QUALITY ASSURANCE 5.1.5.1 DUKE POWER'S AUDIT DMSION No audits were performed by Quality Verification in 1994. Following the 1993 audit, it was announced by Quality Verification that audits by them would be performed biannually.
5-1
5.1.5.2 DUKE POWER'S NUCLEAR PRODUCTION INTERCOMPARISON PROGRAM The Radiological and Environmental Services group panicipated in the Duke Power Nuclear Generation Depanment Intercomparison Program during 1994.
Interlaboratory cross-check standards, including marmelli beakers, air filters, air cartridges, gross alpha / beta on smears, and tritium in water samples were analyzed at various times of the year by the four counting laboratories in Duke Power Company for this program.
5.1.5.3 U.S. NUCLEAR REGULATORY COMMISSION INSPECTIONS Radiological and Environmental Services was not audited by the NRC in 1994.
5.1.5.4 UNITED STATES ENVIRONMENTAL PROTECTION AGENCY INTERCOMPARISON PROGRAM The Radiological and Environmental Senices Group participated in the Environmental Protection Agency (EPA) Environmental Monitoring Systems Laboratory Intercomparison Program. The EPA sample types included mixed gamma in water, mixed gamma in milk, gamma in air filters, iodine in milk, tritium in water, iodine in water, gross beta in air filters and gross beta in water.
Radiological and Environmental Services prepared and analyzed each sample as quickly as possible. Should the data obtamed be out of EPA limits, Radiological and Enviromental Senices would have performed and documented follow-up imestigations. The Radiological and Environmental Senices EPA Intercomparison Report code is "CP" A summary of the EPA Intercomparison Reports for 1994 is documented in Table 5-A. Of the analyses performed in 1994, none were out of acceptance limits. -
5.1.5.5 NRCISTATE OF N.C. INTERCOMPARISON PROGRAM Radiological and Environmental Senices, and the Radiation Dosimetry and Records group routinely participates with the State of North Carolina Department of Environmental Health and Natural Resources (DEHNR) in an itercomparison program. Radiological and Environmental Senices sends air, water, milk, vegetation, sedtment. and fish samples which have been collected to the State of North Carolina Radiation Protection Section for intercomparison analysis. TLDs are also co-located with the State and NRC at various environmental sites. Also, every six to eight months, the State of North Carolina Radiation Protection Section irradiata emironmental dosimeters and sends them to the Radiation Dosimetry and Records group for analysis of the unknown estunated delivered exposure. A summary of the State of North Carolina Emironmental Dosimetry Intercomparison Report for 1994 is documented in Table S-B. The Radiation Dosimetry and Records group results were within an average of % of the State of North Carolina results (excluding Standard Deviation values) for the 1994 cross-checks.
i 5-2
5.1.5.6 U.S. DEPARTMENT OF ENERGY INTERCOMPARISON PROGRAM There was no DOE intercomparison program during calendar year 1994.
5.2 CONTRACTOR LABORATORY No contractor laboratories were used during 1994.
l J l
5-3
m . . . . _
4 TABLE 5-1 (Page 1 of 3) .
U.S. ENVIRONMENTAL PROTECTION AGENCY INTERLABORATORY COMPARISON PROGRAM f 1994 CROSS-CHECK RESULTS FOR TIE RADIOLOGICAL AND ENVIRONMENTAL SERVICES LABORATORY
.. , .s.. ***c.-
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, , . , it.~ : 9%%;.v . mNM 4;&1 _fg ~ M,. D;:is N.* .
^'f/ANALYSISs < VM 'iDATEP > NUCLIDE(S)] sKNOWNVALUEl ^ 7 90 SIGMAINv3F REPORTEDNALUE '
Gamma in Water 04/19/94 Co-60 20.0 pCi/l 11.3 - 28.7 pCi/l 20.33 pCi/l Cs-134 34.0 pCi/l 25.3 - 42.7 pCi/l 32.33 pCi/l Cs-137 29.0 pCi/l ' 20.3 - 37.7 pCi/l 24.33 pCi/l v
- 6/10/94 Ba-133 98.0 pCi/l 80.7 - 115.3 pCill 91.33 pCi/l i
Co-60 50.0 pCi/l 41.3 - 58.7 pCi/l 52.0 pCill i u
? Zn-65 134.0 pCi/l i11.4 - 156.6 pCi/l 144.0 pCi/l
! Ru-106 252.0 pCi/l 208.6 - 295.4 pCi/l 235.0 pct /l i Cs-134 40.0 pCi/l 31.3 - 48.7 pCi/l 36.67 pCi/l ,
l Cs-137 49.0 pCi/l 40.3 - 57.7 pCi/l 49.67 pCi/l 10/18/94 Co-60 40.0 pCi/l 31.3 - 48.7 pCi/l 40.33 pCi/l
,' Cs-134 20.0 pCi/l 11.3 - 28.7 pCi/l 18.00 pCi/l Cs-137 39.0 pCi/l 30.3 - 47.7 pCi/l 40.0 pCi/l i
D t
l t
_ ___ _ _ _ _ _ _ _ _ _ - . . -,. . 4
TABLE 5-1 (Page 2 of 3)
U.S. ENVIRONMENTAL PROTECTION AGENCY INTERLABORATORY COMPARISON PROGRAM 1994 CROSS-CIIECK RESULTS FOR THE RADIOLOGICAL AND ENVIRONMENTAL SERVICES LABORATORY COLLECTION . CONTROL LIMITS -
ANALYSIS DATE : NUCLIDE(S) ' KNOWNVALUE - '(3 SIGMA; N=3) . REPORTED VALUE.
Gamma in Water 11/04/94 Co-60 59.0 pCi/l 50.3 - 67.7 pCi/l 60.67 pCill Zn-65 100.0 pCi/l 82.7 - 117.3 pCi/l 106.00 pCi/l Cs-134 24.0 pCi/l 15.3 - 32.7 pCi/l 23.33 pCi/l Cs-137 49.0 pCi/l 40.3 - 57.7 pCill 50.67 pCi/l Ba-133 73.0 pCill 60.9 - 85.1 pCi/l 73.33 pCill lodine in Water 02/04/94 I-131 119.0 pCi/l 98.2 - 139.8 pCi/l 123.33 pCi/l 10/07/94 I-131 79.0 pCi/l 65.1 - 92.9 pCi/l 78.33 pCill Air Filter 08/26/94 Cs-137 15.0 pCi/l 6.3 - 23.7 pCi/l 17.67 pCill Gross Beta 56.0 pCi/l 38.7 - 73.3 pCi/l 58.0 pCi/l Tritium in Water 03/04/94 H-3 4936.0 pCi/1 4078.9 - 5793.1 pCi/l 4644.0 pCi/l 08/05/94 H-3 9951.0 pCi/l 8224.7 - 11677.3 pCi/l 10014.0 pCi/l
t TABLE 5-1 (Page 3 of 3)
U.S. ENVIRONMENTAL PROTECTION AGENCY INTERLABORATORY COMPARISON PROGRAM 1994 CROSS-CHECK RESULTS FOR THE RADIOLOGICAL AND ENVIRONMEBTTAL SERVICES LABORATORY
~
COLLECTidNl - LCONTROL LIMITS
-.' ANALYSIS i ; DATEX NUCLIDE(S) ! KNOWN VALUE-f i(3 SIGMA; N=3) ; REPORTED VALUE t- ,
Gamma in Milk 09/30/94 1-131 75.0 pCi/l 61.1 - 88.9 pCi/l 76.33 pCi/l Cs-137 59.0 pCi/l - 50.3 - 67.7 pCi/l 60.0 pCi/l
~
i _.
1 Beta in Water 01/28/94 Gross Beta 62.0 pCi/l 44.7 - 79.3 pCi/l 76.0 pCi/l i
1 c,, 07/22/94 Gross Beta 10.0 pCi/l 1.3 - 18.7 pCi/l 17.0 pCi/l a n-10/18/94 Gross Beta 142.0 pCi/l 105.6 - 178.4 pCill 126.33 pCill .
.+
10/28/94 Gross Beta 23.0 pCi/l 14.3 - 31.7 pCi/l 29.0 pCi/l i
t L
- m. - - or , ere -
f.
l TABLE 5-B STATE OF NORTH CAROLINA DEPARTMENT OF ENVIRONMENTAL HEALTH AND NATURAL RESOURCES ENVIRONMENTAL DOSIMETER CROSS-CHECK - 1994 STATE OF N.C. RD&R ESTIMATED ESTIMATED VALUE VALUE Date of Exposure i.2:posure Estimated Uncertainty Cross-check (mR) (mR) (1S.D. mR)
Jun - 94 50 47.45 1 0.59 Nov - 94 70 65.75 1 0.71
6.0 REFERENCES
- 1. Final Safety Analysis Report, McGuire 1 & 2, Section 1.2.1. )
1
- 2. Final Safety Analysis Report, McGuire 1 & 2, Section 2.1.
l
- 3. Final Safety Analysis Report, McGuire 1 & 2, Section 2.1.1.
