ML20073H408: Difference between revisions
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| number = ML20073H408 | | number = ML20073H408 | ||
| issue date = 12/31/1990 | | issue date = 12/31/1990 | ||
| title = Annual Radiological Environ Operating Rept for Units 1 & 2 for 1990 | | title = Annual Radiological Environ Operating Rept for Units 1 & 2 for 1990 | ||
| author name = Tuckman M | | author name = Tuckman M | ||
| author affiliation = DUKE POWER CO. | | author affiliation = DUKE POWER CO. | ||
Latest revision as of 10:49, 20 May 2020
| ML20073H408 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 12/31/1990 |
| From: | Tuckman M DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9105070106 | |
| Download: ML20073H408 (939) | |
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, DUKE POWER April 29, 1991 ~4 U . S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555
Subject:
McGuire Nuclear Station Docket Numbers 50-369 and -370 Annual Radiological Environmental Operating Report Pursuant to McGuire Nuclear Station's Technical Specifications, attached is the Annual Radiological Environmental Operating Report for calender year 1990. Very truly yours, e S' m M. S. Tuckman areor/ sag cc: Mr. P. K. Van Doorn Senior Resident Inspector McGuire Nuclear Station Mr. T. A. Reed, Project Manager Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 9H3, OWFN Washington, D. C. 20555 Mr. S. D. Ebneter Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900
~ Atlanta, Georgia 30323
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U. S. Nuclear Regulatory Commission i April 29, 1991 Page 2 Amarican Nuclear Insurers c/o Dottie Sherman, ANI Library The Exchange, Suite 245 270 Farmington Avenue Farmington, Cf 05032 Mr. Dayne Brown Department of Environment, Health, and Natural Resources Division of Radiation Protection P. O. Box 27687 Raleigh, North Carolina 27611-7687 9
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e-.- A a-. I I I ! I . I ANNUAL RADIOLOGICAL g ENVIRONMENTAL OPERATING REPORT I , I
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for li ! DUKE POWER COMPANY 'l McGuire Nuclear Station Units 1 and 2 I l l E l I January 1 - December 31 i 1990 I l I
t - 1 TABLE OF CONTENTS I I TITLE PAGE List of Figures . . . . . . . . . . iv List of Tables . . . . . . . . . . v
- 1. Executive Summary 1-1 i
- 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 g 2.3.3 Trend Identification . . . . . 2-11 5 3. Radiological Environmental Monito-ing Program - Discussion, Interpretation, and Tronding of Results . . . . . 3-1 3.1 Airborne Radiolodines and Particulates . . . . 3-2 3.1.1 Radiolodines . . . . . . 3-2 3.1.2 Particulates . . . . . . . 3-4 3.2 Drinking Water . . . . . . . . . 3-6 3.3. Surface Water I 3.4 Milk . .
3-11 3-16 3.5 Broadleaf Vegetation . 3-18 I 3.6 Shoreline Sediment . . . . . . . . 3-20 3.7 Fish. . . . . . . . . . . 3-22 3.8 Direct Gamma Radiation . . , . . . . 3-26 3.9 Food Product . . . . . . . . . 3-28 3.10 Land Use Census . . . . . . . . 3-30 t i i B
l TABLE OF CONTENTS (Continued) I
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TITLE PAGE I 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 . . . . . . 4-2 4.4 Pathway Dose Calculations . . . . . 4-2
- 5. Quality Assurance . . . . . . . . . 5-1 5.1 Duke Power Company's Environmental Laboratories . 5-1 5.2 Contractor Laboratory 5-7 I 6. References . . . .
. 6-1 Appendix A: Environmental Sample and Analysis Proceduros - Summary A-1 I A.1 A.2 Airborne Radiolodines and Particulates Drinking Water . . . . .
A-1 A-2 A.3 Surface Water . . . . . . . . A-2 A.4 Milk . . . . . . . . . . A-2 A.5 Broadlea r v egetation . . . . . . A-2 A6 Shoreline Sediment . . . . . . . A-2 I A.7 A8 Fish . . . Direct Gamma Radiation A-2 A-3 A.9 Food Products . . . . . . . . A-3 A.10 Land Use Census . . . . . . . A-3 I I I I I u
lI TABLE OF CONTENTS g (Continued) I TITLE PAGE I Appendix B: Radiological Environmental Monitoring Program - Summary of Results . . . . . . . B-1 B.1 Radiciodines . . . . . . . . . B-2 B.2 Particulates . . . . . . . . . B-3 B.3 Drinking Water . . . . . . . . . D-4 B.4 Surface Water . . . . . . . . . B-6 B 5 Milk . . . . . . . . . . . B-8 i B.6 Broadleaf Vegetation B.7 Shoreline Sediment B.8 Fish . . . B-9 B-10 B-11 B.9 Direct Gamma Radiation . . . . . . . B-12 B.10 Food Products . . . . . . . . . B-13 Appendix C: Sampling Deviations and Unavailable Analyses . . C-1 1 ^> ~ ~ -- o-u - - - < o-- - o-> Appendix E: Radiological Environmental Monitoring Program Results E-1 g I I I I I I =
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I UST OF FIGURES lI FIGURE TITLE PAGE I 1 Sampling Locations Map (2500 ft. radius) . . . . 2-5 1 2 Sampling Locations Map (ten-mile radius) . . . . 2-6 3 Concentration of Radionuclides in Drinking Water . . 3-6 4 Concentration of Radionuclides in Shoreline Sediment . 3-20 f 5 Concentration of Radionuclides in Fish . . . . 3-25 i 6 .TLD Exposure from Direction Radiation . . . . 3-27 I lI I I I Lg lI .I lI I l
lI LIST OF TABLES I FIGURE TITLE PAGE 2.1-A McGuire Radiological Monitoring Program Sampling Locations . . . . . . . . . . 2-4 2.1 - B McGuire !tadiological Monitoring Program TLD Locations . 2-5 2.2-A Maximum Values for the Lower Limits of Detection . . 2-8 1 2.2-B Reporting Levels for Radioactivity Concentration in Environmental Samples . . . . . . . 2-9 2.2-C McGuire Radiological Monitoring Program Analyses . . 2-10 3.1.1- A Concentration of Radionuclides in Airborne Radiolodines . 3-3 3.1.1 - B Percentages of Reporting Levels for Radiolodines . . 3-2 3.1. 2- A Concentration of Radionuclides in Airborne Particulates . 3-5 3.1.2-B Percentages of Reporting Levels for Particulates . . 3-4 3.2-A Concentration of Radionuclides in Drinking Water . . 3-8 I 3.2-B
- 3. 3- A Percentages of Reporting Levels for Drinking Water .
Concentration of Radionuclides in Surface Water . 3-7 3-13 3.3-B Percentages of Reporting Levels for Surface Water . . 3-12 I 3.4- A 3.4-B Concentration of Radionuclides in Milk Percentages of Reporting Levels for Milk . 3-17 3-16 3.5-A Concentration of Radionuclides in Broadleaf Vegetation . 3-19 3.5-B Percentage of Reporting Levels for Broadleaf Vegetation . 3-18 l 3.6-A 3.6-B Concentration of Radionuclides in Shoreline Sediment Percentages of Reporting Levels for Shoreline Sediment 3-21 3-20 3.7-A Concentration of Radionuclides in Fish . . . . 3-23 3.7-B Percentages of Reporting Levels for Fish . . . . 3-22 g 3. 8- A TLD Exposure from Direct Radiation . . . . . 3-26 m 3.9-A Concentration of Radionuclides in Food Products . . 3-29 3.9-B Percentages of Reporting Levels for Food Products . . 3-28 5.1 U.S. E.P. A. Interlaboratory Comparison Program - 1990 Cross Check Results for the ERL , . . . . 5-8 5.2 North Carolina Department of Environmental Health and Natural Resources Environmental Dosimeter Crosscheck-1990. 5-10 I Y w
1 I l E 1.0 EXECUTIVE
SUMMARY
I This Annual Radiological Environmental Operating Report describes the l McGuire Nuclear Station Radiological Environmental Program and the results I of the program for the calendar year 1990. Included in the report are identification of sampling locations, descriptions I of environmental sampling and analysis procedures, comparisons of present environmental radioactivity levels and preopntational environmental data, i analysis of trends in the environmental rad!oactivity levels sirwe the E beginning of station operation, comparisons of doses calculded from 5 environmental measurements and doses calculated from effluent data, a summary of the results of the 1990 program, discussion of the results, and l I discussion of the quality assurance activities associated with the program. Deviations from program requirements are also included. Supplemental samples also were taken in addition to the required sampling locations. Sampling activities were . conducted as prescribed by Technical Specifications. Required analyses were performed and detection capabilities met Technical Specification requirements. Supplemental samples also were ' taken in addition to the required sampling locations. Concentrations observed in the environment in 1990 for station related I 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 1 Commission (NRC) and given in Technical Specifications. I Statistical analysis of lata indicates that McGuire Nuclear Station has contributed to the tritium (11-3) concentration in drinking water; the i probability for increasing the trend was high to moderate. However,the 1990 drinking water H-3 concentration was a small fraction of the reporting level and the maximum annual dose contribution was only 0.0125 mrem. All
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I other possible trends had moderate to no probability. It can be concluded that the contribution of McGuire to the radioactivity in the environment is slight . l I I I I I l 1-1
I I
2.0 INTRODUCTION
I g 2.1 SITE DESCRIPTION AND SAMPLE LOCATIONS McGuire Nuclear Station is located geographically near the center of the I highly industriallred 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 I 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 l the Catawba River channel and to the north by the 32,510 acro Lake i I Norman. Lake Norman is impounded by Duke Power Company's Cowans Ford ! Dam Hydroelectric Station, which is located immediately west of the site and l on the Catawba River channel. The ta!! water 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 l 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. l E Tables 2.1-A and 2.1-B define the sampling and TLD locations for the ! , 5 McGuire Radiological Monitoring Program. Figures 1 and 2 illustrate these ! locations as compared to McGuire Nuclear Station. I I I i
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E I 2.2 SCOPE AND REQUIREMENTS OF ENVIRONMENTAL MONITORING PROGRAM I An environmental monitoring program has been in effect at McGuire Nuclear Station since 1977, four years prior to the Unit No. I startup in 1981. The I 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 Technical Specifications 3/4.12 with regard to sample media, sampling locations, i 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 Technical Specifications. Table 2.2-C shows the analysis I 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-mad e" environmental radioactivity. The environmental monitoring program also I 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 i appropriate critical exposure pathways to man and satisfies vitalinterests of the company, public, and state and federal agencies concerned with the environment. I I I I I I I 2-2
E M M W M M M MM M M M M M E 'M M M M TABLE 2.1-A l McGuire Radiological Monitoring Program Sampling Locations c
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E3 L 3 $ Code: ' E* b 3 7 3 F W-Weekly SM-Semimonthly 3g g g m g > BW-Biweekly Q-Quarterly S3 3 c g B % M-Monthly SA-Semiannually 3% a: o_ 3 m
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120 Site Boundary (0.7 mi NNE) V 121 Site Boundary (0.5 mi NE) V M J25 Site Boundarv (0.5 mi SW) W 128 Disenaroe Canal Bridae (0 4 mi ENE) M BW J29 Discharoe Canal Entrance to Lake Norman (0.5 mi ENE) 130 SA SA m Hwy 73 Bridae Downstream (0.6 mi SW) d, 131 SA Cowans Ford Dam (0.6 mi W) BW 132 Charlotte Municioal Water Snoolv (11.2 mi SSE) BV 133 Cornelius (6.2 mi NE) W 134C East Lincoln Jr. Hich School (8.7 mi WNW) W M 135C Plant Marshall Intake Canal (12.0 mi N) 136C BW Mooresville Municipal Water Supolv (12.5 mi NNE) BW 137C Pinnacle Access Area (12.0 mi N) 138 SA SA Henry Cook Dairy (2.75 mi ESE) 139 W1111am Cook Dairy (2.25 mi E) SM 140 Kidd Dairy-Cows (2.8 mi SSE) SM 141C Lynch Dairy-Cows (14.8 mi WNW) SM SM 142 Davidson Municipal Water Supply (7.5 mi NE) BW 158 4-5 mile radius (5.0 mi NE) M 184 5 mile radius Gardens M(a) 185 5 mile radius Gardens M(a) (a) during harvest season
W W W W W W W A W W W W W W W W W W W Table 2.1-B MCGUIRE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS (TLD LOCATIONS) SAMPLING LOCATION DESCRIPTION
- SAMPLING LOCATION DESCRIPTION
- 143 SITE BOUNDARY (0.5 MILES NW) 163 4-5 MILE RADIUS (5.0 MILES SE) 144 S'.TE BOUNDARY (0.6 MILES NNE) 164 4-5 MILE RADIUS (4.5 MILES SSE) 145 SITE BOUNDARY (0.5 MILES NE) 165 4-5 MILE RADIUS (5.0 MILES 5) 146 SITE BOUNDARY (0.5 MILES ENE) 166 4-5 MILE RADIUS (5.2 MILES SSW) 147 SITE BOUNDARY (0.5 MILES E) 167 4-5 MILE RADIUS (4.9 MILES SW) 148 SITE BOUNDARY (0.5 MILES ESE) 168 4-5 MILE RADIUS (4.7 MILES W5W) 149 SITE BOUNDARY (0.7 MILES SE) 169 4-5 MILE RADIUS (4.4 MILES W) 150 SITE BOUNDARY (0.5 MILES SSE) 170 4-5 MILE RADIUS (4.5 MILES WNW) 151 SITE BOUNDARY (0.5 MILES 5) 171 4-5 MILE RADIUS (4.5 MILES NW) n> 152 SITE BOUNDARY (0.5 MILES SSW) 172 4-5 MILE RADIUS (5.2 MILES NNW)
E 153 SITE BOUNDARY (0.5 MILES SW) 173 SPECIAL INTEREST (8.5 MILES NNW) 154 SITE BOUNDARY (0.7 HILES WSW) 174 SPECIAL INIEREST (8.7 MILES WNW) 155 SITE BOUNDARY (0.7 HILES W) 175 CONTROL (12.7 MILES WNW) 156 SITE BOUNDARY (0.5 MILES WNW) 176 SPECIAL INTEREST (11.0 MILES SW) 157 4-5 MILE RADIUS (4.8 MILES N) 177 SPECIAL INTEREST (8'6 MILES 5) 158 4-5 MILE RADIUS (4.4 MILES NNE) 178 SPECIAL INTEREST (9.2 MILES SE) 159 4-5 MILE RADIUS (5.0 MILES NE) 179 SPECIAL INTEREST (10.4 MILES ESE) 160 4-5 MILE RADIUS (4.9 MILES ENE) 180 SPECIAL INTEREST (11.5 MILES NNE) 161 4-5 MILE RADIUS (4.7 MILES E) 181 SPECIAL INTEREST (6.7 MILES NE) 162 4-5 MILE RADIUS (4.6 HILES ESE) 182 SPECIAL INTEREST (6.0 MILES NE) 183 SPECIAL INTEREST (5.5 MILES 5)
*All TLD samples are collected quarterly
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REVISION 22
'HARLOTTE WATER WORKS jfjjgg C{ lo 5 e go jo (, - c> l
M M M M- W M M M M M M J M W M M M W M TABLE 2.2-A t t-!AXIt!Illi VAlIlES TOR Ti!E LOWER LIllIIS Of DEIECTIOri (LLD)II}'( ) AIRCORilE PARTICULA 1E OR0A0 LEAF UATER OR GAS FISil !! ILK VEGEIATIO!1 SEDIllElli ! AllALYSIS (pCi/1) (pCi/m 3) (pCi/kg, wet) (pCi/l) (pCi/kg, wet) (pCi/lg, dry) Gross beta 4 fl. A. fl. A. it A. fl. A. fl. A. 11- 3 2000* II.A 11. A. 11. A. fl. A. 11. A. 1 i
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fe-59 30 fl. A. 260 11. A. fl. A. fl. A. m Cn-58, 60 15 11. A. 130 15. A. 11. A. 11. A. i O 2n-65 30 11. A. 260 fl. 4. 11. A. ft. A. i Zr-95 15 11. A. ft. A. 11. A. fl. A. fl. A . lib-95 15 11. A. 11. A. 11. A. fl. A. fl. A. 1-131 3 -2 1 7 X 10 fl. A. 1 60 fl. A. Cs-134 15 5 X 10-2 130 15 60 150
.fs-137 18 6 X 10 -2 150 18 80 180 Da-140 15 fl. A. ft. A. 15 11. A. fl. A .
La-140 15 ti. A. 11. A. 15 11. A. fl. A. A If no drinking water pathway exists, a value of 3000 pCi/1 may be used.
W W M M M M M.M M M M M M M M M M M M - TABLE 2.2-B REPORilllG LEVELS FOR RADI0 ACTIVITY C0tlCEllTRATI0ftS Ill EllvittorfffEllIAL SAf1PLES REPORb!!GLEVELS BROA0 LEAT WATER AllI00 Rile PAllTICULATE F1511 tillK VEGEIAllOll AllALYSIS (pCi/1) OH GASES (pCi/m3 ) (pCi/Kg, wet) (pCi/l) (pCi/Kg, wel) 11- 3 2 x 10 H.A. 11. A. fl. A. 11. A. Mn-54 1 x 10 fl. A. 3 x 10 fl. A. fl. A. 2 fe-59 4 x 10 II. A. 1 x 10 ft. A. II. A. m Co-58 1 x 10 3- it. A. 3 x 10 II. A. 11. A. 2 4 Co-60 3 x 10 fl. A. 1 x 10 ll. A. ft. A. Zn-65 3 x 10 2 11. A. 2 x 10 4
- 11. A. I1. A.
Z r-lib-95 4 x 10 2 ,, , 3, ,,, 3, ,,, 3, ,,, 3 , I-131 2 1 ft. A. 3 1 x 10 Cs-134 30 10 1 x 10 3 60 Ix 10 3 Cs-137 50 20 2 x 10 70 2 x 10 2 N.A. Ba-La-140 2 x 10 11. A. . fl. A. 3x 10 2 (1) for drinking water samples. This is 40 CfR Part 141 value. I f no drinting water patimay exist <,. a value of 3 x 104 pCi/l may be used.
E M M M M M M M M M W W W W M M M M' W Table 2.2-C McGuire Radiological Monitoring Program Analyses Analyses Sample Analyses Gammi Tritium Low Level Gross TLD Medium Schedule Isotopic I-131 Beta Radiolodine X
& Weekly Particulates X X Direct Radiation Quarterly X Biweekly X Surface Monthly Composite X Water Quarterly Composite X 7
e Biweekly X Drinking Monthly Composite X Water Quarterly Composite X X Shoreline Sediment Semiannually X Hilk Semimonthly X X Fish Semiannually X Broadleaf Vegetation Monthly X Food Products Monthly (*) X (a) During harvest season
I I 2.3 STATISTICAL AND CALCULATIONAL METHODOLOGY I 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 intucator and the I 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 Environmentul Monitoring Program. The following equation was used to estimate the mean: I {x N 1 (eq. 2-1) 73"1" l I Where: 5 = estimate of the mean, i = individual sarrule, N = total number s t samples with a net activity (or concentration) I x, = net activity (cr 'oncentration) for sample 1. NOTE: " Net activity (or concentration)" is the activity (or I concentration) determined to be present in the sample. No
" Minimum Detectable Activity", " Lower Limit of Detection", "Less Than Level", or negative activities or concentrations are ,
included in the calculation of the mean. 2.3.2 LOWER LEVEL OF DETECTION AND MINIMUM DETECTABLE ACTIVITY
-I The Lower Level of Detection (LLD) and Minimum Detectable Activity (MDA) are used throughout the Environmental Monitoring Program, both in the Technical Specifications and in the implementation of the specifications.
The LLD, as defined in the Technical Specifications, is the smallest concentration of radioactive materialin a sample that will yield a net count, I- above 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 I LLD is dependent upon the standard deviation of the background counting rate, the counting efficiency, the sample size (mass or volume), the l radiochemical yield, and the radioactive decay of the sample between sample l collection and counting. The " required" LLD's for each sample medium and selected radionuelldes are given in the Technical Specifications. lI The MDA may be thought of as an " actual" LLD for a particular sample measurement remembering that the MDA is calculated using a sample 2-10 i
I background instead of a system background. In gamma spectroscopy analyses , the sample background may be elevated above the system background due to the continuum produced by higher energy gammas from I other radionuclides (either man-made or naturally produced). The continuum increases the smallest concentration of a particular radionuclide that could be positively identified in the sample. Therefore, to insure that I the " required" LLD is not exceeded for any radionuclide in a sample medium, the MDA is calculated based on the actual background in the area of the identifying gamma energy and is compared to the " required" LLD. I If the MDA nxceeds the " required" LLD, the sample is counted for a longer time period so that the standard deviation of the sample backgr'ound is minimized. If the " required" LLD exceeds the MDA, then the analysis of the sample meets the requirements for the detection capability for environmental I sample analysis. For " gross" counters (such as alpha / beta proportional counters and liquid I scintillation counters), the MDA is calculated using a batch background count. This MDA is then compared to the " required" LLD. If the MDA exceeds the " required" LLD, the sample is counted for a longer time period so that the standard deviation of the batch background is minimized. If the I " required" LLD exceeds *.he MDA, then the analysis of the sample meets the requirements for the detection capability for environmental sample analysis. I 2.3.3 TREND IDENTIFICATION I 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 II 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 ,I 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 l (radioactive decay, deposition, resuspension, etc.) are influencing the l concentration. 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 I 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 I and the amount of radionuclides in a particular environmental medium, the lease squares regression method may be used to define the linear relationship. To determine if the data actually correlate to the straight line I 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 I calculated from the equation on the next page: 2-11
I I NEXY-EXE Y y 2 [(NEX .(3y)2)(y3 y2-(E y)2)] (eq. 2-2) I Where: r = correlation coefficient for the data set of X and Y, X = the year or point in time, I Y = the radionuclide concentration associated with X, N = number of observations. l l I 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 I 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 (-) I correlation coefficient indicates a decreasing trend. The ranges of a correlation coefficient may be summarized as following: l j I 1> lrl > 0.7 High to moderate probability of a trend. 0.7 3 Irl > 0.3 Moderate to poor probability of a trend. !
- 0. 3 [ l r l >_ 0 Poor to no probability of trend.
Identifying a trend by using the correlation coefficient is only useful for the I 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 I 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, I determined from the environmental data. Other factors that may affect environmental levels of radionuclides include prevailing weather conditions (periods of drought or heavier than normal precipitation), construction in or around olther the nuclear plant or the sampling location, addition or I 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 not only on the least squares regression method, but will include come judgement by plant personnel on the factors affecting environmentallevels. I 2-12
I ~
! 3.0 RADIOLOGICAL ENVIRONMENTAL -
MONITORING PROGRAM MONITORING ,I PROGRAM - DISCUSSION, INTERPRETATION AND TRENDING OF I RESULTS I The radionuclides with Technical Specifications reporting levels in the I environmental media samples have been historically trended over an oleven-year period from 1979 - 1990. 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 l would have produced correlation coefficients and averages that were not representative. The highest annual mean concentration of each Technical , Specification radionuclide from the indicator and control locations for each l I 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 i g concentration for each radionuclide for that year. Ilowever, when L preoperational comparisons were necessary, only the preoperational report was used. Twelve annual means were used to determine trends and often the average concentrations reported were negative. All negative values (concentrations) were replaced with a zero to properly represent I environmental conditions. presentation of the annual mean concentrations for drinking water, Figures 3 through 6 provido a graphical shoreline sediment, fish, and TLD data. Some of these figures show both I indicators and controls for significant radionuclides, while others show only indicators for 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 Technical Specifications reporting levels were calculated for each reportable radionuclide in each media type. I Only the radionuclides with Technical Specifications reporting levels were historically trended and compared with the eleven-year average and control levels. It is important to note that while historical trends are helpful in determining radioactivity buildup, environmental radionuclido levels could I be affected without exhibiting increasing or decreasing trends. No Technical Specifications icporting levels were exceeded in 1990 due to plant offluents. Sample analysis reports (SAR'S) are included in Appendix E. On many of I these reports naturally occurring radionuclides (NOR) are listed. In most cases the listed NOR's are potussium-40 (K-40) and Bery111um-7 (Be-7). I I 34
3.1 AIRBORNE RADIOIODINES AND PARTICULATES I 3.1.1 RADIOlODINES I In 1990, 259 radiolodine samples were analyzed, 207 at four indicator locations and 52 at the control location. The I-131, Cs-134, and Cs-137 concentrations did rmt significantly differ from the eleven-year average, preoperational data, or controllocation levels for the eleven-year period. The historical trends based on highest annual I mean for indicator and control locations for I-131, Cs-134, and Cs-137 showed moderate to no probability of increasing or decreasing trends as l illustrated in Table 3.1.1-A. Cs-137 activity which was present on the I cartridge, but not on the particular filter was determined to be inherent in the charcoal and was not included for trending purposes (see page 5-1) l I Table 3.1.1-B shows the percentages of environmental concentrations to the Technical Specifications reporting levels for the indicators at the locations with the highest annual mean for 1990. I I lable 311-B Radionuhlide Concentration Reporting Percentage (pCum*) wel(PcUm*) 1-131 0.00E0 1.00E0 0.00% Cs-134 0.00E0 1.00El 0.00% Cs-137 0.00E0 2.00El 0.00% I I I I I I -
, I I Iable_Ma- A_.CancentrationaLBadionuclidesJn Althorne_Badiolodinea I Cm:enuatum (Pet /m') YEAR l-131 CS-134 Cs-137 trdcator Conuol trecator Cmuel Irdnator Connel 1979
- 3.28E-3 1.04E-3 1.19E-3 -7.64 E-4 4.40E-3 1.47E-3 1980* 2.04 E-3 1.10E-3 -5.89E-5 -2.45 E-4 6.7(16 - 3 4.53E-3 1981
- 4.17E-3 6.27E-4 1.1$ E-3 2.09E-4 6.16E-3 5.32E-3 1982
- 1.42E-3 2 48E-3 4.85 E-4 2.27E-3 3.82E-3 2.29E-3 1983* 1.99E-3 2.01 E-4 6.80E-4 4.98 E-4 2.93 E-3 3.21E-3 1984 3.17E-3 - 1.15 E-3 1.54E-3 3.0$E-4 4.67E-3 3.39E-3 1985 3.15 E-3 1.04E-3 2.43E-3 9.24E-4 4.49E-3 3.56E-3 I ;986 1.27E-2 6.10'-3 1.18E-3 1.09E-3 3.32E-3 2.99E-3 1987 1.07E-2 6.60E-3 1.08E-2 8.04E-3 1.49E-2 6.41E-3 1988 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1989 2.18E-2 0.00E0 0.00E0 0.00E0 1.02E-2 3.52E-2 11 YEAR AVERAGE 5.86E-3 1.93E-3 1.77E-3 1.22E-3 5.60E-3 6.22E-3 19,3 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 CORRELATION COEFFICIENT 0.37 0.11 0.14 0.16 -0.01 0.32 I
- Radiolodines and Particulates analyzed together.
