ML20095H884
| ML20095H884 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, McGuire  |
| Issue date: | 12/31/1991 |
| From: | Mcmeekin T DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9204300319 | |
| Download: ML20095H884 (124) | |
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,; ; April 24,1992
. UJ d. Nuclear Regulatory Commission H ' ATTN: Document Control Desk
- Washington, DC 205551 1- 1
Subject:
McGuire Nuclear Station Docket Nos. 50-369 and 50-370
- Annual Radiological Environmental Operating Report Reference TS 6.9.1.6-Gentlemen:
Pursuant to Technical Specification 6.9.1.6 for'McGuire Nuclear Station, attached is the subject report for
.1992 inc'uding Appendix E. ,
l- For questiors concerning this report, please contact Kathleen Mullen at (704) 875-4302. Very truly yours,- f_ 9
-T. .
huf L eekin Vice Presidert ' McGuire Nuclear Site = Attachments - :-Report-
-Appendix E-- ;p Jcc: -(With Report)
A Mr. T. A. Reed, ONRR l Washington D. Cl 20r3 Mr. S. D.~ Ebneter, R?ar.11 7 Atlanta, Georgia 30Mr., .U : Mr. P. K. VanDoorn, Senior Resident inspector
~ McGuire Nudear Station -;u Mr. D. Brown, Chief -
Radiation Protection Branch
; -- State of NC ,e Ms. Dottie Sherman,L ANI Library-. /
W .. _ s Farmington, CT 06032 - l 920430031?-911:31 [ Je l q PDR- ADOCK-05000369 PDR f y R / g unammn - h: l~ 'f h~ ,:2 .
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xc: (With Report and Appendix E) File: MC-801.01 (Helen Froebe-WC26A) File: MNS Master File 1.3.8.1 (With Report) J.W. Fot'3r (MNS/RP) J.S. Pope (MNS/RP) D.W. Phillips (MNS/SA) J.G. Twiggs (GO/RP) _ L.E. Loucks (GO/RP) M.W. Funderburke (GOiRP) M.D. Lane (MG03A) W.M. Carter (MG03A) E.H. Wehrman (ONS/RP) C.V. Wray (CNS/RP) (Without Attachments) R.L. Gill, Jr. (WC26A) R.O. Sharpe (MNS) G.D. Gilbert File: MC-801.01/MNS
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I I I I . . . . 3 ANNUAL RADIOLOGICAL g ENVIRONMENTAL OPERATING REPORT I I for I DUKE POWER COMPANY l McGu re Nuclear Station I - I I January 1 - December 31 1991 I I I
I _ TABLE OF CONTENTS I TITLE PAGE List of Figures . . . . . . . . . . iv List of Tables . . . . . . . . . . v
- 1. Executive Summary . . . . . . . . . 1-1
- 2. Introduction . . . . . . . . . 2-1 2.1 Site Description and Sample Locations . . . . 2-1 2.2 Scope and Requirements of Environmental Monitoring 1 Program . . . . . . . . . . 2-2 2.3- Statistical and Calculational Methodology g . . . . 2-10 3 2.3.1 Estimation of the Mean Value . . . . 2-10 2.3.2 Lower Level of Detection and Minimum Detectable Activity . . . . . . . . 2-10 2.3.3 Trend Identification . . . . . 2-11 2.3.4 Test Statistic . . . . . . . 2-13
- 3. Radiological Environmental Monitoring Prognun Discussion, Interpretation, and Trending of Results . . . . . 3-1 3.1 Airborne Radiolodines and Particulates I 3.1.1 Radiciodines . . .
. . 3-2 3-2 3.1.2 Particulates . . . . . . . 3-4 3.2 Drinking Water . . . . . . . . . 3-6 3.3. Surface Water . . . . . . . . . 3-11 3.4 Milk . . . . . . . . . . . 3-16 3.5 Broadleaf Vegetation . . . . . . . . 3-18 3.6 Shoreline Sec11 ment . . . . . . . . 3-20 3.7 Fish. . . . . . . . . . . 3-22 3.8 Direct Ganr.na Radiatic,n I 3.9 Food Product . .
3-20 3-28 3.10 Land Use Census . . . . . . . . 3-30 I i
I I TABLE OF CONTENTS (Continued) TITLE PAGE
- 4. Evaluation of Dose from Environmental Measurements Versus Estimated Dose from Releases . . . . . . . 4-1 4.1 Dose from Environmental Measurements . . . 4-1 4.2 Estimated Dose from Releases . . . . . 4-1 4.3 Comparison of Doses . . . . . . 4-2 4.4 Pathway Dose Calculations . . . . . 4-2 5 5. Quality Assurance . . . . . . . . 5-1 5.1 Duke Power Company's Environmental Laboratories . 5-1 5.2 Contractor Laboratory . . . . . . 5-6
- 6. References . . . . . . . . . . G-1 Appendix A: Environmental Sample and Analysis Procedures - Summary A-2
- 1. Change of Sampling Procedures . . . . . A-2 I II. Change of Analysis Procedures III. Sampling and Anal' sis Procedures A-2 A-3 lg A.1 Airborne Radiciodines and Particulates . . . A-3
! 3 A.2 Drinking Water . . . . . . . . A-3 A.3 Surface Water . . . . . . . . A-3 A.4 Milk . . . . . . . . . . A-3 I A.5 Broadicar Vegetation . . . . . . A-4 A.6 Shoreline Sediment . . . . . . . A-4 A.7 Fish . . . . . . . . . . A-4 A.8 Direct Gamma Radiation . . . . . . A-4 A.9 Food Products . . . . . . . . A-5 A.10 Land Use Census I . IV. Sampling and Analysis Improvements
. A-5 A-5 I
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I I TABLE OF CONTENTS I (Continued) 1 TITLE PAGE Appenaix B: Radiological Environmental Monitoring Program - Summary of Results . . . . . . . B-1 B.1 Radiciodines . . . . . . . . . B-2 B.2 Particulates . . . . . . . . . B-3 B.3 Drinking Water . . . . . . . . . B-4 B .4 Surface Water . . . . . . . . . B-6 5 B .5 MHk . . . . . . . . . . . B-8 B.6 Broadleaf Vegetation . . . . . . . B-9 B.7 Shoreline Sediment . . . . . . . . B-10 B.8 Fish . . . . . . . . . . B-11 B.9 Direct Gamma Radiation ' . . . . . . . B-12 B.10 Food Products . . . . . . . . . B-13 I Appendix C: Sampling Deviations and Unavailable Analyses . . C-1 A;.pendix D: Analytical Deviations - Lower Limits of Detection . D-1 I Appeneix s: ma,iologio.1 z.vironment.1 Monitoring er. gram ...It. s-1 I I I
- I
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l I I I UST OF FIGURES I 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 5 Concentration of Radionuclides in Fish . . . . 3-25 6 TLD Exposure from Direction Radiation . . . . 3-27 I
- I I
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I I UST OF TABLES I FIGURE TITLE PAGE 2.1 - A McGuire Radiological' Monitoring Program Sampling - Locations . . . . . . . . . . 2-4 2.1 -B McGuire Radiological Monitoring Program TLD Locations I 2. 2- A Maximum Values for the Lower Limits of Detection . .
. 2-5 2-8 2.2-B Reporting Levels for Radioactivity Concentration in I 2. 2-C Environmental Samples . . . . . . . 2-9 McGuire Radiological Manitor'ng Program Analyses . . 2-10 3.1.1- A Concentration of Radionuclides in Airborne Radiciodines . 3-3 3.1.1-B Percentages of Reporting Levels for Radiciodines . . 3-2 3.1. 2- A Concentration of Radionucli4s 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 3.2-B Percentages of Reporting Levels for Drinking Water . . 3-7 3.3-A Concentration of Radionuclides in Surface Water . . 3-13 3.3-B Percentages of Reporting Levels for Surface Water . . 3-12 3.4-A Concentration of Radionuclides in Milk . . . . 3-17 i 3.4-B Percentages of Reporting Levels for Milk . . . . 3-16 3.5-A Concentration of Radionuclides in Broadleaf Vegetation . 3-19 3.5-B Percentage of Reporting Levels for Broadleaf Vegetation . ; 18
- 3. 6-A Concentration of Radionuclides in Shoreline Sediment . 3-21 3.6-B Percentages of Reporting Levels for Shoreline Sediment . 3-20 3.7-A Concentration of Radionuclides in Fish . . . . 3-23 l g 3.7-B Te; entages of Reporting Levels for Fish . . . . 3-22 l5 -3.8-A TLD Exposure from Direct Radhtion . . . . . 3-26 l 3.8-B Comparison of Inner Ring / Outer Ring TLD Results . . 3-27 l 3.9-A Concentration of Radionuclides in Food Products . . 3-29 l
3.9-B Percentages of Reporting Levels for Food Products . . 3-28 l: 3.10 Land Use Census Results . . . . . . . 3-31 5.1 U.S. E.P. A. Interlaboratory Comparison Program - 1991 Cross Check Results for the ERL . . . . . 5-7 5.2 North Carolina Department of Environmental Health and I Natural Resources F .vironmental Dosimeter Crosscheck-1991. 5-9 V
I _ I 1.0 EXECUTIVE
SUMMARY
I This Annual Radiological Environmental Operating 11eport describes the I McGuire Nuclear Station Radiological Environmental Progra,m and the results of the program for the calendar year 1991. Included in the report are identification of sampling locations, descriptions -I of environmental sampling and analysis procedures, comparisons of present environmental radioactivity levels and preoperational environmental data, analysis of trends in the environmental radioactivity levels since the
- g- beginning of station operation, comparisons of doses calculated from E environmental measurements and doses calculated from effluent data, a summary of the results of the 1991 program, discussion of the results, and discussion of the quality assurance activities associated with the program.