- 4. Final Safety Analysis Report, McGuire 1 & 2, Section 11.6.1.
l
- 5. Final Safety Analysis Report, McGuire 1 & 2, Section 11.6.3.
l
- 6. Final Safety Analysis Report, McGuire 1 & 2, Section 11.6.4.
- 7. Selected Licensee Commitments Manual Section 16.11-13.
- 8. McGuire Nuclear Station Technical Specification 6.9.1.6.
- 9. Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I", U.S. Nuclear Regulatory Commission, Rev.1, October 1977.
- 10. Probability in Statistics in Engineering and Management Science, Hines and Montgomery,1969, pp. 287-293.
- 11. Practical Statistics for the Physical Sciences, American Chemical Society, 1988, pp.84-100.
6-1
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l.
APPENDIXA l
l l
ENVIRONMENTAL 1
SAMPLINGAND ANALYSIS PROCEDURES A-1
APPENDIX A ENVIRONMENTAL SAMPLING AND ANALYSIS PROCEDURES 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 Records, Fisheries, and Aquatic Ecology.
Starting at Section A.1, this appendix describes the environmental sampling frequencies and analysis procedures by media type.
- l. CHANGE OF SAMPLING PROCEDURES The air deposition parameters (D/Q) changed in 1994 due to improved calculational methodology. In the environmental program, these deposition factors are used to determine air, broadleaf vegetation and milk sampling locations. As a result of this new calculation McGuire's sectors with the three highest values changed. In response, the changes are outlined below.
l Deletions to the sampling program for 1994 are as follows: TLD's 150 and 155 were deleted January; Broadleaf Vegetation site 158 was deleted after the February 1994 '
collection. Drinking Water site #142 at the Davidson Municipal Water Supply was discontinued on 10/3/94 due to the closing of that water supply facility.
Additions to the sampling program for 1994 are as follows: TLD #191 was added first quarter,1994; TLD #196, #197, #198 and #199 were added in third quarter,1994.
Drinking water site #194 was first collected 1/4 - 1/18/94; air site #192 was first collected 12/28/93 - 1/4/94 and air site #195 was first collected 6/21 - 6/28/94; broadleaf vegetation site #193 was first collected April 8,1994.
Although the technical site boundary in the nonh sector is over water, the sites added in this sector were located on a strip ofland at the discharge canal.
Beginning in June, Nonh Carolina State food products site changed from site #184 to site
- 188.
The scavenger fish spe:ies changed this year from catfish to carp due to the greater availability of carp.
Environmental direct radiation is monitored using the Harshaw TLD with LiF and CaF.
Descriptions of all above changes are given under applicable media headings.
- 11. CHANGE OF ANALYSIS PROCEDURES A new procedure was added in 1994 covering the operation of the Packard 2550 Liquid Scintillation System.
On January 1,1994 a new TLD system was placed in service at Duke Power Company.
The Harshaw 8807 replaced the Teledyne PB2. The Teledyne system was replaced due '
to age. The new Harshaw system provides better reliability and stability. A colocation study was performed at Oconee Nuclear Station to compare the performance of the two systems. The data indicated that the Harshaw results were generally higher. However, good statistical agreement existed between the two systems.
Ill. SAMPLING AND ANALYSIS PROCEDURES .'
A.1 AIRBORNE PARTICUL. ATE AND RADIOlODINE Airbome particulate and radiciodine samples at exh of seven locations were composited continuously by means of continuous air samplers. Air particulates were collected on a particulate filter and radiciodines were collected in a charcoal cartridge situated behind the filter in the sampler. The samplers are designed to l operate at a constant flow rate (in order to compensate for any tilter leading) and are .
set to sample approximately 2 cubic feet per minute. Filters and canridges were collected weekly. A weekly gamma analysis and gross beta analysis was performed on each filter and a weekly gamma analysis was performed on each charcoal cartridge. The filter and charcoal canridge were analyzed independently. The continuous composite samples were collected from the locations listed below.
Location 120 = Site Boundary (0.4 mi. NNE)
Location 121 = Site Boundary (0.5 mi. NE) <
Location 125 = Site Boundary (0.4 mi. SW)
Location 133 = Comelius, NC (6.2 mi. NE)
Location 134 = East Lincoln Junior High School (8.7 mi. WNW) location 192 = Penninsula development (2.81 mi. NNE)
Location 195 = Fishing Access Road (0.2 mi. N)
A-3
A.2 DRINKING WATER Biweekly composite samples were collected. A low-levelIodine-131 analysis was performed on each composite sample. A gross beta and gamma analysis was performed on monthly composites. Tritium analysis was performed on the quarterly composites. The composites were collected biweekly from the locationslisted below.
Location 132 = Charlotte Municipal Water Supply (11.2 mi. SSE)
Imation 136 = Mooresville Municipal Water Supply (12.5 mi. NNE)
Location 142 = Davidson Municipal Water Supply (7.5 mi. NE)
Location 194 = East Lincoln Water Supply (6.88 mi. NNW)
A.3 SURFACE WATER Biweekly composite samples were collected. A low-level Iodine-131 analysis was performed on each composite sample. A gamma annysis was performed on the monthly composites. Tritium analysis was performed on each sample. The composites were collected biweekly from the locations listed below.
Location 128 = Discharge Canal Bridge (0.4 mi. ENE) l Location 131 = Cowans Ford Dam (0.7 mi. W)
Imation 135 = Plant Marshall Intake Canal (12.0 mi. N)
A.4 ggg j Biweekly grab samples were collected at each dairy and a gamma and low-level i Iodine- 131 analysis was performed on each. The biweekly grab samples were collected from the locations below.
Location 138 = Henry Cook Dairy - COWS (2.75 mi. ESE) l Location 139 = William Cook Dairy- COWS (2.6 mi. E)
Location 140 = Kidd Dairy- COWS (2/i mi SSE)
Location 141 = Lynch Dairy - COWS (14.8 mi. WNW)
A.5 BROADLEAF VEGETATION Monthly samples were collected and a gamma analysis was performed on each. The samples were collected from the locations listed below.
I.ocation 120 = Site Boundary (0.4 mi. NNE)
Location 125 = Site Boundary (0.4 mi. SW)
L Location 134 = East Lincoln Junior High School (8.7 mi. WNW)
Location 193 = Site Boundary (0.3 mi. N)
A-4
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~
I l
1 i
A.6 ShQRELINE SEDIMENT l Semiannual samples were collected and a gamma analysis was performed on each :
following the drying and removal of rocks and clams. The samples wem collected from the locations listed below. -
location 129 = Discharge Canal Entrance to Lake Norman (0.6 mi.
ENE)
Location 130 = Highway 73 Bridge Downstream (0.6 mi. ENE)
Imation 137 =
Pinnacle Access Area (12.0 mi.N)
A.7 E!$H Semiannual samples were collected and a gamma analysis was perfonned on the edible portions of each sample. Boney fish such as sunfish wem prepared whole minus the head head tail portions. The samples were collected from the locations listed below.
Location 129 = Discharge Canal Entrance to Lake Norman (0.6 mi.
ENE)
Imation 137 =
Pinnacle Access Area (12.0 mi. N)
A.8 DIRECT GAMMA RADIATION (TkQ}
Thermoluminescent dosimeters (TLD) were collected quarterly at forty-eight locations. A gamma dose rate was determined for each TLD. The TLDs were placed asindicatedbelow.
An inner ring of 14 TLDs at the site boundary, one in each available meteorological sector. The site boundary locations 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.
At the begining of third quarter,1994, four (4) additional TLD's were added to the south sector.
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.
A-5
A.9 EQMLPRODUCTS I
a Samples were collected monthly when available during the harvest season and a igammaanalysis was performed on each. The samples were collected at the locations listed below.
Imcation 184 = 5 Mile Radius (2.5 mi. ENE) - Gardens (Davenport's Residence) location 188 = 5 Mile Radius (2.8 mi. N) - Gardens (Austin's i Residence)
A.10 ANNUAL LAND USE CUNSUS 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 completed June 15,1994 and the results are shown in Table 3.10 (pages 3-32 and 3-33).
A-6
IV. PROGRAMIMPROVEMENTS Trending of both air sampler and site location is performed for continuous identification of tre' ads impacting the deviation rate in the Radiological Environmental Monitcring Program (REMP).