NOTE: All negative values were replaced with "zero's" for calculational purposes. I I I 33 g
1 3.1.2 PARTICULATES In 1990, 259 particulate samples were analyzed, 207 at the four indicator I locations and 52 at the controllocation. The 1-131, Cs-134, and Cs-137 concentrations did not significantly differ from I the eleven-year average, preoperational data, and controllocation leveln. The historical trends for the indicator and control locations with the highest annual mean for 1-131, Cs-134, and Cs-137 showed moderate to no probabilities of increasing or decreasing trends as illustrated in Table 3.1.2-A. Table 3.1.2-B shows the percentages of environmental concentrations to the Technical Specifications reporting levels for the indicator locations with the I highest annuni mean for 1990. No activity was detected and therefore no reporting levels were approached. I labje 3.1,2-B I Radionuclide Corcentrauon (pCUm') Reporting Level (pCum') Percentage 1-131 0.00LO 1.00E0 0.(04r Cs-134 0.00E0 1.00E1 0.(0% Cs-137 0.00E0 2.00El 0.00% I I I I I I I 3-4
. . -. -= ._
l - , ..- .. - I IAble_312-A ConCenitatioB_oLBadionuclideSJnAlthonle Particulates I Concentration (pCUm') l YEAR l-131 Cs-134 Cs-137 trda.;or Control Ird.:ator Control Indicator Control 1979
- 3.28E-3 1.(ME-3 1.19E-3 -7.64 E-4 4.40E-3 1.47E-3 l
1980
- 2.04E-3 1.10E-3 -5.89E-5 -2.45E-4 6.70E-3 4.53E-3 1981* 4.17E-3 6.27E-4 1.15 E-3 2.99 E-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 3.21 E-3 1984 2.72E-3 2.08E-3 9.90E-4 8.83 E-4 1.74E-3 8 i ?E-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 7.25 E-3 0.00E0 1.07E-2 7.91 E-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 11 YEAR AVERAGE 2.85E-3 2.01 E-3 1.44 E-3 5.35E-4 3.89E-3 2.72E-3
- 1990 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 CORRELATION COEFFICIENT .17 .18 ,12 .22 - 46 -0.34
- Radiolodines and Particulates analyzed together.
NOTE: All negative values were replaced with "zero's" for calculational purposes. I I I g 2.s
I I 3.2 DRINKING WATER I in 1990, 39 drinking water samples were analyzed for 1-131/LL, 26 at the two indicator locations and 13 at the control location. Tritium (11-3) analyses were performed on 12 composite samples, eight at indicator locations and four at the control location. Thirty-nine samples were analyzed for all the other radionuclides with Technical Specifications l reporting levels, 26 at indicator locations, and 13 at the control location. I Analyses showed zero ranges for allindicator locations which means no detectable activity was measured. All radionuclides did not significantly I differ from the eleven-year average. All radionuclides, except tritium, did not significantly differ from preoperational data. A high to moderate probability of an increasing trend was indicated for I the indicator locations for 11-3. Ilowever, the 1990 11-3 concentration only resulted in 3.66% of the Technical Specifications reporting level. The correlation coefficients indicated a high to moderate probability of l a decreasing trend for Co-60 indicator, Zr-95 indicator, Fe-59 control, I and I-131 (indicator and control) locations. All other radionuclide indicators and controls exhibited moderate to no probabilities of l increasing or decreasing trends. Table 3.2-A and Figure 3 illustrate l these trends. FIGURE 3 I I CONCENTRATION OF TRITIUM IN pcl/l DRINKING WATER 2500 y 10% OF REPORTING LEVEL 2000 1500 I 1000+ s
/
I O im m, 4. im mom 4. m, i i. 4. Year I I 3-6 I
E - I Table 3.2-11 shows the percentages of environmental concentrations to the Technical Specifications reporting levels for the indicators at the locations with the highest annual mean for 1990. Iabk124. I Concentration (pCi/l) Radionuclide Reponing Level (pCi/l) Percentage I fi-3 7.32E2 2.00E4 3.66 % Mn-54 0.00E0 1.00E3 0.(0% Fe-59 0.00E0 4.(CE2 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.C0% I N1-95 0.00E0 4.00E2 0.00% . l Zr-95 0.00E0 4.00E2 0.00% l 1-131/LL 0.00E0 2.(CEO 0.00% Cs-134 0.00E0 3.00EI 0.00 % Cs-137 0.00E0 5.00El 0.00% Ba/La-140 I 0.00E0 2.00E2 0.00 % I I I I
- I 3-'
- I I Iablel2-A_ Concentration.otfladlonuc.IldesjnArinking_Watet (Page 1 of 3)
I Corwenuation gCL/ liter) Yeat 11- 3 hin-54 Fe-59 Co-58 trxbcator Conuel trxticator Conuel trdicator Connot trxhcator Conuol 1979 1.65E2 1.50E2 1.46E0 4.27E-l 1.29E0 5.96E-1 1.14E0 2.01E0 1980 1.63E2 2.05E2 6.20E-l -4.29E- 1 1.77E0 5.20E-l 5.62E-1 -3.72E-l 1981 1.88E2 1.78E2 1.40E-1 - 1.96E0 4.58E0 1.13E0 9.36E-1 4.33E-1 1982 2.43E2 1.45E2 8.63E-1 7.0$E-2 3.50E0 -7.39 E- 1 7.71 E-1 6.26E-1 1983 2.65E2 1.45E2 4.18E-1 -3.06E-2 1.44E0 7.93 E-l 6.78E-l -2.60E-l 1984 5.77E2 2.45E2 1.0$E0 1.42E-l 2.15E0 1.60E-1 8.89E-l -2.57E-l 198$ 5.93E2 4.00E2 7.14E-2 9.49E-2 7.73 E-1 -4.73 E- 1 3.39E-l 6.16E-1 1986 1.14E3 4.37E2 9.76E-1 -4.59 E-2 2.16E0 -4.92 E- 1 3.82E-l 1.04E-2 1987 1.35E3 7.75E2 4.80E0 0.00E0 6.60E0 0.00E0 4.20E0 0.(CEO 1988 9.92E2 7.llE2 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.(VE0 11 Yr. Avg. 5.67E2 3.08E2 9.45E-1 2.94E-1 2.21EO 2.91 E-1 9.00E-1 3.36E-l 1990 7.32E2 6.llE2 0.00E0 0.00E0 0.00E0 0.00E0 0(CEO 0.(CEO Con. Coef 0.73 0.56 -0.02 0.22 -0.29 -0.70 -0.09 -3.59 NOTE: All negative values were replaced with "zero's" for calculational purposes. I I ~ I ; 3.s g
I Iable12- A_ConcentLation.oLB adlonu clid esja DrinklD LWateL (Page 2 of 3) I Corwentratim (gGhteo Yeat Co-60 Zn-65 Nt>-95 Zr-95 I trdicator Cmtrol trxiicator Control trxticator Cmtrol Indicator Control 1979 2.30E0 2.01E0 1.10E-1 2.56E-1 2.52 E0' -3.74 E-2 ' 2.52E0' 3.74E-2' 1980 2.26E0 1.80E0 1.18E0 -7.44 E- 1 1.71E0' 6.52 E-l
- l.71 E0' 6.52 E-l
- 1981 1.43E0 1.34 E-1 1.76E0 1.29E0 2.30E0 1.47E0 2.42E0 1.81E0 1982 8.25 E-1 5.98E-1 1.16E-1 9.43E-1 1.35E0 1.42E0 2.49E0 2.02E0 1983 1.26E0 1.22E0 -6.0$ E-2 -2.48E0 -3.99E- 1 2.32E-l 1.82E0 1.0$E0 7.22 E- 1 -2,81 E-1 5.03E-1 1.29E-l 7.47E-l 1.91E-1 2.70E0 -1.06E0 l 1984 1985 8.44 L- 1 7.CNE-1 -3.43 E- 1 -7.20E-2 9.32E-1 4.63E-1 1.09E0 5.70E-l 1986 2.33E-1 -3.46E-1 2.44 E-1 7.25 E-2 9.87E-1 1.0600 5.17E-1 -4.4 3 E- 1 1987 0.(CEO 0.00E0 0.00E0 0.00E0 5.30E0 0.00E0 0.(CEO 7.10E0 1988 0.00E0 4.50E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.(CEO 1989 0.00E0 0.00E0 Ol0E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 11 Yr.
Avg. 8.98E-1 9.97E-1 3.56E-1 2.45E-1 1.44 E0 4.99 E- 1 1.39E0 1.19E0 1990 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 Corr. Coef -0.94 -0.54 -0.48 -0.30 -0.46 I -0.87
.13 0.02
- Nb-95 and Zr-95 analyzed as Nb/Zr-95 NOTEt All negative values were teplaced with "zero's" for calculational purposes.
I I l l 3-9
I I Iable12-A Concentration _oLBadionuclides.In_DrjnkingMalet_ (Page 3 of 3) I Cm.cntration (JGtter) Year 1-131 Cs-134 C6-137 IWLa-140 . trxticator Control lidicator Cornrol Irdicator Control Irdicator Control I
~
1979 4.9500 6.97E-l -1.09E0 -4.12 E- l 2.5500 2.86E-1 1.6. i 1.54 E-2 1980 7.39E-l 8.96E-1 -3.54 E- 1 -6.24 E- l 9.53 E- 1 1.73 E() 8.53E-2 2.06E-i
~
1981 1.83E0 1.0500 1.46E0 4.77E-1 1.13E0 1.1 tn 1.09E0 -8.20E-l - 1982 2.45E0 7.79E-2 5.35lE- 1 2.64E0 1.0800 3. ef.D : ' 28E-1
-6.73 E- 1 i
1983 4.34 E-1 -5.57E- 1 6.29E- 1 1.54 E() 8.91 E- 1 5.3.- ; .26E-1 1.13 EC) 1984 9.46E-2' -8.65 E-2' 6.16E-1 -2.01 E- l 2.80E0 6.07E-i 1.1600 -7.66E- l 1985 - 1.84 E- l ' - 1.27 E- l ' l .(CEO 5.$$E-l 1.4300 - 1.79 E- 1 5.15 E-l 7.75 E- 1 1986 3.07E-2' 5.63E-2' b.18E-1 -1.45E-2 2.5S E- 1 2.83E-1 7.53 E-1 -1.llE-l 1987 4.10E-1 0.00E0 0.00E0 5.90E0 4.20E0 2.80E0 0.00E0 4.(CEO 1988 0.(CEO 0.00E0 0.00E0 0.00E0 0.(CEO 0.00E0 0.00E0 0.00E0 1989 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.(CEO 11 Yr. Avg. 9.57E-1 2.52E-1 4.60E-1 1.01E0 1.39E0 9.91 E-1 5.89E-1 5.57E-1 1990 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.(CEO 0.(CEO Corr. Coef -0.73 -0.74 0.30 0.06 -0.31 -0.34 -0 68 0.17
- l-131/LL analysis data used.
NOTEt All negative values were replaced with "zero's" for calculatiot al purposes, 1 I I 3-2
4 I 3.3 SURFACE WATER 1 I In 1990, 39 surface water samples were analyzed for 1-131/LL, 20 at the two indicator locations and 13 at the control location. Analyses for 11-3 were performed on 12 samples, eight at indleator Ic ations and four at the control location. Thirty-nine samples were a:uu3 :ad for all other E E radionuclides with Technical Specifications reporting levels, 20 at indicator locations and 13 at the control location. All technical specification radionuclides except 11-3 showed zero ranges indicating I that no detectable activity was measured. All radionuclides, except 11-3, were not significantly different from preoperational data and the control location levels. Tritium activity in 1990 showed a decrease from the 1989 I sample results and as all other radionuclides, did not differ signific".ntly from the eleven-year average, There is a moderate to poor probability of an incressing trend for 11-3 i< indicator. There is a high to moderate probability of a decreasing trend for Co-56 (indicator), Co-60 (control) and 1-131 (indicator). The 1990 concentration of it-3 resulted in 3.39% of the Technical Specifications I reporting levels. All other radionuclide indicators and controls exhibited moderate to no probability of increasing or decreasing trends. Table 3.3-A illustrates these trends. I t l l I I I E l 3-11
I Table 3.3 D shows the percentages of environtnental concentrations to the Technical Specifications reporting levels for the indicators at the location with the highest annual rnean for 1990. Iable_.3A-B I Radionuclide Correntration (pCi/l) Reporting level (pCi/l) Percentage H-3 6.77E2 2.00E4 3.39 % Mn-$4 0.00E0 1.00E3 0.(0% Fe-$9 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 % Nt>-95 0.00E0 4.00E2 0.00 % i Zr-95 0.00E0 4.COE2 0.00 % l-131/LL 0.00E0 2.00E0 0.00% Cs-134 0.00E0 3.00El 0.00 % Cs-137 - 0.00E0 $.00El 0.004 8a/La-140 0.00E0 2.00E2 0.00 % I I I I.
- I I
3-12 g
I I IaMe_313-A ContentratioB_olBa.dionun!!deSJnEMtfate_WaleL (Page 1 of 3) g _ Corgentratkm (pCi/ liter) Year 11 - 3 hin-54 Fe-59 Co-58 Irdcator Control Irdcator Control Irdcator Control Irdcator Control 1979 1.85E2 1.66E2 8.95 E-l 6.35 E-1 1.6900 2.55E0 1.47E0 1.90E- l 1980 2.13E2 1.93 E2 2.17E0 5.81E-1 5.2 t E-l 9.48 E-1 1.17E0 -5.16E-2 1981 1.75E2 1.70E2 4.95E-2 -1.10E0 1.79E0 3.40E0 9.74 E-l - 1.35 E-1 1982 3.30E2 1.23E2 1.02E0 - 1.22 E- 1 1.97E0 -3.99E-2 1.63 E- 1 5.10E-1 1983 5.75E2 3.67E2 -2.30E-1 9.74 E-l 1.76E0 -7.08E- 1 6.14 E-l 5.08E-2 1984 4.10E2 2.65E2 -7.56E-2 -4.19E- l -4.88 E-1 9.15E-l 3.30E-l 4.24E-1 1985 7.33E2
- 1.01E0 -4.75 E- 1 3.91 E-1 1.04E0 7.61 E-l I.65 E-l 1986 2.33E3 6.13E2 5.13E 1 3.97E-1 -1.67E-1 4.36E-2 -2.95 E-3 3.31 E-l 1987 9.20E2 7.70E2 0/X)E0 0.00E0 1.10El 0.00F.0 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 11 Yr.
l Avg. 6.94E2 2.42E2 5,14E-1 2.35E-l 1.74E0 8.09 E- 1 4.98 E- 1 1.52E-l 1990 6.77E2 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 Co:T. t Coef 0.53 -0.05 -0.59 -0.51 -0.02 -0.67 -0.85 -0.27
- No samplo analyzed.
NOTE: All negative values were replaced with "zero's" for calculational purposes. 1 3-13
I I Iable_313-A-- Concmittailon_o.LBadionus11 des in Surface Walet (Page 2 of 3) I l l I Concentration (pCi/ liter) Year Co-60 Zn-65 Nb-95 Zr-95 l I Indicator Control Indicator Control Irdicator Control Indicator Control 1 1 1979 2.45E0 2.60E0 8.62 E-1 -5.33 E- ! -2.53 E- l ' 5.77E-l* -2.53 E-l
- 5.77E-l' i 7.70E-l 1980 1.36E0 1.12E0 1.80E0 1.00E0' -2.54 E-l
- 1.00E0' -2.54 E-l
- 1981 2.47E-l 1.54E0 -4.29 E-1 6.93E-1 -2.92 E- 1 3.50E-2 1.96 E0 9.(M E- 1 1982 1.14E0 6.02E-1 6.28E-1 -3.93 E-1 2.16E0 8.89E-1 2.2".E0 8.92E-1 1983 1.66E0 2.01 E0 -1,20E0 4.71 E-1 3.22E-1 1.15E0 3.21E-2 !.41E0 1984 1.47E0 3.38E-1 -9.79E-2 5.91 E-1 8.59E-1 2.66E-2 1.67E0 - 1.45 E. l 1985 3.86E-1 9.97E-l 1.22E0 -2.43E-2 6.10E-l 4.17E-l 1.16E0 1.74E0 1986 -1.36E-1 2.24 E-2 -1.24E0 -1.65E0 1.05E0 1.19E0 1.33E0 -3.91 E-l 1987 5.20E0 0.00E0 0.00E0 0.00E0 4.50E0 0.00E0 1.20El 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 0.00M 0.00E0 11 Yr.
Avg. 1.26E0 8.39E-1 5.62E-1 3.23E-1 9.55 E-l 3.90E-1 1.95E0 5.02E-l 1990 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 Cori. Coef -0.22 -0.81 0.01 -0.54 0.04 -0.28 0.11 -0.39
- Nb-95 and Zr-95 analyzed as Nb/Zr-95 NOTE: ' All negative values were replaced with "zero's" for calculational purposes.
t I ' ! 3-14 l
I Iahle_.13-A Conceultallau nLBadlonucl. ides in Sudace Walet_ l (Page 3 of 3)
)
I Correntration (pCi/ liter) Year 1-131 Cs-134 Cs-137 Dvla-140 Irdcator Control Irdcator Control Irdcator Control tr@cator Control 1979 2.66E0 -8.27E-1 -3.62 E- 1 - 1.00E- 1 2.63E0 -2.21 E- 1 2.26E-l -4.25 E- l 1980 1.13E0 1.20E0 -2.60E- l -9.98 E-l 1.97E0 1.27E0 9.70E- 1 -3.20E-l 1981 2.32E0 4.85 E-1 2.10E-2 1.88E-1 1.0$E0 2.45E0 6.98E-1 8.66E-l 1982 -3. l l E-1 -9.19 E- 1 -5.68 E- 1 8.34E-1 1.23E-l 1.65E0 4.30E-1 -4.11 E- 1 1983 1.89E0 2.88E0 7.87E-1 2.50E-1 8.43 E-1 2.39E-l 1.38E0 2.89E-1 1984 3.02E-2
- 1.58E-l* 7.36E-1 1.70E0 9.46E-l 3.30E-2 -2.84 E- 1 -6.81 E-3 1985 -8.69E-2 * -7.90E-2
- 1.72E0 1.25E0 1.23E0 3.26E-l 3.79E-1 4.53E-l 1986 8.94 E-2' 2.13 E-2' 7.54E-l 1.13 E-1 5.61E-1 1.97E-1 8.72 E-1 8.29E-I 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 I 11 Yr.
Avg. 7.38E-1 3.87E-1 7.65E-1 3.94 E-1 1.28E0 5.60E-1 4.50E- 1 2.22E-l 1990 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 i Corr. Coef -0.74 -0.28 0.22 -0. I 4 -0.29 -0.57 -0.52 -0. I 5
- I-131/LL analysis data used.
NOTE: All negative values were replaced with "zero's" for calculational purposes. I l 3-15
, 3.4 MILK H In 1990,104 milk samples were analyzed, 78 at the three indicator i locations and 26 at the control location. Mn-54, Co-58, Fe-59, Co-60, 2n-65 Nb-95, Zr-95,1-131, Cs-134, and Ba/La-140 showed a zero range indicating no detectable activity was measured in 1990. The 1-131/LL, Cs-134, Cs-137, and Da/La-140 lI concentrations did not significantly differ from the eleven-year average, preoperational data, and control levels. A high to moderate probability of a decreasing trend was indicated for Cs-137 (indicator) . Six of 78 indicator samples showed detectable activity for Cs-137 in 1990. The 1990 concentration for Cs-137 only I resulted in 7.57% of the Technical Specifications reporting level. All other radionuclide indicators and controls exhibited moderate to no probability of increasing or decreasing trends. These trends are illustrated in Table 3.4-A. Table 3.4-B showst he percentages of environmental concentrations to the Technical Specifications reporting levels for the indicators at the I location with the highest annual mean for 1990. Iable 3.4-B. Radionuchdo Concentration Reporting Percentage (pCl/l) Level (pC!/l) 1-131/LL 0.00E0 3.00E0 0.00 % Cs-134 0.00E0 6.00E1 0.00 % Cs-137 5.30E0 7.00E1 7.57% Ba/La-140 0.00E0 3.00E2 0.00 % 3-16
I I la ble.) A-8.._C O!)Ce fl{r 0110 fl_Q1..Ra d.lo n u clides _lfLMlik Corwenuatno (pCL/ liter) Cs-134 Cs-137 Ba'La-140 Year 1-131 Control trdicator Control trdicator Control trdicator Control tidicator
-7.05 E- 1 7.63 E-1 2.48El 6.04E0 0.00E0 4.15E-1 1979 6.87E-3 -6.13 E-2
-7.94E-2 -6.12E- 1 1.72El 4.13E0 1.29E0 1.33 E-l 1980 1.06E0 3.22E-2 1.37E0 -2.88 E- 1 2.NEl 4.15E0 3.77E-1 -7.95 E-2 1981 -3.70E-3 -5.54E-2 9.44 E-1 -4.38E-2 1.21 El 5.20E0 2.11E-1 -4. l l E-1 1982 -3.22 E-2 -8.49 E-2 1.55E0 2.02El 2.82E0 4.44 E- l 2.35 E-l 1983 1.23E-2 -4.57E-2 1.26E0 1.80E0 1.48El 2.56E0 4.79E-1 1.43E-1 1954 1.78E-2 -4.30E-2 1.08E0 9.32E-l 1.99E-1 1.42El 2.72E0 5.78E-1 5.97E-1 1985 2.00E-2 -5.80E-2 2.36E0 9.38E-1 3.74E0 3.45E0 2.95 E-1 1.08E-1 1986 8.30E-1 7.55E-l 3.f0E0 5.20E0 8.60E0 0.00E0 4.40E0 1987 4.80E-1 0.00E0 5.10E0 0.00E0 0.00E0 3.40E0 2.90E0 0.00E0 0.00E0 1988 0.00E0 0.00E0 0.00E0 0.00E0 6.00E0 5.60E0 0.00E0 0.00E0 1989 0.00E0 0.00E0 11 Yr.
Avg. 2.21E-1 7.16E-2 1.19E0 8.0$E-l 1.29El 4.38E0 3.36E-1 5.llE-l 0.00ED 0.00E0 5.30E0 2.60ED 0.00E0 0.(CEO 1990 0.00E0 0.00E0 Coa.