Deviations from program requirements are abo included, Sampling activities were conducted as prescribed by Selected Licensee Commitments. Required analyses were performed and detection capabilities I met Selected Licensee Commitments Manual requirements. Supplemental samples also were taken in addition to the required sampling locations. Concentrations observed in the environment in 1991 for station related radionuclides were within the ranges of concentrations observed in the past. All positive indications of radioactivity due to plant operations were I less than the reporting levels specified by the Nuclear Regulatory Commission (NRC) and given in Selected Licencee Commitments. The environmental doses also were well below specified limits. Statistical an.dysis of data indicates that there are no radionuclides demonstrating high to moderate increasing trends. All possible increasing I trends showed moderate to no probability. It can be concluded that the contribution ti McGuire to the radioactivity in the environment is slight. I I I I I I 3 1-1
I I
2.0 INTRODUCTION
I 2.1 SITE DESCRIPTION AND SAMPLE LOCATIONS I McGuire Nuclear Station is located geographically near the center of the I highly indust:lauzed 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 resewoir. 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 I the Catawba River channel and to the north by the 32,510 acre Lake Norman. Lake Norman is impounded by Duke Power Company's Cowans Ford Dam Hydroelectric Station, which is located immediately west of the site and on the Catawba River channel. The tailwater of Cowans Ford Dam is the I 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 I 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.
-3 Tables 2.1-A and 2.1-B define the sampling and TLD locations for the 5 McGuire Radiological Monitoring Frogram. Figures 1 and 2 illustrate these locations as compared to McGuire Nuclear Station.
I I I I l !I I I i 2-1
I 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 levela for the site and vicinity which may be used to determine whether increases in environmental levels are attributable to the station. I The operational program provides surveillance and bsekup support of detailed effluent monitoring which is necessary to evaluate the significance, if any, of the contributions to the existing environmental radioactivity l levels that result from station operation. This monitoring program is based on NRC guidance as reflected in Selected l Licensee Commitments Manual Section 16.11-13 with regard to sample media, i 5 sampling locations, sampling frequency, and analytical sensitivity requirements. Tables 2.2-A and 2.2-B show the maximum values for LLD : and the reporting levels , respectively, from Selected Licensee I Commitments. Table 2.2-C shows the analysis schedule for each medium and the type of analysis required. Indicator and control locations were established for comparison purposes to distinguish radioactivity of station I origin from natural or other " man-made" environmental radioactivity. The environmental monitoring program also verifies projected and anticipated radionuclide concentrations in the environment and related exposures from releases of radionuclides from McGuire Nuclear Station. This program I provides surveillance of all appropriate critical exposure pathways to man and satisfies vitalinterests of the company, public, and state and federal agencies concerned with the environment. I I I I I I l 'I g 2-2
W W M M W W W W W W W M M M M M W W W TABLE 2.1-A McGuire Radiological Monitoring Program Sampling Locations Code: W-Weekly BW-BlWeekly SM-Semimonthly M-Monthly 0-Ouarterly C-Control SA-Semlannually A Sampling Location Description d Q"" Q"9 [ M. rw n v 120 Site Boundary (0.4 mi NNE) W M 121 Site Boundary (0.5 mi NE) W 125 Site Boundary (0.4 mi SW) W M 129 Discharge Canal Bridge (0.4 mi ENE) BW 129 Discharge Canal Entrance to Lake Norman (0.8 mi ENE) SA SA 130 Hwy 73 Bridge Downstream (0.6 mi SW) SA ga 131 Cowans Form Dam (0.7 mi W) BW . " 132 Charlotte Municipal Water Supply (11.2 mi SSE) BW 133 Cornelius (6.2 mi NE) W 134C East Lincoln Jr. High School (8.7 mi WNW) W M 135C Plant Marshall intake Canal (12.0 mi N) BW 136C Mooresville Municipal Water Supply (12.5 mi NNE) BW 137C Pinnacle Acx:ess Area (12.0 mi N) SA SA 138 Henry Cook Dairy (2.75 mi ESE) SM 139 William Cook Dairy (2.6 mi E) SM 140 Kidd Dairy-Ccws (2.8 mi SSE) SM 141C Lynch Dairy-Cows (14.8 mi WNW) SM 142 Davidson Municipal Water Supply (7.5 mi NE) BW 158 4-5 mile radius (5.0 mi NNE) M 184 5 mile radius Gardens (2.5 mi ENE) M(a) 185 5 mile radius Gardens (4.9 mi N) - Special interest M(a) 188 5 mile radius Gardens (2.8 mi N) - Special Interest M(a) (a) during harvest season
m M M M M M M M M M M M M M M M M M M Tc.bb 2.1-B MCGUIRE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS (TLD LOCATIONS)- SAMPLING LOCATION DESCRIPTION
- SAMPLlHG LOCAT10N DESCRIPTION
- 143 SITE BOUNDARY (0.3 MILES NW) 164 4-5 MILE RADIUS (4.5 MILES SSE) 144 SITE BOUNDARY (0.4 MILES NNE) 165 4-5 MILE RADIUS (5.0 MILES S) 145 SITE BOUNDARY (0.5 MILES NE) 166 4-5 MILE RADIUS (5.2 MILES SSW) 146 SITE BOUNDARY (0.5 MILES ENE) 137 4-5 M!LE RADIUS (4.9 MILES SW) 147 SITE BOUNDARY (0.4 MILES E) 168 4-5 MILE RADIUS (4.7 MILES WSW) 148 SITE BOUNDARY (0.5 MILES ESE) 169 4-5 MILE RADIUS (4 4 MILES W) 149 SITE DOUNDARY (0.6 MILES SE) 170 4-5 MILE RADIUS (4.5 MILES WNW) y 150 SITE BOUNDARY (0.5 MILES SE) 171 4-5 MILE RADIUS (4.5 MILES NW) 151 SITE BOUNDARY (0.4 MILES S) 172 4-5 MILE RADIUS (5 2 MILES NNW) 152 SITE BOUNDARY (0.5 MILES SSW) 173 SPECIAL INTEREST (8.5 MILES NNW) 153 SITE BOUNDARY (0.5 MILES SW) 174 SPECIAL INTEREST (8.7 MILES WNW) 154 SITE BOUNDARY (0.5 MILES W) 175 CONTROL (12.7 MILES WNW) l 155 SITE BOUNDARY (0.5 MILES WNW) 176 SPECIAL INTEREST (11.0 MILES SW) 156 SITE BOUNDARY (0.5 MILES WNW) 177 SPECIAL INTEREST (8.6 MILES S) 189** SITE BOUNDARY (0.4 MILES SSE) 178 SPECIAL INTEREST (9.2 MILES SE) 190 " SITE BOUNDARY (0.5 MILES WSW) 179 SPECIAL INTEREST (10 4 MILES ESE) 157 4-5 MILE RADIUS (4.8 MILES N) 180 SPECIAL INTEREST (11.5 M LES NNE) 158 4-5 MILE RADIUS (4.4 MILES NNE) 181 SPECIAL INTEREST (6.7 MILES NE) 159 4-5 MILE RADIUS (5.0 MILES NE) 182 SPECIAL INTEREST (6.0 MILES NE) 160 4-5 MILE RADIUS (4.9 MILES ENE) #83 SPECIAL INTEREST (5.5 MILES 5) 161 4-5 MILE RADIUS (4.7 MILES E) 186 SPECIAL INTEREST (0.2 MILES NNW) 162 4-5 MILE RADIUS (4.6 MILES ESE) 187 SPECIAL INTEREST (0.3 MILES N) 163 4-5 MILE RADIUS (5.0 MILES SE)
All TLD samp!ss are co!!ected quarterly. These TLD's were added 12/91 as a result of GPS data (See Appendix A)
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- TLD LOCATIONS MCGUIRE NUCLEAR STATION y4: A ALL OTHER SAMPLING LOCATIONS s /, -
Figure 2 Figure 2 Map orimMP Sampling Locations
- hARLOTTE WATER WORKS Pg 2 6
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gg g^ gg . Table 2.2-A MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD) WATER Al BORN PARTICME BROAD LEAF
^^ FISH MILK SEDIMENT (pCl/1)
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pCl (pCilkg, dry) pC e Gross beta 4 N.A. N.A. N.A. N.A. N.A. H-3 2000* N.A. N.A. N.A. N.A. N.A. Mn-54 15 N.A. 130 N.A. N.A. N.A. m Fe-59 30 N.A. 260 N.A. N.A. N.A. O Co-58,60 15 N.A. 130 N.A. N.A. N.A. Zn-65 30 N.A. 260 N.A. N.A. N.A. Zr-95 15 N.A. N.A. N.A. N.A. N.A. Nb ,5 15 N.A. N.A. N.A. N.A. N.A. 1-131 1 7x19 # N.A. 1 60 N A. Cs-134 15 5 x 10 # 130 15 60 150 Cs-137 6 x 10 4 IB 18 150 80 180 Ba-140 15 N.A. N.A. 15 N.A. N.A. La-140 15 N.A. N..a 15 N.A. N.A.
- If no drinkW;. vater pathway exists, a value of 3000 pCl/l rnay be used.