Radiological Environmental Monitoring Program (REMP) site locations were relocated using Global Positioning System (GPS) differential corrections giving most locations an accuracy of +/- 2 meters.' The locations had previously been positioned using a GPS unit without the availability of differential correction.
Deviations in sampling due to equipment failure requiring a work request are now reported to facilities maintenance via MMRS. Utililization of this computer program assists with timely reporting of problems and tracking of the status of work requests.
Broad leaf vegetation sites were supplemented with the planting of two each of R.
Stevens Holly and Wax Myrtle plants at each site in June of 1994. The vegetation will be used to provide samples during winter months. It will take approximately two years for the plants to mature before they can be harvested.
A-7
l APPENDIXB RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OF RESULTS 1994 Summary sheets for each media have been includedin this Appendix .
B-1
.. - . . , , , . _ . _ ._ , . - - . _ , . . ..,-,,,m.c--...
B.1 RADIO!0 DINES Environmentst Radiological Monitoring Program Summary Name cf facility
~
- McGuire Nuclear Station Docket Number : 50 369,370
. Location af Facility : Mecklerburg County, N.C. Reporting Period : 1-JAN-1994 through 31-DEC-1994
- fine Report Generated
- 12 JAN-1995 11:12:38 Database Name : 50lSK1:(USER. ASC]MNS94.SAF;104 l l l l Location with Highest Mean l lNo.of Medium er l Type & Total l Lower l All Indicator l --------- -- ------ ---------l l Non-P:thway l Ntsuber of l Limitofl Locations l Name, Distance and Direction l Control Locations l Routine Sampled - l Analyses l Detection l Mean (Fraction). l Location' Mean (Fraction) l Mean (Fraction) l Report (Units) l Performed l (LLD) l Range l Code Range l Range l Meas.
j................................................................................................................................
1 RA01010 DINES l l l l l l l/M3) l l l l l l l
l l l l l 134 (8.7 Mi WNW) l
$ations lMN54 345l 0.00E+00l 0.00E+00( 0/ 294) l 0.00E+00( 0/ 53) l 0.00E+00( 0/ 51) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l 1 I I I I Co-58 345l 0.00E+00l 0.00E+00( 0/ 294) 0.00E+00( 0/ 53) l 0.00E+00( 0/ 51) l 0 l l 0.00E+00-- 0.00E+00 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l 1 I I
! FE 59 345l 0.00E+00l 0.00E+00( 0/ 294) 0.00E+00( 0/ 53) l 0.00E+00( 0/ 51) l 0 l l 0.00E+00-- 0.00E+00 , 0.00E+00 0.00E+00 l 0.00E+00--0.00E+00l l l l 1 1 I lCo-60 345l 0.00E+00l 0.00E+00( 0/294)l 0.00E+00( 0/ 53) l 0.00E+00( 0/ 51) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 1 I I I I I lZN65 345l 0.00E+00l 0.00E+00( 0/ 294) l 0.00E+00( 0/ 53) l 0.00E+00( 0/ 51) l 0 l l l l 0.00E+00- 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l I I 1 1 I I i jNs-95 345l 0.00E+00] 0.00E+00( 0/ 294) l 0.00E+00( 0/ 53) l 0.00E+00( 0/ $1) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00-0,00E+00l 0.00E+00- 0.00C+00 l 1 I I I I I l2R-95 345l 0.00E+00l 0.00E+00( 0/ 294) l 0.00E+00( 0/ 53) l 0.00E+00( 0/ 51) l 0 l l l 0.00E+00-0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l l l l l l lI-131 345l 7.00E02l 0.00E+00( 0/ 294) l 0.00E+00( 0/ 53) l 0.00E+00( 0/ 51) l 0 l l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l l l 1 l l lCS-134 345 5.00E-02 0.00E+00( 0/ 294) l 0.00E+00( 0/ 53) l 0.00E+00( 0/ 51) 0 l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00-- 0.00E+00 l l l 1 1 I I I l lCS137 345l 6.00E-02l 0.00E+00( 0/294)l 0.00E+00( 0/ 53) l 0.00E+00( 0/ 51) l 0 l
l l l 0.00E+00-0.00E+00l 0.00E+00-0.00E+00l 0.00E+00-0.00E+00l l l j l l l lBALA-140 345l 0.00E+00l 0.00E+00( 0/ 294) l 0.00E+00( 0/ 53) l 0.00E+00( 0/ 51) l 0
! l l l 0.00E+00 0.00E+00 0.00E+00-- 0.00E+00 0.00E+00-. 0.00E+00 l.................................................................l................................l.......................l........
fandrangebasedupondetectabl3measurementsonly lon of detectable measurements at specified locations is indicated in parentheses, (Fractior.)
renga indicates no detectable activity measurements is equal to 0, then LLD is not required by Selected Licensee tcmmitments lon 120 = Site Boundary (0.4 Mi NNE) Location 134 = East Lincoln Junior High School (8.7 Mi WNW) lon 121 = Site Boundary (0.5 Mi NE) Location 192 = Peninsula (2.8 Mi NNE) len 125 = Site soundary (0.4 Mi SW) Location 195 = Fishing Access Road (0.2 Mi N) lon 133 = Cornelius, NC (6.2 Mi NE)
B-2
l 8.2 PARTICULATES Environmental Radiological Monitoring Program Surinary Name of Facility : McGuire Nuclear Station Docket Nunber : 50-369,370 Loc tion of Facility : Mecklenburg County, N.C. Reporting Period : 1-JAN 1994 through 31-DEC-1994 Time Report Generated : 12-JAN 1995 11:12:38 Database Name 50!SK1:(USER.ASC MNS94.SAF;104
................................................................................................].... ......... .................
l l l l Location with Highest Mean Medlun or l Type & Total l Lower All Indicator lNo.of P:thway l Number of l Limitofl l
Locations l - - - ~ - - - ~ - ~ - - - - ' " ' - - ' ll l Non-Sampled l Name, Distance and Direction l Control Locations l Routine l Analyses l Detection l Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) l Report (Units) l Performed l (LLD) Range l
.....................................................................................ge l Code Ran l Range l Meas.
PARTICULATE l l l l
/S) l l l l l l cations lMN-54 l 134 (8.7 Mi WNW) l 345l 0.00E+00l 0.00E+00( 0/ 294) l 0.00E+00( 0/ 53) l 0.00E+00(
l l 0/ 51) l 0 l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l 0.00E+00--0.00E+00l l l l 1 I lCo-58 i 345l 0.00E+00l 0.00E+00( 0/ 294) l 0.00E+00( 0/ 53) l 0.00E+00(
l l 0/ 51) l 0 i l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l l 1 I I l lFE-59 345l 0.00E+00l 0.00E+00( 0/ 294) l 0.00E+00(
l 0/ 53) l 0.00E+00( 0/ 51) l 0 l l 0.00E+00 ~ 0.00E+00 l 1 I I 0.00E+00 ~ 0.00E+00 l 0.00E+00--0.00E+00l I I lCo-60 I 345l 0.00E+00l 0.00E+00( 0/ 294) l 0.00E+00( 0/ 53) l 0.00E+00(
l l 0/ 51) l 0 l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l l 1 I I I lZN-65 i 345l 0.00E+00l 0.00E+00( 0/294)l 0.00E+00( 0/ 53) l 0.00E+00(
l l 0/ 51) l 0 l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l 0.00E+00 ~ 0.00E+00 l 1 I I I I lNB-95 i 345l 0.00E+00l 0.00E+00( 0/ 294) l 0.00E+00( 0/ 53) l 0.00E+00(
l l 0/ 51) { 0 l 0.00E+00~ 0.00E+00 l 0.00E+00 ~ 0.00E+00 l 0.00E+00 ~ 0.00E+00 l l l l I I l2R95 I 345l 0.00E+00l 0.00E+00( 0/ 294) l 0.00E+00( 0/ 53) l 0.00E+00(
l l 0/ 51) l 0 l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00 ~ 0.00E+00 l l l 1 1 I ll-131 i 345l 7.00E-02l 0.00E+00( 0/ 294) l 0.00E+00( 0/ 53) l 0.00E+00(
l l 0/ 51) l 0 l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00 ~ 0.00E+00 l l l l l 1 lCS134 I
( 345l 5.00E-02l 0.00E+00( 0/ 294) l 0.00E+00( 0/ 53) l 0.00E+00(
l l 0/ 51) l 0 I l 0.00E+00-.0.00E+00l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l I I I I I f lCS137 I 345l 6.00E-02l 0.00E+00( 0/ 294) l 0.00E+00( 0/ 53) l 0.00E+00(
l l 0/ 51) l 0 l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l l l l l l lBALA140 345l 0.00C+00l 0.00E+00( 0/ 294) l 0.00E+00( 0/ 53) l 0.00E+00(
l l 0/ 51) l 0 l 0.00E+00--0.00E+00l 0.00E+00 ~ 0.00E+00 l 0.00E+00 ~ 0.00E+00 l l l l l133(6.2MiNE) l l l BETA 345l 1.00E-02l 1.97E-02( 294/ 294) l 2.28E-02( 53/ 53) l 2.02E 02( 51/ 51) l 0 l l l 6.37E-03~ 0.25 l 7.92E-03-- 0.25 m................................................................................ l 5.91E-03~ 3.46E-02 l nnd rrnga based upon detectable measurements only ion of detectable measurements at specified locations is indicated in parentheses, (Fraction) rcngt indicstes no detectable activity measurements
)
is equal to 0, then LLD is not required by selected Licensee Conunitments ion 120 = Site Bomdary (0.4 Mi NNE)
Location 134 = East Lincoln Junior High School (8.7 Mi WNW)
'on 121 = Site Boundary (0.5 Mi NE)
Location 192 = Peninsula (2.8 Mi NNE) 125 = Site Boundary (0.4 Mi SW)
Location 195 = Fishing Access Road (0.2 Mi N)
,on 133 = Cornelius, NC (6.2 Mi NE)
B-3 I
O.3 ORINKING WATER Envirornental Radiological Monitoring Program Sunnary Came of Facility : McGuire Nuclear Station Docket Ntsuber : 50 369,370 Location of Facility : Mecklenburg County, N.C. Reporting Period : 1-JAN-1994 through 31 DEC 1994 Tint) Report Generated : 12-JAN-1995 11:12:38 Database Name . SDISK1:(USER. ASC]MNS94.SAF;104 l l l l Location with Highest Mean l lNo.of Dedium or l Type & Total l Lower l All Indicator l------------------------------l l Non-Pathway l Nunber of l Limitofl Locations l Name,DistanceandDirectionl Control Locations l Routine Sampled l Analyses l Detection l Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) l Report (Units) l Performed l (LLD) l Range l Code Range l Range l Meas.