-0.16 0.15 0.12 0.07 -0.88 -0.10 -0.53 0.21 Coef NOTE: All negative values were replaced with "zero's" for calculational purposes, I
1 I _
i ? 3.5 BROADLEAF VEGETATION L [ In 1990,48 broadleaf vegetation samples were analyed, 30 at the three indicator locations and 12 at the controllocation. The 1956 data is higher than the other years due to the Chernobyl accident. All technical specification radionuclides except Cs 137 showed zero ranges indicating that no detectable activity was measured. Only two of 30 samples 'I taken indicated Cs-137 activity. The correlation coefficients for the location with the ldghest annual mean I indicated a moderate to poor probability of an increasing trend for Cs-137 indicator and control. Ilowever, this concentration resulted in only 2.01, of the w Technical Specifications reporting level. Since there were anomalous results g 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. The remaining radionuclide indicators and controls exhibited poor i to no probabilities of increasing or decreasing trends. These trends are 111ustrated in Table 3.5-A. 3 Table 3.5-B shows the percentage of environmental concentrations to the l Technical Specifications reporting levels for the indicators at the locations with the highest annual mean for 1990. Igble 3.5-B l Radionuclide Concennation Reporting Percentare (pCiAg) Level 4Gr) l-131 0.00E0 1.(CE2 0.(0% I Cs-134 0.(CEO 1.(CE3 0.(0% Cs-137 4.00E l 2.(CE3 2.00% i 3-18
Iable 3,5-A_ConcentLqtion_oLRedlonuclidesJrLBroadleal Megetat!on Ctukentratavi lpC@-w et) YEAR l-131 C$-134 C5-137 B trdicator Cmtrol tidicator Control Irdicator Control 1979 -5.82E0 7.30E-l -1.00El - 1,06E l 2.19El 1.93El 1980 1.91El 6.15E0 -2.59E0 - 1.25El 2.30E1 1.92El 1981 - 1.87E0 3.16E0 1.24El 5.96E0 3.04El 2.02El 1982 1.4101 6.59E0 1.50El -6.31 E- l 2.46El 1.22El 1983 1.13El 7.19E0 4.13E0 1.2400 9.0700 7.85E0 1984 6.(6 00 5.99E0 8.46E0 2.8000 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.COE0 1.10El 1.70El 2.50El 2.20El 1.70El 1988 0.(CEO 0.00E0 0.00E0 0.00E0 3.90El 3.40El 1989 0.00E0 0.(CEO 0.00E0 0.00E0 9.60El 0.00E0 11 YEAR AVERAGE 7.70E0 5.38E0 8.37E0 6.57E0 2.95El 1.39El 1990 0.00E0 0.00E0 0.(CEO 0.(CEO 4.00El 0.00E0 CORRELATION COEFFICIENT -0.26 -0.09 -0.02 0.21 0.53 -0.32 i NOTE: All negativo values were replaced with "zero's" for calculational purposes. 3-19
s J - 3.6 SHORELINE SEDIMENT l In 1990, six shoreline sediment samples were analyzed, four from two J indicator locations and two at the controllocation. l The correlation coeffleient for the location with the highest annual mean indleated a moderate to poor probability of an increasing trend for Cs-137 indicator, llowever, the Cs-137 concentration only corresponds to a small percentage of the Technical Specifications reporting level na shown in Table 3.6-B Cs-134 Indicator and control and Cs-137 control exhibited poor to no probability of an increasing or decreasing trend. These trends are illustrated in Table 3.0-A and Figure 4. Table 3.6-B l Raionuclide Cm.cntratum Repontng Percentage (pCvkg) LevelftGig) Cs-134 0.00E0 3.f 0E3 0104 C5-137 6.10E1 310E3 2.03% I FIGURE 4 i CONCENTRATION OF RADIONUCLlDES IN SHOREUNE SEDIMENT pctrewet 300 ; , 4 , l l 1 goo ._. -
- 7. ,i -
7 ' l : I ! I' j i j_-_ _. {__L_,__ 300 I o, m i . ,a., 4 . i l
. i.
i . 4 V ,.n
- i. i i.,.
Year n
+ Co 137 indcator + Co 137 Control j 3-20
] Inble_34-A,_ Conc.entrat!on oLBadlonuclides_in.Shorellne_ Sediment
)
l Corcentranon yO/Lp-dry) Year Cs-134 Cs-137 l Indicator Control inicator Control 1979 0.00E0 1.20El 1.20El -1.77E l 1980 -3.53 E0 -1.85 E l 1.44 E l 6.88El 1981 3.97El 6.08E0 3.36El 1.65 E0 1982 7.67El 4.6 t El 4.40El 2.13El i983 7.eSei 2.78ei 8.02e, 3.2ee, g 1984 3.34El 1.32El 9.13El 3.65El 1985 2.02E l 1.03El 1.61E2 1.70El 1986 6.30El 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 11 Year Average 3.76El 1.60El 9.87El 2.08El 1990 0.00E0 0.00E0 6.10El 2.10El Correlation 0.02 -0.21 0.58 -.0.21 Coefficient NOTE: All negative values were replaced with "zero's" for calculational purposes , I 3-21
f 3.7 FISH in 1990,12 fish samples were anlyzed, six at the indicator locations and six at the control location. All technical specification radionuclides except Co-58, Co-60, and Cs-137 showed zero ranges indicating no detectable activity was measured. The radionuelides named above were not significantly different from the eleven-year average, preoperational data, and controllocation levels. In addition, these concentrations only correspond to small percentages of the Technical Specifications reporting levels as shown in Table 3.7-B. The correlation coefficients for the location with the highest annual mean indicated a moderate to poor [ probability of an increasing trend for the indicator concentrations of Co-58, Co-60, and Cs-137 and a high to moderate probability of a decreasing i trend for the control concentration of Fe-59. All other radionuclide indicators and controls exhibited moderate to no probability of l increasing or decreasing trends. These trends are illustrated in Table B 3.7-A and Figure 5. IabidJ-B_ l Radunuclide Concenuatan (pCWg) Reponing Level (pCdg) Percentage hin-54 0.00E0 3.(CE4 0.(0% Fe-59 0.00E0 1.00E4 0.001 Co-58 5.60El 3.00E4 0.19 % Co-60 4.10El 1.00E4 0.41% Zn-65 0.00E0 2.00E4 0109 Cs-134 0.00E0 1.00E3 0.004 Cs-137 3.30El 2.00E3 1.654r 3-22
) Iable_3J-A Concenttation_p1Badlonucildes in Elsh_ (Page 1 of 2) r Corwentration (pCds-w et) Yeat Mrr$4 Fe-59 Co-58 Co-60 Irdicator Control Irdicator Control Irdicator Control Irdicator Control
* * * -2.78E-1
- 9.86E0 1979 0.00E-0 3.71El 1980 -1.97El 1.14El -1.95 El 4.74El 8.3Cd0 8.60E0 -2.25 E l 1.14El 1981 -2.71 E0 2.74E0 3.70E0 2.97El -2.98E0 4.25E0 -2.65E0 -2.36E0 1982 -3.83 E0 1.28El 0.00E0 8 47El 8.16E0 2.65E0 -4.34 E-l 2.95E0 1983 -2.60E0 -1.84E0 -8.68E0 8.28E0 2.60El -5.31 E0 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 1.55 El 1986 1.03E0 -1.91 E0 - 1.21E0 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 4.0$E2 0.00E0 2.99E2 0.00E0 g 11 Yr.
Avg. 1.07El 3.29E0 7.95F-1 2.16El 9.79El 2.99E0 5.10El 4.55E0 g 1990 0.00E0 0.00E0 0.00E0 0.00E0 5.60El 0.00E0 4.10El 0.00E0 Corr, Coef 0.44 -0.38 -0.18 -0.72 0.58 -0.33 0.55 -0.49
- No sample analynd.
NOTE: All negative values were replaced with 'uro's" for calculational purposes. 3-23
IableJJ-A ConqenttailottoLBadlonuc]ldesjnfish (Page 2 of 2) Concentration (pCi/Lp-w et) YEAR Zn-65 Cs-134 0 -137 Indi;ator Control Ltdicator Control trdicator Control
-4.17 E0
- 1979 1.73E0 2.20El 1980 -3.22E l -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 -1,39 El -9.21 E0 -8.22E-1 3.57E-1 2.69El 9.52E0 1983 ~1.07E0 4.86E0 -1.32E0 -2.57E0 6.03El 2.08El 1984 -2.87E0 -3.26E0 3.llEl -7.(N E- l 4.38El 8.18E0 1985 -2.55 E0 3.17E0 -1.56E0 5.22E0 1.66El 1.48El 1986 -8.09E0 -1.40E l 1.67El 1.56E0 3.49El 8.N EO 1987 0.00E0 0.00E0 2.60El 0.00E0 5.10El 2.90El 1988 0.00E0 0.00E0 2.70El 0.00E0 3.60El 2.30El 1989 0.00E0 0.00E0 1.10El 0.00E0 3.50E! 1.50El 11 YEAR AVERAGE 4.62E-1 9.93E-1 1.12El 1.48E0 3.25El 1.75El 1990 0.00E0 0.00E0 0.00E0 0.00E0 3.30El I.60El CORRELATlON COEFFICIENT -0.31 -0.30 0,44 -0.24 0.56 0.11 1 0 No sample analyzed, NOTE: All negative values were replaced with "zero's" for calculational purposes.
3-24
I FIGURE 5 l y _ CONCENTRATION OF CO-60 pe % we I eoo IN FISH 8% REPORTING LEVEL l 5 { l I 400 3on 4 ... _ 200-- -- l 100 979 1D80 1981 1982 1963 1984 1985 1986 1967 1988 1989 1990 Yost i I I I I I I 1 l i 3-25
l l
" 3.8 DIRECT GAMMA RADIATION I In 1990, le3 TLD's were analyzed,159 at indicator locations and four at the control location. The 1990 exposure rate at the indicator location with the highest annual mean did not significantly differ from the I preoperational data or eleven-year average. The historical trends showed moderate to no probability of decreasing trends for both the a indicator and control. Table 3.5-A and Figure 3.8 illustrate this g summary.
Table 3.8-A TLD_ Exposure froy Direc_tJafflallon l Enosure (mrenVyr) ! trxticator Cmtrol 1979 8.76El 8.32E1 1980 1.16E2 1.0$E2 1981 1.45 E2 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 1.0SE2 5.48El 1989 9.77El 7.55El 11 Year Average 1.27E2 9.99El 1990 830El 6.23El Correlation Coefficient -0.28 -0.47 i NOTE: The expected background for North Carolina is 120 mrem per year from FSAR 11.6.1. g 3 2e
] FIGURE 6 l I mR/yr FROM D R CT R DIATION
- 1 i l l l i 160 + -
; 4 l .,
80 - I i i 1 1 40 0
'379 1980 1981 1982 1963 19B4 1965 1900 1987 1908 19S9 1990 Year
-*- TLD Indicator + TLD Control i
I I 3-27
] 3.9 FOOD PRODUCTS In 1990, twelve food products (crops) samples were analyzed, all at the l indicator location. No control site was available for food products in 1990. All Technical Specification radionuclides exhibited a zero range indicating no measurable activity present. The 1-131, Cs-137, and Cs-134 concentrations did not significantly differ from the eleven-year average and preoperational data. All of the I radionuclides exhibited moderate to no probability of a decreasing trend. No control sites were available for 1984 through 1990; therefore, a R representative correlation coefficient could not be calculated for the B control data. Table 3.9-A illustrates this summary. No activity was detected and therefore no reporting levels were approached. Table 3.9-B shows the percentages of environmental concentrations to the Technical Specifications reporting levels for the indicators at the location with the highest annual mean for 1990. No activity was detected and therefore no reporting levels were approached. I I@tt3A-R I Radionuclide Corcentration (pCiAg) Reponing Level (pCiAg) Percentage 1-131 0.00E0 1.00E2 0.00% Cs-134 0.00E0 1.00E3 0.00% Cs-137 0.00E0 2.00E3 0.00% 9 3-28
I J_RhjQ_3.,.9-A Concentr.at[on.91Badlonuc1[ des in Food Producja I Concentration (pCi/kg-w et) l YEAR l-131 Cs-134 Cs-137 Indicator Control Indicator Control Irxticator Control i 1979' -5.82E0 7.30E-1 -1.00El -1.06E l 2.19El 1.93El 1080' l91El 6.15E0 -2.59E0 -1.25El 2.30El 1.92El 1981* -1.87E0 3.16E0 1.24El 5.96E0 3.04El 2.02El 1982* 1.41El 6.59E0 1.50El -6.31 E-1 2.46El 1.22El 1 1983* 1.13El I 7.19E0 4.13E0 1.24E0 9.07E0 7.85E0 l l 1984 -5.08E-1 4.49ti-1 8.45E0 " 1985 1.02E-1 " -2.48E0 " " 7.99E0 1986 1.52El " 1.74E0 " " 2.15El 1987 0.00E0 " 0.00E0 " " 2.90El l 1988 0.00E0 " 0.00E0 " " j 000E0 I 1989 0.00E0 " 0.00E0 ** 0.00E0 " i 11 YEAR AVERAGE 5.44E0 4.76E0 3.07E0 1.44E0 1,60El 1.58El 1990 0.00E0 " 0.00E0 " " 0.00E0 CORRELATION COEFFICIENT -0.39 -
-0.41 -
-0.65 -
- 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 ca5culational purposes.
~*
I
3.10 LAND USE CENSUS l MCGUIRE NUCLEAR STATION ANNUAL LAND USE CENSUS PERFORMED MAY 14-18, 1990 SECTOR DISTANCE N Nearest Residence 2.7 miles Nearest Meat Animal None in 5 miles Nearest Garden 2.7 miles Nearest Cow None in 5 miles Nearest Goat None in 5 miles I NNE Nearest Residence 1.5 miles Nearest Meat Animal None in 5 miles Nearest Garden 2.4 miles I Nearest Cow None in 5 miles Nearest Goat None in 5 miles NE Nearest Residence 2 miles Hearest Heat Animal None in 5 miles Nearest Garden 3.7 miles Nearest Cow None'in 5 miles Nearest Goat None in 5 miles ENE Nearest Residence 2.5 miles 1 Nearest Heat Animal 4 miles Nearest Garden 2.5 miles Nearest Cc'd 4 milec Nearest Goat Hone in 5 miles E Hearest Residence .5 miles Nearest Heat Animal 4.8 miles Nearest Garden .7 miles Nearest Cow 2.3 miles Nearest Goat 1.8 miles ESE Nearest Residence .5 miles Nearest Heat Animal 2 miles Nearest Garden .8 miles Nearest Cow 2.8 miles Hearest Goat None in 5 miles SE Nearest Residence 1.5 miles Nearest Meat Animal 2 miles Nearest Garden .6 miles Nearest Cow 1.5 miles Nearest Goat None in 5 miles
~
SSE Nearect Residence .5 miles Nearest Meat Animal 1.8 miles Hearest Garden .8 miles Hearest Cow 2.8 miles 3-30
f Nearest Goat 1.8 miles SECTOR DISTANCE l S Nearest Residence 1.8 miles Nearest Meat Animal None in 5 miles l Nearest Garden 1.2 miles ! 5 Nearest Cow 3.3 miles Hearest Goat None in 5 miles i SSW Nearest Residenc'e 3 miles Nearest Meat Animal None in 5 miles Nearest Garden 2.4 miles ! Nearest Cow None in 5 miles I Nearest Goat None in 5 miles SW Nearest Residence 2 miles I Nearest Heat Animal 2 miles Nearest Gr.rden 3.8 miles Hearest Cow None in 5 mile = Nearest Goat None in 5 miles WSW Nearest Residence 1.5 miles Nea' rest Heat Animal None in 5 miles I Nearest Garden .7 miles Hearest Cow None in 5 miles Nearest Goat None in 5 miles W Nearest Residence .5 miles NNrest Heat Animal 3 miles Nearest Garden .6 miles i Hearest Cow Mone in 5 miles Nearest Goat None in 5 miles WNW Nearest Residence .8 miles Hearest Heat Animal 2.5 miles Hearest Garden 1.8 miles I Nearest Cow Nearest Goat None in 5 miles None in 5 miles I NW Nearest Residence Nearest Heat Animal Nearest Garden 1.5 miles None in 5 miles None in 5 miles Nearest Cow None in 5 miles i Nearest Goat None in 5 miles NNW Nearest Residence 2 miles Nearest Heat Animal None in 5 miles I Hearest Garden 3.5 miles Hearest Cow None in 5 miles Hearest Goat None in 5 miles I - 3-31 I
E l LAND USE CENSUS RESULTS FOR 1990 I The Annual Land Use Census for McGuire was completed May 18, I 1990. The results of this census are shown on pages 3-30 and 3-31. There were several milk animals and irrigated gardens located in sectors with high D/Q's that were not I used to collect samples for the 1990 Radiological Environmental Monitoring Program. All the respective owners at these locations were questioned to determine if they were interested in providing samples for McGuire's environmental program. Below are the results of this survey. MEDIA LOCATION REASON Goat 1.8 miles E Milk not used for human consumption Goat 1.8 miles SSE Milk not used for human consumption Cow 1.5 miles SE Unwilling to participate I Cow 3.3 miles S Milk not used for human consumption Irrigated 2.5 miles NNE Unwilling to participate I Garden Irrigated 4 miles NE Unwilling to participate Garden Irrigated 2 miles NW Food not grown this year / Garden Unwilling to participate Irrigated 3.5 miles NNW Unwilling to participate Garden A new irrigated garden located 4.9 miles North was found during this census. Sampling at this location began in i August, 1990 and it was added to the program as crop location 185. All remaining gardens identified were not 1rrigated. I_ I 3-32
] 4.0 EVALUATION OF DOSE FROM ENVIRONMENTAL MEASUREMENTS J VERSUS ESTIMATED DOSE FROM RELEASES i l 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 I controllocation, had been subtracted; the maximum exposed individual's doses are summarized below:
;; Maximum g Organ Critical Age Critical Pathway Dose (mRom/yr)
Skin Teen Shoreline Sediment 3.13E-3 I Bone Liver Infant. Infant T. Body Adult Milk hulk Broadleaf Vegetation 4.65E-1 5.44E-1 1.83E-1 I Thyroid Kidney Lung Child Infant Infant Drinking Water Milk hulk 1.25E-2 1.46E-1 5.92E-2 GI-LLI Adult Fish 5.31E-2 4.2 ESTIMATED DOSE FROM RELEASES Doses were estimated for release concentrations of radionuclidos in direct pathways to man using NRC Regulatory Guide 1.109 methodology. The doses were calculated using GASPAR and LADTAP computer programs. The maximum exposed individual's doses are summarized below: LIQUID RELEASES Maximum Organ Critical Age Critical Pathway Dose (mrem /yr) Skin Teen Shoreline Sediment 3.32E-2 Bone ' Child Fish 2.60E-1 Liver Teen Fish 3.98E-1 T. Body Adult Fish 2.97E-1 Thyroid Infant Drinking Water 1.28E-1 Kidney Teen Fish 1.75E-1 Lung Child Drinking Water 1.20E-1 GI-LLI Adult Fisn 6.94E-1 4-1
GASEOUS RELEASES L [~ Maximum Organ Critical Age Critical Pathway Dose (mrem /yr) Thyroid Teen Inhalation 2.30E-1 I I l 4.3 COMPARISON OF DOSES
.Although there are differences in the doses calculated from environmental samples and the doses calculated from releases, these differences are about a factor of ten (10) or less. In addition, for t*1e I infant milk pathway, only six out of 78 samples for the indicator locations showed detectable activity. Only one radionuclide, Cs-137, was detected.
The doses, as calculated using the environmental sample results, are well below the limits as specified in Technical Specification 3.11.4. I l 4.4 PATHWAY DOSE CALCULATIONS l Dose calculations for each age and pathway can be found on the following pages. 4-2
m imus a mm gun m m m m nas a m aus m m m m m m Dose from Air Particulate Inhalation Pathway for 1990 Data Maximum ExposedAdult Usage (Intake rate)- 8000 (m3fyr) Highest AnnualMean Concentration Aoun kihalation dose Smetor
@mem per pCI Wets M Does (mrense y)
Radionucede Bone Uwor T. Boc+y T!ryced Kidney Limg OMil8e m W3) Bone Uver T. Body Thead Kidney tur.0 GS--LU IAn-64 NO DATA 4.96E-ce 7.37E-07 NO DATA 1.23E-os 1.74E-04 967E-06 ALL 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00F+00 Co-68 NO DATA 1 SSE-07 2 59E-07 NO DATA NO DATA 118E-04 1.33E-05 ALL o00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E 00 Fe-60 t47E-06 3 47E4e 1.32E-46 NO DATA NO DATA 127E-04 2 36E-05 All 000E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Co-ee NODATA 1.44E-46 1 SSE-c6 NO DAYA NO DATA 7.4eE-04 3 5eE-05 Att 000E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Zn-e5 4 05E-46 129E-05 6 2SE-48 NO DATA 8 82E-06 108E-c4 e esE-OS ALL 000E+00 0 00E+00 0 00E+00 0 00E+00 c00E+30 0 00E+00 0 00E+0D 000E+00 Mb-45 1.75E-06 9 77E-c7 62eE-07 NO DATA 9 ETE-47 e 31E-05 1 M -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 Zr-46 134E-05 4 M-46 2 9tE46 NO DATA 6 77E-ce 221E-04 1 SSE-45 ALL 000E+00 0 00E+00 0 00E+00 0 00E+00 0 00E40 0 00E+00 3 00E+00 0 00E+00 l-131 3.15E-c6 4 47E-ce 2 SeE-ce 149E-03 7 eeE-OS NO DATA 7 35E-47 ALL 000E+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 1DeE-04 910E-05 NO DATA 3 59E-c5 127E-05 1.30E-46 ALL 000E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 0X+00 0 00E+00 Co-137 5 96E45 7.7t% 5.35E-45 NO DATA 2 7tE-oS 9 40E-os 105E-06 ALL 000E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Bate-140 4 SSE-46 613E49 3 20E-47 NO DATA 2 00E-c0 15eE-04 2 73E-OS ALL 000E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 TOTAL DOSE EOUfVALENT(mromfyr). 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 i
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a SECTION 5. F I QUALITY ASSURANCE l 5.1 DUKE POWER COMPANY'S PRODUCTION ENVIRONMENTAL SERVICES 5.1.1 SAMPLE COLLECTION l The station or other sample collection groups perf orm the environmental sample collections as specified by approved sample collection procedures. I 5.1.2 SAMPLE ANALYSIS l The Radionnalysis Laboratory performs the environmental sample analyses as specified by approved analysis procedures. In 1989, reviewed data indicated detection of Cs-137 in airborne radiciodine cartridges, but not in associated airborne filters for the same sampling period and location. An extensive investigation was conducted in 1990 to determine reasons why low level Cs-137 activity, approximately 1 to 8 picocuries per total cartridge, was being detected on a low percentage basis of all cartridges counted by the Duke Power Radionnalysis Laboratory. The Radioanalysis Laboratory had increased the possibility of detecting low-level activity due to installation of low background shields for gamma spectroscopy. In addition to the new shields employed, analysis techniques in some instances used extended count times. Experimental results determined that the Cs-137 activity was due to the activated carbon media and was present prior to placement into field sampling units. 5-1
I l Various airborne radiciodine cartridges were obtained from different vendors nationwide which had similar characteristics as the cartridges that were in current use by the Duke Power environmental collection team, Findings support that low-level C5-137 is a fallout product that is incorporated into carbon media. It is anticipated that continual observance of low activity Cs-137 will be detected on a random basis in airborne radioiodine cartridges and any trending of this data will be l reported by the Radioanalysis Laboratory to appropriate nuclet.r station personnel for consideration. I 5.1.3 I 00$1 METRY ANALYSIS The Dosimetry Laboratory performs environmental dosimetry measurements as specified by approved dosimetry analysis procedures. I 5.1.4 I INTRALABORATORY QUALITY ASSURANCE The Radioanalysis Laboratory and the Dosimetry Laboratory performed an internal review during 1990 in order to demonstrate an ability and willingness to perform self-audits, and also to aid in performing duties. I The Radioanalysis Laboratory has-an internal quality assurance program which monitors each type of instrumentation for reliability and accuracy. Daily quality control checks ensure 5-2
W 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 f rom weekly to annually to verify that efficiency calibrations are velid. The frequency is depehdent upon instrument use and performance. Investigations are performed and docun,)nted should calibration verification data fall out of limits. l 5.1.5 INTERLABORATORY QUALITY ASSURANCE 5.1.5.1 DUKE POWER'S AUDIT DlvlS10N The Radionnalysis Laboratory, Dosimetry Laboratory, and Health and Radiological Projects were participants in a Quality Assurance audit in 1989, performed by Duke Power's Audit Division. Two recommendations were identified in the audit. Actions were taken to enhance laboratory operations based upon the two recommendations. No Quality Assurance Audit was performed in 1990. 5.1.5.2 DUKE POWER'S NUCLEAR PRODUCTION INTERCOMPARISON PROGRAM The Radioanalysis Laboratory participated in the Duke Power Nuclear Production Intercomparison Program during 1990. Unknown body burden standards, marinelli beake s, air filters, air cartridges, gross 53
I alpha / beta on smears, and tritium in water samples are analyzed at various times of the year by the four counting laboratories in Duke Power Company for this program. 5.1.5.3 V.$. NUCLEAR REGULATORY COMMISSION INSPECTIONS The Radioanalysis l.aboratory was audited by the NRC in 1990, No violations, deviations or follow up items were identified by the inspector. Vf b 5.1.5.4 UNITED STATES ENVIRONMENTAL PROTECTION AGENCY INTERCOMPARISON PROGRAM a The Radionnalysis Laboratory participates in the Environmental Protection Agency (EPA) Environmental Monitoring Systems Laboratory Intercomparison Program. The EPA sample types include mixed gamma in water (3 times per year), mixed gamma in milk' (2 times per year), gamma in air filters (2 times per year), iodine in milk (2 times per year), tritium in water (3 times per year), iodine in water (1 time per year), gross alpha / beta in air filters (2 times per year), and gross alpha / beta in water (3 times per year). The Radioanalysis Laboratory subunit prepares and analyzes each sample as quickly as possible and performs and
. documents fC low-up investigations should the data l obtained by the Radioanalysis Laboratory be out of EPA limits. The Radionnalysis Laboratory EPA Intercomparison 5-4
1 l I i Report code is "CP". A summary of the EPA Intercomparison l Reports for 1990 is documented in Table 5.1. Of the ! t'hirty-eight (38) analyses performed in 1990, one analysis (tritium in water cross-check, reference date 2/23/90) was out of EPA acceptance limits. Liquid scintillation vial preparation and analysis was investigated and evaluated in 1990 because of the unacceptable tritium cross-check results. The original results were almost consistently biased high, significantly overestimating the tritium activity of the cross-check, Further investigation of low activity vials such as that of the tritium cross-check and background vials revealed a f requently observed CPM variance of 0.00 to 3.00. This variance appears to have been a key influence affecting the poor performance of the lI l original analysis. lI Additional testing and investigation aimed at reducing the CPM variance mentioned above included:
- 1. Increased dark adaptation time l
I 2. Geometry modification
- 3. Decreased counting times
! These measures have significantly increased sample reproducibility and accuracy .o f results. l investigation and testing have documented that both l
- Beckman liquid scintillation counters and current methodology is acceptable and measures to improve consistency of data as mentioned above have been I
, s.s
. I I
l E l incorporated into sample preparation methodology. Additional documentation of this investigation is available from the Radioanalysis Laboratory. I 5.1.5.5 NRC/ STATE OF S.C. ENVIRONMENTAL MONITORING PROGRAM l The ONS Chemistry Section and Radioanalysis Laboratory routinely participate with the State of South Carolina in their NRC/ State Contract Environmental Monitoring Program, The ONS Chemistry Section splits water, milk, vegetation, sediment, and fish samples with the Bureau of Radiological Health of the State's Department of Health and Environmental Control (DEHC) for analysis. DHEC collects air samples from two of the locations sampled for air by ONS. Results of the analyses performed on split and duplicate samples by the Radicarilysis Laboratory and DHEC Laboratory are compiled by DHEC and provided to the NRC. TLDs are also co-located with the State and NRC at various environmental sites. I 5.1,5.6 NRC/ STATE OF N.C. INTERCOMPARISON PROGRAM g Health and Radiological Projects, Radioanalysis Laboratory, and Dosimetry Laboratory routinely participate with the State of North Carolina Department of Environmental Health and Natural l i Resources (DEHNR) in an intercomparison program. Health and Radiological Projects sends air, water, milk, vegetation, sediment, and fish samples which
'I 5-6 l
I 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 irradiatu environmental dosimeters and sends them to the Dosimetry Laboratory for analysis of the unknown estimated delivered exposure. A summary of the State of North Caerlina I Environmental Dosimetry Intercomparison Report for 1990 is documented in Table 5.2. The Dosimetry Laboratory results are within 11% of the State of North Carolina results (excluding Standard Deviation values). 5.1.5.7 U.S. DEPARTHENT OF ENERGY INTERCOMPARISON PROGRAM There was no DOE intercomparison program during calendar year 1990. 5.2 CONTRACTOR LABORATORY No contractor laboratories were used during 1990. 5-7
m m m M M M e m W W W W W m m m TABLE 5.1 U.S. ENVIRONMENTAL FROTECTION AGENCT INTERLABORATORT COMPARISON PROGRAM 1990 CROSS-CHECK RESULTS FOR THE ERL CONTROL LIMITS ANALYSIS DATE NUCLIDE(S) KNOWN VALUE (3 SIGMA: N=31 REFORTED VALUE Ganuna in Water 2/09/90 Ba-133 74 pCi/L 61.9 - 86.1 pCi/L 77 pCi/L Co-60 15 pCi/L 6.3 - 23.7 pCi/L 16 pCi/L Zn-65 139 pCi/L 114.8 - 163.2 pCi/L 149 pCi/L Ru-106 139 pC1/L 114.8 - 163.2 pCi/L 148 pCi/L Cs-134 18 pCi/L 9.3 - 26.7 pCi/L 18 pCi/L Cs-137 18 pCi/L 9.3 - 26.7 pCi/L 19 pCi/L 6/08/90 Ba-133 99 pCi/L 81.7 - 116.3 pCi/L 104 pCi/L Co-60 24 pCi/L 15.3 - 32.7 pCi/L 27 pC1/L Zn-65 148 pC1/L 122.0 - 174.0 pCi/L 156 pCi/L Ru-106 210 pCi/L 173.6 - 246.4 pCi/L 223 pCi/L Cs-134 24 pC1/L 15.3 - 32.7 pCi/L 25 pCi/L Cs-137 25 pCi/L 16.3 - 33.7 pCi/L 27 pCi/L T m 10/05/90 Ba-133 110 pCi/L 90.9 - 129.1 pC1/L 114 pCi/L Co-60 20 pCi/L 11.3 - 28.7 pCi/L 22 pCi/L Zn-65 115 pCi/L 94.2 - 135.8 pri/L 120 pCi/L Ru-106 151 pCi/L 125.0 - 177.0 pC1/L 154 pCi/L Cs-134 12 pCi/L 3.3 - 20.7 pCi/L 12 pCi/L Cs-137 12 pCi/L 3.3 - 20.7 pCi/L 12 pCi/L 8/10/90 I-131 39 pCi/L 28.6 - 49.4 pCi/L 38 pCi/L Air Filter 3/30/90 Cs-137 10 pCi/ Filter 1.3 - 18.7 pCi/ Filter 11 pCi/ Filter Gross Alpha 5 pCi/ Filter 0.0 - 13.7 pCi/ Filter 9 pCi/ Filter Gross Beta 31 pCi/ Filter 22.3 - 39.7 pCi/ Filter 34 pCi/ Filter
M M M M E E TABLE 5.1, (cont.) ENVIRONMDITAL PRCTTECTION AGDICT INTERLABORATORT COMPAFISON PROGRAM 1990 CROSS-CHECK RESULTS FOR THE ERL CONTROL LIMITS ANALYSIS DATE NUCLIDE($1 DiOWN VALUE (3 SIG % N=3) FIFORTED VALUE 11.3 - 28.7 pCi/ Filter 22 pCi/ Filter Air Filter B/31/90 Cs-137 20 pCi/ Filter Gross Alpha 62 pCi/ Filter 1.3 - 18.7 pCi/ Filter 54 pCi/ Filter Gross Beta 10 pCi/ Filter 53.3 - 70.7 pCi/ Filter 17 pCi/ Filter 4976 pCi/L 4113.4 - 5838.6 pCi/L 6196 pCi/L* Tritium in Water 2/~3/90 H-3 2933 pCi/L 2311.9 - 3554.1 pCi/L 2948 pCi/L 6/22/90 H-3 7203 pCi/L 5053.8 - 8452.2 pCi/L 7169 pCi/L 10/19/90 H-3 81.7 - 116.3 pCi/L 102 pCi/L Gamma in Milk 04/27/90 I-131 99 5,ci/L 25 pCi/L Cs-137 24 pC1/L 15.3 - 32.7 pCi/L 47.6 - 68.4 pCi/L 62 pCi/L T 09/28/90 1-131 56 pCi/L 22 pC1/L
- Cs-137 20 pCi/L 11.3 - 28.7 pCi/L 12 pCi/L 3.3 - 20.7 pCi/L 13 pCi/L Alpha-Beta 1/26/90 Gross Alpha 13 pCi/L Gross Beta 12 pCi/L 3.3 - 20.7 pCi/L in Water 22 pCi/L 11.6 - 32.4 pCi/L 21 pCi/L 5/11/90 Gross Alpha 17 pCi/L Grcss Beta 15 pCi/L 6.3 - 23.7 pCi/L 10 pCi/L 1.3 - 18.7 pCi/L 14 pCi/L 9/21/90 Gross Alpha 13 pCi/L Gross Beta 10 pCi/L 1.3 - 18.7 pCi/L
- NOTE: Please see explanation for failure of this cross-check, Section 5.1.5.4.