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~
a e e a e en - e [m e um mm an eM m 'M Table 2.2-B REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS
^ AIRDOPN PARTICULATE BROAD LEAF ANALYSIS OR GAS pCI pC g ey VEGETATION (pCl/m') (pCl/kg, wet)
H-3 2 X 10dN N.A. N.A. N.A. N.A. Mn-54 1 x 10' N.A. 3 x 10' N.A. N.A. Fe-59 4 x 10' N.A. 1 x 10' N.A. N.A. Co--58 1 x 10' N.A. 3 x 10' N.A. N.A. Co-60 3 x 10 N.A. 1 x 10' N.A. N.A. 2 Zn-65 3 x 10 N.A. 2 x 10' N.A. N.A. Zr-Nb-95 4 x 102 N.A. N.A. N.A. N.A. 1-131 2 1 N.A. 3 1 x 10' Cs-134 30 10 1 x 10' 60 1 x 10' Cs-137 50 20 2 x 10' 70 , 2 x 10' Ba-La-140 2 x 10 N.A. N.A. 3 x 10' N.A. (1) For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a va!ue of 3 x 10' pCl/l may be used. _m-__ m--_ _ _ _ - _ _ _ _ . _ _ - _ . _ _ . _ _ _ _ _ _
g g - g g >m a e sue M WM M M M M M E W W E Table 2.2--G McGuire Radiological Monitoring Program Analysis Analyses dampfe Analyses Gamma Medium Tritium L w Level Gross Schedule isotopic l-131 Beta TLD Radiciodine X
& Weekly Particulates X X Direct Radiation Quarterly X
Biweekly X ce Monthly Composite X E, Quarterly Composite X j Biweekly X Drinking Monthly Composite X Water Quarterly Composite X X ho n gg n Semiannually X Mit Semimonthly X X Fish Semlannually X B d' y at Semiannually X Foo( Monthly y Products (dt, ting harvest season)
1 I I ! l 2.3 STATISTICAL AND CALCULATIONAL METHODOLOGY l 2.3.1 ESTIMATION OF THE MEAN VALUE I There was one (1) basic statistical calculation performed on the raw data resulting from the environmental sample analysis program. The calculation involved the determination of the mean value for the indicator and the control samples for each sample medium. The mean is a widely used I statistic. This value was used in the reduction of the data generated by the sampling and analysis of the various media in the Environmental Monitoring _ Program. The following equation was used to estimate the moon: N Ex;
.I p /=1 N
Where: 'j Ic = estimate of the mean, W i = individual sample, N = total number of samples with a net activity (or concentration) x, = net activity (or concentration) for sample 1. NOTE: " Net activity (or concentration)" is the activP" (or concentration) determined to be present in the samp. No
" Minimum Detectable Activity", " Lower Limit of Detection", "Less Than Level", or negative activities or concentrations are included in the calculation of the mean.
I 2.3.2 LOWER LEVEL OF DETECTION AND MINIMUM DETECTABLE ACTIVITY The Lower Level of Detection (LLD) and Minimum Detectable Activity (MDA) are used throughout the Environmental Monitoring Program, both in the Selected Licensee Commitments and in the . implementation of - the _I specifications.
' The LLD, as defined in the Selected Licensee Commitments Manual is the L
smallest concentration of radioactive materialin a sample that will yield a net count, above system background, that will be detected with 95% probability l with only 5% probability of falsely concluding that a blank observation i 3 represents a "real" signal. The LLD is an a priori lower limit of detection. !3 The actual LLD is dependent upon the standard deviation of the background counting rate, the counting efficiency, the sample size (mass or volume), the radiochemical yield, and the radioactive decay of the sample between sample collection and counting. The " required" LLD's for each sample medium and selected radionuclides are given in the Technical Specifications . 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 background instead of a system background. In gamma sps.troscopy analyses , the sample background may be elevated above the system background due to the continuum produced by higher energy gammas from other radionuclides (either man-made or naturally produced). The
- continuum increases the smallest concentration of a particular radionuclide s that could be positively identified in the sample. Therefore, to insure that 15 the " required" LLD is riot exceeded for any radionuclide in a sample 5- medium, the MDA is calculated based on the actual backgound in the area of the identifying gamma energy and is compared to the " required" LLD.
If the MDA exceeds the " required" LLD, the sample is counted for a longer jI time period so that the standard deviation of the sample background is minimized. If the " required" LLD exceeds the MDA, then the analysis of the sample meets the requirementa for the detection capability for environmental sample analysis. For " gross" counters (such as alpha / beta proportional counters and liquid 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
-g so that the standard deviation of the batch background is minimized. If the g " required" LLD exceeds the MDA, then the analysis of the sample meets the requirements for the detection capability for environmental sample analysis.
2.3.3 TREND IDENTIFICATION Il One of the purposes of an environmental monitoring program is to determine W if thereis a buildup of radionuclides in the environment due to the operation of the nuclear station. Tnis is traditionally done by looking at historical ,3 data (including preoperational datc) and determining if a tend exists.
- 3 Trends, if they exist, may be either positive or negative. Sinco nuclear reactor operations do not normally remove radioactivity from the surrounding environment, a negative trend in a particular radionuclide's concentration in an environmental medium does not indicate that reactor operations are removing radioactivity from the environment but that reactor operations are not adding that radionuclida to the environment in quantities exceeding the preoperational level and that the normal removal processes (radioactive decay, deposition, resuspension, etc.) are influencing the 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 value from the data which will permit a meaningful interpretation of the relationship existing between the varietions 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 least squares regressian method may be used to define the linear relationship. To determine if the data actually correlate to the straight line assumption, the theoretical variance is compared to the actual variance. The numerical value that summarizes this comparison is known as the correlation coefficient. This correlation coefficient, symbolized by "r", is a determination of how closely the data fit a straight line and may be I calculated from the equation on the next page: 2-11
v NEXY-EXE Y [(NEX2 _(3y)2)(g3)c_(3y)2))$ Where: j
=
r correlation coefficient for the data set of X and Y, X = the year or point in time, Y = the radionuclide concentration associated with X, N = number of observations. The range of values as calculated by the correlation coefficient lies between positive on (+1) and negative on (-1). The absolute value of the correlation coefficient represents the probability of a trend. Zero (0) represents no indication of either a positive or negative trend. A positive (+) correlation coefficient indicates an increasing trend, and conversely, a negative (-) correlation coefficient indicates a decreasing trend. The ranges of a correlation coefficient may be summarized as following: I 11 f rl > 0.7 High to moderate probability of a trend. 0.7 2 f rl > 0.3 Moderate to poor probability of a trend. 0.31 lrl 10 Poor to no probability of trend. Identifying a trend by using the correlation coefficient is only useful for the time periods where the discharge from the nuclear plant is relatively stable I and no other sourecs of radioactivity are present. Substantialincreases or decreases in the amount of a' particular radionuclide's release from the nuclear plant will greatly affect the resulting environmental levels; !- therefore, a knowledge of the release of a radionuclide from the nuclear plant is necessary to completely interpret the trends, or lack of trends, determined from the environmental data. Other factors that may affect environmentallevels of radionuclides include prevailing weather conditions (periods 'of drought or heavier than normal precipitation), construction in
-I or around either the nuclear plant or the sampling location, addition or deletion of other sources of radioactive materials (such as the Cherncbyl
- g accident), etc. . Some of these factors may be obvious while others are 3 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 clepend
-not only on the least squares regression method, but will include come l judgement by plant personnel on the factors affecting environmentallevels.
. 2-12
I 2.3.4 TEST STATISTIC In some cases, we would not expect to observe a buildup of radionuclides in I' the environment, but instead would expect to see a measurable increase in levels over a short duration. This is the case for direct radiation measurements, where the radiation level is measured over a finite period I and is dependent upon whether plant discharges were occurring at that titre or not. In this case, the correlation coefficient is not a sufficient indicator of whether effluents are having an impact on the environment, since there is no bioaccumulation. Another test is needed to give us a meaningful interpretation of the data. If we assume that the naturally occurring radiation levels around the plant are normally distributed and that the effluents are not affecting the environment outside of this normal distribution, then we can compare the values of two sets of measurements taken at different times around the plant. One measurement can be taken when we are certain no effect is occurring and one when an effect may be occurring, to determine if they are statistically different from one another. The statistic that compares the means from two sets of measurements to determine if there is a statistically significant difference is called the test I statistic, or t-statistic, and is calculated as follows: X~X 1 2 s,}lln, + 1/n2 Where: ! ( = the mean value of the first set of measurements I ( = the mean value of the second set of measurements sp = the average standard deviation of the two sets of measurements I = h I Where: I 2 s' = (ni - 1)s i n,
+
+ n2 (n2 - I) 32
- 2 l5 ni = the number of measurements in the first set n2 = the rumber of measurements in the second set 2-13
I. The calculated value of the test statistic is then compared to expected values of the test statistic tabulated based on the number of measurements taken and the degree of confidence required for the results. For our purposes, the expected value of the test statistic will always be chosen to give a 95% confidence level that a positive result is truly oositive with only a 5% probability that a po.sitive result is truly negative. This confidence
-l level is chosen since it is consistent with the standard confidence levels E specified for similar measurements.
Due to the existence of naturally occurring differences in background
-I radiation levels over time (as a result of solar cyc:es and other meteorological phenomena) and systematic errors due to instrument variability, ratios of measurements can be used to calculate the t-statistic instead of individual measurements. By using ratios, the errors associated with the measurement process then cancel each other out and allow us to more accurately compare results from one year to the next. Specifically, in 'g the case of TLD measurements, the inner ring of TLD results is ratioed with 3 the outer ring of TLD measurements in a given year and the ratio for one year is compared to the ratio for another year.
As with other environmental samples, outside factors may affect the results observed and the resulting trends identified. Therefore, the significance of trends will be based in part on judgment of plant personnel fnmiliar with the factors affecting environmental levels, as well as the statistical results. s I I I
- I L
I 2-14
r
! 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MONITORING l PROGRAM - DISCUSSION, INTERPRETATION AND TRENDING OF RESULTS The radionuclides with Selected Licensee Commitments reporting evels in l g the environmental media samples have been historically trended over a l E twelve-year period from 1979 - 1991. Analyses from 1977 - 1978 have been excluded since these results were much higher than the other preoperational i years due to outside influence such as weapons testing. Including these !
results would have produced correlation coefficients and averages that were not representative. The highest annual mean concentration of each Selected Licensee Commitments radionuclide from the indicator and controllocations I for each media *ype was used for the estimation of the mean value and correlation coetlicient. The preopnational analyses from 1981 were combined with the operational analyses from the latter part of 1981 and averaged to give one concentratiori for each radionuclide for that year. I However, when preoperational comparisons were necessary, only the preoperational report was used. Thirteen annual means were used to determine trends and often the average concentra+ ions reported were negative. All negative valuce (concentrations) were replaced with a zero to properaf represent i environmental conditions. Figures 3 through 6 provide a graphical presentation of the annual mean concentrations for drinking water, 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 specialinterest purposes or because they consistently show detectable activity for a few radionuclidos. In additfor, the percentages of Selected Licensee Commitments reporting levels were calculated for each reportable radionuclide in each media type. I Only the radionuclides with Selected Licensee Commitments 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 radionuclide I levels could be affected without exhibitingincreasing or decreasing trends. No Selected Licensee Commitments reporting levels were exceeded in 1991 due to plant effluents. Sample analysis reports (SAR'S) are included in Appendix E. On many of i I these reports naturally occurring radionuclides (NOR) are listed. In most cases the listed NOR's are Potassium-40 (K-40) and Beryllium-7 (Be-7). l' 3-1 l
I l 3.1 AIRBORNE RADIOIODINES AND PARTICULATES I 3.1.1 RADIOIODINES In 1991, 261 radiolodine samples were analyzed, 209 at four indicator
. locations and 52 at the control location.