................................................................................................................................ T HING WATER l l l l l l
'/ LITER) l l l l l 136 (12.5 Mi NNE) l
- ations 50l 1.0 l 0.00E+00( 0/ 37) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 #
l ANAL 1-LL l l l 0.00E+00-0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l l l l l l l ANAL 2-LL 49l 1.0 l 0.00E+00( 0/ 36) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l l l l I I lMN-54 50 l
- 15. l 0.00E+00( 0/ 37) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l , l 0.00E+00--0.00E+00l 0.00E+00-.0.00E+00l 0.00E+00--0.00E+00l l l l l l l lCO-58 50 l 15. l 0.CE+00( 0/ 37) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00-- 0.00E+00 l l l l l l l lFE-59 50 l 30. l 0.00E+00( 0/ 37) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00-0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l l l l l 1 lCO-60 50 l 15. l 0.00E+00( 0/ 37) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l l l l l l 1 lZN-65 50 l 30. l 0.00E+00( 0/ 37) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l l l l l l lN895 50 l 15. l 0.00E+00( 0/ 37) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 1 I I I I l lZR95 50l 15. l 0.00E+00( 0/ 37) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l '
1 I I I I I lI131 50l 15. l 0.00E+00( 0/ 37) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00- 0.00E+00 l 0.00E+00--0.00E+00l l l l l l 1 ,
lCS-134 50l 15. l 0.00E+00( 0/ 37) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l
l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l 1 I I I I I lCS-137 50l 18. l 0.00E+00( 0/ 37) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00-.0.00E+00l I I I I I I lBALA-140 50l 15. l 0.00E+00( 0/ 37) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l and range based upon detectable measurements only l tion of detectable measurements at specified locations is indicated in parentheses, (Fraction) f range indicates no detectable activity measurements lLD is equal to 0, then LLD is not required by Selected Licensee Consnitnents ition 132 = Charlotte Municipal Water Supply (11.2 Mi SSE) Location 142 = Davidson Municipal Water Supply (7.5 Mi NE) tion 136 = Mooresville Municipal Water Supply (12.5 Mi NNE) Location 194 = Lincoln County Water Supply (6.9 Mi NNW)
B-4
Environmental Radiological Monitcring Program Suumary same cf facility- : McGuire Nuclear Station Docket Number : 50-369,370 (oc:tioncfFacility : Mecklenburg County, N.C. Reporting Period 1-JAN-1994 through 31 DEC-1994 j JimeReportGenerated: 12-JAN-1995 11:12:38 Database Narte : S0!SK1: (USER . ASC)MNS94.SAF;104 j p...............................................................................................................................
l l l l Location with Highest Mean l lNo.of ,
tediua er l Type & Total l Lower l All Indicator l--------------------------l l Non- l Pathway Nunber of l Limitofl Locations l Name,DistanceandDirectionl Control Locations l Routine Saapted Analyses l Detection l. Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) l Report l(Units) l. Performed l (LLD) l Range l Code Range l Range l Meas.
L...............................................................................................................................
JING WATER l l l l l l 7 LITER) l l l l l l l l l l132(11.2MiSSE) l 136 (12.5 Mi NNE) ktions l BETA 50l 4.0 l 2.52( 22/ 37) l 2.47 ( 7/ 13) l 2.9 ( 10/ 13) 0 l l l 0.72 - 5.18 [ 0.72 -- 5.18 l 1.1 -- 9.0 l
)lTIUM l l l l l l 7trTER) l I [ l .l l I I I I i l lH-3 16l 2.00E+03l 0.00E+00( 0/ 12) l 0,00E+00( 0/ 4) l 0.00E+00( 0/ 4)l 0 l l l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l 0.00E+00- 0.00E+00 l p...............................................................................................................................
and rarge based upon detectable measurements only
)fon of detsetable measurements at specified locations is indicated in parentheses, (Fraction)
- rangs indicates no detectable activity measurements j A is equal to 0, then LLD is not required by Selected Licensee Conenitments
)fon 132 = Charlotte Municipal Water Supply (11.2 Mi SSE) Location 142 = Davidson Municipal Water Supply (7.5 Mi NE)
) ion 136=MooresvitteMunicipalWatersupply(12.5MiNNE) Location 194 = Lincoln County Water Supply (6.9 Mi NNW) l B-5
. ~.. . - - - .- - - .~ ~. . .
?.4 $URFACE WATER Environmental Radiological Monitoring Program Suenary Nales of Facility : McGuire Nuclear Station Docket Nudier : 50-369,370 loc 3tioncfFacility : Mecklenburg County, N.C. Reporting Period i 1 JAN-1994 through 31-DEC 1994 Time Report Generated : 12 JAN-1995 11:12:38 Database Name : $0lSK1:(USER. ASC]MNS94.SAF;104 l l l Location with Highest Mean l lNo.of Medlun er Type & Total l Lower l All Indicator l--------~~----------~~l l Non-Pathway. l Number of l Limitofl Locations l Name,DistanceandDirectionl Control Locations l Routine .
- Sampled l Analyses l Detection l Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) l Report
- (Units) l Performed l (LLD) l Range l Code Range l Range l Meas.
TE WATER l l l l l l
/ LITER) l l l l l 135 (12.0 Mi N) l 30tions l ANAL 1-LL 39 l 1.0 l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l V l l l 0.00E+00 ~ 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 l ,
l l l l128(0.4MiENE) l l l ANAL 2LL 39 l 1.0 l 0.38 ( 1/ 26) l 0.38' ( 1/ 13) l 0.00E+00( 0/ 13) l J l l l 0.38 - 0.38 l 0.38 -- 0.38 l 0.00E+00--0.00E+00l [
l l I I I 1 MN-54 39 l 15. l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 13) l 0.00F+00( 0/ 13) l 0 ,
l l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 0.00E+00~ 0.00E+00 l 1 I I l ;
lCo58 39l 15. l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 ;
j l 0.00E+00--0.00E+00l l 0.00E+00~ 0.00E+00 l 0.00E+00--0.00E+00l l 1 I I I l FE-59 39l 30. l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l 0.00E+00~ 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l ,
I I i l i I lCo-60 39 l 15. l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00~ 0.00E+00 l 0.00E+00 ~ 0.00E+00 l 0.00E+00 ~ 0.00E+00 l 1 I I I I -
l2N-65 39 30. l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00 ~ 0.00E+00 l 0.00E+00- 0.00E+00 l 0.00E+00--0.00E+00l l l 1 I i ! ;
lN8-95 39 l 15. l 6 00E400( 0/ 26)l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13)l 0 l l l 0.00E+0n" 9.00E+00 l 0.00E+00-0.00E+00l U.00E+00--0.00E+00l
> I I I I I I :
lZR-95 39l 15. l 0.00E+00( 0' 26) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00 ~ G.00E+00 l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 1 I I I I i lI-131 39l 15. l 0.00E+00( 0/ 26)l 0.00E+00( 0/ 13)l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 l 0.00E+00-0.00E+00l l l l l , 1 lCS134 39 l 15. l 0.00E+00( 0/ 26) [ 0.00E+00( 0/ 13) 0.00E+00( 0/ 13) 0 l l l 0.00E+00 ~ 0.00E+00 l 0.00E+00-- 0.00E+00 0.00E+00~ 0.00E+00 l I I I I I l CS-137 39 l 18. l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00~ 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 l l l 1 I I I lBALA-140 39l 15. l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 ,
l l l 0.00E+00 ~ 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l s... ~............................................................................... ~........................................