M M M M M M M M M M M M M M M M TABLE 5.2 STATE OF NORTH CAROLINA DEPARTMENT OF ENVIRONMENTAL HEALTH AND NATURAL RESOURCES Eff1IRONMF.NTAL DOSIMETER CROSS-CHECK 1990 State of N.C. Dosimetry Laboratory Estimated value Estimated valus Exposure Estimated Exposure Estimated (mR) Uncertainty (mR) Uncertainty (1 S.D. e.R) (1 S.D. mR) t 66.1 1 4.6 58.8 1 1.4 T a; r r L
I
6.0 REFERENCES
I 1. Final Safety Analysis Report, McGuire 1 & 2 Section 1.2.1,
- 2. Final Safety Analysis Report, McGuire 1 & 2, Section 2.1.
- 3. Final Safety Analysis Report, McGuire 1 & 2, Section 2.1.1.
- 4. Final Safety Analysis Report, McGuire 1 & 2, Section 11.6.1.
- 5. Final Safety Analysis Report, McGuire 1 & 2, Section 11.6.3.
- 6. Final Safety Analysis Report, McGuire 1 & 2, Section 11.6.4.
- 7. McGuire Nuclear Station Technical Specification 3/4.12.
- 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. I I I I I I I
'I I e-1
- 1. ___ .-_-_ ____--_____ _ -_ _ __ _ _ _ _ ____ _ ______
J APPENDIX A ERYlRQHt1 ENTAL S AM011H2_hMD_ARALYItLS PROCEDURS Adherence to established procedures for sampling and analysis of all environmental media at McGuire was required to ensure compliance to the Station Technical Specifications. Analytical procedures were employed to ensure that Technical Specification detection capabilitias were achieved.
- Envircreental sampling and analyses were perfort.ed by the Duke Power Production Environmental Services Health & hadiological Projects, Radioanalysis Laboratory, Dosimetry Laboratory, end fisheries suounits.
Starting at Appendix A.1, the remainder of this Appendix describes the environmental sampling and analysis procedures by media type. I. QihMGE OF SAMPLING PEDfEQUES The Land Use Census identified an additional food products location at the residence of Elbert Brewer. The Brewer's residence was identified as food prcducts location number 185, and is 4.9 miles from station site in the North sector. Sampling at the Brewer's residence began August 7. 1990. I Surface water sampling location 130 (0.6 mi SW) was moved upstream 0.2 l K miles to the Cowans Ford Dam (0.6 mi W) in August 1986 be c t.use of excessive clogging with the sampling line and pump at the 0.6 mi SW site. The sampling location number is in the process of being changed to 131 to avoid confusion with the location 130 sediment sampling site. II. QltJ1GE OF ANALYSIS PROCEDURES No significant changes to analysis procedutes occurred in 1990. III. SME11HQ_AND ANALYSIjLEEQCEEVEES A.1 h1EBORNE PARTICULATES AND_EhDJ.Q1QD.1HE l Airborne particulate and radioiodine samples at each of five [ locations were composited continuously by means of continuous air samplers. Air particulates were collected on a particulate filter and radioiodines were collected in a charcoal cartridge situated behind the filter in the sampler. Filters and cartridges 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 cartridge gamma analyses were performed separately. I I A-1
l 1 E 5 A.2 DRINKING hAIG I Biveekly composite semples were collected si t Charlotte Municipal Weter Supply (11.2 mi. SSE), Mooresville Municipal Water supply (12.5 mi. NNE), and Davidson Municip 41 Water Supply (7.5 mi. NE). A low-level 1-131 analysis was performed on each sample. A gtoss beta and I gamme analysis were performed on monthly composites. analysis was done on quat terly composites. Tritium - A.3 SURTACE WATEB Biweekly composite samples were collected at the Discharge Canal Bridge (0.4 mi. ENE), Cowans Ford Dam (0.6 mi. W). and Marshall Steam i Station Intake Canal (12.0 mi. N). A gamma and 1-131 analysis were performed on each sample. A gamma analysis was performed on monthly compositen. Tritium analysis was done on quarterly composites. A.4 tilM Biweekly grab samples were collected at Lynch Dairy (14.8 mi. WNw), Henry Cook Dairy (2.75 mi. ESE), William Cook Dairy (2.25 mi, E) and Kidd Dairy (2.8 mi. SSE). A gamma and a low level 1-131 analysis were performed on each sample. An ion exchange resin is used to I remove and concentrate any lodine. The resin is then analyzed by gamma spectroscopy. A.$ BaoADLEAr VEgEI,ti@N Honthly samples were collected at the Health rhysics Emergency Deat I House (0.7 mi. NNE), McGuire Settling ronds (0.5 mi. SW), East Lincoln Junior High School (8.7 mi. WNW), and the intersection of Bethel Church Rd. and Lola Dr. (5.0 mi, NE). A gamma analysis was performed on each sample. I A.6 SHORELINE,,iEDIMENT I Semiannual samples were collected at the Discharge Canal Entrance (0.6 mi. ENE), Hwy. 73 Bridge Downstream (0.6 mi. SW), and Finnacle Access Area (12.0 mi N). A gamma analysis was performed on each sample after drying and removal of rocks and clams. I A.7 E111] l Semiannual samples were collected et the Discharge Canal Entrance 5 (0.6 mi. ENE), and the Pinnacle Access Area (12.0 mi. H). A gamma analysis was performed on the edible portions of each sample. I E I . I A-2
f 5 A.O Dif1CI GMiFA_fJalAll01L11LD.1 Thermoluminescent dosimeters (TLD) were collected quar terly at for ty locations. A gamma dose tate was determined for each TLD. I TLDs were placed as follows: An inner ring of 14 TLDs, one in each meteorological sector (except those prohibited by water,11 and IJtN) in the general area of the site tsoundary; an outer ring of 16 TLDs, one in each meteorological sector in the 6 to B km ranger and I the remaining were placed in special interest areas pepulation centers, residential, schools and control locations. such as A.9 IOOD_PRODEIF Samples were collected monthly, when available, during the harvest season at the Davenport's residence (1.0 mi . E), and the Brewer's I residence (4.9 mi N), A gamma analysis was performed on each sample. A.10 Mi! GAL _1,MiD USE CE115UA An annual land use census was conducted to identify within a distance of 6 km ($ mi.) from the station, the nearest location from the site I boundary following in each of the sixteen meteorological sectors, nearest residence, nearest meat animal, nearest garden, and nearest milk animal e.g., cow, goat. the I I i 1 1 I A-3
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!! LLI il equal to 0, then LLO 15 not retuired by Tethaltal Spetilitatices The LLt's listed above are the valuti required by station Technical $petilltattoos location 120 = Sitt tourdary (0.7 Mi NNE) location 131 Cornellut N; (6.2 Mi NI)
Lotation 121 e Site hundary (0.5 Mi ND Location 134 = tast Littoln Junior me 50.001 (8.7 aaw Location 125 : lite Boundary (0.5 Ri Sul B-3
D.3 DRINKING WATER J [nvireftstrial Raficittital Monitoring Frcgras its+,ary katt of fattlity i Mt6utre49titar$tatten Ictnet b eter i50349,370 Location of facility 1 Mettler4urg County, N.C. Reportleg Period I l Jan 1990 through 31 !st 1940 l fist Report $tittrated t 16-JAA*199113:37123 Catatalt hatt iID!$kt:(UltR.45ClPNS90$M(7 L
! ! ! ! Location etth Highest St an ! ' he cf r
J Medike of l fypt 4 fetal I Ltote : All !rgitator !-~~----~~~~---~~~~ non-Pathsay I k6 ster ef l Latit cf I Locations hast, tillantt and Dtrettnen ! Ccetreltotatteel ' 3cwitet
$4epted 1 Analystl 1fettttien: Rain (Frattlee) : Location Peas (frattitH : Pfan i8 attien' f ecor t (Vrtill : Perlerstd : (LLI) 8angt (cit 8aett l $4ett *tal.
0 1 1(RlktlNSbat[R PC1/LlfER) ! l l 136 ti!.$ "I 44[' 3Lctattnet i ANAll-LL 39 1.0 : 0.00t401 Oi 26) : 0 Mt+Nt 0/ 13) : 0.0M+N( 0/ 1D l 0
- ! . 0.M(+N- 0.0M40 0.Ml+M - 0.0M 40 0.0M40- 0 N[40 1 l : ! : : ;
; AhAL2 LL 19 l 1.0 . 0.0 M 40( 0/ ;e) ! 0.M(+MI 0/ 13) 1 0.00(+Mt 0/ :D ' 0
- : . 0 M(40-- 9.M:40 : 0.0M40- 0.0M+M i 0.vM+M- 0.0M40 1 : ; l 84 54 39: !!. ! 0.00[40( 0/ 16) ! 0.Mt+M t 0/ 13) : 0. M( +M ( 0! !!i 0 1 l 0.Mf 40 - 0.ME40 : 0.0M40- 0.M(401 0.0M40- 0.Mt
- I ! ! ! !
- CC49 39 : !!. l 0.MI40( 0/ 06) '
O.N[40 ( 0/ 13) : 0.0M40( 0/ !!) 0
- : : 0.M(40- 0.00f +M l 0.00(+M- 0.0X+M I 0.M(+M- 0.00140 lB 4
l t 1 i
! FE49 39 i M. : 0.0M40( 0/ 26) : 0 Mt40( 0/ 13): 0.00C +M t 0/ 131: 0
! ! l 0.00t 40- 0. Mi 40 0.M(40- 0.0M401 0.0M*00- 0 M(+N '
i : : l I l tCD40 39 ! !!. : 0.00[40( 0/ 26) : 0.0M 40< 0/ 13) 0 ME40( 0!
! : 0 ME+M- 0.00E40 l 0.Mid:- 0.0M +00 0.0M40- 0. Mio:
I ! : l l l
=
l INi$ t 39 1
- 20. : 0.M(40( 0! 06) :
- 0.M t 40 - 0 NE*00 1 0 Mt+Mt 0/ 13) i 0.ME40( e .D 0.Mi40- 0.0M40 t 0.00t+00- 0. Xtt
- 1 :
- hi 95 39 1 !!. 1 0.00E40( 0/ 26) '
O.N(401 0/ 13) : 0.0M*00( 01 !D ' I : : : 0.0M 40- 0.00E+00 :
- 0. ME 40- 0.0M 40 ! 0 Mt+M- 0 Nt+%
- I g i !R 95 39 ! 15. 0. Mt +M I 0/ 26) : 0 NE401 01 13) 1 0.ME40( 0' :')
g i I 0.ME40-- 0.M(40 1 0.00(+M-- 0.0M +00 1 0.0M40- 0.NE6 > l l t : : 1131 39 I !!. 1 0.ME401 0/ 26) : 0.Mt40( 0/ 13) : 0. 00E + M ' 0! 1: l l l 0.00t 40- 0 Mf 40 l 0.ME+N- 0.ME40 1 0 M(+M- 0.0t !+ l l l I
!C5136 39 t 15. t 0.00t40( 0/ 26) : 0.00E40( 0' 13) : 0.0 M 40( 0/ in I 0.0M+M- 0.ME40 : 0.M(40 - 0.M(40 ! 0.00(40- 0,MI M
! I : :
I CS 137 39 1 10. : 0.00E+M t 0/ 26) t 0.00( 4 01 0/ 13) : 0.00E40( 0/ !!!
! ! : 0.00E40-- 0.HE40 : 0 Mt40- 0.0M401 0.00E+M 0.ME*e-i ! I i !
! BALA-140 39 : 15. : 0.ME40( 0/ 26) : 0.00[40( 0/ 13) ! 0.0M40( 0/ :D 1 : 0.ME+M- 0.00(40 0.M(+M- 0 M(+M ! 6. Ht+M - 0.00( 40 tan and range based upon atttttable staturteents only Frattien of detectable staturteents at specified locations is indicatti in parenthelet, (Frattion) ero ramte indicates no detettahlt activity statureernts
( LLD 15 equal to 0, then LLO ti not required by itettnttal Specif ttations he LLD's listed above s're the valutt required by station Technical Stettfitalical Locatics 132 Cra !ctte Meittpal Water Sucoly (11.2 Mi SSEl Location th * *cortsville Muittsal tater Supply (12.$ Pt hatt) g.4 Location la2 e Davlase6 annitical sater Suetiv l7.5 at ifEl
levironeestal Radiclogical Monitoring Prograe luosary h m of Facility i attutre kutloar Station Octtet b eter 50369,370 B Location of Fatil;ty a hettienburg County, k.C. Ro erting Perici : 1 Jan 1990 through 31 tet it90 flu Report 6estrated i 16 N-itti 13:37:23 Catatate hate i Stiltit(USER.AttinWito $Ui2 I I t l Location eith Highest Pean L ho, of Rettua or i frpt& fetal 1 Leser 1 All intitator l l ker-Fathsay I hutter of I Llett of I Locations : hast, Distatte set Directlen : toetrol Localical E ttet g laspled ! Analytti lletettienI Rear (Frattton) : Location $t an (Frattion) l ' tan (Fractien! Ftport 3 (Units) 1 Fetforeta ! (LLtl ! Raage Code Paage ! Rarit
- tat.
liRINKlk$h4TER 1 l l : : (PCl/LittR) l 1 : : 136 (12.$ at h%It t ! ' 142 (7.5 Pi WE) : 3 Locations !It?A 39I 4.0 1 3.4 ( 17/ 26) : 3.7 ( '/ 13) 1 4.3 ( I! LD 0 1 1 l 2.2 -
- 9. 0 1 2.2 -- 9.0 l 2.5 -- 12.
s.NTRit!DR 1 : : : : (PCl/LittR) ! l 1 l l!!6(12.5atMkil I : : : 142 (7.5 Rt Nil : : I3Lotationi iH3 12l 2.00t+031 6.72t*02( 4I I) : 7.32t*02f 21 4) 1 6.11[+02( ll 41 ' 0 t ! ! 4.92t+C2* 9.71[+02 : 4.92t+02- 1.71t'02 1 6.1tt+02 6.11(+02 ' E Mean and range based upon tetettable staturterets only Frattion of atttttatte staturteents at specified locations is indicated te carrethests, 8Frattioni lere rangt indicates no detectable activity statureetnts 14 LLO is equal to 0, then LLD is not required by fathnical Specifications i itt LLl's listed abovt are the values required by station techattal Spettlicatices 132 Charlttte Nnittpal kater Supply (11.2 Ri $$ti 136
- Poortiville Municipal Water Supply (12.5 Ri ut)
I 142 ' Davidlon Munitipal batte $upply (7.$ Ml N!l 5 B-5
~ J B.4 $URFACE WATER [nvireesentalRadiologicalReuternetPretras$uasary lete of Fattlity i Pt$virt Ntlear I Station Dettet h.eter i M 369.370 Locattori cf Facility : MecklenburgCounty,N.C. #t porting Perles i 1 Jaelt90 throup 314tt 1990 l itet Report 6treratti i 16 JAN 199113:37123 tatatist hast i Olltit!U!!R. A$0lul90.$Mt2 1
! I t : Locatice n th Nie tst mean ! l no, of f Pesius er Fathoav i Type 6 total I (cser i huller Cf I Lttli Of I
- A!! Indicator LCtationi
--~~~~~~~~---~~~l I hate Olltarte and brettice s (catrtlLocatitel kee bitre taalled l Analytti t Detettien 1 Peth (frattton) :Letatten Mese d'attleM i Mean (Trattico , attert (Units) t Per f orsed I (LLD) : Paete : tede Sarp larp : *eas.
l13FACEtAf[R ! l t : B(Ptt/ lit [R) ! l 1 : !!! (12.0 R1 0 ' 33 Locations : AhAtt4L !9' 1.0 t 0.Mt40( 0/ 26) : 0.Ml401 C/ 13) ! 0.0M40( 0/ ID g i t ! 0.M(40 - 0.0M40 0. N E 40~ 0.Ht+M : 0.0M40~ 0.M!+M l I l : 1 ANAL 24L 39 l 1.0 1 0. Mt + M ( 0/ 26) O.NE401 0/ 13) l 0.ME40( 0/ 13) 0 I l l 1 0.M(+M - 0.Mt40 t 0.Mt40~ 0.0M+M t 0.Mt+M- 0.Nt40 ' l I Mh44 39 1 1;. 1 0. Mt+ M t 0/ 06) O.Ml40( t/ 13) : 0.0M40( 0/ 1D : 0
- l 0 Mt+M 0.Mt40 0.00E 4 0~ 0.00! 40 1 0.Mt40- 0.0+:(40 .
1 I ! I i C049 39l 15, l 0.MDMI 0/ 26) 1 0 M(40( 01 13) ! 0 vM40( 01 1D 0 g I ! l 0.MDM- 0.0X+M ! 0.Mt40~ 0.ME+M t 0.0M40~ 0.Mt+00 : g ! ! ! l t 1 Ft49 29 : !0. 0.Mt40( 0/ 06) 0.0M 40( 0/ 13) l 0.0M40( 0/ ID ' o 1 : l 0. Mt + Na 0.0([+M I 0.0M+ M ~ 0.0M +00 t 0 Mt40- 0.M[4^ l l
! CD40 t
39l l l 15. l
! 0.00(+MI 0/ 26) !
- 0.MDM- 0.0M40 :
0.00t
- M I Ol 13) 1 0. 0M *M ( 0/ 1D 0.00t 40- 0.00( 40 1 0.0M40- 0.00t40 g l l l : 1 E i IW45 39 ! 30. : 0.Ml+M t 0/ 26) t 0.00t40( 0/ 13)! 0.00( 4 0( 0/ ID '
I t l 0.NDM- 0.00(40 0.ME40- 0.Mt40 0.Mt40~ 0.Mt.M
- l l l t
- NB45 39! 15. ! 0.00E40( 0I 26) l 0.NE40( 0/ 13) ! 0.0M40( 0! 131 :
! : 0 ME 40- 0.00( 40 t 0.Mt40" 0.00(40 : 0.0 M 40 ~ 0.04t* F I l l ; I l
B t IR 95 39 :
- 15. : 0.00t+Mt 0/ 06) :
1 0.00! 40~ 0.0M 40 l 0.00DM( - 0/ !!) : 0.ME40(
- 0. M(+ M - 0.0M 40 ! 0.00E 4 0- 0. Mt e 01 C t : ! : I i 1 131 39 : 15. : 0.ME40( 0/ 26) l 0.ME+M I 0/ 19 1 0. 0M +M t 0! !?