The I-131, Cs-134, and Cs-137 concentrations did not significantly diffar from the twelve year average, preoperational data, or controllocation levels for the twelve-year period. The historical trends based on highest annual I, mean for indicator and control locations for 1-131, Cs-134, and Cs-137 showed poor to no probability of increasing or decreasing trends as 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) g Table 3.1.1-B shows the percentages of environmental concentrations to the B selected Licensee Commitments reporting levels for the indicators at the locations with the highest annual mean for 1991. I I Table 3.1.1-B Radionuclide Concentration Reportmg Perceadage (pCdm') Level (pCi/m') 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 3-2
I Table 3.1.1-A Concentration of Radionuclides _iB Airborne Radiolodines Concentration (pCi/n?) YEAR 1-131 Cs-134 Cs-137 Indicator Control Indicator Control Indicator Control 1979
- 3.28E-3 1.04E-3 1.19E-2 -7.64 E-4 4.40E-3 1.47E-3 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 1.15E-3 2.99E-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 2.01E-4 6.80E-4 4.98E-.4 2.93E-3 3.21E-3 1984 3.17E-3 -1.15E-3 1.54E-3 3.05 E-4 4.67E-3 3.39E-3 1985 3.15E-3 1.04E-3 2.43E-3 9.24E-4 4.49E-3 3.56E-3 1986 1.27E-2 6.10E-3 1.18E-3 1.09E-3 3.32E-3 2.99E-3 5 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 1990 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 12 YEAR I AVERAGE 1991 5.37E-3 0.00E0 1.77E-3 0.00E0 1.62E-3 0.00E0 1.12E-3 0.00E0 5.13E-3 0.00E0 5.70E-3 0.00E0 CORRELATION COEFFICIENT 0.21 0.01 0.05 0.08 . -0.17 0.20
- Radiciodines and Particulates analy". i t.'gether.
NOTE: All negative values were replaced with "zero's" for calculational purposes. I E lg 3-3 l
_- - _ _ - - - . - - -_ - - - _ - . - - ~- - - - - 3.1. PARTICULATES
, in 1991, 261 particulate samples were analyzed, 209 at the four indicator locations and 52 at the control location.
The I-131, Cs-131, and Cs-137 concentrations did not significantly differ from the '.w ilve-year average, preoperationni data, and control location levels. The hister. cal trends for the indicator and controllocations with the highest annual mean for 1-131, Cs-134, and Cn-137 showed moderate to no probabilities of increasing or decreasing trends as illustrated in Tablo 3.1.2-A. Table 3.1.2-B shows the percentages of environmental concentrations to the l Selected Licensee Commitments reporting levels for the indicator locations with I the highest annual mean for 1991. No activity was detected and therefore no reporting levels were approached. t Iable 3.1.2 .B_ Radionuchde Concentration Repomng Percentage l (pCi/m') Level (pCi/m') l 1-131 0.00E0 1.00E0 0.00% Cs-134 0.00d0 1.00El 0.(O% [ Cs-137 , 0.00E0 2.00El 0.(U4 I f ,lf E I I ti i
~
I 3-4
l I IableM2-A QQncentration..o.LBadionu.clkipain Altbprne_P_ art [cylates Concentration (pct /m') YEAR l-131 Cs-134 Cs-137 Irdicator Conuul Irdiestor Control Irdicator Connel 8 1979
- 3.28E-3 1.04E-3 1.19E-3 -7.64 E-4 4.40E-3 1.47E-3 -
1980* 2.(ME-3 1.10E-3 -5.89E-5 -2.45 E-4 6.70E-3 4.53E-3 1981
- 4.17E-3 6.27E-4 1.15E-3 2.99E-4 6.16E-3 5.32E-3 1982
- 1.42E-3 2.48E-3 4.35E-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 2.0SE-3 9.90E-4 8.83E-4 1.74E-3 8.29E-4 1985 1.57E-3 2.05E-3 1.38E-3 1.0$E-3 1.86E-3 1.32E-3 l 1986 4.42E-3 3.36E-1 2.76E-3 8.90E-4 4.98E-3 3.03E-3 1987 9.73E-3 0.00E0 7.25E-3 0.00E0 1.07E-2 7.91 E-3 1988 0.00E0 9.15E-3 0.00E0 0.00E0 0.90E0 0 00E0 1 1989 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1990 0.00E0 0.00E0 0.00E0 0.00E0 0.00E O.00E0 -
12 YEAR AVERAGE 2.61E-3 1.84E-3 1.32E-3 4.91E-4 3.57E-3 2.49E-3 1991 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 CORRELATION I COEFFICIENT -0.27 0.06 0.02 -0.28 -0.53 -0.42
- Radiolodines and Particulates analyzed together.
NOTE: All negative values were replaced with "zero's" for calculational purposes. I I I 3-5
I I 3.2 DRINKING WATER, In 1991, 39 drinking water samples were analyzed for 1-131/LL, 26 at the two indicator locations and 13 at the control location. Tritium ('H-3) I 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 Selected Licensee Commitmerits reporting levels, 26 at indicator locations, and 13 at the controllocation. Analyses showed zero ranges for allindicatorlocations except for tritium, which means no other detectable activity was measured. All radionuclides did not sipificantly differ from the I twelve-year average. All radionuclides, significantly differ from preoperational data. except tritium, did not A moderate to poor probability of an increasing trend was indicated for 1 the indicator locations for H-3. However, the 1991 H-3 concentration only resulted in 2.61% of the Selected Licensee Commitments reporting level. The correlation coefifelents indicated a high to moderate probability of a decreasing trend for Co-60 indicator, Zr-95 indicator, i Ba/La-140 indicator, and I-131 (indicator and control) locations. All other radionuclide indicators and controls exhibited moderate to no I probabilities of increasing or decreasing trends. Table 3.2-A and Figure 3 illustrate these trends. FIGURE 3 I h CONCENTRATION OF TRITIUM IN DRINKING WATER pcl/l g 25oo i i i i i i 2000 103 OF FtEP RTING LEVEL l 1500 , 1000 + l s00 g,,i g , 1979 1980 1981 1982 1963 1964 1985 1986 1987 1988 19f') 1990 1991 1 b Year 3-6
l Table 3.2-B shows the percentages of environmental concentrations to the Selected Licensee Commitments reporting levels for the indicators at the locations with the highest annual mean for 1991. Iable_3,2-B i Radioruclide Concentration (pCi/l) Reponing Level (pCi/l) Percentage 11 - 3 5.22E2 2.00E4 2.619r Mn-54 0.00E0 1.00E3 0.00% Fe-59 0.00E0 4.00E2 0.00 % Co-58 0.00E0 1.00E3 0.00 % Co-60 0.00E0 3.00E2 0.00% Zn-65 0.00E0 3.00E2 0.(X)% Nb-95 0.00E0 4.00E2 0.00 % Z.r-95 0.00E0 4.00E2 0.00 % I-131/LL 0.00E0 2.(X)E0 0.00 % Cs-134 0.00E0 3.00El 0.00% Cs-137 0.00E0 5.00El 0.00% Ba/La-140 0.00E0 2.00E2 0.00% i
<1 I
I I l ; E
E I Iable 3,2-A Concentral10D_oLHadioBuclides in Drinking _ Water _, (Page 1 of 3) I Concentration (pCi/ liter) Year 11-3 Mn-54 Fe-59 Q>-58 Irdicator Qxarol Indicator Control Indicator Control Irdicator Gotrol 1979 1.65E2 1.50E2 1.46E0 4.27E-1 1.29E0 5.96E-1 1.14E0 2.01E0 1980 1.63E2 2.05E2 6.20E-1 -4.29E-1 1.77E0 5.20E-1 5.62E-1 -3.72E-1 1981 1.88E2 1.78E2 1.40E-1 -1.%E0 4.58E0 1.13E0 9.36E-1 4.33E-1 1982 2.43E2 1.4$E2 8.63 E-1 7.05E-2 3.50E0 -7.39E-1 7.71 E-l 6.26E-1 1 1983 2.65E2 1.45E2 4.18E-1 -3.06E-2 1.44E0 7.93 E-1 6.78E-1 -2.60E-1 1984 5.77E2 2.45E2 1.0$E0 1.42E-1 2.15E0 1.60E-1 8.89E-1 -2.57E-1 1985 5.93E2 4.00E2 7.14E-2 9.49E-2 7.73 E-1 -4.73E-1 3.39E-1 6.16E-1 1986 1.14E3 4.37E2 9.76E-l -4.59E-2 2.16E0 4.92E-1 3.82E-1 1.04E-2 1987 1.35E3 7.75E2 4.80E0 0.00E0 6.60E0 0.00E0 4.20E0 0.00E0 1988 9.92E2 7.11E2 0.00E0 2.50E0 0.00E0 0.00E0 0.000A 0.0002 1989 5.62E2 0'.(X)E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E' O.00E0 1990 7.32E2 6.1IE2 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 12 Yr. Avg. 5.81E2 3.34E2 8.67E-1 2.70E-1 2.02E0 2.67E-1 8.25E-1 3.08E-1 i 1991 5.22E2 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 Corr. Coef 0.63 0.30 -0.10 0.14 -0.37 -0.69 -0.18 -0.58 I NOTE: All negative values were replaced with "zero's" for calculational purposes. l 3-8
.. _ ..< s.