End rungs based upon detectable measurements only 31on of detectable measurements at specified locations is indicated in parentheses, (Fraction) range indicates no detectable activity measurements is equal to 0, then LLD is not required by Selected Licensee Comitments lon 128 = Discharge Canal Bridge (0.4 Mi ENE) Location 135 = Plant Marshall Intake Canal (12.0 Mi N) ,
ton 131 = Cowans Ford Dam (0.7 Mi W) l B-6 i
j
Environmental Radiological Monitoring Program Suunary i-
[: .
Name af Ftcility - : McGuire Nuclear Station Docket Number : 50-369,370 loc:tionofFacility : Mecklenburg County, N.C. Reporting Perlod : 1 JAN-1994 through 31-DEC 1994
$1meReportGenerated: 12 JAN-1995 11:12:38 Database Name : $0!SK1: lUSER. ASC]MN$94.SAF;104 p...............................................................................................r...............................
l l l l Location with Highest Mean l lNo.of Medium er Type & Total l Lowcr l All Indicator l----- ------ - -- ----
l l Non-Psth:=y l Nunber of l Lialtofl. Locations l Name,DistanceandDirectionl Control Locations lRouthe j sampled .
Analyses l Detection l Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) lRepcrt ]
(Units) l Performed l (LLD) l Range l Code Range l Range l Meat p............................................................................................................................... -
)lflUM l l l l l l fLITER). l l l l l l l l l l l 135 (12.0 Mi N) l htions H3 12l 2.00E+03l 0.00E+00( 0/ 8) l 0.00E+00( 0/ 4) l 0.00E+00( 0/ 4) l 0 l l l l 0.00E+00-- 0.00E+00 0.00E+00-- 0.00E+00 0.00E+00 0.00E+00 p................................................................l................................l........................l........
!and r&ngs based upon detectable measurements only I lon of detectacle measurements at specified locations is indicated in parentheses, (Fraction) l range indicates no detectable actlvity measurements
_is equal to 0, then LLD is not required by Selected Licensee Commitments f
hion128=DischargeCanalBridge(0.4MiENE) Location 135 = Plant Marshall Intake Canal (12.0 Mi N) lion 131 = Cowans Ford Dam (0.7 Mi W) f i
l l
B7 1
B.5 MILK Envirormental Radiological Konitoring Program Sunnary hoe of Facility : McGuire Nuclear Station Docket Nunber : 50-369,370 Locition af Facility : Mecklenburg County, N.C. Reporting Period : 1-JAN-1994 through 31-DEC 1994 time R? port Generated : 12-JAN-1995 11:12:38 Database Name : $0!$K1:(USER. ASC]MNS94.SAF;104
-l l l l Location with Highest Mean l l No. of 4edlun cr l Type & Total l Lower l All Indicator l"~---------~~~~-----~l l Non- I Pathway l Nurtaer of l Limitofl Locations l Name, Olstance and Direction Control Locations l Routine Sampled l Analyses l Detection l Mean (Fraction) l Location Mean (Fraction) Mean (traction) l Report (Units) l Performed l (LLD) l Range l Code Range l Range l Meas.
I I I I I I
/ LITER) l l l l l l l l l l l 141 (14.8 Mi WNW) l
- stions lMN54 104l 0.00E+00l 0.00E+00( 0/ 78) l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 26) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00- 0.00E+00 l 0.00E+00~ 0.00E+00 l 1 i l I I i 1 lCO-58 104l 0.00E+00l 0.00E+00( 0/ 78) l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 26) l 0
)
l l l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l !
I I I I I lFE-59 104l 0.00E+00l 0.00E+00( 0/ 78) l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 26)l 0 l l l l 0.00E+00~ 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 l 1 I I I I I lCo-60 104l 0.00E+00l 0.00E+00( 0/ 78) l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 26) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 l 1 I I I I i lZN-65 104l 0.00E+00l 0.00E+00( 0/ 78) l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 26) l_ 0 l l l 0.00E+00-0.00E+00l 0.00E+00 ~ 0.00E+00 l 0.00E+00--0.00E+00l 1 I I I I i lNB-95 104l 0.00E+00l 0.00E+00( 0/ 78) l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 26) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 l l l 1 I I I l2R-95 104l 0.00E+00l 0.00E+00( 0/ 78) l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 26) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 l l I I I I I lI-131 104l 15. l 0.00E+00( 0/ 78) l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 26) l 0 ,
j l l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l 1 I I I I I lLL1-131 104l 1.0 l 0.00E+00( 0/ 78) l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 26) l 0 l l l 0.00E+00~ 0.00E+00 l 0.00E+00 ~ 0.00E+00 l 0.00E+00--0.00E+00l l l l l l lCS-134 104l 15. l 0.00E+00( 0/ 78) 0.00E+00( 0/ 26) l 0.00E+00( 0/ 26) l 0 l l l 0.00E+00-- 0.00E+00 0.00E+00 ~ 0.00E+00 l 0.00E+00--0.00E+00l l l l l lCS-137 104l 18. l 0.00E+00( 0/ 78) 0.00E+00( 0/ 26) 0.00E+00( 0/ 26)l 0 l l l 0.00E+00-- 0.00E+00 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l 1 I I ,
i I lBALA-140 104l 15. l 0.00E+00( 0/ 78) l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 26) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l and rtnge based upon detectable measurements only
- ion of detsctable measurements at specified locations is indicated in parentheses, (Fraction) rangt indicates no detectable activity measurements D is equal to 0, then LLD is not required by Selected Licensee Conimitments ion 138 = Henry Cook Dairy (2.75 Mi ESE) Location 140 = Kidd Dairy (COWS (2.8 Mi SSE) ion 139 = William Cook Dairy (2.6 Mi E) Location 141 = Lynch Dairy - COWS (14.8 Mi WNW)
B-8 l
k i.6BROADLEAFVEGETATION Environmental Radiological Monitoring Program Surunary ,
same of_Ftcility : McGuire Nuclear Static 9 Docket Number : 50-369,370
.ocation of Facility : Mecklenburg County, N.C. Reporting Period : 1 JAN 1994 through 31-DEC 1994 rime Report Generated : 12-JAN 1995 11:12:38 Database Name $0!SK1:IUSER. ASC]MNS94.SAF;104 l l l l Location with Highest Mean l lNo.of ledium er l' Type & Total l Lower l All Indicator l---- ---------- .-- ----- -
-l l Non-Pathway l Number of l Limitofl Locations l Name,DistanceandDirectionl Control Locations l Routine Sampled l Analyses l Detection l Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) l Report (Units) l Performed l (LLD) l Range l Code Range l Range l Meas.