I I I 0. Mt 40 ~ 0.00( 40 ' O.00E+M~ 0.0M401 0.ME40~ 0.hD5 l l 1 : I t CS 134 39 t t!. t 0.MDM ( 01 26): 0.00E40( 0/ 13) i 0.0M +00( 0/ :D I i O.MDM~ 0.0M401 0.MDM-- 0 ME40 t 0.0M40~ 0.0'.~e t ; I l l
! CS 137 391 10. t 0.M[40( 0/ 26) 1 0.Mt40( 0/ 13) 1 0.Mt40( 0! !D .
1 l l 0. M t 4 0 ~ 0.0 M 4 0 ! 0.ME40- 0.0M+M i 0.ME40" 0.ME*M 1 l l l l
! 6ALA 140 39I 15. t 0.ME40( 0/ 26) 1 0.00E40( 0/ 13) : 0.0M+00( 3/ !D i I I 0.00DM-- 0.00E40 ! 0.00E 40~ 0.0M 40 1 0.0M+M- 0.Mt+M Mean and ranp based upon detectable aesturesents only Fraction of dettttable staturteents at tettified locations it intitated in parentheses, (Fractioni
!tre range indicates fio detettable attivity staturteents if LLO is equal to 0, then LLD ti not required by Technical spectittations the LLD's listed dove are the values required by station technstal 5:ectfications locatten 128 althcarp Canal Brit o (0.4 Ri Ekt) location !!! e (cuans Ford las 40.6 Pt WI (16 i....... e . e .. .. . ..
s (nvirpeental Rasiclogita! honitoring Pregras luonary nameoffattlity Re6uire hstitar $tation totttt hweter 10369,370 totatiot of Fettlity I hecklenturg County, 6.C. 8trerting Ferned i 1 Jan Itt0 through 31 Ott it90 Ilet ktport 6eattated i 16 J8A itti 13:37:23 Catatant kast : It!$tli!L$lR.elt)PW590.tV12 H l I ! ! Location enth highest Mean I ! he ci hedits or i Type i Total i Loort t All !ceitator 1 ~ ~~-~~~~ --- - ~~ ' Ace. 7 Pathsay I huster of I Ltatt of i Letations t nast,DistaettandtitetttenI Contrel Locattenn ' Peuttet taapted I imalysts ! t'etection ! hvan (Frattion) l Location me an (Fraction) : hean !FratticM ' 8 toert (Unitsi t Perforard 1 (Lt.ll ! Rangt l Cett Rangt ; targe etag,
$tTR!flUR : : ! l l (PCIILitLR) 1 I ! ! 135 (12,0 P1 t' '
t i I l 120 (0,4 Ri Ek(I !
- 3 Locations IH3 121 2.0M*03
- 6,57(+02( a' I) : 6.77(+02( 3/ 4) 1 0.00t+00t 0! 41 0 t t : 5,03t+02- 9.22t+02 : 5.03(+02 9.22E+02 1 0.00t+00- 0, N(+00 >
9 tan and rangt basti apon fetettante staturtstett only Traction of detettable staturteents at litt:4tta locatters it inlitated ir parentnetti, (Frattlant I!tro range indicatti ne tetettable attivity staturteents li 4015 tasal to 0, then LLO 16 not etutred by technical $pectfications the LLl's listed above art the values reivired by station technical letttftcatteet Locatten 128 e Distrarge Canal irtegt (0.4 Pi (Nil [ Location 131 ! nant Ford taa (0.6 et 0 y Lccation 13$ Plar:t Marshall Intate Canal (12,0 Mi N) i i l i 1 5 B-7
B.6 MILK taviroanntal f atteltglial hcettertag Prtyas lustary saw of Fattltty i ht69tre kutlear $tation 00ttet % sbee i 10 169,370 Letation of Fattlity Rettletturg Cntity N.C. leportlet Perict i 1 Ju 1990 tt* rough 314et 1990 l fine Report 6teersted i 16 Ja* 199113:37 ;3 Cateten base i selittilt'stR.A$C W .90.5&J i2
...... .... .. .... - ..... . ........... ... ~..................~.......... .......... ................................
t 1 ! l t:tation enth nient Man ! ' hp. cf CeQlte of l Iype 4 Istal ! 60ser ! AllIr.iltat0r ; 40t-Pattsay ! haattr tf ! Litti 04 ! LDtatt0rt ha H i Dtit ute and Dirtttlen ! Centr 31 (statttfl 8 wttre i fatilti tuaits) i Ar.alius PeH:'etd
'tetettlee!
'LLil :
'e n d'attloo 8Ple
- Ltt a ti on
- Cete Se p drattico Raete
*e o Prattt:0 sp;,
' lettet e,eg,
- i I Mid (PCl/L!IER) ;
l . l 11812.7$'ititi '
- t l l 41,ttatiget iPk-14 104 t0 l 0. Mt + M ( 0/ 76) I L Mt+00( 0/ 20 l 0.0M+M( i! .'O .
t l 0 Mt+Ma 0 Mt*M i L Mt+Ma 0.0M40 0.M(+M~ 0.Ht*M
- C0-58 104 0.0 O.Mt* M t 0! 78) '
O.Mt40( 01 26) ' O.0M+Mt 01 lL ' I t Ft19 104 I L0 l 0.M!+M - 0.Mt+M 1 t l 0.00t+MI 0/ 78) 1 0 Mt40~ 0.00(40 0.Mt*N( 0/ 26) i 0.0M*M( I 0.0M+M-. 0.Mi M 0/ 26) . 0 g l t 0.Mt 40" 0.00t*H I 0. Mt 40- 0. M1 40 l 0.0M+M~ 0.Mt*H t 3 i t ; ; J l C0 60 104 0.0 1 0 Mt40( 0/ 78) O.00(401 01 20 1 0.0M 40t 0/ 20 , 0 i ! ! 0.MDM~ 0.0M*H l 0.Ml40~ 0.Mt401 0.Mt40~ 0.Mt*M ' I :
;lh*6$
104 0.0 i L Oct+M t 0/ 78) l 0.0M+M- 0.0M401 0.00!40( 01 261 ! 0.Mt +M( 0/ h) ' 0.Mt40~ 0.00(401 0.0M40- 0.Mt*M ' 1
^
I l l t !
! Q 95 10s t 0.0 1 0.0M+M( 01 78) l 0Mt+M( 0/ 20 l 0.0M 40( 0! l0 )
L Nt40.- 0.0M+00 1 0 Mt40~ 0 Mt401 0.0M40--0.Ht0 I I i l 1 1
! ZR 95 104 1 0.0 1 0.00t+Mt 0/ 78) : 0.00t+Mt 0/ 26) 1 0.0M +M ( 0! l0 .
I ! I L MD M- 0.Mt+M i 0.Mt40- 0.Mt+M l 0.Mt+M~ LWie' I 1 1 I : 1 131 104 l
- 15. l 0.Mt+MI 0/ 78) 1 0,00t+M~ 0.Mt40 t l 0.Mt+M I 01 26) i 0.Mt40( U lt' 0.00t+Ma 0.Mt+M i 0.0M*M~0.Nt '
1 t LLt 131 104 : 1.0 1 0.Mt +00( 0/ 78) : 0.Ht +M t 0/ :D hMt40( f'l 20 O.Mb00~ 0.0M+M i 0 Mt 40~ 0.0 M 40 1 0.Mt+M" t Nt M l t i 1 l 1 CS 134 104 t 15. 1 0.Mt+M t 01 71) l 9.Mt+00( 0/ 20 l 0.9M+00( 0/ h* 1 1 1 0.Mt+M- 0.0M40 ' O.00(40~ 0.0M*001 0.Mt40~ ant ** i ! ! l 119(2.75Mi($t) i ICS137 104 1 18. I a.7 I 6/ 78) ! 5.3 t il 20 t 2.6 ' !! hi 9
! ! I 2.2 - 7. 4 : $.3 - 5.3 1 2.6 -
- .t t t t l 1
- 88 0 140 104 1 15. 0.ME+M t 0/ .78) : 0.MDM t 0/ 20 1 0.Mt40( 0! h' i i ! 0.MDM- 0.0M*M i 9.Mt40 . 0.00t+M 0.0M+M~ 0.Mte^
Cean ut rule based usca detectable stature 6ents only Frutton of detectable menurnets at trettitte locatices is indicated in parentheses Uratttoni lePo range teditates t.c detettable sttivity seassrHents if LLD 15 t;ust to 0, then LLD 15 not requista by fethnical $pettlications The LLl's !!sted above are the values reqvtred by statics fethettal Specificatterns Locatten !!I e Henry C:ok tairy (2.75 Mi (Sil Location 140 o Kidd Dairy - COWS (2.8 Pi $$D Location 139 + tillies test f airy (2.25 Mi () Location 141 = Lynth latry COWS 114.8 Mi m) B-B
B.6 BROADLEAF VEGETATION Invironeental Rattelogical heetterleg Prtgese $westry kaseofFattlity I ht6 wire Atlear $tation Dottet h.eter i 50 369,370 Location of f attlity i Pettlenhrt County. n.C. Reporting Pertet i 1 he 1990 throup 314et let0 Datatate haae : IlllilitultR.A$CI MS90.5AF i2 B .......flee Report
............. 6teersted
.............. i 16 JAh lH113:37:23 I 1 1 ! l Lccation eith Mtpelt me an ; ; ha :(
. nev n e or i tn e 6 fetal 1 to.er : All lecitator ;-~~.------~~~-- her.
Fathay I h6tter of l Lisit of I Locatters ! hase, Otttante see Ottettton : Coett:1 Letations . Fowitte laspitd I Artalytet ! Dettttit'n ! Penn (frattton) . Location *ean W attleel les* 8t actt:0 ' 8etert (l)nitti ! Perforste ; 'LLO)
. l P aa.it C tt 8 aa.;e l Esa;e :
- eat.
HM LEAT VHE1 ! 9:!/htitr6) . : : 1:4 't,' %mi :
- : l tth$4 al : 0.0 1 0. Ml+ M ( 0/ 3D ! 0. N(+ 001 0/ 12)1 0.0M+M( 9/ !D ?
54 Locations l : 0.00(+ M - 0 NE 40 : 0.Ml+M- 0.00(+M t 0.Mt+00.0.Wi40:
! 1 l l :
ICD!B 48 : 0.0 0.Mt+Mt 0/ !6) ! 0.Mt+MI 0/ 12) : 0.00(40( 0/ 12) ' 0 B ! l . 0.M(+M- 0.00160 1 0 Mt+M- 0.00E 40 t 0.0M40- 0.ME40 ' l l : !
! 8E !9 49: 0.0 : 0.Ml+ M I 0/ !D (. 0vt+ M t 0I 12) : 0 NE+MI 0/ 121 - 0 I ! ! ! 0.M(40- 0.M(40 t 0 ME+M- 0.M(40
- 0.H(+M - 0.Mt40 l l l l t l tC040 49 1 0'. 0 1 0.00[40( 0/ 26) : 0.00t40( 0/ 12) 1 0.ME+M( 0,' 121i '
I ! i
! 2445 4I 1
0.0 l 0 Mt+M- 0.0M W l l 0 Mt40( 0/ 3D : t 0.ME+M- 0.0M*M I 0.Mt+M- 0 ME40 ' 0.M(40 ( 0/ 12) ! 0.00(40( 0/ 12) 0
- I ! 0.00E40- 0.HE*00 : 0 ME40- 0.0Mt00 ! 0.0M40- 0.0M40 :
I ; I 0/ 36)
- 1 of : 0.NE 40 ' 0/ 121 1 0.0M +M I 0/ 12) 1 NI*t5 0.0 O.ME+M( '
- : 0.001 40- 0.00( 40 i 0.00(40- 0 M(+00 t 0.Hi+ M-- 0 M I 40 '
- ! ! I t IR45 al 1 0.0 1 0.ME+Mi 0/ 3D 0.00E40( 0/ 12)1 0.ME+005 0! 1D >
i i 0 ME+M - 0.0M 40 0.00(40 0.0M40 t 0 Mt+e0 0,Mie. I l 1*l31 'l ' 60. l 0 M(+M( 0/ 36) . 0.00(40( 0/ 12) ! 0.0M40t or 12' l ! 0. ME+ M - 0.00( 40 : 0.00t40- 0.ME+00 1 0.0M+00- 0 M(40 I
- I : :
- CS134 49t 60. 0. M(+ Mi 0/ 34) : 0 M(+Mi 0/ ID 0.00E +M t 0/ !D 1 : : 0 M(+M- 0.00E*00 ' O 00(40- 0.M(40 : 0,M(40- 0,N(40 .
' 125 (0.5 m SW)
I i l l :
! CS 137 48l 90. ! 37. t 2/ 36) : 40. ( 1/ 12) l 0.00E40( 0/ :D t l l 34. -
- 40. l 40. -
- 40. ; 0.H(+M. 0.09EO :
1 1 i i t BAL6140 46 1 0.0 1 0 Mt40t 0/ 3D t 0. ME +" 2/ !2) : 0.00E+00( 0! tb > I l 1 1 0.M(40- 0.0M401 0.0M49- 0 M(401 0.00E*M. 0,t)(+F. Mean and rangt aled upon detettable setturteents only IFrattien of detettable seas.: resents at specified locations it inditated in parenthtnes, (Fraction) lero range tatttates no detectable activity staturteents If LLD is toLil to 0, then LLD tt not required by technical Specifications the LLD's listed above are the salatt retaired by station techattal Soetificattent Location 120
- Site Boundary (0.7 Rt %El Location 125
- Site Boundary (0.5 Mi SW)
I location 134
- Catt Libelon Junter High School (8.7 Mi mi location 150
- 4 t Mile Radigt (5.0 Mt NE)
B-9
B.7 SH0 RELINE SEDIMENT Environmental Radiological Gonitoring Progras Suewy Naa, of Facility : Mc6uire butlear Station Docket Nueber 50 369,370 i Location of Facility : Mecklenburg County, N,0. Reporting Period : 14an 1990 through 314et 1990 Time Report Generated i 164M 199113:37:23 Catatale Nase t 40lSX1t(USER.ASC)MNS90.SAF 2 1 Medlue or 1 1 i Type 6 total l Loser All Incicator
! Location nith Highest Mean ! I Nc. of l l :-~~-~~------------I : Non-Pathsay 1 Nueber of 1 Lisit of I Locations ! Maet, Distance and Direction !
I Control Locations Routine Stapled ( *nalyses
. 1 Ottection I hean (Fraction) 1 Location Mean (Fraction) : Pean (Frattion) i Report (Units) i Perforced I (LLDI I Range i Code Racgt i Range ! Meas.
l ! l 1 I l 5 SEDIMENT (PC!/ CRY /K6) I ! 137 (12.0 M1 N) : 1 1 1 l 129 (0.6 Mt ENE) i ! j 3 Locations ! MN 54 6 0.0 l 38. ( ll il l 38. ( II 2) ! 0.0M+M( 0/ 2) 0
! l l 30. - 38. ! 38. --
- 30. t 0.00E 4 0- 0. M E 40 i l l l l129 l l l r0 58 6: 0.0 1 27. ( ll 4) ! 27. I 1/ 2) 1 0.0M +00( 0/ 2) :
I 0 l 1 27. - 27. l 27. --
- 27. t 0.ME40-- 0.00E*H !
! : : I l FE 59 61 0.0 1 0.00E+M( 0/ 4) : 0.0M+00( 0/ 2): 0.00E +M( 0/ 2} l 0
! 1 0.ME40- 0.MEd01 0. ME 4 4-- 0.00E 4 0 1 0.0M40-- 0.00E40 :
5 I
!CD-60 61 1
0.0
- N' t
! 1.68f ' 2/ 4) : 1.6BE+02( 2/ 2) 1 0.0M+00( 0/ 2) : 0 l l t.3 W E+02 i I
l 1.33E 42 - 2.02E 4 2 1 0.ME40 - 0.00E40 t l l l ; ; 1 i IR45 61 0.0 t
.. w de'li c 4) : 0.00E40( 0! 2) 1 0.00E40( 0/ 2) : 0 1 1 : 0 4 C a-- 0 A
- 40 1 0.ME+M - 0.ME40 l 0.0M+00- 0.00E40 i I l l NS 95 1
6i 1 1 0.0
! 0.0 4t0h 0
! 0.026 + ' ;0E40
- 4) 1 l 1 0.00E40( 0/ 2)1 0.00E+M( 0/ 2) :
0.00E40- 0.0M40 t 0.00E+M- 0.ME40 ' 0 I i t IR 95 6l 0.0
! 0.0M40( 0/ 4) 1 0.00E40 - 0.0M+001 1
0.00E+M t 0/ 2) t 0.0M40( 0/ 2) : 0.00E+M - 0.0M 40 1 0.0M+M-- 0.ME40 : l 0 i I I ! ; l !13l 6i 0.0 1 0.00E+M( 0/ 4) 1 0.@E401 0/ 2) 1 0.00E40( 01 21 l 0 1 l l 0. ME 40-- 0. ME+00 1 0.00E40-- 0.0M+00 t 0. ME40- 0.00E 40 :
- i l l I lCS134 t
1 6l 1.50E42: 0.00E+00( 0/ 4) 1 I I i
- 0. M E 40 0.0 M 40 ;
0.00E+00( 0/ 2) : 0.ME40( 0.00E+M- 0.0M40 1 0.0 M 40 - 0. M E40 : i 130 (0.6 Mi SW) l 0! 2) : 0 I 6t 1.80E+02 1 i CS 137 49. I 4/ 4) : 61. ( 2/ 2) : 21, t l/ S: 0 l t 1 27. -
- 91. t 31. --
- 91. l 21. -- 21. '
t i '
! I :
8ALA-140 61 0.0 1 0.0M40( 0/ 4) l 0.ME+00( 0/ 2) t 0.00E*M( 0/ H ' ^ i 1 1 0.00E 40-- 0.00E+00 1 0.00E40-- 0.00E+00 t 0.ME 40- 0.00E 40 ' I Gean and range based ust... detectable seasurteents only IFraction lere range indicates of detectable no detectableseasurteents attivity esasurementsat specified locations is indicated in pareatheses (Fraction) 1f LLD is equal to 0, then LLD is not required by Technical Specificatient The LLD's listed above are the values required by station Technical Specifications l L.ocation 119 = Distharge Canal Entrance te Lake Norman (0.6 Mi ENE) Location 130 = Highsay 73 Bridge Downstreas (0.6 Mi SW) Location 137 = Pinnacle Access Area (12.0 Mi N) B-10
EQvieoneea*al Ragialgical Constortag Prog 7as Suesary llate of Facility : McGuire Nuclear Station Docket huecer i 50 369,370 Location of Fattlity Mecklenburg County, N.C. Peportteg Period i 1 Jan 1990 through 3l4et 1990 l Time Report Generated a 16 JAN-1991 13:37:23 Database Nase t 80!Sil:(L'5ER. ASCIMWS90.SAFl2
- I t l Location enth Highest mean 1 ! he, et Medite or i Type n Total'I Lower ! All Indicator 1-~~-----~~~~-~~~~~t : N:e-Pathsay i Nueber of I Lient of I Locations hase, Distance and tirection i Control Locations ! Routtre Sainted 1 Analyses ! Detection ' Pean (Frattion) I Location Mean (Fraction) l Rean (Fraction) fRecert
(!! nits) l Perforced ! (LLD) i Range C:dt Raege : Range t Meat. [ FISH I i i . i : l(PCl/uE1/K6) 1 i I l l 137 (12.0 M 0 '
! l t l l l 3 Lo:ations ! MN 54 12 1 1.30E 42 : 0.0M 40( U 6) ! 0 NE*M( 0/ 6) t 0.0M40( 0/ 6) : 0 1 0.ME40-- 0.ME+00 l 0.00E 40 ~ 0.00E 40 1 0.ME40- 0.0M+M :
I l l 129 (0.6 Mi ENE) l l 00 58 12 : 1.20E+02 i 56. i 1/ 6) 1 56. ( 1/ 6) 1 0.ME 40( 0/ 61 1 0 lB l 1 t t t
- 56. ~ $6. l I
$6. ~ 56, l
t 0.ME*M~ 0.00E40 : t FE-59 12 1 2.60E42 1 0.ME40 t 0/ 6) 0.ME+M( 0/ 6) 1 0.0M 40( 0/ 6) : 0 l : I 0.00E40-- 0.0M+M l 0.ME40-- 0.0M40 l 0.0M40- 0.NE+M ' I t t t 129 i l CD 60 12 1 1.3M42 1 41. ( 2/ 6) ! 41. ( 2/ 6) : 0.00E+00( CI 6) : 0 l l l 36. ~
- 47. ; 36. --
- 47. t 0.ME40- 0.00E+M :
- : : i i :
I IN 65 12 ! 2.6M +02 0. ME +M t 0/ 6) : 0.00E+001 0! 6) i 0.0M40( 0/ 61 1 0 < l i i 0.00E+M- 0.00E40 ! 0.00E40~ 0.ME40 ! 0.0M 40-- 0.ME+ M l ) lB t 1095 1 0.00E40( 0/ 6) 1 I ! l 12 1 0.0 0.00E40( 0/ 6) 1 0.0M 401 0! O: 0 i I 0.00E40~ 0.ME+00 0.NE40~ 0.0M401 0.00E 40-- 0.00E 40 1 i i 1
- IR-95 12 1 0.0 1 0.0M40( 0/ 6) i 0.00E+NI 01 6) 1 0.0M 40( 0/ e: 0
! : 0.0M40-- 0.00E+00 0.00E+M~ 0.0M40 1 0. ME+00- 0,ME 49 l ! ! : :
l I-131 12 1 0.0 l 0.00E+00( 0/ 6) t 0.00E40( OI 6) ! 0.0M40( 0/ P( 0 I l t 0.00E 40 - 0.00E 40 1 0.00E+M~ 0.00E401 0.0M+00~ 0.00E+00 i ! ! ! l : l t CS-134 12 1.30E42 1 0.00E40I 0/ 6) 1 0. 0M+00 ( 0/ 6) 1 0.00E+00( O' Cl ' l l t i 0.00E+ M- 0.0 M +00 t 0.00E40- 0.0X40 ! 0.0M40- 0.ME40
! ! ! l129
! CS-137 12! 1.50E*021 33. ( 5i 61 l 33. 51 6) l 16< ( 1/ e '
t i ! 12. --
- 44. ! 12. - 44. ! 7.5 - 27 !
l 1 ! i ! l BALA 140 12 1 0.0 i 0.00E+00( 0/ 6) 1 0 ME4 ( 0/ 61 t 0.ME40( 0! O: ' I I I 0.0M+00-- 0.0M+00 0.00E+M-- 0.00E40 1 0.0M+00~ 0.0M40 ' Mean and range based upon detectable seasureatats only f action of detectable seasurteents at scecified locations is indicated in parentheses, (Fra: tion) evo range indicates no detectable activity seasurteents if LLD is aqual to 0, then LLD is not required by Te:hnical Specifications lhe LL9's listed above are the values required by statier. Technical Specifications Location 129
- Discharge Canal Entrance to take Noraan (0.6 Mi ENE)
Location !!7 = Pinnacle Access Area (12.0 Mi N) l B-11 '
l B.9 DIRECT GAMMA RADIATION (aviron6 ental Qadtolceital Gonitoring Prtgras Suesary g Nata of Factitty : McGuire hclear Station Doctet heter 50 369,370 g Location of Facility Meckledurg County, N.C. Reporting Perted i 1 lan 1990 through 314ec 1990 flee Report Generated 16 JM 199113:41133 Datatste kaea i 40!$tt:(USER. ASClHKS90.SWi2
........- ~ ...... - .. ............ ...... ...... .. .. . .... .. .... .... .. ........
j i I ! ! Location eith Highest Mean i l ho, of W Medlue or ! Type 6 total i Leser All ledicator l---~~---------------~l I Non* Pathsay i Rueber of I Liest 04 1 Locations I hase, Distance and Direttien 1 Control Locations : Routiet I Stapled (Units) 1 Analyttl
! Perf or ced 1 Dettttien !