I, TjyM&3,Sonrenitation oJ_BadLonucnde in orink. Jag _ water d (Page 2 of 3) Concentration (pCi/ liter) Year - Co-60 Zn45 N b95 7.r-95 Irx12cator Control Indicator Control Indicator Control Indicator Control 1979 230E0 2.0lE0 1.10E-1 2.56E-1 2.52E0* -3.74 E-2
- 2.52E0* -3.74 E-2
- 1980 2.26E0 1.80E0 1.18E0 -7.44E-1 1.71E0* 6.52E-l
- 1.71E0* 6.52E-l
- 1981 1.43E0 1.34E-1 1.76E0 1.29E0 2.30E0 1.47E0 2.42E0 1.8'IE0 1982 8.25E-1 5.98E-1 1.16E-1 9.43E-1 1.35E0 1.42E0 2.49E0 2.02E0 1983 1.26E0 1.22E0 4.05E-2 -2.48E0 -3.99E-1 2.32E-1 1.82E0 1.05E0 1984 7.22E-1 -2.81 E-1 5.03E-1 1.29E-1 7.47E- 1 1.91E-1 2.70E0 -1.06E0 1985 8.44E-1 7.09E-1 -3.43E-1 -7.20E-2 9.32E-1 4.63E-1 1.09E0 5.70E-1 1986 2.33E-1 -3.46E-1 2.44 E-1 7.25E-2 9.87E-1 1.06E0 5.17E-1 -4.43E-1 I 1987 1988 0.00E0 0.00E0 0.00E0 4.50E0 0.00E0 0.00E0 0.00E0 0.00E0 5.30E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 7.10E0 0.00FA 1989 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1990 0.00E0 0.ME0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 12 Yr.
Avg. 8.23E-1 9.14E-1 3.26E-1 2.24E-1 1.32E0 4.57E-1 1.27E0 1.09E0 1 1991 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 I Corr. Coef -0.92 .20 -0.55 -0.49 -0.37 -0.50 -0.88 -0.05 I
- Nb-95 and Zr~95 analyzed as Nb/Zr-95 Lg NOTE: All negative values were replaced with "zero's" for calculational purposes.
'I I 3.e
l l I Iable12-A Concenttalion of Raillonucl! des in DdahlDQMa101 l (Page 3 of 3) l l I 1 m _ j Concentration (pCi/ liter) Year 1-131 Cs-134 Cs-137 BWLa-140 Indicato Control Irdicator Control Irdicator Control Irxtiemor Control 1 1 1979 4.95E0 6.97E-1 - 1.09E0 -4.12E-1 2.55E0 2.86E-1 1.62E0 1.54E-2 1980 7.39E-1 8.96E-1 -3.54 E-1 -6.24 E-1 9.53E-1 1.73E0 8.53E-2 2.06E-1 1981 1.83E0 1.0$E0 1.46E0 4.77E-1 1.13E0 1.16E0 1.09E0 -8.20E-1 1982 2.45E0 7.79E-2 5.38E-1 2.64E0 1.08E0 3.$0E0 8.28E-1 -6.73 E-1 1983 434E-1 -5.57E-1 6.29E-1 I 5.315-1 1.54E0 8.91E-1 4.26E-1 1.13E0 1984 9.46E-2 * -8.65 E-2
- 6.16E-1 -2.01 E-1 2.80E0 6.07E-1 1.16E0 -7.66E-1 1985 -1.84 E-1 * -1.27E-l
- 1.00E0 5.55E-1 1.43E0 -1.79E-1 5.15E-1 7.75E-1 1986 3.07E-2
- 5.63 E-2
- 8.18E-1 -1.45E-2 2.58E-1 2.83E-1 7.53E-1 -1. l l E-1 1987 4.10E-1 0.00E0 0.00E0 5.90E0 4.20E0 2.80E0 0.00E0 4.00E0 1988 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1989 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1990 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 12 Yr.
I Avg. 8.77E-1 2.31E-1 4.225-! 9.26E-1 1.27E0 9.08E-1 5.40E-1 5.l lE-1 1991 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 Corr. Coef -0.71 -0.72 -0.37 -0.01 -0.39 -0.39 -{}.71 0.09 01-131/LL analysis data used. NOTE: All negative values were replaced with "zero's" for calculational purposes. I 3-10
l 3.3 SURFACE WATER
.l In 1991, 39 surface water samples were analyzed for I-131/LL, 26 at the M'
two indicator locations and 13 at the control location. Analyses for 11-3 were performed on 12 samples, eight at indicator locations and four at the control location. Thirty-nine samples were analyzed for all other I radionuclides with Selected Licensee Commitments reporting levels, 26 at indicator locations and 13 at the control location. All Selected Licensee Commitments radionuclides except 11-3 showed zero ranges indicating that no other detectable activity was measured . All 4 radionuclides, except 11 - 3 , were not significantly different from
- preoperational data and the controllocation levels. All radionuclides did I not differ significantly from the twelve year average. 1 There is a moderate to poor probability of an increasing trend for 11-3
'E indicator. There is a high to moderate probability of a decreasing trand 4 g for Co-58 (indicator), Co-60 (control) and I-131 (indicator). The 1991 concentration of 11-3 resulted in 3.77% of the Selected Licensee Comrdtments reporting levels. All other radionuclide indicators and I controls exhibited nioderate to no probability of increasing or decreasing trends. Table 3.3-A illustrates these trends. l5 .I I
- I I
t I I I I 3 11
Table 3.3-D shov.'s the percentages of environmental concentrations to the Selected Licensee Commitments reporting levels for the indicators at the location with the highest cnnual mean for 1991. 1 Table 3.3-B l I l Radionuclide Concentratico QCill) Reponing Level QCV1) Percentage l 11- 3 7.53E2 2.00E4 3.77 % Mn-54 0.00E0 1.00E3 0.00 % Fe-59 0.00E0 4.00E2 0.(0% m' Co-58 0.00E0 1.00E3 0.00% Co-60 0.00E0 3.00E2 0.00% Zn-65 0.00E0 3.00E2 0.(0% Nb-95 0.00E0 4.00E2 0.00 %
-95 0.00E0 4.00E2 0.00 %
l-131/LL 0.00E0 2.00E0 0.(0% C.-l>4 g e.eeee 3.eee, e.ee% Cs-137 0.00E0 5.00E1 0.00 % Ba/La-140 0.00E0 2.00E2 0.00% I I I I I I I 3-12
I I Igbjn.13-A CDncAntration oLBadlonuclidasjn_Syriapp_WAtef (Page 1 of 3)
- l E Correntration (pCi/ liter) l Year 11 - 3 Mn-54 Fe-59 Co-58 l
Irxiicator Cmtrol Indicator Control lixlicator Control trxlicator Courol
]
i : I , 1979 1.85E2 1.66E2 8.95 E-1 6.35E-1 1.69E0 2.55E0 1.47E0 1.90E-1 j 1980 2.13E2 1.93E2 2.17E0 5.81E-1 5.21E-1 9.48E-1 1.17E0 -5.16E-2 1981 1.75E2 1.70E2 4.95E-2 -1.10E0 1.79E0 3.40E0 9.74E-1 -1.35 E-1 1982 3.30E2 1.23E2 1.02E0 -1.22E-1 1.97E0 -3.99E-2 1.63E-1 5.10E-1 1983 5.75E2 3.67E2 -2,30E-1 9.74E-1 1.76E0 -7.08E-1 6.14E-1 5.08E-2 I 1984 4.10E2 2.ME2 -7.55E-2 -4.19E-l -4.88E- 1 9.15 E-1 3.30E-i 4.24E-1 1985 7.33E2
- 1.01E0 -4.75E-1 3.91E-1 1.(ME0 7.61E-1 1.65E-1 1986 2.33E3 6.13E2 5.13E -I 3.97E-1 -1.67 E-l 4.36E-2 -2.93E-3 3.31E-1 1987 9.20E2 7.70E2 0.00E0 0.00E0 1.10El 0.00E0 0.00E0 0.00E0 1988 9.40E2 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1989 8.22E2 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1990 6.77E2 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 12 Yr.