>LEAFYEGETl l l l l l MT/KG) l l l l l l l l l l l 134 (8.7 MI WNW) l
$tions lMN54 42l 0.00E+00l 0.00E+00( 0/ 31) l 0.00E+00( 0/ 11) l 0.00E+00( 0/ 11) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l I I I I I I lCO-58 42 l 0.00E+00l 0.00E+00( 0/ 31)l 0.00E+00( 0/ 11) l 0.00E+00( 0/ 11)l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 1 1 I I I I lFE-59 42 l 0.00E+00l 0.00E+00( 0/ 31) l 0.00E+00( 0/ 11) l 0.00E+00( 0/ 11) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 1 I I I I I lCo-60 42 l 0.00E+00j 0.00E+00( 0/ 31) l 0.00E+00( 0/ 11) l 0.00E+00( 0/ 11)l 0 l l l 0.00E+00--0.00E+00l 0.00E+00.-0.00E+00l 0.00E+00--0.00E+00l l 1 1 I I I l2N65 42l 0.00E+00l 0.00E+00( 0/ 31) l 0.00E+00( 0/ 11) l 0.00E+00( 0/ 11) l 0 l l l 0.00E+00- 0.00E+00 l 0.00E+00-0.00E+00l 0.00E+00--0.00E+00l l l l 1 I I lNB95 42 l 0.00E+00l 0.00E+00( 0/ 31) l 0.00E+00( 0/ 11) l 0.00E+00( 0/ 11) l 0 l 0.00E+00--0.00E+C0l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l I I - 1 I I lZR95 42 l 0.00E+00 0.00E+00( 0/ 31) l 0.00E+00( 0/ 11) l 0.00E+00( 0/ 11) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l 0.00E+00--0.00E+00l I I I I I I lI-131 42l 60. l 0.00E+00( 0/ 31) l 0.00E+00( 0/ 11) l 0.00E+00( 0/ 11) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l l l 1 I I lCS134 42 l 60. l 0.00E+00( 0/ 31) l 0.00E+00( 0/ 11) l 0.00E+00( 0/ 11)l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l I I I I I lCS137 42 l 80. l 0.00E+00( 0/ 31) l 0.00E+00( 0/ 11) l 0.00E+00( 0/ 11)l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l l 1 1 I I lBALA-140 42 l 0.00E+00l 0.00E+00( 0/ 31) l 0.00E+00( 0/ 11) l 0.00E+00( 0/ 11) l 0 l
l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l cnd range based upon detectable measurements only ,
ion of detsctable measurements at specified locations is indicated in parentheses, (Fraction) l ftngi irdicates no detectable activity measurements
@ is equal to 0, then LLD is not required by Selected Licensee Commitments ion 120 = Site Boundary (0.4 Mi NNE) Location 134 = East Lincoln Junior High School (8.7 Mi WNW)
-lon 125 = Site Boundary (0.4 Mi SW) Location 193 = Site Boundary (0.3 Mi N) l B-9 l I
).7 SNORELINE SEDIMENT Environmental Radiological Monitcring Program Suenary lame cf Facility : McGuire Nuclear Station Docket Nudwr : 50 369,370 ectionofFacility : Mecklenburg County, N.C. Reporting Period : 1 JAN-1994 through 31-DEC-1994
!ime Report Generated : 12-JAN 1995 11:12:38 Database Name $0!SK1:(USER.ASC]MNS94.SAF;104 l l l l Location with Highest Mean l lNo.of diumor l Type & Total l Lower l All Indicator l---------------*--*---------l l Non-Dathway. l Number of l Limitofl Locations l Name,DistanceandDirectionl Control Locations l Routine
- Oampled l Analyses. l Detection l Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) l Report Range Range 4 Units) l Performed l (LLD) l Range l Code l l Meas.
ERY/KG) l l l l l l l l l l l130(0.6MiSW) l 137 (12.0 Mi N) l i htions lMN-54 6l 0.00E+00l 41. ( 1/ 4) l 41. ( 1/ 2) l 0.00E+00( 0/ 2) l 0 l l l l 41. -- 41, [ 41. --
- 41. l 0.00E+00--0.00E+00l 1 I I I I I lCO-58 6l 0.00E+00l 0.00E+00( 0/ 4) l 0.00E+00( 0/ 2) l 0.00E+00( 0/ 2) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l 1 I I I I lFE-59 61 0.00E+00l 0.00E'+00( 0/ 4) l 0.00E+00( 0/ 2) l 0.00E+00( 0/ 2) l 0 l ,
l 0.00E+00--0.00E+00l 0.00E+00- 0.00E+00 l 0.00E+00--0.00E+00l 1 i l i i i i lCo-60 ,i 0.00E+00l 0.00E+00( 0/ 4) l 0.00E+00( 0/ 2) l 0.00E+00( 0/ 2) l 0 l l l l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l 0.00E+00--0.00E+00l l l t I I I l' lZN-65 6l 0.00E+00l 0.00E+00( 0/ 4) l 0.00E+00( 0/ 2) l 0.00E+00( 0/ 2) l 0 l l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l j 1
l I I I I I l
N8 95 6l 0.00E+00l 0.00E+00( 0/ 4) l 0.00E+00( 0/ 2) l 0.00E+00( 0/ 2) l' 0 l
l l l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l 0.00E+00--0.00E+00l l l l l l ZR-95 6l 0.00E+00l 0.00E+00( 0/ 4) l 0.00E+00( 0/ 2) l 0.00E+00( 0/ 2) l 0 l
l l l 0.00E+00- 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l I I I I I I lI-131 6l 0.00E+00l 0.00E+00( 0/ 4) l 0.00E+00( 0/ 2) l 0.00E+00( 0/ 2) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 l 0.00E+00--0.00E+00l l l l I I I lCS-134 6l 1.50E+02l 0.00E+00( 0/ 4) l 0.00E+00( 0/ 2) l 0.00t+00( 0/ 2) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l l l l130 l l lCS137 6l 1.80E+02l 8C, ( 2/ 4) l 80. ( 2/ 2) l 0.00E+00( 0/ 2) l 0 l l l 62. -- 99. l 62. --
- 99. l 0.00E+00--0.00E+00l 1 1 I I I I lBALA-140 6l 0.00E+00l 0.00E+00( 0/ 4) l 0.00E+00( 0/ 2) l 0.00E+00( 0/ 2) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00 ~ 0.00E+00 l 0.00E+00--0.00E+00l landrangebcsedupondetectablemeasurementsonly lion of detectable measurements at specified locations is indicated in parentheses, (Fraction) ranga irdicates no detectable activity measurements is equal to 0, then LLD is not required by Selected Licensee Comitments lon 129 = Discharge Canal Entrance to Lake Norman (0.6 Mi ENE) Location 137 = Pinnacle Access Area (12.0 Mi N) icn 130 = Highway 73 Bridge Downstream (0.6 Mi SW)
B-10
.8 FISH Environmental Radiological Monitoring Pragram Stanary of Facility McGuire Nuclear Station Docket Number : 50-369,370 ocation of Facility : Mecklenburg County, N.C. Reporting Period : 1-JAN-1994 through 31 DEC-1994 les eteport Generated : 12-JAN 1995 11:12:38 Database Name : S0!SK1:(USER.ASC]MNS94.SAF;104 l l l l Location with Highest Mean l lNo.of
'Jedium or l Type &fotall Lower l All Indicator l-------------~~---------l l Non-Pathway l Number of l Limitofl Locations l Name,OfstanceanoDirectionl Control Locations l Routine Sampled l Analyses l Detection l Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) l Report (Units) l Performed l (LLO) l Range l Code Range l Range l Meas.
g...............................................................................................................................
l l l l l l 1 T/KG) l l l l l l l l l l l 137 (12.0 Mi N) l atIons lMN54 12l 1.30E+02l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0 l l l 0.00E+00 ~ 0.00E+00 l 0.00E+00~ 0.00E+00 l 0.00E+00 ~ 0.00E+00 l l l l l l 1 lCo58 12l 1.30E+02l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0 l l l 0.00E+00 ~ 0.00E+00 l 0.00E+00-0.00E+00l 0.00E+00 ~ 0.00E+00 l 1 I I I i l lFE-59 12l 2.60E+02l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0 l l l 0.00E+00~ 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 l l l l l l l lCo60 12l 1.30E+02l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00 ~ 0.00E+00 l 0.0CE+00~ 0.00E+00 l l l l l l I lZN65 12l 2.60E+02l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 l l 1 I I I I 12l 0.00E+00l 0.00E+00( 0/ 6) l 0/ 6) l 0.00E+00( 0/ 6) l '
lNS-95 0.00E+00( 0 l l l 0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l I I I I I I l2R95 12l 0.00E+00l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 l 0.00F+00 ~ 0.00E+00 l l l l 1 I I ll-131 12l 0.00E+00l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l l l l l l lCS134 12l 1.30E+02l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0 ,
l l l 0.00E+00 ~ 0.00E+00 l 0.00E+00-0.00E+00l 0.00E+00 ~ 0.00E+00 l l l l l 129 (0.9 Mi ENE) l l lCS-137 12l 1.50E+02l 31. ( 2/ 6) l 31. ( 2/ 6) l 0.00E+00( 0/ 6) l 0 l l l 30. - 33. l 30. --
- 33. l 0.00E+00~ 0.00E+00 l l l l l 1 l lBALA-140 12l 0.00E+00l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00 ~ 0.00E+00 l 0.00E+00-0.00E+00l and range based upon detectable measurements only llon of detectable measurements at specified locations is indicated in parentheses, (Fraction) range indicates no detectable activity measurements
,0 is equal to 0, then LLD is not required by Selected Licensee Conunitments lion 129 = Discharge Canal Entrance to Lake Norman (0.6 Mi ENE) lion 137 = Pinnacle Access Area (12.0 Mi N)
B-11
)
_wahwm
B.9 DIRECT GAfstA RADIATION Environmental Radiological Monittring Program Sumnery Name af Facility : McGuire Nuclear Station Docket Number : 50-369,370 Loc. tion of Facility : Mecklenburg County, N.C. Reporting Period : 1.JAN-1994 through 31 DEC-1994 Time Report Generated : 12.JAN.1995 11:16:50 Database Name : SDISK1:(USER.ASC]MNS94.SAF;104 l l l l Location with Nighest Mean l lNo.of Medlun or l Type & Total l Lower l All Indicator l-..-.-...--..........-...-.-...l l Non.