I (LLD) l Mean (Frattion) Rangt
! Location
! Code Mean (Fraction)
Range l i Mean (Frattient Range i Peport 1 #est. DIRECTRAD-TLD 1 ! ! ! ! l I(sR/OuaPter) l I I i i ISO (11.5 Mi UE) 1 I 175 (12.7 M kNul ! l
! allocatlons I eR/0tr 163 1 0.00E+00 l 12. I!!9/159) I 21. I 4l 4) ! 16. ( 41 4) :
h3 0
, t ! l 4.9 -
- 26. I 16. - 24. l 11. ~
- 23. :
Mean sad range based upon detectable etasurements only IFeaction Zere range of detectable indicates no detectablesessurteents activity eraturteentsat specified locations is indicated in parentheses, (Fractioni if Lt.@ is equal to 0, then LLO is not required by itchnical Specificattoes I 143
- Site Boundary (0.5 Mi H )
144 = Site loundary (0.6 Mi HE) ' 163 = 4 5 Mile Radius (5.0 Mi SE) 164
- 4 5 Mile Radius (4.5 Mi SSE) jl st 145
- Site Boundary (0.5 Mi NE) 146 : Site Boundary (0.5 Mi ENE) 165 = 4 5 Mile Radius (5.0 Mi S) 166 = 4 5 Mile Radius (5.2 Mi SSW) 147 = Site Boundary (0.5 Mi E) 167 = 4 5 Mile Radius (4.9 Mi SW) 148
- Site Boundary (0.5 Mi ESE) 168
- 4 5 Mlle Radius (4.7 Mi WSW) 149 = Site Boundary (0.7 Mi SE) 169 = 4 5 Mile Radius (4.4 M1 W) 150 : Site Boundary (0.5 Mi SSE) 170 4 5 Mile Radius (4.5 Mi uw) 151
- Site Boundary (0.5 Mi S) 171 s 4 5 Mile Radius (4.5 Mi H) 152 = Site Boundary (0.5 Mi SSWI 172 = 4 5 Mile Radius (5.2 Mi HW) 153
- Site Boundary (0.5 Mi SW) 173 Special Interest (B.5 Mi MW) 154: Site foundary (0.7 M NSW) 174 = Soecial Interest (0.7 Mi kW) 155 = Site Boundary (0.7 Mi W) 175 a CONTROL (12.7 Mi kW )
156
- Site Boundary (0.5 Mi HW) 176 = Special Interest (11.0 Mi SW) 157
- 4 5 Mile Radius (4.8 Mi N) 177 = Snecial laterest (6.6 Mi $)
158 4 5 Mile Radius (4.4 Mi MEl 178 : Special Interest (9.2 Mi SEI 159 a 4 5 Mile Radius (5.0 Mi WE) 179 Speciat '* rest (10.4 Mi ESE) 160 4-5 Mile Radius (4.9 Mi ENE) 180 : Special Interest (11.5 Mi ME) 161 = 4-5 Mile Radius (4.7 Mi El 181 Special Interest (6.7 Mi NE) 162 = 4 5 Mile Radius (4.6 Mi ESE) 182 = Scecial laterest (6.0 Mi NE) 153 = Scecial Interest (5.5 Mi S) , 1 B-12 1
i B,10 F000 PRODUCTS l Environeestal Radioletttal Conitoring Progras Suasary Name of Facility : Mt6uire Nuclear Station locket husber i 50 369.370 i Location of Facility : MeckledurtCounty,N.C. Reporting Peried i 1 Jan 1990 through 314et 1990 24tatase haee : HISKli(L!SER. A$ClRN$90.$Afl2 Time Report Generated i 16*JAN 199113:37:23
-t I Locattori sith Highest Mean : No. of I Medies or 1
i Type n Ictal I Leser 1 1 All Indicator !---~~~-~~----~~--- I hen-Path:4y l Nueber of I Liait c4 ! Locations I hase, Distance and Direction I control Locations ! Routine
! Detection ! '!ean (Frattion) : Location Mean (Frattion) l Mean (fraction) : Report Saapled l Analties I (l)nt ts) l Peffersed 1 (LLD) : Range : Code Range ! Range l Reas.
. ~. .... ........ .. .... .............. -...................... ~..............- ..........~ .......... ............ ....
l 1 1 : : ICit0P6 (pct /WE1/K6) I i 1 I i l No Control Locatiens : 1 2 ! MF 54 12 0.0 : 0.0M+Mt 0/ 12) : 0.NE+M( 0/ 7) 1 0.ME+00( 01 01 1 0
- 0.00E+M-- 0.0M40 : 0.ME+M- 0.0X401 0.00E*00 0.NE*M :
5 ' Locations ! i l i : 1 i
! CD 58 12 1 0.0 t 0.ME+Mt 0/ 12) ! 0.NE40( 0I 7) i 0.ME 40( 0/ 0) 1 0 t l l 0.00E40- 0.0M+001 0 ME+M- 0.0X40 t 0.0M+00- 0 ME40 I t- l t t t FE 59 12 : 0.0 i 0.ME40( 0/ 12) 1 0. 0M+M t 0/ 7) 1 0,00E+M( 0/ 0) ! O
. . . 0.00E+M- 0 ME*00 l 0.NE+M - 0.0M 40 1 0.0M40- 0.ME*M i t
I : CD-60 12 l 4.0 l 0.M!40( 0/ 12) 1 I t 0 ME40( 0/ 7) 1 0,0M @0( 0/ 0) 0 t i ! 0.00E 40- 0.00E 40 1 0.ME+M- 0.ME401 0.0M+00- 0.00E+M ! l ! ! l
! l l !N 65 12 1 0.0 t 0.00E+Mt 0/ 12) : 0.00E40( 0/ 7) 1 0.00E +00( 0/ 0) ! 0 1 : I 0 NE+M- 0,00E401 0.00E40-- 0.0M401 0.0M+M- 0.00E+00 l 1 I i ! !
I hi 95 12 1 0.0 1 0.00E40( 0/ 12) : 0.00E40( 0/ 7) : 0.00E+00( 0/ 01 0 i t i ! 0.00E+M-. 0.0M+00 : 0. ME 40-- 0.0M 40 1 0 ME40- 0.Mt+M ' i 1 i I i IR 95 12 1 0.0 1 0.0M+M t 01 12) 1 0.00E40( 0/ 7) 1 0.0M+00( 0/ ^) . 0 l .I ! 0.00E+M- 0.ME40 ! 0.0M+M- 0.ME40t 0.00E40- 0.NE+M : l l l l : i l 131 12 : 60. 0 NE 40( 0/ 12) 1 0.00E40( 01 7) : 0.0M40( 0/ 0) 0 i : 0.00E40- 0.ME40 t 0.0M40- 0.00E40 0.M!+M. 0.00E40 : I t i t l l CS 134 12 l 60. : 0.00E40( 01 12) ! 0.00E40 t 0/ 7) 1 0.0M + M t 0/ 0) 0
- 1 I 0.ME40- 0,0M+00 0.00E+M- 0.0M401 0.ME+00-- 0.00E 40 t t t i t CS-137 12 1 80. t 0.00E40( 01 12) ! 0.NE40( 0/ 7) ! 0.00E+00( O! 0' '
l l t 0,00E+M- 0.0M40 -; 0.00E 4 0 - 0.00E+00 1 0.ME+00- 0.NE40 : BALR140 12 t 0.0 ' 0.NE+00( Ol 12) : 0.00E40( 01 7) : 0.00E+00( 0! 0' 0 1 1 1 0.ME40- 0.ME40 : 0.ME+M 0.0M401 0.0M40- 0.00Edo Cean and range based usan detectable seasureaents only Fraction el detectable seasuresents at 59etified locations is indicated in pare-theses, (Frattion) Itro range indicates no detectable activity seasuresents if LLD is equal to 0, then LLD is not required by Technical Specifications The LLD's listed above are the values required by station iethnical Specilitations location 184 = 5 elle radius (2.5 Mi EE) - Gardens (Davenport's Residwce) Location 185 = 5 alle radius (4.9 Mi N) - Gardens (Breuer's Residentei B-13
APPENDIX C
]
MCGUIRE NUCLEAR STATION SAMPLING DEVIATIONS AND UNAVAILABLE ANALYSES I. SAMPLING DEVIATIONS The deviations from sampling procedures that occurred during 1990 are listed below. A. Air Filter /Cartridae
- 1. Location #121, 4/24/90 to 5/1/90 Reason Sampler found not running due to a blown fuse.
M112D i Replaced fuse and restarted sampler. Sampler ran for 47.4 hours.
- 2. Location #133, 6/5/90 to 6/12/90 Reason: Sampler found not running due to a blown fuse.
M11cDi Replaced fuse and restarted sampler. Sampler ran for 11.8 hours,
- 3. Location #133, 6/12/90 to 6/19/90 hunni Sampler found not running due to a blown fuse.
Action Replaced fuse and restarted sampler. Sampler ran for 51.3 hours.
- 4. Location #133, 8/7/90 to 8/14/90 Reason, Sampler found not running due to a blown fuse.
Action: Replaced fuse and restarted sampler. Sampler ran for 83.7 hours.
- 5. Location #133, 8/14/90 to 8/21/90 Rea. son: Sampler found not running due to a blown fuse.
betion: Replaced fuse and restarted sampler. Sampler ran for 116.1 hours.
- 6. Location #133, 8/20/90 to 9/2/90 hassni Sampler found not running due to a blown fuse.
Action: Replaced fuse and restarted sampler, plan to install surge protector. Sampler ran for 116.3 hours. C-1
I I 7. Location #133, 9/4/90 to 9/11/90 ERA 10D i- Sampler found not running due to a blown fuse. Action Replaced fuse and restarted sampler. Sampler ran for 62.3 hours.
- 8. Location #133, 9/25/90 to 10/2/90 Beason: Sampler found not running due to a blown fuse.
Action Replaced fuse and restarted sampler. Sampler ran for 34 hours.
- 9. Location #133, 10/2/90 to 10/9/90 Reaso.ni Sampler found not running due to a blown fuse.
Action Replaced fuse and restarted sampler. Installed surge protector. Sampler ran for 32.3 hours.
- 10. Location #133, 10/'s/90 to 10/16/90 Reason: Sampler found not running due to a blown fuse.
Action: Replaced fuse and restarted sampler. Sampler ran for I 69.5 hours.
- 11. Location #133, 10/16/90 to 10/23/90 Reason: Sampler found not runnign due to a blown fuse.
Action: Replaced fuse and restarted sampler. Replaced sampler due to history of blown fuses. Sampler ran for 49.6 hours.
- 12. Location #120, 10/16/90 to 10/23/90 Reason: Sampler found not running, the electrical plug worked out of the socket.
Action Plugged in and restarted sampler.
- 13. Location #121, 11/6/90 to 11/13/90 Reason: Sampler found not running due to a blown fuse.
Actioni Replaced fuse and restarted sampler. Sampler ran for 138.7 hours.
- 14. Location #125, 11/27/90 to 12/4/90 Beasont Damage to the charcoal cartridge occurred during C-2
collection. The cartridge became fused to the sample L head and had to be pryed loose to collect. A small amount of the charcoal was lost in the process. The particulate filter and the sampler run time was not [J affected. This is an ANALYTICAL deviation. Action: A new sample head without such a fine tolerance was placed on the sampler. l B. Surface Water
- 1. Location #128, 2/20/90 to 3/6/90 Reason: Sample timer malfunction.
ActioD: Collected grab sample, adjusted timer and notified Technical Services personnel of the malfunction.
- 2. Location #130, 2/20/90 to 3/6/90 Reason: Sample timer malfunction.
Action: Collected grab sample, adjusted timer and notified Technical Services personnel fo the malfunction.
- 3. Location #.135, 5/1/90 to 5/15/90 Reason: Sampler not operating due to electrical problems.
Action Collected grab sample, notified Technical Services I personnel for repair.
- 4. Location #135, 7/10/90 to 7/24/90 I Reason: Composite sampler malfunction.
l Action: Collected grab sample, notified Technical Services B personnel for repair.
- 5. Location #135, 7/24/90 to 8/7/90 Reason: Sampler not operating due to a surge protector malfunction.
Action: Replaced surge protector on 7/26/90 at 09:35. Collected an abbreviated sample on 8/7/90. C. Drinkine Water
- 1. Location #132, 5/1/90 to 5/15/90 Reason: Sampler not operating due to pump replacement by water department personnel.
C-3
s t Action Collected grab sample.
- 2. Location #132, 5/15/90 to 5/29/90 l Brjul2D: Sampler not operating due to pump replacement by water department personnel.
Action: Collected grab sample,
- 3. Location #132, 5/29/90 to 6/12/90 8eason: Sampler not operating due to pump replacement by water department personnel.
Action: Collected grab sample.
- 4. Location #132, 6/12/90 to 6/26/90 Reason: Sampler not operating due to pump replacement by water department personnel.
Action: Collected grab sample.
'5 . Location #132, 6/26/90 to 7/10/90 Reason: Sampler not operating due to pump replacement by water I department personnel.
Actioni Collected grab sample.
- 6. Location #132, 7/10/90 to 7/24/90 Reason: Sampler not operating due to pump replacement by water department personnel.
Action: Collected grab sample,
- 7. Location #132, 7/24/90 to 8/7/90 Reason: Sampler not operating due to pump replacement by water department personnel.
Action: Collected grab sample. B. Location #132, 8/7/90 to 8/21/90 Reasorp S mpler not operating due to pump replacement by water department personnel. Action: The pump was placed back in service 8/10/90 @ 1200. An abbreviated sample was collected. C-4
I I II. UNAVAILABLE ANALYSES some unavailable .. analyses due to inappropriate or lost samples occurred I during the year. These are described below. A. Air Fil_ter/Cartridga I 1. Location #133, 9/11/90 to 9/18/90 I Benson: Blown fuse resulted in only 1.4 hours .un time. was not enough volume to meet LLD requirements. This Action Replaced fuse and restarted sampler. B. Direct Radiation (TLD)
- 1. Location #153, 9/16/90 to 12/6/90.
ECA12D TLD missing at time of collection, hrd12n Placed new TLD in the field. I I I I. I I I I I I C-5
I APPENDIX D MCGUIRE NUCLEAR STATION ANALYTICAL DEVIATIONS I LOWER LIMITS OF DETECTION I Air sampling site #125 charcoci cartridge for collection period 11/27 - 12/4/90 incurred damr:ge upon removal from sample head due to becoming tightly seated during composite period. The charcoal cartridge required prying to loosen it I from sample head, and in process, cartridge integrity was lost, allowing approximately 15% of the charcoal granules to escape. Metal casing of charcoal canister was bent, thereby altering cartridge geometry. l Sample run time and the corresponding air particulate filter were not adversely affected. Sample analysis was performed and all required lower limits of , l detection (LLD) were met within an acceptable counting time. I Sample head of air sampler at location #125 was replaced to alleviate the l recurrence of this problem, I i i I ) I ; I I I I I il I . D-1
used ] APPENDIX E
~
I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS This appendix includes all sample analysis reports from each sample medium for 1990. Appendix E is located separately from this report. I I I I 9 E-1
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I DUKE F 0WER COMPANY APPLIED SCIENCE CENTER - RAD 10 ANALYSIS LABORATORY I VAX/VMS Semple Analysis Report generated : 31-JAN-1990 10:59: 53 P1 ant Name : MNS I Sample Number Type / Location Sample Date 103
- DRINKING WATER / 132
- 23-JAN-1990 12:05:00 g Acq. Start Time : 23-JAN-1990 15:56:43 3 Sample Ouantity : 3.50000 LITERS Sample ID : 27DEC TO 23JAN90 Measurement Type : ROUTINE
***** Alternate Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pC1/ LITER) Error reg LLD Rpt. Level I ANAL 1-LL ANAL 2-LL ALPHA 364.48 < 0.654 364.48 < 0.635 0.00 <-0.858 0.000E+00 0.000E+00 0.429 0.00 2.59 I 0.854 BETA 0.000E+00
***** Damma-Spectroscopy Analysis *****
I Nuclide MN-54 Energy 834.83 < Activity (pCi/ LITER) 4.85 1-Sigma MDA> Frac. of Error req LLD Rpt. Level 0.000E+00 I CO-58 FE-59 CO-60 810.76 1099.22 1332.49 5.29 5.69 5.39 0.000E400 0.000E+00 0.000E+00 ZN-65 1115.52 < 7.94 0.000E+00 I NB-95 ZR-95 I-131 765.79 756.72 4.56 10.2 0.000E+00 0.000E+00 364.48 < 4.37 0.000E+00 CS-134 604.70 < 3.47 0.000E+00 LI CS-137 661.65 < 5.44 0.000E+00 BALA-140 1596.49 < 6.26 0.000E+00 Total Fraction of Reporting Level 000 00 Damma results are listed as Less Than Levels using Tech Spec LLD E equation. LLD = 4.66 SORT B/t. Presence of less than sign for gamma results means no peak was found end the zero error is not applicable. I Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD Analyzed by: No%/ Approved by: 2 [- Dates / /.3.4/ _ e .
//
/
I
0LIKE FOWER COMPANY APPLIED SCIEtt:E CENTER RADIOANALYSIS . AFORA10RY
,I VAX/VMS Samtle Analysis Repor t generated : 2-F E B- 1990 10 : 44: 51 Plent Name MN3 Sample Number 102 Type /Locetion : DRINKING WATER / 136 Sample Date : 23-JAN-1990 00: 45:00 t 23-JAN-1990 16:00:12
] Acq. Start Time Semple Ouantity : 3.50000 LITERS I Sample ID Nessurement Type : CONTROL 27DEC TO 23JAN90
***** Alternate Analysis *****
Activity 1-Sigma NDA) Frac, of Nuclide Energy (pCi/ LITER) Error reg LLD Rpt. Level ANAL 1-LL ~364.49 < 0.696 0.000E>00 ANAL 2-LL 364.48 < 0.693 0.000E+00 I ALPHA BETA 0.00 <-0.706 0.00 < 2.29 0.526 0.881
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/ LITER) Error reg LLD Rpt. Level I NN-54 CO-50 FE-59 834.03 < 810.76 < 109).22 < 5.29 3.81 8.14 0.000E+00 0.000E+00 0.000E+00 I CO-60 ZN-65 NB-95 1332.49 < 1115.52 < 765.79 < 6.56 8.18 5.89 0.000E+00 0.000E+00 0.000E+00 ZR-95 756.72 < 7.05 0.000E+00
'I I-131 CS-134 364.48 <
604.70 < 4.23 4.16 0.000E+00 0.000E+00 CS-137 661.65 < 4.84 0.000E+00 I BALA-140 K-40 1596.49 < 1460.81 4.93 78.9 0.000E+00 18.6 Total Fraction of Reporting Level 0.000E+00 Gamma results are 12sted as L.*ss Than Levels using Tech Spec LLD equation. LLD = 4.66 SORT b/t. Presence of less than sign for gamma I results means no peat, was found and the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the I activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD Analyzed by m Scm o J
~ M P. -
2 - e . 7o
-I ...... .......... . ..... ....... .......................--............. DUKE POWER COMPANY AFPLIED SCIENCE CENTER RAD 10 ANALYSIS LABORATORY VAX/VMS Sample Analysis Report generated : 30-JAN-1990 13:02:15 I Plant Name Sample Number
- HNS 77 I Type / Location Sample Date Acq. Start Time DRINKIN'3 WATER / 140
- 23-JAN-1990 09:00:00
- 24-JAN-1990 09:51:14 Sample Ouantity a 3.50000 LITERS I Sample ID Neacurement Type 27DEC TO 23JAN90 ROUTINE
***** Alternste Analysis *****
I Nuclide ANAL 1-LL Energy 364.48 Activity (pCi/ LITER)
< 0.623 1-Sigma Error reg LLD Rpt. Level 0.000E+00 MDA> Frac. of ANAL 2-LL 364.48 < 0.691 0.000E+00 ALPHA 0.00 <-0.423 0.519 PETA 0.00 2.50 0.845 0.000E+00
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of I Nuclide NN-54 00-58 Energy 834.03 810.74 (pCi/ LITER) 4.90 4.66 Error reg LLD Rpt. Level 0.000E+00 0.000E+00 FE-59 1099.22 < 9.09 0.000E+00 CO-60 1332.49 < 5.05 0.000E+00 ZN-65 1115.52 < 10.6 0.000E+00 NB-95 765.79 < 4.52 0.000E+00 I ZR-95 I-131 CS-134 756.72 364.48 604.70 0.09 3.73 3.42 0.000E+00 0.000E+00 0.000E+00 I CS-137 BALA-140 K-40 661.65 1596.49 1460.01 5.94 6.77 61.8 0.000E+00 0.000E+00 24.9 Total Fraction of Reporting Level 000E 00 Gamra results are listed as Less Than Levels using Tech Spec LLD I equation. LLD = 4.66 SORT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicable. I Tritium, Alpha and Deta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level, CL. CL = 0.5 LLD Analyzed by L bla m-Reviewed / Approved By. E d- - n.... ,.w/.e
.WkE POWEF COMF ANY l APPLIED SCIENCE CENTER RAD 10 ANALYSIS LABORATORY I . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . _ . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . _ .
' LAX /VM A Samole Analssas Retort centrated : 2-MAR-1990 16:11:23 Plant Name : MN3 Samcle Number : 162 Troe/ Location : DRINKING WATER ' 132 I Samole Date Acc. Start Time Samole Ouantity 20-FEF-1990 11:25:00 21-frB-1990 11:42:25 3.50000 LITERS I Sample ID Measurement Type : ROUTINE
- 23JAN TO 20FEB90
***** Alternate Analvste *****
Activity 1-51oma MDA: Frac. of I Nuclide ANAL 1-LL ANAL 2-LL Enerav 364.48 364.48 (pC1/ LITER) t 0.626 C 0.643 Error rea LLD RDt. Level 0.000E+00 0.000E+00 I ALPHA BETA 0.00 0.00 2.30 2.85 0.754 0.849 0.000E+00 0.000E+00
***** Gamma-Scectroscopy Analysis *****
Activity 1-Sioma MDA3 Frac, of Nuclide Eneroy (pCi/ LITER) Error reg LLD Rot. Level I MN-54 CO-58 FE-59 834.83 810.76 1099.22 < 13.2 5.78 4.90 0.000E+00 0.000E+00 0.000E+00 g CO-60 1332.49 < 4.58 0.000E+00 g ZN-65 1115.52 < 16.9 0.000E+00 NF-95 765.79 5.25 0.000E+00 ZR-95 756.72 < 10.2 0.000E+00 1-131 364.48 < 6.38 0.000E+00 CS-134 604.70 4.57 0.000E+00 CS-137 661.65 < 5.26 0.000E+00 I BALA-140 1596.49 < 8.23 0.000E+00 Total Fraction of Reportina Level 0.000E+00 Gamma results are listed as Less Than Levels usina Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for oamma results means no peak was *ound and the zero error is not applicable. Tritium. Alpha and Beta results are the best estimate of the activity and the less than sign indicates thet the net activity is lett than the critical level. CL. CL = 0.5 LLD Approved by _ ,- M f .' // Date: J_/ .,g_/ p_ l / /
DUKE F'0WER COMF ANY I APPLIED SCIENCE CENTER RADI0 ANALYSIS LAFORATORY
/ MS S me e na vs s port e ated A 90 :
I Plant Name Sample Number Type / Location
- MNS
- 164
- DRINKING WATER / 136
$ ample Date : 20-FEB-1990 09:35:00 I Aco. Start Time Sample Quantity Sample ID
- 21-FEF-1990 10:34:36 3.50000 LITERS 23JAN TO 20FEF90 Measurement Type : CONTROL
.I . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
***** Alternate Analysis *****
Activity 1-Sioma MDA) Frac, of Nuclide Energy (DC1/ LITER) Error rea LLD Ret. Level ANAL 1-LL 364.48 < 0.305 0.000E+00 ANAL 2-LL 364.48 < 0.568 0.000E+00 ALPHA 0.00 1.01 0.570 0.000E+00 BETA 0.00 2.51 0.823 0.000E+00
***** Damma-Spectroscopy Analysts *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/ LITER) Error rea LLD Rpt. Level MN-54 834.83 < 5.12 0.000E+00 I CO-58 FE-59 CO-60 810.76 1099.22 1332.49 6.57 14.5 7.77 0.000E+00 0.000E+00 0.000E+00 g
- ZN-65 1115.52 < 13.0 0.000E+00 3 NF-95 765.79 < 6.89 0.000E+00 ZR-95 756.72 < 10.6 0.000E+00 I-131 364.48 < 5.79 0.000E+00 I CS-134
-CS-137 BALA-140 604.70 661.65 1596.49 5.44 4.62 6.63 0.000E+00 0.000E+00 0.000E+00 I Total Fraction of Reportino Level 0.000E+00 I
Gamma results are listed as Less Than Levels usino Tech Spec LLD equation. LLD = 4.66 CORT B/t. Presence of less than sian for oamma results means no peak was found and the zero error is not applicable. I .T ri t i u m . Aloha and Beta resvits are the b0st estimate of the activity and the less then sian indicates that the net activity is less than the critical level. CL, CL = 0.5 LLD Anai,,ed h,, _a .tM. I Ap,,oved e,t ms t . du Daie, _,./.,_,r-o I
DUKE F0WER COMPANY I APPLIED SCIENCE CENTER RAD 10 ANALYSIS L ABORATORY A/ Sam e a ys Repo an ttd A 1 6:1 7 I Plant Name Samole Number Type / Location MNT 165
- DRINKING WATER / 14?