Avg. 6.93E2 2.22E2 4.71E-1 2.16E-1 1.59E0 7.41 E-1 4.57E-1 1.39E-1 I. - 1991 7.53E2 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00F4 0.02E0 Corr. Coef 0.49 -0.16 -0.61 -0.53 -0.06 -0.67 -0.85 -0.34 0 No sample analyzed. NOTE: All negative values were replaced with "zero's" for calculational purposes. I e 3-13
l Table 3 13-A Concentration of Radioljuc11@s la_ Surface Water _ _ (Page 2 of 3) .I Concentratim (pCi/ liter) ' Year - Co-60 Zn45 NI>-95 Zr-95 Indicator Contral Irx!icator Control Indicator Control Indicator Control 1979 2.45E0 2.60E0 8.62E-1 -5.33 E-1 -2.53 E-1
- 5.77E-l * -2.53 E-l
- 5.77E-l*
1980 1.36E0 1.12E0 7.70E-1 1.80E0 1.00E0' -2.$4 E-l ' l.00E0' -2.54 E-l
- 1981 2.47E-1 1.54E0 --6.29E-1 6.93E-1 -2.92E-1 3.50E-2 1.98E0 9.04E-1 1982 1.14E0 6.02E-1 6.28E-1 -3.935-1 2.16E0 8.89E-1 2.23E0 8.92E-1 1983 1.66E0 2.01E0 -1.20E0 4.71 E-1 3.22E-1 1.15E0 3.27E-2 1.41E0 1984 1.47E0 3.3SE-1 -9.79E-2 5.91E-1 8.59E-1 2.66E-2 1.67E0 -1.45E-1 1985 3.86E-1 9.97E-1 1.22E0 -2.43 E-2 ti.10E-1 4.17E-1 1.16E0 1.74E0 1
1986 -1.36E-1 2.2d E-2 -1.24E0 -1.65E0 1.0$E0 1.19E0 1.33EO -3.91 E-1 i 4 I 1987 1988 5.20E0 0.00E0 0.00E0 0.00E0 0.00E0 2.70E0 0.00E0 0.00F0 4.50E0 0.00E0 0.00E0 0.00E0 1.20El 0.00E0 0.00E0 0.00E0 1989 0.00E0 0.00E0 0.00E0 0.0020 0.00E0 0.00E0 0.00E0 0.00E0 15'90 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 12 Yr. l Avg. 1.16E0 7.69E-1 5.15E-1 2.%E-1 8.75E-1 3.57E-1 1.78E0 4.60E-1 1 1991 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 I Corr. Coef -0.29 -0.81
-0.08 -0.54 -0.05 -0.34 0.03 -a43 I C Nb-95 and Zr-95 analyzed as Nb/Zr-95 i
NOTE: All negative valttes were replaced with "zero's" for calculational purposes. I E s-u
I l I Iable_3.3-A ConteB1Lailon_of RadioDucildes in SpffaceMater (Page 3 of 3) I Comentration (pCi/ liter)
=
Year 1-131 Cs-134 Cs-137 Ba/La-140 Indicator Control Irxiicator Control Indicator Control Indicator Control I
~
1979 2.66E0 -8.27E-1 -3.62E-1 -1.00E-1 2.63E0 -2.21 E-1 2.26E-1 -4.25 E-1 1980 1.13E0 1.20E0 -2.60E-1 -9.98 E-1 1.97E0 1.27E0 9.70E-l -3.20E-i 1981 2.32E0 -6.85 E-1 2.10E-2 1.88E-1 1.05E0 2"E0 6.98 E-1 8.66E-1 1952 -3. l l E-1 -9.19E-1 -5.68E-1 8.34 E-1 1.23E-1 1.65E0 4.30E-1 -4.11 E-1 1983 1.89E0 2.88E0 7.87E-1 2.50E-1 8.43E-1 2.39E-1 1.38E0 2.89E-1 1984 3.02E-2* 1.58E-l* 7.36E-1 1.70E0 9.46E-1 3.30E-2 -2.84E-1 -6.81 E-3 1985 -8.69E-2* -7.90E-2
- 1.72E0 1.25E0 1.23E0 3.26E-1 3.79E-1 4.53E-1 1986 8.94 E-2* 2.13E-2
- 7.54E-1 1.13E-l 5.615-1 1.97E-1 8.72E-1 8.29E-1 1987 0.00E0 0.00F0 4.40E0 0.00E0 4.70E0 0.0CEO 0.00E0 0.00E0 1988 0.03E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0
- I 1989 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0 00E0 1990 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 12 Yr.
I Avg. 6.77E-1 3.55E-1 7.02E-1 3.61E-1 1.17E0 5.14E-1 4.13E-1 2.03E-1 1991 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 Corr. Coef -0.73 -0.31 0.12 -0.20 -0.36 -0.58 -0.56 -0.21 I
- I-131/LL analysis data used.
NOTE: All negative values were replaced with "zero's" for calculational purposes.
~
I- 3 1s
;h 3.4 MILK I In 1991, 108 milk samples were analyzed, 81 at the three indicator locations and 27 at the control location.
All Selected Licensee Commitments radionuclides showed a zero range indicating no detoctable ectivity was measurad 'n 1991. The I-131/LL, a Cs-134, Cs-137, and Ba/La-140 concentrations did not significantly g differ from the twelve-year average, preoperational data, and control levels. A high to moderate probability of a decreasing trend was indicated for I.. Cs-137 indicator. 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 shows the percentages of environmental concentrations to the Selected Licensee Commitments reporting levels for the indicators at I the location with the highest annual mcan for 1991. I g Table 3.4-B. Radionuclide Concentration Rp:>rting Percentage (pCl/1) Levcl(pCi/l) 1-131/LL 0.00E0 3.00E0 0.00 % Cs-134 0.00E0 6.00E1 0.00 % Cs-137 0.00E0 7.00E1 0.00 % Ba/La-140 0.00E0 3.00E2 0.00 % I I I I I l
.-u 1 3-10
I !B lable 3.4..A Concentration of Radionuclides in Milk .I Concentratim (pCi/ liter) Year - 1-131 Cs-134 Cs-137 Ba/La-140 Irxiicator Control Indicator Control Indicator Control Indicator Control 1979 6.87E-3 -6.13 E-2 -7.05E- I 7.63E-1 2.48El 6.04E0 0.00E0 -6.15 E-1 1980 1.06E0 3.22E-2 -7.94 E-2 -6.12E-1 1.72El 4.13E0 1.29E0 133E-1 1981 -3.70E-3 -6.54 E-2 1.37E0 -2.88E-1 2.04E1 4.15E0 3.77E-1 -7.95E-2 19112 -3.22E-2 -8.49E-2 9.44 E-1 -4.38E-2 1.21El 5.20E0 2.31E-1 -4.11 E-1 1983 1.23E-2 -4.57E-2 1.26E0 1.55E0 2.02El 2.82E0 4.44E-1 2.35E-1 1984 1.78E-2 -4.30E-2 1.08E0 1.80E0 1.48El 2.56E0 4.79E-1 1.43E-1 1985 2.00E-2 -5.80E-2 9.32E-l 1.99E-1 1.42El 2.72E0 5.78E-1 5.97E-1 1986 8.30E-1 7.55E-1 2.36E0 9.38E-1 3.74E0 3.4$E0 2.95E-1 1.08E-1 1987 4.80E-1 0.00E0 5.10E0 3.60E0 5.20E0 8.60E0 0.00E0 4.40E0 1 1988 0.00E0 0.00E0 0.00E0 0.00E0 3.40E0 2.90E0 0.00E0 0.00E0 1989 0.00E0 0.00E0 0.00E0 0.00E0 6.00E0 5.60E0 0.00E0 0.00E0 1990 0.00E0 0.00E0 0.00E0 0.00E0 5.30E0 2.60E0 0.00E0 0.00E0 l 12 Yr. Avg. 2.02E-1 6.56E-2 1.09E0 7.38E-1 1.23El 4.23E0 3.08E-l 4.68E-1
- I 1991 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 l Corr.
Coef -0.21 0.06 0.01 -0.03 -0.90 -0.33 -0.56 0.14 lI NOTE: All negative values - cre replaced with "zero's" for calculational purposes. I I LI 3-n t
~
l 3.5 BROADLEAF VEGETATION y In 1991, 48 broadleaf vegetation samples were analyed, 36 at the three indicator locations and 12 at the controllocation. The 1986 data is higher than the other years due to the Chernobyl accident. . All Selected Licensee Commitments radionuclides except Cs-137 showed zero I ranges indicating that no detectable activity was measured. Only one of 3G samples taken indicated Cs-137 activity. The correlation coefficients for the !ccation with the highest annual mean I indicated a moderate to poor probability of an increasing trend for Cs-137 indicator and control. liowever, this concentration resulted in only 1.65% of the Selected Licensee Commitments reportinglevel. Since there were anomalous I results in 1984 for Cs-134 and Cs-137, new concentrations for these radionuclides were calculated using the location with the highest annual mean excluding these anomalies. The remaining radionuclide indicators and controls a exhibited poor to no probabilities of increasing or decreasing trends. These g trends are illustrated in Table 3.5-A. Table 3.5-B shows the percentage of environmental concentrations to the I Selected Licensee Commitments reporting levels for the indicators at the locations with the highest annual mean for 1991. Table 3.5-El Radiorrxlide Concentration Reporting Pen:entage l (pCiAg) Level (pCiAg) I-131 0.00E0 1.00E2 0.00% Ce-134 0.00E0 1.00E3 0.00% Cs-137 3.30El 2.00E3 1.65 % 1 I I l l
-18
l l InbleA5.- A Conp_enttation of Radiony.cJldRS_kLB_toadJgaf
.VegetatLon I
Concentradon (pCi.ig-wet) YEAR l-131 Cs-134 Cs-137 Indicator Control Indicator Control Indicator Control
-5.82E0 7.30E-1 -1.00El -1.06El 2.19El 1.93El I
1979 1980 1.91El 6.15E0 -239E0 -1.25El 2.30El 1.92El 198! -1.87E0 3.16E0 1.24El 5.96E0 3.04El 2.02El 1982 J.41El 6.59E0 1.50El -4.31E-1 2.46El 1.22El 1983 1.13El 7.19E0 4.13E0 1.24E0 9.07E0 7.85E0
-1984 6.06E0 5.99E0 8.46E0 2.80E0 1.02El 1.05El I 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 1.2'iEl 1987 0.00E0 1.10El 1.70El 2.50El 2.20El 1.70El 1988 0.00E0 0.00E0 0.00E0 0.00E0 3.90E1 3.40E1 1989 0.00E0 0.00E0 0.00E0 0.00E0 9.60El 0.00E0
- s 19M) 0.00E0 0.00E0 0.00E0 0.00E0 4.00El 0.00E0 12 YEAR AVERAGE 7.06E0 4.93E0 7.67E0 6.03E0 3.04El 1.27El 1991 0.00E0 0.00E0 0.00E0 0.00E0 3.30Ei 0.00E0 CORRELATION COEFFICIENT -0.32 -0.19 -0.13 0.10 0.48 -0.43 NOTE: All negative values were replaced with "zero's" for calculational purposes.
d I I I 2-1e
3.6 SHORELINE SEDIMENT l In 1991, six shoreline sediment samples were analyzed, four from two indicator locations and two at the control location. The currelation coefficient for the location with the highest annual mean indicated a moderate to poor probability of an increasing trend for Cs-I 137 indicator. liowever, the Cs-137 concentration only corresponds to a small percentage of the Selected Licensee Commitments reporting level j as 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 i trend. These trends are illustrated in Table 3.G-A and Figure 4. l Iable 3.6-El i i g I Radionu:lide Concentration Reponing Percentage , (pCiAg) Level (pCiAg) Cs-134 0.00E0 3.00E3 0.00 % Cs-137 1.03E2 3.00E3 3.43 % g ~h FIGURE 4 CONCENTRATION OF RADIONUCLIDES IN SHORELINE SEDIMENT PCIAg wet 0 I i
"" 200 M
l l 100 I
. I 0
I I I
%Y'"!lD 1879 1980 1901 1982 1943 1964 1998 1900 1907 1988 1940 1900 1981 Year
-#= Ca-137 indcator -dr
- Cs-137 Control I r I
I
i l I E .