Pathway l Nunber of l.Limitofl Locations l Name,DistanceandDirectionl Control Locations Routine Sanpled l Analyses l Detection l Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) Report (Units) l Performed l (LLD) l Range l Code Range l Range Meas.
IRECT RAD TLD l l l l l l .
e/Quartsc) l l l l l l I
l l l l164(4.5MiSSE) l 175 (12.7 Mi WNW)
I Locations lMR/Qtr 181l 0.00E+00l 18. (177/177)l 42. ( 4/ 4) l 24. ( 4/ 4) l 0 l l l 12. --1.32E+02l 12. --1.32E+02l 22. --
- 25. l pan and range based upon detectable measurements only ction of detectable measurements at specified locations is indicated in parentheses, (Fraction) tra rangi indicates no detectable activity measurements F LLD is equal to 0, then LLD is not required by Selected Licensee Connitments m:, tion 143 = SITE BOUNDARY (0.3 Mi NW) Location 167 = 4-5 MILE RADIUS (4.9 Mi SW) 2xtfon 144 = SITE BOUNDARY (0.4 Mi NNE) Location 168 = 4-5 MILE RADIUS (4.7 Mi WSW) xstion 145 = SITE BOUNDARY (0.5 Mi NE) Location 169 = 4-5 MILE RADIUS (4.4 Mi w)
- ation 146 = SITE BOUNDARY (0.5 MI ENE) Location 170 = 4-5 MILE RADIUS (4.5 Mi WNW) motion 147 = SITE BOUNDARY (0.4 Mi E) Location 171 = 4-5 MILE RADIUS (4.5 Mi NW) totion 148 = SITE BOUNDARY (0.5 Mi ESE) Location 172 = 4-5 MILE RADIUS (5.2 Mi NNW) tion 149 = SITE BOUNDARY (0.6 Mi SE) Location 173 = SPECIAL INTEREST (8.5 Mi NNW) tion 151 = SITE BOUNDAR*, (0.4 Mi S) Location 174 = SPECIAL INTEREST (8.7 Mi WNW) tion 152 = SITE BOUNDARY (0.5 Mi SSW) Location 175 = CONTROL (12.7 Mi WNW)
%ction153=SITEBOUNDARY(0.5MiSW) Location 176 = SPECIAL INTEREST (11.0 Mi SW) bation 154 = SITE BOUNDARY (0.5 MI W) Location 177 = SPECIAL INTEREST (8.6 Mi S)
$stion156=SITEBOUNDARY(0.5MiWNW) Location 178 = SPECIAL INTEREST (9.2 Mi SE) betion 157 = 4-5 MILE RADIUS (4.8 Mi N) location 179 = SPECIAL INTEREST (10.4 Mi ESE) betion 158 = 4-5 MILE RADIUS (4.4 Mi NNE) Location 180 = SPECIAL INTEREST (11.5 Mi NNE) hation159=4-5MILERADIUS(5.0MINE) Location 181 = SPECIAL INTEREST (6.7 Mi NE)
$stion 160 = 4-5 MILE RADIUS (4.9 Ml ENE) Location 182 = SPECIAL INTEREST (6.0 Mi NE)
$ation 161 = 4-5 MILE RADIUS (4.7 Mi E) Location 183 = SPECIAL INTEREST (5.5 Mi S) isation 162 = 4 5 MILE RADIUS (4.6 Mi ESE) Location 186 = SPECIAL INTEREST (0.2 Mi NNW)
$stion163=4-5MILERADIUS(5.0 MISE) Location 187 = SPECI AL INTEREST (0.3 Mi N)
Estion 164 = 4 5 MILE RADIUS (4.5 Mi SSE) Location 189 = SITE BOUNDARY (0.4 ml sse) petion 165 = 4 5 MILE RADIUS (5.0 Mi S) Location 190 = SITE BOUNDARY (0.5 m! wsw) bation 166 = 4-5 MILE RADIUS (5.2 Mi SSW) Location 191 = SPECIAL INTEREST (2.8 Mi NNE)
Location 1% = SPECIAL INTEREST (1.0 Mi S)
Location 197 = SPECIAL INTEREST (1.12 Mi S)
Location 198 = SPECIAL INTEREST (1.35 Mi S Location 199 = SPECIAL INTEREST (1.49 Mi S) i i
f B-12 l
)
l
l.10 FOOD PRODUCTS Environmental Radiological Monitoring Program Sumnery Isme cf facility : McGuire Nuclear Station Docket Nun 6er : 50 369,370 ;
.oc: tion of Facility : Mecklenburg County, N.C. Reporting Period : 1-JAN-1994 through 31-DEC 1994 ime Report Generated : 12 JAN-1995 11:12:38 Database Name : S0!SK1:[ USER. ASC]MNS94.SAF;104 ,
l l l l Location with Highest Mean l No. of ledium or l Type & Total l Lower l All Indicator l----~~---~~-~~--~--~l Non-Pathway l Number of l Limit of Locations l Name,DistanceandDirectionl Control Locations l Routine Sampled l Analyses l Detection Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) l Report (Units) l Performed l (LLD) l Range l Code Range l Range l Meas.
I I I I I I
' WET /KG) l l l l l l l l l lNoControlLocationsl ctions MN-54 16l 0.00E+00l 0.00E+00( 0/ 16) l 0.00E+00( 0/ 12)l 0.00E+00( 0/ 0) l 0 l l 0.00E+00 ~ 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 l l l 1 I I lCo-58 16[ 0.00E+00l 0.00E+00( 0/ 16)l 0.00E+00( 0/ 12) l 0.00E+00( 0/ 0) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l 1 I I I I I lFE-59 16l 0.00E+00l 0.00E+00( 0/ 16) l 0.00E+00( 0/ 12) l 0.00E+00( 0/ 0) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l 1 I I I I lCo-60 16 l 0.00E+00l 0.00E+00( 0/ 16) l 0.00E+00( 0/ 12) l 0.00E+00( 0/ 0) l 0 l l l 0.00E+00 ~ 0.00E+00 l 0.00F+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l l 1 I I i lZN-65 16l 0.00E+00l 0.00E+00( 0/ 16) l 0.00E+00( 0/ 12) l 0.00E+00( 0/ 0) 0 l l l 0.00E+00~ 0.00E+00 l 0.00E+00- 0.00E+00 l 0.00E+00-0.00E+00l l 1 I I I I lN895 16l 0.00E+00l 0.00E+00( 0/ 16) l 0.00E+00( 0/ 12) l 0.00E+00( 0/ ' 0) l 0 l l l 0.00E+00~ 0.00E+00 l 0.00E+00 ~ 0.00E+00 l 0.00E+00--0.00E+00l 1 1 I I I ZR-95 16l 0.00E+00l 0.00E+00( 0/ 16) l 0.00E+00( 0/ 12) 0.00E+00( 0/ 0) l 0 l l l 0.00E+00~ 0.00E+00 l 0.00E+00 ~ 0.00E+00 0.00E+00~ 0.00E+00 l '
l l l l \ \
lI131 16l 60. l 0.00E+00( 0/ 16) l 0.00E+00( 0/ 12) l 0.00E+00( 0/ 0) [ 0 l l l 0.00E+00~ 0,00E+00 l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l l l 1 1 I I lCS-134 16l 60. l 0.00E+00( 0/ 16)l 0.00E+00( 0/ 12) l 0.00E+00( 0/ 0) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l 0.00E+00--0.00E+00l 1 1 I I i l lCS137 16 l 80. l 0.00E+00( 0/ 16)l 0.00E+00( 0/ 12)l 0.00E+00( 0/ 0) l 0 l l l 0.00E+00~ 0.00E+00 l 0.00E+00 ~ 0.00E+00 l 0.00E+00~ 0.00E+00 l l l l l l l lBALA-140 16 l 0.00E+00l 0.00E+00( 0/ 16) l 0.00E+00( 0/ 12) l 0.00E+00( 0/ 0)l 0 l l l 0.00E+00~ 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00 ~ 0.00E+00 l and range based upon detectable measurements only lon of detectable measurements at specified locations is indicated in parentheses, (Fraction) ringa indicates no detectable activity measurements 3 is equal to 0, then LLD is not required by Selected Licensee Commitments ton 184 = 5 Mlle Radius (2.5 Mi ENE) - Gardens (Davenport's Residence) lon 188 = 5 Mile Radius (2.8 Mi N) - Gardens (Austin's Residence)
P B-13 a
1 APPENDIX C l SAMPLING DEVIATIONS AND UNAVAILABLEANALYSES 1
1994 l
1 C-1 l
APPENDIX C MCGUIRE NUCLEAR STATION SAMPLING DEVIATIONS AND UNAVAILABLE ANALYSIS L SAMPLING DEVIA110NS l
I The following deviations from sampling requirements occurred during 1994:
5 ISarhgde] ' [l$ation$ .[SclAdukEI) AbithlCollediAni '
UDMation? '
casonj' '
~ Action ** , " , ,
m ye? t Collection Dates L SuDatesY , sf Air Particulates 134 5/31-6/7/94 5/31-6/1/94 Sample did not collect for entire 7 No power due to lightning striking Notified Rutherforton Electric.