I i 20-FEB-1990 09:15:00 Sample Date Aca. Stert Time : 21-FEB-1990 13:37:10 Sample Quantity 3.50000 LITERS Sample ID : 23JAN TO 20FEB90
***** Alternate Analysis *****
Activtty 1-Sigma MDA) Frac of Nuclide I ANAL 1-LL ANALO-LL Energy 364.48 < 0.606 364.48 < 0.686 (pC1/ LITER) Error reg LLD Rot. Level 0.000E+00 0.000E+00 ALPHA 0.00 1.04 0.586 0.000E+00 BETA 0.00 3.50 0.872 0.000E+00
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/ LITER) Error req LLD Rpt. Level MN-54 834.83 < 3.95 0.000E+00 I CO-58 FE-59 810.76 1099.22 4.72 0.74 0.000E+00 0.000E+00 CO-60 1332.49 < 4.70 0.000E+00 I ZN-65 NB-95 ZR-95 1115.52 765.79 756.72 7.97 4.96 10.8 0.000E+00 0.000E+00 0.000E+00 l-131 364.48 < 4.72 0.000E+00 ~I CS-134 CS-137 604.70 < 3.94 0.000E+00 661.65 < 4.76 0.000E+00 BALA-140 1596.49 < 7.39 0.000E+00 I Total Fraction of Reportina Level 0.000E+00 I Gamma results are listed as Less Than Levels using Tech Spec LLD ecuation. LLD = 4.66 SORT B/t. Presence of less than sian for camme results means no peak was found and the zero error 15 not applicable. Tritium. Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level. CL. CL = 0.5 LLD I An.1,,ee e,, oue. Ap,_d ,y, a D.1e, m.,1, _ ,_ g m <F 7
I ................................................,........................ DUKE POWER COMPANY APPLIED SCIENCE CENTER RADI0 ANALYSIS LABORATORY VAX/VMS Sample Analysis Report generated : 06-MAR-1990 10: 47: 40 I Plant Name : MNS Sample Number 251 I Type / Location Sample Date
- DRINKING WATER / 13 20-MAR-1990 08:05:00 Acq. Start Time : 21-MAR-1990 10:28:05 I Sample Quantity Sample ID Measurement Type : ROUTINE 3.50000 LITERS 20FEB TO 20 MAR 90
***** Alternate Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pC1/ LITER) Error reg LLD Rpt. Level ANAL 1-LL 364.48 < 0.678 0.000E+00 I ANAL 2-LL ALPHA BETA 364.48 < 0.676 0.00 < 0.357 0.00 3.28 0.000E*00 0.437 0.765 0.000E+00 u*** Gamma-Spectroscopy Analysis ***** Activity 1-Sigma MDA> Frac, of I Nuclide MN-54 C0-58 Energy 834.83 810.76 (pC1/ LITER) 5.70 4.31 Error 0.000E+00 0.000E+00 rea LLD Rpt. Level I FE-59 C0-60 2N-65 1099.22 1330.49 1115.52 9.39 5.61 12.0 0.000E+00 0.000E+00 0.000E+00 NB-95 765.79 < 5.94 0.000E+00 I 2R-95 1-l'1 CS-134 756.'2 < 10.7 364.48 604.70 ' 5.40 4.36 0.000E+00 0.000E+00 0.000E+00 I CS-137 BALA-140 K-40 661.65 < 5.54 1596.49 1460.81 6.70 28.9 0.000E+00 0.000E+00 04.8 I Total Fraction of Reportino Level 0.000E+00 Gamma results are listed as Less Than Levels using Tech S W !LD equa tion. LLD = 4.66 SORT B/t. Presence of less than s ', a a resul ts means no peak was found and the Iero error is not m- . I Tritium. Aloha and Beta re3ults are the bes t es tima te of the activity and the less than sign indicates that the net ect) ei-than the critical level. CL, CL = 0.5 LLD
'c s
............ ............ ................ ..... ......-..._. j I
An.1,,ee m s' w' '
~~224 9. h - ,.n.o
I ............... ................. ................................... -.. I DUKE POWER COMPANY APPLIED SCIENCE CENTER RAD 10 ANALYSIS LABORATORY VAX/VMS Sample Analysis Report generated 26-MAR-1990 10:47 53 Plant Name : MNS Sample Number 252 I Type / Location Sample Date Acq. Start Time
- DRINKING WATER / 136
- 20-MAR-1990 13:30:00
- 21-MAR-1990 10:30:54 Sample Ouantity 3.50000 LITERS I Sample ID Measurement Type : CONTROL 20FEB TO 20 MAR 90
***** Alternate Analysic *****
I Nuclide ANAL 1-LL Energy 364.48 ' O.671 Activity (pC1/ LITER) 1-Sigma MDA> Error reg LLD Rpt. Level 0.000E+00 Frac. of ANAL 2-LL 364.48 < 0.517 0.000E+00 I ALPHA BETA 0.00 < 0.327 0.00 3.59 0.400 0.778 0.000E+00
***** Oamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA> Frac, of Nuclide Energy (pC1/ LITER) Error reg LLD Rpt. Level MN-54 834.83 < 4.37 0.000E+00 CO-58 810.76 < 4.8? 0.000E+00 FE-59 1099.22 < 9.57 0.000E+00 -I CO-60 ZN-65 1332.49 s 5.88 1115.50 < 9.85 0.000E+00 0.000E+00 NB-95 765.79 < 4.12 0.000E+00 ZR-95 756.70 c. 9.48 0.000E+00 I-131 364.48 ( 5.05 0.000E+00 CS-134 604.70 < 3.68 0.000E+00 -g CS-137 661.65 < 2.98 0.000E+00 g BALA-140 1596.49 7.24 0.000E+00 K-40 1460.81 56.6 26.2 Total Fraction of Reportino Level 0.000E+00 Oamma results are listed as Less Than Levels usino Tech Spec LLD equation.. LLD = 4.66 SORT B/t. Presence of less than sign for mme
.I. results means no peak was found and the zero error is not acpi: t Tritium. Alpha and Beta results are the best es tima te of the
'I activity and the less than sion indicates that the net act1ei' than the cri.ical t level. CL, CL = 0.5 LLD
.i Analyzed ey:. .m V
, hdd/pah b
/
B 4. $ $ , .u .ro
I ............................. -- ............ ........................... DUKE POWER COMPANY AFFLIED SCIENCE CENTER RAD 10 ANALYSIS LABORATORY VAX/VMS Sample Analysis Report generated : 26-MAR-1990 10: 48:25 I Plant Name : MNS Sample Number : 250 I Ty pe/Lo c a tion Sample Date Acq. Start Time
- DRINKING WATER / 142
- 20-MAR-1990 12:00:00
- 21-MAR-1990 10:33:32 I Sample Quantity Sample ID
- 3.50000 LITERS
- 20FEB TO 20 MAR 90 Measurement Type i ROUTINE
***** Alternate Analysis *****
Attivity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/ LITER) Error rea LLD Rpt. Level ANAL 1-LL 364.40 < 0.314 0.000E+00 I ANAL 2-LL
' ALPHA BETA 364.48 < 0.607 O.00 <-0.386 0.00 2.17 0.000E+00 0.273 0.721 0.000E+00
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sigma MDA' Frac. of I Nuclide MN-54 CO-58 Energy 834.83 810.76 < 5.36 (pCi/ LITER) 5.59 Error req LLD Rpt. Level 0.000E+00 0.000E+00 FE-59 1099.22 13.1 0.000E+00 I CU-60 ZN 65 1332.49 < 5.06 1115.52 11.4 0.000E+00 0.000E+00 NP-95 765.79 < 5.51 0.000E+00 I ZR-95 1-131 CS-134 756.72 <. 10.6 064.48 604.70 s 5.72 4.50 0.000E+00 0.000E+00 0.000E+00 I CS-137 661.65 5.30 0.000E+00 BALA-140 1596.49 6.37 0.000E+00 Total Fraction of Reportino Level 0.000E+00 Gamma results are listed as Less Than Levels usina lech Spec LLD equation. LLD = r.66 SORT B/t. Presence of less than sinn - - 33 results means no peat was found and the zero error is not .3 0 D 1 1 tie. Tritium. Alpha and Beta results are the best es'.imate et th-activity and the less than sion indicates that the net acte..'- I ice-than th9 cri+1 cal level. CL. CL = 0." LLD Aaye b _ Approved by: _M1_ / , ,, Date: _3_/14 / j e .
. uke POWER COMPANY 3
l I APPLIED SCIENCE CENTER NAD10 ANALYSIS LABORATORY I
..........i............................................................--
uAX/VMS Same'le Analysis Reoort oenerated : 05-AFR-1990 07:17: 30 Plant Name : MN? Samole Number 357 Tvoe/ Location : DRINKING WATER / 13 I Samole Date : 17-APR-1990 11:55:00 Acc. Start Time : 17-APR-1990 15:28:00 Sample Quantity 3.50000 LITERS Samole ID : 20 MAR TO 17APR90 I Measurement Type : ROUTINE
***** Alternate Analysis *****
Activity 1-Sloma MDA) Frac. of I Nuclide ANAL 1-LL ANAL 2-LL Eneroy 364.48 < 0.691 364.48 < 0.470 (oCi/ LITER) Error ree LLD Rot. Level 0.000E+00 0.000E+00 ALPHA 0.00 1.08 0.572 0.000E+00 I BETA 0.00 3.74 0.858
***** Damma-Soectroscopy Analysis *****
0.000E+00 Activity 1-Sioma MDA> Frac. of Nuclide Eneroy (pCi/ LITER) Error rea LLD Rpt. Level 0.000E+00 I MN-54 CO-58 FE- 59 834.83 810.76 1099.22 3.34 2.71 6.57 0.000E+00 0.000E+00 CO-60 1332.49 < 2.86 0.000E+00 ZN-65 1115.52 < 6.79 0.000E+00 NP-95 765.79 < 3.81 0.000E+00 ZR-95 756.72 < 4.70 0.000E+00 I I-131 CS-134 CS-137 364.48 604.70 661.65 2.94 2.95 2.73 0.000E+00 0.000E+00 0.000E+00 BALA-140 1596.49 < 2.86- 0.000E&OO Total Fraction of Reportino Level 0.000E+00 I Gamma results are listed as Less Than Levels usino Tech Spec LLD ecuation. LLD = 4.66 SORT B/t. Presence of less than stan for oamma results means no peak was found and the zero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the activity and the less than sian indicates that the net activity is less than the critical level. LL. CL = 0.5 LLD I Analyzed by:O Approved by:
-- bn,tyMu.
~~7C)/2 f. ,[W_-
J
/( Dates 7/j[/9e /
ll ..
DUKE POWER COMPANY I AF PLIED SCIENCE CENTER RAD 10 ANALYSIS LABORATORY VAX/VMS Same'le Analvsis Report cenerated i 25-ATR-1990 07: 19:49 Plant Name : MNS Sample Number 358 Troe/ Location DRINKING WATER ' 136 I Samole Date Aco. Start Time Samole Ouantity
- 17-APR-1990 10:05:00
- 17-APR-1990 15:31:38 3.50000 LITERS I Samole ID Measurement Tvoe : CONTROL
- 00 MAR TO 17APR90
***** Alternate Analysis *****
Activity 1-Sioma MDA> Frac. of I Nuclide ANAL 1-LL ANAL 2-LL Energy 364.48 < 0.614 364.48 < 0.661 (oC1/ LITER) Error rea LLD Rot. Level 0.000E+00 0.000E+00 0.410 I ALPHA 0.00 < 0.410 SETA 0.00 4.51 0.871 0.000E+00
***** Gamma-Soectroscopy Analysis *****
Activity 1-Sioma MDA> Frac. of Nuclide Eneroy (pCi/ LITER) Error rea LLD Rpt. Level MN-54 834.83 < 3.11 0.000E+00 CD-58 810.76 < 2.51 0.000E+00 FE-59 1099.22 < 7.13 0.000E+00 CO-60 1332.49 < 4.48 0.000E+00 I ZN-65 NB-95 ZR-95 1115.52 < 5.60 765.79 < 3.79 756.72 < 6.42 0.000E+00 0.000E+00 0.000E+00 I I-131 CS-134 CS-137 364.48 < 3.11 604.70 < 3.39 661.65 < 3.44 0.000E+00 0.000E+00 0.000E+00 I BALA-140 1596.49 < 4.50 0.000E+00 Total Fraction of Reportino Level 0.000E+00 Oaan'a results are listed as Less Than Levels usino Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than stan for oamma results means no peak was found and the zero error is not applicable. Tritium. Alpha and Beta results are the best estimate of the activity and the less than sion indicates that the net activity'is less than the critical level. CL. CL = 0.5 LLD I Analyzed by n, m [o,rn&A Approved bys ~7F)At f . - Dates f
/(
/_ti/
/o I
s DUKE POWER COMPANY APPLIED SCIENCE CENTER ~ RADI0 ANALYSIS LABORATORY l
......... 1..............................................................
VAX/VMS Samp'le Analysis Report oeneratec : 05-AFR-1090 07:19:48 Plant Name : MNS Sample Number 362 Type / Location DRINKING WATER / 142 Sample Date : 17-APR-1990 09:40:00 1 Aco. Start Time : 17-APR.1990 15:33:13 Sample Ouantity : 1.00000 LITERS Sample ID : 20 MAR TO 17APR90 I Measurement Type : ROUTINE
***** Alternate Analysis *****
Activity 1-Sioma MDA> Frat. of Nuclide Energy (DC1/ LITER) Error reo LLD Rot. Level I A NAL 1 -LL 364.48 c. 0.663 0.000E+00 ANAL 2-LL 364.40 < 0.520 0.000E+00 ALPHA 0.00 1.06 0.563 0.000E+00 l BETA 0.00 3.09 0.825 0.000E+00
***** Gamma-Spectroscopy Analysis *****
Activity 1-Sioma MDA> Frac. of Nuclide Eneroy (pCi/ LITER) Error reg LLD Rot. Level 9N-54 834.83 < 6.34 0.000E+00 I 00-58 FE-59 810.76 1099.22 5.64 12.7 0.000E+00 0.000E+00 CO-60 1332.49 < 6.98 0.000E+00 ZN-65 1115.52 < 18.2 0.000E+00 I NB-95 765.79 < 6.35 0.000E+00 ZR-95 756.72 < 10.5 0.000E+00 l I-131 364.48 < 6.02 0.000E+00 B CS-134 604.70 < 6.58 0.000E+00 CS-137 661.65 < 6.19 0.000E+00 BALA-140 1596.49 < 0.88 0.000E+00 1 Total Fraction of Reportino Level 0.000E+00
,h Gamma results are listed as Less Than Levels usino Tech Spec f.LD equation. LLD = 4.66 SORT B/t. Presence of less than sign for oamma results means ho peak was found and the zero error is not applicable.
Tritium, Alpha and Beta results are the best estimate of the activity and the less thaa sion indicates that the net activity is less than the critical level. CL. CL = 0.5 LLD Approved by: T/> G Dates / ,tg_/ a
.u
DUKE POWER COMPANY II APFLIED SCIENCE CENTER RADIDANALYSIS LABORATORY r
~
VAX/VMS Sample Analysis Report generated i 21-FEB-1991 12:57:52 Plant Name : MNS Sample Number : 1510 Type / Location i DRINKING WATER / 132 I Sample Date Acq. Start Time Semple Ouantity 2 15-MAY-1990 10:45:00
- 16-MAY-1990 11: 24:39 a 3.50000 LITERS Sample ID : 4/17-5/15/90 (D)
I Measurement Type Elapsed Live Times ROUTINE 0 02:05:20.94
***** Alternate Analysis *****
I Nuclide ANAL 1-LL Energy 364.48 Activity (pC1/ LITER)
< 0.633 1-Sigma MDA>
Error req LLD Rpt. Level 0.000E+00 Frac. of ANAL 2-LL 364.48 < 0.684 0.000E+00 I ALPHA BETA 0.00 0.00 1.20 3.58 0.567 0.700 0.000E+00 0.000E+00
*+**+ Gamma-Spec troncopy Analysis *****
Activity 1-Sigma MDA> Frac. of I Nuclide MN-54 CO-58 Energy 834.83 810.76 (pCi/ LITER) 6.01 4.64 Error reg LLD Rpt. Level 0.000E+00 0.000E+00 FE-59 1099.22 14.3 0.000E'00 I CO-60 1332.49 < 4.42 0.000E+00 ZN-65 1115.52 < 12.1 0.OQ0E+00 NB-95 765.79 < 6.34 0.000E+00 I 2R-95 1-131 CS-134 756.72 364.48 604.70 9.24 4.62 4.60 0.000E+00 0.000E+00 0.000E+00 CS-137 I BALA-140 661.65 1596.49 6.16 8.24 0.000E+00 0.000E+00 Total Fraction of Reporting Level 0.000E+00 Gamma results are listed as Lens Than Levels using Tech Spec LLD equation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicabl: . Tritium, Alpha and Beta results are the best estimate of the I activity and the less than sign indicates that the net activity in less than the critical level, CL, CL = 0.5 LLD I ' unnto e4: S ~. %. -me~
\
I A Dd M Q. DO 6 nh a m J e. ,.w'. m .. C , L n u ,. ~ OYi no e{ 5 / - c; /nis b}o w e mnb a dev'i
<b 5
~ U aTici,r.,
ew d q
- L'n1 8 DWE A COMF ANY B AF FLIED SCIENCE CENTER
. tad 10AFMLYSIS L AFORATORY uAX/VMS Sample Analvs s Report eenerated 09-MAY-1990 06:07:07 i Flant Name Sample Number
- MUI a 490 I , fvce/Locatten Sample Date Acc. Start Time DRINK!HO WATER ' 136
- 15-MAY-1990 09:05:00
- 16-MAY-1990 16:56 39 Sample Quantity 3.50000 LITERS I Samole ID Measurement Type : CONTROL
- 17AFR TO ISMAY90
***** Alternate Analysis t***s i PAiclide ANAL 1-LL Enerov 364.40 < 0.609 Activatv (oCn/ LITER) 1-91oma Error reo LLD Rot. Level 0.000E+00 MDA) Frac. of ANAL 2-LL 364.40 < 0.679 0.000E400 I .ALFHA BETA-0.00 0.00
<-0.319 3.15 0.00$
0.679 0.000E+00
***** Damma-Soectroscopy Analysis *****
Activity 1-Sigma MDA> Frac. of 3 tAiclide Eneroy (DCi/ LITER) Error rea LLD Rot. Level 5 ""-54 834 83 ' 2 5' O.000E+00 - C0-58 010.76 < 1.73 0.000E+00 FE-59 1099.00 < 3.30 0.000E+00 C0-60 1330.49 < 1,64 0.000E+00 l
= 4.. '- 6 b 1115.52 < 3.52 0.000E+00 l NB 'S 765.79 < 1.01 0.000E+00 lg ZR-4 756.70 2.71 0.000E+00 3 1-1 064.40 < 1.67 0.000E+00 j CS-?A 604.70 < 1.40 0.000E+00 i CS 137 661.65 < 1,72 0.000E+00 l BALA-140 1596.49 < 1.01 0.000E+00 K-40 1460.01 63.0 12.1 Total fraction of Reoortano Level 0.000E+00 .
Deena results are listed as Less Than Levels usino Tech Spec LLD
-g couation. LLD = 4.66 SORT B/t. Presence of less than stan for oamma
.E l r'* ult
- a'aa' ao o'*k **$ found and th' ra 'rror 25 act *ool2 cab 2'-
l Tritium. Aloha and Beta results are the best estimate of the activity and the less than sion indicates that the net activity as less than the critical level. CL. CL
- 0.$ LLD Analyzed by: 4 ?f* W4 [f M l n.,i 4fa,,,,,4 sy:w, t.h w
a c .u . an J-
I . ......,.... ............. ............................................ I NIE 00WER COMFANY AF FLIED SCIENCE CENIEk RADIDANAtit15 LA140RA10kV VAX/VMS Samele Analvt15, keport cenerateo 25-MAY-1990 07:39: 15 i Plant Name Sample Number
- MN!
487 Tvee/ Location : DRINKING WATER / 140 I ' fample Date Acc. Start Time
- l'.MAY-1990 00:45:00
- 16-MAY-1990 14: 57: 35 Sample Ouantity 3.50000 LITERS I Sample ID : 17AFR TO 15MAY90 Measurement fvoc : FOUTINE 448t* Alternate Analvtis 84*84 Activity 1-51oma MDA? Frac, of I Nuclide ANAL 1-LL ANAL 2-LL Enerov 364.40 < 0.690 364.48 foC1/ LITER) 0.692 Error 0.000E+00 0.000E+00 reo LLD Rot. Level ALPHA 0.00 < 0.190 0.424 i LETA 0.00 3.35 0.690 0.000E+00
***** Gamma-Soectroscoey Analysis *****
Activatv 1-31oma MDA; Frac. of Nuclide Eneroy (DCi/ LITER) Error rea LLD Rot. Level MN-54 034.03 s 5.16 0.000E+00 CO-50 010.76 < 5.07 0.000E+00 FE-59 1099.22 < 0.15 0.000E+00 I CD-60 2N-65 N14-95 1330.49 < 5.76 1115.52 < 9.71 765.79 ' 3.60 0.000E+00 0.000E+00 0.000E+00 2R-95 756.70 - 9.93 0.000E+00 1-131 364.48 < 4.89 0.000E+00 1- CS-134 604.70 < 3.24 0.000E+00 CS-137 661.65 ' 5.46 0.000E+00 0ALA-140 1596.49 < 4.00 0.000E+00 Total fraction of Reportino Level 0.000E+00 Gamma results are listed as Less Than Levels usano Tech Socc LLD ecuation. LLD i 4.66 SORT B/t. Presence of less than ston for oamma results means no peak was found and the tero error 15 not apDlicabic. I Tritium. Aloha and beta results are the best estimate of the activity and the less than sion indicates that the net activity is Acts than the critical level. CL. CL = 0.5 LLD
, . . f __ __
Approved by: %L f, Date 4/ g -- -4/ ,M g
l l l .........................................................................
.L'tE F0WER CONF ANY l AftLIED SCIENCE CENTER
'AD10 ANAL 1 SIS LAlORATORY 9Ai'VMS Eamele Analvttt hetert oenerated Ji-JUN-19&O 15:31:23 I Plant Name semole Numter
- PNB 620 I Tvee/Leutten famole Date Acc. Start Time DRINKING WATER / 132 10-JUN-19YO 10:00:00 14-JUN-1990 17:29:00 fample Ouentity 3.50000 LITERS I Samole ID Measurement Type Elaosed Live Times 5/29-6/12/90 (D)
ROUTINE 0 12:00:00.00
***** Alternate Analvsts ***te Activity 1-Sigma MDAT Frac, of Nuclide Energy (DC1/ LITER) Error reo LLD Ret. Level ANAL 1-LL 364.40 < 0.553 0.000E+00
'l ANAL 2-LL ALPHA BETA 364.40 < 0.609 0.00 < 0.000E+00 0.00 3.50 0.000E+00 0.417 0.077 0.000E+00
***** Gamma-Socctroscopy Analysis est**
Activity Frac of I 1-510ma MDA) Nuclide Eneroy (pC1/ LITER) Error rea LLD Rot. Level MN-54 834.03 < 1.77 0.000C+00 CO-58 010.76 4' 1.61 0.000E+00 I FE-59 CD-60 ZN-65 1099.22 < 3.27 1332.49 < 2.01 1115.52 < 3.56 0.000E+00 0.000E+00 0.000E+00 i NB-95 ZR-95 1-131 CS-134 765.79 756.72 364.40 604.70 1.69 2.76 1.79 1.52 0.000E+00 0.000E+00 0.000E+00 0.000E+00 t CS-137 BALA-140 K-40 661.65 1596.49 1460.01 1.73 0.23 63.0 0.000E+00 0.000E+00 9.60 I Total Fraction of Reporting Level 0.000E+00 Gamma results are listed as Less than Levels using Tech Spec LLD i ecuation. LLD = 4.66 SQRT B/t. Fresence of less than sign for gamme results means no peak was found and the zero error is not applicabic. I Trittum, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level. CL. CL = 0.5 LLn f l .............................................
.Btticwed/AnorovedBrMf hdl-Analyzed by:
l Ma,a&c.malya u wdu.54u e,a,G..4 1n* 4L m Rt a s - . M w ,s h-
- d e T' m -
DUKE ROWER COMFANY I AF FLIED SCIENCE CENTER RAD 10 ANALYSIS LAFORATORY VAX/VMS Sample Analysis Report generated 21-JUN-1990 15:31:25 I Plant Name Sample Number
- MNS 621 I Type / Location Sample Date Acc. Start Time
- DRINK!!IO WATER / 136
- 10-JUN '990 12: 40:00
- 15-JUN-1990 07: 56:36 Sample Ouantity 3.500f0 LITERS Sample ID ISMAY TO 120VN90 Measurement Type : CONTROL Elapsed Live Times 0 01:00:00.00
***** Alternate Analysis *****
Activity 1-Sige. MDA) Frac. of Nuclide Energy (DC1/ LITER) Error reg LLD Ret. Level ANAL 1-LL 364.40 < 0.640 0.000E+00 i ANAL 2-LL ALPHA BETA 364.40 < 0.602 0.00 < 0.000 0.00 2.69 0.000E+00 0.465 0.041 0.000E+00
***** Oamma-Seectroscopy Analysts *****
I 1-Sigma Activity MDA) Frac. of Nuclide Eneroy (pC1/ LITER) Error rea LLD Rot. Level MN-54 034.03 < 7.25 0.000E+00 CD-50 010.76 < 4.37 0.000E+00 l I FE-59 CO-60 ZN-65 1099.22 < 12.6 1332.49 < 10.2 1115.52 < 10.0 0.000E+00 0.000E+00 0.000E+00 j g NB-95 765.79 < 6.09 0.000E+00 t g IR-95 756.72 < 10.5 0.000E+00 1-131 364.40 < 0.17 0.000E+00 l CS-134 604.70 < 5.10 0.000E+00 h W CS-137 661.65 < 7.65 0.000E+00 BALA-140 1596.49 < 7.74 0.000E+00 BE-7 477.59 20.7 19.2 1 I Total Fraction of Reporting Level 0.000E+00 Gamma results are listed as Less Than Levels using Tech Spec LLD l i ecuation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and the aero error is not applicable. I Tritium, Aloha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level. CL. CL = 0.5 LLD Ana1xtee ex, >w/A -m- A l / g. il (..tl* O
DUKE POWER COMF ANY APPLIED SCIENCE CENTER AAD10 ANALYSIS LABORATORY 1 VAx/VMS Samole Analysis Report eenerated 21-JUN.1Y90 15:31:27 F Plant Name : MN! Samole Numt>er 622 Troe/ Location : DRINKIhm WATER / 142 Semele Date : 12-JUN.1990 14:00:00
- Acc. Start Time : 15-JUN-1990 07:59:26 Sample Quantity 3.50000 LITERS 3 Sample ID : ISMAY TO 120VN70 l Measurement Type : ROUTINE Elapsed Live Times 0 02:38:27.00
***** Alternate Analysts s****
Activity 1-Sigma Frac. of I Nuclide ANAL 1.LL Energy 364.48 < 0.528 (oC1/ LITER) MDA> Error rea LLD Rot. Level 0.000E+00 g ANALO-LL 364.48 < 0.662 0.000E+00 ALPHA 0.00 < 0.000E+00 0.407
; BETA 0.00 ,
0.18 0.812
***** Gamma-Spectroscopy Analysts *****
Activity 1-Sigma MDA; Frac. of g Nuclide Energy (pCi/ LITER) Error reo LLD Rpt. Level l MN-54 834.83 < 3.63 0.000E+00 CO 58 810.76 < 4.95 0.000E+00 FE-59 1099.22 < 9.48 0.000E+00 CO-60 1332.49 < 4.53 0.000E+00 1 ZN-65 1115.52 < 10.8 0.000E+00 i NB-95 765.79 < 5.24 0.000E+00 2R-95 756.72 < 9.48 0.000E+00 I-131 364.48 < 6.36 0.000E+00 CS-134 604.70 < 4.96 0.000E+00 CS-137 661.65 < 6.01 0.000E+00 BALA-140 1596.49 < 7.77 0.000E+00 Total Fraction of Reporting Level 0.000E+00 Gamma results are listed as Less Than Levels ustno Tech Spec LLD ecuation. LLD
- 4.66 SORT B/t. Presence of less than sign for gamma results means no peak was found and the aero error is not applicable.