- l Igble 3.6-A Concentrat]on otRadlonuclides in sitoreline' Sediment I
Concentration (pCi/kg-dry) I Yes Cs-134 Cs-137 I ! 1979 Indicator 0.00E0 Control 1.20El Indicator 1.20El Control
-l r7El 1980 -3.53E0 -1.85El 1.44El 6.88El 1981 3.97El 6.08E0 3.36El 1.65E0 1982 7.67El 4.61El 4.40El 2.13El 1983 7.65El 2.78El 8.02El 3.28El 1984 3.34El 1.32El 9.13El 3.65El 1985 2.02El 1.03EI 1.61E2 1.70Ei 1986 6.35El 3.67El 1.53E2 1.95El 1987 4.20E1 2.40El I.65E2 0.00E0 1938 9.10E0 0.00E0 2.66E2 1.70El 1989 5.30El 0.00E0 6.50El 1.40El 1990 0.00E0 0.00E0 6.10El 2.10El j 12 Year Average 3.45El 1.47El 9.53E! 2.09.E l 1991 0.00E0 0.00E0 1.03E2 0.00E0
! Correlation Coefficient -0.14 -0.30 0.53 -0.32 l NOTE: All negative values were replaced with "zero's" for calculational purposes.
- I I
tI i s-n
I l 3.7 FISH In 1991,12 fish samples were anlyzed, six at the indicator locations and I 'six at the control location. All Selected Licensee Commitments radionuclides except Mn ,.'t. Co-58, Co-GO, Cs-134, and Cs-137 showed zero ranges indicating 1)o detectable activity was measured. The radionuclides named above were not significantly different from the I twelve-year average, preoperational data, and control location levels. In addition, these concentrations only correspond to small percentages I of the Selected Licensee Commitments 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 Mn-54, Co-58, Co-60, Cs-134, and Cs-137 and a high to moderate probability of a decreasing trend for the control concentration of Fe-59. All other radionuclide indicators and controls exhibited moderate to no probability ofincreasing or decreasing trends. These trends are illustrated in Table 3.7-A and Figure 5.
, l Bble 3.7-B I Radionuclide Con:entrariar. (pC /kg) Reponing Level (pCi/kg) Percentage Mn-54 6.20E0 3.00E4 0.02 % Fe-59 0.00E0 1.00E4 0.00 % Co-58 1.40El 3.00E4 0.05% Co-00 6.50El 1.00E4 0.65 % s i Zn-65 0.00E0 2.00E4 0.00% Cs-134 5.90E0 1.00E3 0.59 % Cs-137 2.60El 2.00E3 1.30 % 1 I , i 3-22
I l Igble 3,7-A bncentratiortof Radionucjides in Fish {Page 1 of 2) I Concentration (pCVkg-we0 Year Mn-SC Fe-59 Co-58 Co-60 Indicator ] Cmtrol trol Indicator Control Indicator Contrul h Indicator f 1979
- 0.00F-2 *
- 3.71El -2.78E-1
- 9.86E0 1980 -1.97El 1.14Es alMEl 3.74El 8.36E0 8.60E0 -2.25El 1.14El 1981 -2.71E0 2.74F0 3.70E0 2.97El -2.98E0 4.25E0 -2.65E0 -2.36E0 1982 -3.83E0 1.28El 0.00E0 8.47El 8.16E0 2.65E0 -4.34 E-1 2.95E0 1983 -?,60E0 -1.84E0 -8.68E0 8.28E0 2.60El -5.31E0 1.llEl 2.42E0 1984 3.61E0 3.37ED -1.23El 2.21El 1.45E2 4.15E0 2.82El 2.83E0 1985 2.53E-1 -1.75E0 4.25E0 4.49E0 7.19E0 1.32El 1.72El 1.55El 1986 1.03E0 -1.91 E0 -1.21E0 3.77E0 3.17El -1.79E0 2.%El 5.13E0 1987 0.00E0 lI 0 00E0 0.00E0 0.00E0 2.71E2 0.00E0 1.23E2 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 1990 0.00E0 0.00E0 0.00E0 0.00E0 5.60El 0.00E0 4.10El 0.00E0 12 Yr.
Avg. 9.72E0 3.02E0 7.23E-1 1.98El 9.41El 2.74E0 5.01El 4.17E0 I 1991 6.20E0 0.00E0 0.00E0 0.00E0 1.40El 0.00E0 6.50El 0.00E0 Corr. Coef 0.37 -0.42 4.21 -0,72 0.44 -0.37 0.52 -0.53 Y I
- No sample analyzed.
NOTE: All negative values were replaced wnh "zero's" for calculational purposes. I I s-23
I l l h Iahle 3.7-A Concenitation of Ritdiolluclides in Fish (Page 2 of 2) l tI Comentratim (pCiAg-wet) l l YEAR Zn-65 Cs-134 Cs-137 i ludicator Control Indicator Control Indicator Cel 1979 * *
- 1.73E0 -4.17E0 2.20El 1980 -3.22El -2.26El -2.70El -2.!0E0 -4.13 E0 8.07E0 1981 4$2E0 1.16E0 -1.99E0 0.09E0 1.80El 2.77El 1982 -1.39El -9.ME0 8.22E-1 3.57E-1 2.69El 9.52E0 1983 -1.07E0 4.86E0 -1.32E0 -2.57E0 6.03El 2.08El
,I 1984 -2.87E0 -3.2600 3.llEl -7.09E-1 4.38El 8.18E0 1985 -2.55E0 3.17E0 -1.56E0 5.22E0 1.86El 1.48El 1986 -8.09E0 -1.40El 1.67El 1.56E0 3.49El 8.64E0 1987 0.00E0 0.00E0 2.60El 0.00E0 5.10El 2.90El 1988 0.00E0 0.00E0 2.70EI 0.00E0 3.60El 2.30EI 1989 0.00E0 0.00E0 1.10El 0.00E0 353El 1.50El 1990 0.00E0 0.00E0 0.00E0 0.00E0 3.30El I.60El 12 Year Average 4.20E-1 9.10E-1 1.02E1 1.35E0 3.25El 1.74El 1991 0.00E0 0.00E0 5.90E0 0.00E0 2.60El 0.00E0 CORRELATION COEFFICIENT -0.31 -0.34 0.35 -0.28 0.47 -0.16 J
- No sample analyzed.
NOTE: All negative values were replaced with "zero's" for calculational purposes. I t, 8 2.x
i l 4 FIGURE 5 j I ' l I CONCENTRATION OF CO-60 peng-w t IN FIGH . 600 . r > i ! 4 f j l i i , i $% REPORTING LEVEL ! ,~ l l
.I 500 t
i I i i i i i w i j i
,' l 400 7 i 1 ; , i
! ! l : l ! i i ! i I- 300 ' ; l ;
j l 7_ , l j l I l! ! l l I i i I ' i 4 , i j i I I l l j ! i I l { g _ 1979 1980 1991 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 Year g I I I I lI I !I
- I I
!I l 3-25
l 3.8 DIRECT GAMMA RADIATION i In 1991,170 TLD's were analyzed,166 at indicator locations and four at the control location. The 1991 exposure rate at the indicator location with the highest annual,mean did not significantly differ from the preoperational data or twelve-year average. Table 3.8-A and Figure 6 illustrate this summary. I Table 3.8-A TLD Exposure from Direct Radiation I Exposure (mrem /yr) I YEAR Indicator Control 1979 8.76El 8.32El 1980 1.16E2 1.05E2 1981 1.45E2 1.0$E2 1982 1.36E2 1.10E2 1983 1.75E2 1.30E2 1984 1.20E2 9.02El 1985 1.52E2 1.27E2 1986 1.40E2 1.10E2 1987 1.43E2 1.23E2 1988 1.08E2 5.48El 1989 9,77El 7.55El 1990 8.30El 6.23El 12 Year Average 1.24E2 9.67El 1991 9.60El 6.80El LI NOTE: The expected background for North Carolina is 120 mrem per year from FSAR 11.6.1. I
. 3-26
I - g FIGURE 6 TLD EXPOSURE
! m R/yr FROM DIRECT RADIATION j
2, , , f : l I l ; f 160;
~
i , , l j ! . l l 120 T- - - - I - l < 1 i i , i 80 - - -H 40 ,
, i ,
o 1979 1960 1981 1982 1983 1904 1965 1996 1967 1968 1969 1990 1991 I r Year
-e- TLD Indicator -*- TLD Control n
a The test statistic, or t-test, was used to compare the TLD measurements during preoperation to those taken during 1991. In this case, ratios of results from the 1-2 mile radius and the 4-5 mile radius were compared from one year to the next. Since the inner ring of TLD's are most likely to be affected by plant
.E operations, the hypothesis was used that a significant change in the ratio from .5 one year to another would be indicative of an environmental effect or some other phenomena requiringinvestigation. A statistically significant change in the ratio was determined by comparing the calculated t-value to the expected I values of the test statistic based on the number of measurements and the desired accuracy of the results.