and day period. power line. Power was restored between Cn &
Air Radiodines 6/14.
l 6/14-6/21/94 6/14-6/15/94 Sample did not collect for entire 7 Blown fuse. Replaced fuse and tagged sampler l
day period. LVAS #6.
l n 7/19-7/26/94 7/19-7/21/94 Sample did not collect for entire 7 Blown fuse. Replaced fuse in sampler #6.
l " day period.
l 10/18-10/25/94 10/18-10/22/94 Sample did not collect for entire 7 Iess of power to srmple station. Reported to responsible personnet day period.
10/25-11/1/94 10/28-11/1/94 Sample did not collect for entire 7 Power was shut down to install Power switched on 10/28/94.
day period. power poles.
l I1/1-11/8/94 11/1-11/2/94 Sample did not collect for entire 7 Blown fuse. Replaced fuse in sampler #6.
day period.
I1/22-11/29/94 11/22-11/24 Sample did not collect for entire 7 Power was turned off at the breaker, Restored power.
day period. probably due to vandalism.
I1/29-12/6/94 11/29-12/4/94 Sample did not collect for entire 7 Blown fuse. Replaced fuse in sampler #6.
day period.
192 5/10-5/17/94 5/10-5/14/94 Sample did not collect for entire 7 Dlown fuse. Replaced fuse.
day period.
195 6/14-6/21/94 6/14-6/16/94 Sample did not collect for entire 7 Power supply to -ampler failed. Notified Dennis Scronce to day period. investigate.
S2rnpic i ination - f Scheduled Actual CollectionT i Deviationl ?Reasoni '
f sus Type Collection Datesi . Dates . >
Air Particulates 195 6/21-6/28/94 6/23-6128/94 Sample did not collect for entire 7 Breaker was not reset due to Breaker reset & power restored on and day period. unfamiliarity with new site. 6/23/94.
Air Radiodines 9/6-9/13/94 9/6-9/10/94 Sample did not collect for entire 7 Sampler malfunction. Replaced samplcr LVAS #13.
day period.
r Drinking Water 142 9/27-10/11/94 9/27-10/3/94 Sariple did not collect for entire 2 Water plant closed on 10/3/94. A replacement sampling location has week period. been selected in Mt. Ilolly.
Equipment to be installed at later date.
l 194 12/20-l/4/94 1/4/94 No sample available. Sample site is not in service due to Commodities and facility personnel problem with interval timer. have been notified.
I 1/4-1/18/94 1/18/94 No sample available. Sample site is not in service due to Commodities and facility personnel l problem with interval timer. have been notified.
ca 1/18-2/1/94 2/1/94 No sample available. Sample site is not in service due to Commodities and facility personnel i problem with interval timer. have been notified.
l 2/1-2/15/94 2/15/94 No sample available. Sample site is not in senice due to Commodities and facility personnel l problem with interval timer. have been notified. ,
l 2/15-3/1/94 2/18-3/1/94 Sample did not collect for entire 2 Sampler was out of service until Sampler was repaired on 2/18.
week period. , 2/18.
l l
l l Surface Water 128 6/7-6/21/94 6/7-6/20/94 Sample did not collect for entire 2 Pump out of service. Notified Dennis Scronce on 6/21.
week period.
l l
6/21-7/5/94 6/28-7/5/94 Sample did not collect for entire 2 Loss of power to pump. Power was restored on 6/28.
week period.
I31 1
1/4-1/18/94 1/18/94 No sample available. Sample lines are probably frozen. Contacted maintenance. Collected a grab sample.
1/18-2/1/94 2/1/94 No sample available. Sample lines burst. Contacted maintenance. CoUected a grab sample.
i P / . .
l nn -
w m;s , ,g ng / l Yhctical'I'm W
' Reason ,' %
$ahI '
I [Idation1 ^ !SchStilidi ActualCollSction? r -
$idsilaffod$ . .s
' Ojpei
? Collection Dates" + Dates" ' ^
x -f8E P<
Surface Water 131 2/1-2/15/94 2/15/94 No sample available. Frozen sample lines and pump New pump was ordered. Grab malfunction. sample collected.
2/15-3/1/94 2/21-3/1/94 Sample did not collect for entire 2 Pump being repaired. Sampler rett:rned to service on 2/21.
week period.
Sample did not collect for entire 2 Damaged pump. Pump repaired and returned to
( 3/1-3/15/94 3/11-3/15/94 week period. service on 3/11.
i l
6/7-6/21/94 6/16-6/21/94 Sample did not collect for entire 2 Pump was moved to a floating Pump was restarted on 6/16. An week period. platform. abbreviated sample was collected.
135 5/24-6/7/94 6/7/94 No sample available. Equipment failure. Contacted maintenance. Collected grab sample.
6/7-6/21/94 6/9 4/21/94 Sample did not collect for entire 2 Pump malfunctioned. New pump was installed on 6/9. An week period. abbreviated sample was collected.
O S.
9/13-9/27/94 9/27/94 No sample available. Power loss to sample station. Notified Dennis Schronce.
Collected grab sample.
9/27-10/1I/94 10/3-10/11/94 Sample did not collect for entire 2 Loss of power to sample station due Problem found and power restored.
week period. to installation of power poles.
ILD 166 9/26-12/29/94 10/18-12/29/94 Sample did not stay in field for full TLD was reported missing on A replacement TLD was placed in quarter. 10/11/94. field on 10/lR/94.
MCGUIRE NUCLEAR STATION IL UNAVAILALLE ANALYSES The following unavailable analyses occurred during 1994:
e esp ;g ' : : ;@ a.gf .ggg gg::;ggg
- f sc% M '[ y p.4 ... qp 5 % p ,'s 3M;g3 ' ggy '^
y +y5
'y';
' ' ' ,>tjegseg$g,_ ., 7 mys ggphfgge 3~~Eg,.y g t$?y :- Q' im mew s S $dendidedi; s , , gl 4[$y$ sini empic"~1.dc Ml4 S ~'x '
W-ynsi ! 0 946 Op8ectknillaissi '
'~?'
:!!M < t "F ibME J 5:." '
~
49 w O
6n-6/14/94 No sample available. Power failure due tolightning Power restored between 60 & 6/14.
& Air Particulates 134 stniang power line. Sampler switch and Air Radioiodines left off.
12/6-12/13/94 Sample didnot collect for entire 2 Blown fuse. Replaced sampler LVAS #6 with week period. (2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> only) LVAS #16.
7
_d,-:
- g s m e
~
. .s s 3/28-6/27/94 TLD not available. Missing at time ofcollection. 3rd Qtr TLD was placed in field.
TLD 159 179 9/26-12/29/94 ILD not available. Missing at time ofcoIIection. Ist Qtr 1995 ILD was placed in field.
1R7 3/28-6/27/94 TLD not available. Missing at time of collection. 3rd Qtr TLD was placed in field.
t c
t
_s .s_ . _ - - _ . _ _ _ _ . _ . _ . _ . _ _ _ _ . _ _ _ _ . _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ - - . -- , -e . ..m--- i.
APPENDIXD ANALYTICAL DEVIATIONS LOWER LIMITS OFDETECTION l
I No analytical deviations were incurred for the 1994 environmental sampling program.
D-1
l l
I 1
j APPENDIXE 1 l
i RADIOLOGICAL ENVIRONMENTAL l
MONITORING PROGRAM RESULTS 1
1994 This appendix includes all of the sample analysis reports generated from each sample medium for 1994. Appendix E is located separately from this report and is permanently archived at Duke Power Company's Environmental Center radiological environmental data master file, located at the McGuire Nuclear Station Site in Huntersville, NC.
(
E-1
i 1
4 i
l l
i i
l I
5 k
6 L_.