Tritium. Aloha and Beta results are the best estimate of the activity and the less than ston indicates that the net activity as lett than the critical level. CL. CL = 0.5 LLD
/'
/
3 s. G ~ 71/90
mr sgypp cgg ogy I AF5 LIED SCIENCE CENTEF LADIOpiAlisti LAteFAfDRt I ...... ...... . ............ .................. ..._ ........... ...
'IAUVMS Samele Analysis Report ceneratro : 24-JUL.1900 Oi! 06: 07 I Plant Name Semote Numter
- MUi i 707 I 13:
T y ee /Le c a t i on : PRINKlHO WATER fample Dete 10-JUL-1990 11:25:00 Aco. Start Tree : 11-JUL-10SO 16: 3 ' 11 Samole Ouantity : 3.50000 LITERS I Samole ID Measurement ivoe Elaosed Live Times
- U26 7'10/90 (Di ROUTINE 0 12:00:00.00
***** Alternate Analvsis *****
Activity 1-Saoma MDA? Frac. of Noclide Enerov (DC1/ LITER) Error rea LLD Rot. Level ANAL 1-LL 364.19 < 0.630 0.000E+00 I ANAL 2-LL ALPHA BETA 364.49 c. 0.691 0.00 < 0.000E+00 0.00 1.86 0.000E+00 0.260 0.699
***** Gamma-Soectroscopy Analysis *****
Activity 1-Sioma I MDA> Frac. of Nuclide Eneroy (DCi/ LITER) Error rea LLD Rot. Level MN-54 934.03 < 1.29 0.000E+00 CD-50 910.76 < 1.45 0.000E+00 I FE-59 CD-60 ZN-65 1099.22 < 2.71 1332.49 < 1.86 1115.52 , 0.97 0.000E+00 0.000E+00 0.000E+00 I ND-95 ZR-95 1-131 765.79 ( 1.50 756.72 < 2.35 364.48 < 1.60 0.000E+00 0.000E+00 0.000E+00 CS-134 604.70 1.09 0.000E+00 I CS-137 BALA-140 K-40 661.65 < 1.71 1596.49 < 1.95 1460.01 48.9 0.000E+00 0.000E+00 10.9 . I fotal Fraction of Reportino Level 0.000E+00 Gamma results are listed as Lers Than Levels usino Tech Spec LLD j I ecuation. LLD = 4.66 SORT B/t. Presence of less than sion for comme results means no ceak wu found and the fero error is not aop11:able. i Tritium. Alpha and Beta results are the best estimate of the (l l 55 activity and the less than slan Indicates that the net activ. tty at less I than the critical level. CL. CL = 0.5 LLD 1 - Anaivred eva _p / h .. m--r 26,7 l M kyuUu u.~ f q %.on. d Q.u. w,, vu a . 4. AIy 9.s;L m ,,0.vt.J.'n,s, -f sJLL a.i., _ a ,,a a. w ~
. _ - - _ - _ . . - . . . . . . _ - ~ . . - - - - - - - . - . - _ _ . . - _ . _ . . . . - - - - -
I . ............................................................... ... ... I M'6E 5'0WEL CDMFANY Aff'.!ED SCIL' ICE CENTLR AADIDANALYSIS LAFOAATORY uAK/VMS Samole Analvsst Ferort oenerated 1-Al'0-1990 11: 02:51 5 Flant Name : MNS Samele Nut,er 706 Tereslocation I Semele Dete Ace. Start Time
- DRINKING WATEP ' 13t
- 10-JUL-19v0 09: 30:00 11-JUL-19VO 10:09: 30 Sample Ouentity : 3.$0000 LITEFS I Samole ID Measurtment free Elaesed Live Times
- 12JUN TO 103UL90 CONTFOL 0 02:16:03.99
***** Alternate Analysis *****
Activity 1-Sioma MDA4 Frac. of nuclide Enerov foC1/ LITER) Errer rea LLD Rot. Level ANAL 1-LL 364.48 0.456 0.000E+00 I ANAL 2-LL ALFHA BETA 364.48 0.00 0.00 0.507 1.56 11.7 0.000E+00 0.520 1.07 0.000E+00 0.000E+00
***** Gamma-St,ectrostooy Analysts *****
Activity 1-Sioma MDAt Frac, of Nuclide Eneroy (DCi/ LITER) Error rea LLD Rpt. Level MN-54 034.63 < 5.80 0.000E+00 00-50 010.76 ' 6.33 0.000E+00 I 9.67 FE-59 1099.22 < 0.000E+00 00-60 133?.49 ' 5.06 0.000E+00 ZN-65 1115.52 / 11.4 0.000E+00 g UB-95 765.79 ' 4.50 0.000E+00 g ZR-95 756.70 - 8.56 0.000E+00 1-131 364.40 ( 6.43 0.000E+00 CS-134 604.70 ' 5.59 0.000E+00
- l. h CS-137 661.65 < 6.94 0.000E+00 l E BALA-140 1596.49 *: 6.75 0.000E+00 Total fraction of Reportino Level 0.000E+00 -
'I l Gamma results are listed as Less Then Levels usino Tech Sotic LLD cauation. LLD = 4.66 SORT D/t. F resence of less than saan for osmme I. results means no Deak was found and the zero error 15 not applicable, i Tritium. Aloha and Beta results Are the best estimate of the activity and the less than s2an 2ndacates that the net activitv is lets l l CL = 0.5 LLD lW than the critical level. CL. l Analvred by: vM b r'nrne g w _ Rev.iewed/Appr0ved Br M 7-g I oss. _
/
s 1/
/
e ?,
I ............................................................. ........... I SUrE t0WEF COMPANY AF F LIED iCIENCE CEuf EF
& ADIDAHAL151S L ABOL ATOFT I .........................................................................
VAX/VMS Sample Analvt2s Aeoort eenerated : 31-JUL-1990 10:3't3' Plant Name : M U!- 5,m p l e Nu m t.c r 704 Trot / Location : DRINKluG WATER / 14; Samole Date : 10-JUL-19&O 09: 10:00 Acc. Start Time : 11-JUL-1000 10:11:09 Samole Ouantity a 3.50000 LITrks Sample ID 10JUN TO 10J( l m 0 Measurement Tvoc ROUTINE Elaosed Ltve Times 0 01:17:24.99 I ........ .................................................................
**ste Alternate Anelvsts $4888 I Nuclide ANAL 1-LL Energy 364.48 < 0.693 Act2vitt (oC1/ LITER) 1-Stoma MDA> Frac. of Erro- rea LLD Rot. Level 0.000E+00 I ANAL 2-LL ALPHA BETA 364.49 0.00 < 0.779 0.00 0.506 9.03 0.000E+00 0.411 0.983 0.000E+00
**48* Damma-90ectroscopy Analysts tete
- Activity 1-51oma MDAS Frac, of I Nucinde MN-54 C0-50 Eneroy 034.83 < 5.46 010.76 < 3.09 (pC1/ LITER) Error 0.000E+00 0.000E+00 rea LLD Rot. Level I FE-59 CD-60 ZN-65 1099.02 < 10.4 1330.49 < 4.16 1115.52 < 11.5 0.000E+00 0.000E+00 0.000E+00 NF-95 0.000E+00 I
765.79 < 5.45 ZF-95 756.72 4 10.3 0.000E+00 1-131 *64.48 < 5.85 0.000E+00 CS-134 604.70 < 4.96 0.000E+00 I CS-137 BALA-140 K-40 661.65 < 5.85 1596.49 < 9.57 1460.81 90.6 0.000E+00 0.000E+00 08.3 Total Fraction of Reportano Level 0 000E+00 Gamma results are listed as Less Than Levels usino Tech Spec LLD j I eopation. LLD = 4.66 SORT B/t. Presence of less than ston for comme results means no Deak was found and the zero error as not appl 3caelo. g Tritium. Alpha and Beta results are the best estimate of the l 3 activity and the less than slon indicates that the net activity it Itts ! than the critical level. CL. CL = 0.5 LLD 1 . l Analyzed bya N /(d b 4$lt b .. RwiewW/Approyd Br. M /ld-
~
'7 lg f Deter S '/* 9 8
I II I ......................................................................... DUKE F 0WEk EOMF ANY AFtLIED SEIENCE CENTER AAD10ANALYE!S LA00AAT00Y I VAX/VMS Sample Analysis Aroort oenerated i 20-AUG-19VO 13:!0:02 Plant Niee : MHS I Sample Non,ber Troe/ Location Sample Date 1 003
- DRINKING WATER / 132 7-AUG-1990 12: 40:00 I Ato. Start Time Sample Ouantity Sample ID
- 0.AVO-1990 17:16:03 3.50000 L11ERS 7/04-8/7/90 (D)
I Measurement 1voc : ROUTINE Elapsed Live Times 0 12:00:00.00
$$t** Alternate Analysis $58t*
Activity 1 51ama MDA) Frac. of I Nuclide ANAL 1-LL ANAL 2-LL Energy 364.40 < 0.617 (oct/ LITER) 364.40 < 0.679 Error reo LLD Rot Level 0.000E400 0.000E+00 0.00 <-0.749 0.374 I ALPHA BETA 0.00 < 1.63 0.799
**s** Damma-Spectroscopy Analysis s****
Activity 1-51oea MDA> Frac. of Nuclide Eneroy (pC1/ LITER) Error rea LLD Rpt. Level I MN-54 00-50 FE-59 034.03 < 010.76 1099.22 1.33 1.52 3.06 0.000E+00 0.000E+00 0.000E+00 CO-60 1332.49 < 1.00 0.000E+00 I ZN-65 NP-95 ZR-95 1115.52 766.79 756.72 3.25 1.52 2.75 0.000E+00 0.000E+00 0.000E+00 I I-131 CS-134 CS-137 364.40 604.70 661.65
!.62 1.51
!.61 0.000E+00 0.000E+00 0.000E+00 BALA-140 1596.49 < 2.10 0.000E+00 I K-40 1460.01 B3.7 10.3 Total Fraction of Reportino Level 0.000E+00 Gamma results are listed as Less Than Levels usino Tech Spec LLD ecuation. LLD = 4.66 SQRT B/t. Presence of less than sign for oamma results means no peak was found and the zero error is not applicable.
Tritium, Alpha and Beta results are the best estimate of the activity and the less than $1on indicates that the net activity 15 less than the critical level. CL. CL = 0.5 LLD I Anaiy ed bx: d % d 6 tcN A142c m :_ rr <
"** #C n....
D" c . ,, . so
DUKE F 0WER CONFANY AFPLIED SCIENCE CENTER ' RAD 10 ANALYSIS LAF0kATORY VAX/VMS Samole Analysis Report oenerated 20-AUG-1990 14:00:15 Plant Name MNS Sample Number 799 I T v oe/Lo ca ti on DRINKING WATER / 136 Sample Date : 7-AUG-1990 11:00:00 l Aco. Start Time : 0-AUG-1990 13:54:47 l Sample Ouantity 3.50000 LITERS Samole ID 10JUL TO 7AUG90 Measurement Type : CONTROL
.....$.. 5 . .. .... . .
***** Alternate Analysis ss***
Activity 1-Sioma MDA> Frac of Nuclide Eneroy (sci / LITER) Error rea LLD Rct. Level I ANAL 1-LL ANAL 2-LL 364.48 < 0.683 364.48 < 0.611 0.000E+00 0.000E+00 ALPHA 0.00 < 0.902 0.651 PETA 0.00 < 1.24 0.770 -
***** Gamma-Spectroscopy Analysis **ssa Activity 1-Sioma MDAS- Frac. of Nuclide Eneroy (pC1/ LITER) Error rea LLD Rot. Level MN-54 034.03 < 4.76 0.000E+00 i CO-59 FE-59 010.76 1099.22 5.75 0.40 0.000E+00 0.000E+00 0.000E+00 CD-60 1332.49 < 4.72 lN ZN-65 NB.95 1115.52 <
705.79 < 4.19 14.0 0.000E+00 0.000E+00 ZR-95 756.72 < 10.9 0.000E+00 g 1-131 364.48 < 4.56 0.000E+00 l
- CS.134 CS-137 604.70 661.65 5.76 5.10 0.000E+00 0.000E+00 BALA-140 1596.49 < 0.79 0.000E+00 l
Total Fraction of Reportino Level 0.000E+00 Damma results are listed as Less Than Levels using Tech Spec LLD ecuation. LLD = 4.66 SQRT P/t. Presence of less than sion for oemme results means no peak was found and the zero error is not applicable. Tritium. Alpha and Beta results are the best estimate of the activity and the less than sion indicates that the net ~ activity i s } ti d than the critical level. CL. CL = 0.5 LLD
- t% m g , Renewed /Appnad Br.Nu %mo Analyzed by: - ie- /
Dahn#'{*o
I .................................. ............................. ........ SUkE POWER CONF ANf AFFLIED SCIEMCE CENTER RAD 10 ANALYSIS LABORATORY VAX/VMS Sample Analysts Report eenerated : 20-AUG-1990 14: 02:25 I Plant Name MNS Sample Number i B15 I Type / Location Sample Date Aco. Start Time
- DRINKDJO WATER / 142 7-AUG-1990 10:00:00 9-AUG-1990 16:41:00 Sample Ouantity : 3.50000 LITERS l
W SamDie ID : 10JUL TO 7AUG90 Measurement Type : ROUTINE Elapsed Live Times 0 12:00:00.00 I .................................................................. ......
***** Alternate Analysis *****
Activity 1-Sioma MDA> Frac. of 4.i c11 d e Energy (oCi/ LITER) Error rea LLD Rot. Level I ANAL 1.LL
~ ANAL 2-LL ALPHA 364.48 < 0.551 364.48 < 0.694 0.00 < 0.365 0.000E+00 0.000E+00 0.570 BETA 0.00 < 1.00 0.767 I ***** Oamea-Spectroscopy Analysis **s**
I Nuclide MN-54 Enercy 034.03 < 1.53 Activity (pC1/ LITER) 1 Sioma Error rea LLD 0.000E+00 MDA> Frac. of Rot. Level I CO-58 FE-59 CO-60 810.76 < 1.50 1099.22 < 3.24 1332.49 < 1,69 0.000E+00 0.000E+00 0.000E+00 ZN-65 1115.52 < 3.71 0.000E+00 I- NP-95 ZR-95 765.79 < 1.69 756.72 < 3.09 0.000E+0A 0.000E+00 I-131 364.40 < 1.05 0.000E+00 I CS-134 CS-137 BALA-140 604.70 < 1.60 661.65 < 1.72 1596.49 < 2.09 0.000E+00 0.000E+00 0.000E+00 K-40 1460.81 59.7 11.9 Total Fraction of Reportino Level 0.000E+00 Gamma results are listed as Less Than Levels usino Tech Spec LLD E. ecuation. LLD = 4.66 SORT B/t. Presence of less than sion for oamma results means no peak was found and the 7ero error is not applicable. Tritium, Alpha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level. CL. CL = 0.5 LLD l15 Analyzed by: Mw d 2 d LLYr/ - g- ig- t Reviewd/ Approved By: N, m hoe
. ~ .-. . . . = -.. .
I ......................................................................... I .SUKE F0WER COMPANY APPLIED SCIENCE CENTER RADI0 ANALYSIS LABORATORY I ......................................................................... VAX/VMS Samole Analysis Reoort cenerated : 11-SEP-1990 11:26:07 I Plant Name Samole Number
- MNS
- 899 I Troe/ Location Samole Date Aco. Start Time
- DRINKIN3 WATER / 1:2 4-SEP-1990 13:00:00 5-SEP-1990 11:43:30 Sample Quantity 3.50000 LJTERS Samole ID : 8/10-9/4/90 (D)
Measurement Type : ROUTINE Elaesed Live Times 0 01:40:00.00
***** Alternate Analysis *****
Activity 1-Sioma MDA> Frac, of Nuclide Energy (DC1/ LITER) Error rea LLD Rot. Level ANAL 1-LL 364.48 < 0.362 0.000E+00 I ANAL 2-LL ALPHA BETA 364.49 < 0.679 0.00 <-0.186 0.00 < 0.10 0.000E+00 0.322 0.776
***** Gamma-Soectroscopy Analysis *****
I 1-Sioma Activity MDA> Frac. of Nuclide Eneroy (DCi/ LITER) Error rea LLD Rot. Level MN-54 834.83 < 6.46 0.000E+00 CO-50 010.76 < 6.12 0.000E+00 I FE-59 C0-60 ZN-65 1099.22 1332.49 1115.52 14.6 5.61 13.2 0.000E+00 0.000E+00 0.000E+00 I NB-95 ZR-95 1-131 765.79 756.72 364.40 5.49 10.0 5.56 0.000E+00 0.000E+00 0.000E+00 CS-134 0.000E+00 I 604.70 < 4.43 CS-137 661.65 < 5.94 0.000E+00 BALA-140 1596.49 < 9.06 0.000E+00 l Total Fraction of Reporting Level 0.000E+00 Gamma results are listed as Less Than Levels usino Tech Spec LLD ecuation. LLD = 4.66 SORT B/t. Presence of less than sion for oamme results means no peak was found and the zero errer is not aoolicable. Tritium. Aloha and Beta results are the best estimate of the activity and the less than Sion indicates that the net activity is less than the critical level. CL. CL = 0.5 LLD l i I ................................................................. Analvted bytt ~ vrm 6 /11(g,v AppRo,co BN:M V&tpL/ @ 9 -/ #1 M d I dam ne dedgab chunel brin 3 w vina m3! % ak nntmat Miecrim 0erloci 4 8/4-s/2d%. SM # 4 mmP"j
""a
I DUKE P0t'ER COMPANY APPLIED SCIENCE CENTER RADI0 ANALYSIS LAFORATORY VAX/VMS Samole Analysis Report generated 11-SEP-1990 11:26:19 Plant Name I Samole Number Type / Location
- MFS
- 901
- DRINKING WATER / 136 Sample Date : 4-SEP-1990 10:36:00 I
Aca. Start Time : 5-SEP-1990 11:46:04 Samole Ouant2ty 3.50000 LITERS Samole ID : 7AUG TO 4SEP90 I Measurement Type : CONTROL Elaused Live Times 0 02:02:42.99
***** Alternate Analysis *****
Activity 1-Sioma MDA> Frac. of Nuclide Energy (oCi/ LITER) Error rec LLD Rot. Level ANAL 1-LL 364.48 < 0.320 0.000E+00 ANAL 2-LL 364.48 < 0.694 0.000E+00 ALPHA 0.00 < 0.178 0.399 I BETA 0.00 3.46 0.821 0.000E+00
***** Gamma-Soectroscopy Analysis *****
Act2vity 1-Sigma MDA5 Frac. of Nuclide Eneroy (pCi/ LITER) Error rea LLD Rot. Level MN-54 834.83 < 5.51 0.000E+00 CO-58 810.76 < 5.17 0.000E+00 FE-59 1099.22 < 12.7 0.000E+00 I CO-60 ZN-65 NB-95 1332.49 1115.52 765.79 7.80 11.3 5.57 0.000E+00 0.000E+00 0.000E+00 ZR-95 756.72 < 11.0 0.000'+00E I-131 364.48 < 5.89 0.000E+00 CS-134 604.70 < 4.81 0.000E+00 CS-137 661.65 < 5.49 0.000E+00 I BALA-140 K-40 1596.49 1460.81
< 6.71 99.9 0.000E+00 30.7 Total Fraction of Reporting Level 0.000E+00 Gamma results are listed as Less Than Level usino Tech Spec LLD equation. LLD = 4.66 SORT B/t. Prese*2e of less than sign for camma I results means no peak was found and the zero error is not app 12 cable.
Tritium. Aloha and Beta results are the best estimate of the I activity and the less than sign indicates that the net activity is lest than the critical level. CL. CL = 0.5 LLD I ......................... ..................... ................. L L APPRc>ED W f w. 9-/1-9 D
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- DUKE POWER COMPANY APPLIED SCIENCE CENTER RAD 10 ANALYSIS LABORATORY I VAX/VMS Samole Analysis Report generated i 11-SEP-1990 11:26:35 Plant Name : MNS Sample Number 900 Tyoe/ Location DRINKING WATER / 142 Sample Date 4-SEP-1990 10:10:00
- I Aco. Start Time : 5-SEP-1990 11:47:20 Sample Ouantity : 3.50000 LITERS Sample ID : 7AUD TO 4SEP90 I Measurement Type : ROUTINE Elapsed Live Time 0 01:40:00.00
***** Alternate Analysis *****
Activity 1-Sioma MDA> Frac. of I Nuclide ANAL 1-LL ANAL 2-LL Energy (DC1/ LITER) 364.48 < 0.341 364.48 < 0.656 Error rea LLD Rot. Level 0.000E+00 0.000E+00 ALPHA 0.00 < 0.178 0.397
-I BETA 0.00 2.73 0.789 0.000E+00
***** Gamma-Soectrotropy Analysis *****
Activity 1-Sigma MDA> Frac. of Nuclide Energy (pCi/ LITER) Error rea LLD Rot. Level I MN-54 C0-58 Fe-59 834.83 < 4.41 010.76 < 4.45 1099.22 < 8.24 0.000E+00 0.000E+00 0.000E+00 I O 60 1332.49 4 5.94 1115.51 < 6.76 765.79 < 4.21 0.000E+00 0.000E+00 0.000E+00 I 756.72 < 7.94 0.000E+00 I-! 364.40 < 5.20 0.000E+00 CE .; 604.70 < 4.82 0.000E+00 ( 137 661.65 < 6.00 0.000E+00 I \ +4-140 1596.49 < 6.67 0.000E+00 Total Fraction of Reportino Level 0.000E+00 Gamma results are listed as Less Than Levels using Tech Spec LLD eouation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not aoplicable. I Tritium. Aloha and Beta results are the best estimate of the activity and the less than sign indicates that the net activity is less than the critical level. CL. CL = 0.5 LLD Analyzed by b [n I
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I ......................................................................... DUKE POWER COMPANY APPLIED SCIENCE CENTER RAD 10 ANALYSIS LABORATORY I. ................................................................... ..... VAX/VMS Sample Analysis Heport generated i 16-0CT-1990 11:29:!b I Plant Name MNS Sample Number I Type / Location Samole Date : 1121 DRINKINO WATER / 132 2-0CT-1990 13:45:00 Acc. Start Time : 3-0CT-1990 11:00:05 I Sample Quantity : Sample ID Measurement Type 3.50000 LITERS
- 4$EP TO 20CT90 ROUTINE I Elapsed Live Tiaes 0 01: 40:00.00
- Alternate Analysis es***
I Nuclide Energy Activity 1-Sigma MDA> Frac. of (pCi/ LITER) Error rea LLD Rot. Level I ANAL 1-LL ANAL 2-LL ALPHA 364.40 < 0.469 364.40 < 0.609 0.00 <-0.107 0.000E+00 0.000E*00 0.324 BETA 0.00 3.33 0.030 0.000E+00
- Gamma-Spectroscopy Analysis *sses I Nuclide MN-54 Energy 034.03 <
Activity (pCi/ LITER) 5.67 1-Sigma 0.000E+00 MDA> Frac. of Error rec LLD Rot. Level I CO-50 FE-59 CO-60 010.76 1099.22 1332.49 4.36 13.6 6.72 0.000E+00 0.000E+00 0.000E+00 2N-65 1115.52 < 12.9 0.000E+00 NB-95 765.79 < 0.22 0.000E+00 2R-95 756.72 < 10.2 0.000E+00 1-131 364.40 < 7.27 0.000E+00 I CS-134 CS-137 ML A-140 604.70 661.65 1596.49 6.62 7.67 9.13 0.000E+00 0.000E+00 0.000E+00 I K-40 1460.01 94.0 Total Fraction of Reoorting Level 30.2 0.000E+00 I Gamma results are listed as Less Than Levels using Tech Spec LLD ecuation. LLD = 4.66 SQRT B/t. Presence of less than sign for gamma results means no peak was found and the zero error is not applicable. Tritium, Alpha and Beta results are the best estias.te of the activity and the less than sign indicates that the net activity is less than the critical level. CL. , CL = 0.5 LLD Analyzed by: M -
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