I The value of the t-statistic was calculated by comparing preoperational results to 1991. As shown in Table 3.8-B, the t-value was -0.502. This compared well to the expected value of i 2.056, based on 26 degrees of freedom at the 95% I confidence level (at = 0.025, n = 26). Therefore, it can be concluded that the dose rates around McGuire during 1991 did not differ significantly from those measured during preoperation. Table 3.8-B Comparison of Inner Ring / Outer Ring TLD Results 1991 (mr/nt) Preop (mr/hr) Inner Ring 51.42 79.14 Outer Ring 55.91 88.16 Ratio 0.94 0.91 .g Variance 0.03 0.02 5 t-value -0.502 } t-table -2.056 I 3-27
1 E i l 3.9 FOOD PRODUCTS In 1991, 17 food products (crops) samples were analyzed, all at the " indicator location. No control site was available for food products in 1991. All Selected Licensee Commitments radionuclides exhibited a zero range indicating no measurable activity present. ' The I-131, Cs-137, and Cs-134 concentrations did not significsntly I differ from the twelve-year as erage and preoperational data. Ali of the radionuclides exhibited moderate to no probability of a decreasing trend. No control sites were available for 1984 through 1991; therefore, a representative correlation coefficient could not be calculated for the I control data. Table 3.9-A illustrates this summary. Table 3.9-B shows the percentages of environmentul concentrations to I the Selected Licensee Commitments reporting levels for the indicators at the location with the highest annual mean for 1991. No activity was detected and therefore no reporting levels were approached I !l Table 3.9-B 1 Rarbonuclide Concentration (pCi/kg) Report 8n1 i evel (pCL%) 1%rcentage 1-131 0.00E0 1.00E2 0.00% Cs-134 0.00E0 1.00E3 0.00 % Cs-137 0.00E0 2.00E3 0.00 % f I I I1 I 3-28
i l I i l l Iahle 3,9-A Concentration _of Radionucl[ des in Foqd Products Cmeentrathm (pCiAg-wet) I YEAR I-131 Cs-13e Cs-137 Intbeator Control Indicator Cmtrol Indicator Ontrol 1979* -5.82E0 7,30E-1 -1.00El -1.06E l 2.19E1 1.93El 19R0* 1.91El 6.15E0 -2.59E0 -1.25El 2.30El 1.92El 1981* -1.87E0 3.16E0 1.24El 5.%E0 3.(MEl 2.02El 1982* 1.41El 6.59E0 1.50El -6.31 E-1 2.46El 1.22El 1983* 1.13El 7.19E0 4.13E0 1.24E0 9.07E0 7.85E0 1984 -5.08E-1 ** " " 4.49E-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 ** 1988 0.00E0 ** 0.00E0 " 0.00E0 - " 1989 0.00E0 " 0.00E0 " " 0.00E0 1990 0.00E0 " 0.00E0 " " 0.00E0 12 YEAR AVERAGE 4.98E0 4.76E0 2.81E0 1.44E0 1.47El 1.58El 1991 0.00E0 " 0.00E0 " " 0.00E0
! CORRELATION I '
MEFFICIENT
-0.42 -
-0 43
- -0.70 -
I
- Broadleaf vegetation samples used for food products media.
** No control site available.
--- Insufficient data to calculate a representative correlation coefficient.
NOTE: All negative values were replaced with "zero's" for calculational purposes. 3-29
I l 3.10 LAND USE CENSUS The land use census was completed June 94, 1991 and the results are shown in Table 3.10. The 1991 census revealed two new irrigated gardens at 2.8 miles N and 2.6 miles NNE. Due to size ard number of I crop classes, the Austin garden (2.8 miles N) was added to the sampling program as locat!on 188. The census also revealed a location v..iere samplingis required (goat milk at 2.6 miles East), but was not added to the program since the milk is not used for human consumption. I I I I I I I I I I I I
1 I l- Tabla 3.10 Land Use Census Results 1 Page 1 of 2 l ,I SECTOR DISTANM I N ' Nearest Residence Nearest Meat Animal Nearest Garden 2.7 miles None in 5 miles 2.8 niles I NNE Nearest Cow Nearest Goat Nearest Residence None in 5 miles None in 5 miles i.5 miles I Nearest Meat Animal Nearest Garden Nearest Cow None in 5 miles 2.6 miles None in 5 miles Nearest Goat None in 5 miles NE Nearest Residence 2.0 miles Nearest Meat Animal None in 5 miles Nearest Garden 2.2 miles 'I Nearest Cow Nearest Goat None in 5 miles None in 5 miles ENE Nearest Residenes 0.7 miles Nearest Meat Animal 4.0 miles Nearest Garden 2.4 miles Nearest Cow 3.6 miles I E Nearest Goat Nearest Residence None in 5 miles 0.5 miles Nearest Meat Animal 4.0 miles Nearest Garden C.75 miles Nearest Cow 2.6 miles Nearest Goat 2.6 miles ESE Nearest Residence 0 5 miles Nearest Meat Animal None in 5 miles Nearest Garden 0.8 miles '3 Nearest Cow 2.8 miles '3 Nearest Goat None in 5 miles SE Nearest Residence 0.8 miles ,3 Nearest Meat Animal 3.5 miles 3! Nearest Garden 3.4 miles Nearest Cow None in 5 miles
~
Nearest Goat None in 5 miles SSE Nearest Residence 0.9 miles Nearest Meat Animal 2,7 miles Nearest Garden 1.8 miles Nearest Cow 2.8 miles Nearest Goat None in 5 miles I S Nearest Residence 1.3 miles Nearest Meat Animal None in 5 miles Nearest Ga' den 1.2 miles Nearest Cow None in 5 miles Nearest Goat None in 5 miles 3 3-31
--'e ! Table 3.10 Land Use Census Results Page 2 of 2 SECTOR DISTANCE
.I SSW Nearest Residence Nearest k2at Animal 3.3 miles 3.5 miles Nearest Garden 3.5 miles I Nearest Cow Nearest Goat None in 5 miles None in 5 miles SW Nearest Residence 1.8 miles Nearest Meat Animal None in 5 miles Nearest Garden 4.0 miles Nearest Cow None in 5 miles p Nearest Goat None in 5 miles WSW Nearest Residence 1.0 miles Nearest Meat Animal None in 5 miles I Nearest Garden Nearest Cow Nearest Goat 1.25 miles None in 5 miles None in 5 miles I W Nearcst Residence Nearest Meat Animal Nearest Garden 0.9 miles 025 miles 1.2 miles I WNW Nearest Cow Nearest Goat Nearest Residence None in 5 miles None in 5 miles 1.1 miles I Nearest Meat Animal Nearest Garden Nearest Cow None in 5 miles 1.75 miles None in 5 miles
'I NW Nearest Goat Nearcht Residence Nearest Meat Animal None in 5 miles 1.5 miles None in 5 miles I Nearest Garden Nearest Cow Nearest Goat 1.8 miles None in 5 miles Nonn in 5 miles 'g NNW Nearest Residence 1.75 miles B Nearest Meat Animal None in 5 miles Nearest Garden 3.1 miles Nearest Cow None in 5 miles Nearest Goat None in 5 miles I
I I l l
.l 3-32 n .- _ . - _ - - _ ------__ --_ _----_-__ _ _ -
I 4.0 EVALUATION OF DOSE FROM ENVIRONMENTAL MEASUREMENTS I VERSUS ESTIMATED DOSE FROM RELEASES g 4.1 DOSE FROM ENVIRONMENTAL MEASUREMENTS Doses were estimated for measured concentrations of radionuclides in I direct pathways to man using NRC Repiltiory Guide 1.109 methodology. The highest annual mean values for each sample type and radionuclide were used after the background concentrations, as measured at the controllocation, had been subtracted; the maximum exposed individual's I doses are summarized below: Maximum Organ Critical Age Critical Pathway Dose (mrem /yr) Skin Teen Shoreline Sediment 2.88E-3 i Bone Liver Child Child - T. Body Adult Broadleaf Vegetation Broadleaf Vegetation Broadleaf Vegetation
- 2. 81 E-1
- 2. 71 E-1 1.51E-1 Thyroid Child Drinking Water 5.40E-2 Kidney Child Broadleaf Vegetation 8.83E-2 Lung Child Drinking Water 5.40E-2 GI-LLI Adult Fish 6.42E-2
~
4.2 E_STIMATED DOSE FROM RELEASES I Doses were estimated for release concentrations of radionuclides in direct pathways to man using NRC Regulatory Guide 1.100 methodolegy. The doses -were calculated using GASPAR and LADTAP coniputer programs. The maximum exposed individual's doses are summarized I below: LIQUID RELEASFS I Organ Critical Age Critical Pathway Maximum Dose (mrem /yr) g Skin Teen Shoreline Sediment 1.15E-2 3 Bone Child Fish 1.11E-1 Liver Teen Fish 1. 74 E-1 T. Body Adult Fish 1.33E-1 Thyroid Infant Drinking Water 6. 04 E-2 Kidney Child Fish 7.61E-2 Lung Child Drinking Water 4.99E-2 C?-LLI Adult Fish 2.07E-1 4-1
I GASEOUS RELEASES I Maximum Organ Critical Age Critical Pathway Dose (mrem /yr) Thyroid Child Inhalation 1. 4 5 E-1 I l 4.3 COMPARISON OF DOSES I The environmental doser compared well with doses calculated from effluent releases . The differences in the doses calculated from environmental samples and the doses calculated from releases can be ', E attributed to the conservatism used in computing the highest annual E mean. For the broadleaf vegetation pathway, only one of twelve samples indicated detectable activity. The highest annual mean was calculated using only detectable activity without averaging samples less than LLD. The doses, as calculated using the environmental sample results, are well below the umits as specified in Selected Licensee Commitments Manual Section 16.11-12. I 4.4 PATHWAY DOSE CALCULATIONS I Dose calculations for each age and pathway can be found on the follow:ng i pages. I I I I 4-2
l m> ama sum aus amm) - eget aims gume asui uut p usur muu lume aus sus sume aus aus Dose from Air Particulate Inhalation Pathway for 1991 Data Maximum ExposedAdult usag6 (intaF.o rate)- 8000 (matyr) Highest AnnualMean Concentration AduR l bhislatkm does factor (farem per pCIingemed'. Ak Dose (mrom/p) Radionuclide Bono threr T. Body Thpoki fGdney Lung Gl-LU LocatKm (pCum3) Bone Uver T. mxfy Thyroid Kkiney Lung Gl-LU Mn-54 NO DATA d osE-oo 7.87E-07 NO DATA 113E-06 1.74E-04 9 67E-06 ALL 0.00E+00 0.00E *00 0 00E+00 0 00E+00 0 00E*00 0 00E+00 500E+00 0 00E+00 Co-58 NO DATA 1.98E-07 2.59E-07 NO DATA NO DATA 1. tee 44 133E-05 ALL 0.00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Fe-69 1.47E-06 3.47E46 1.32E-06 NO DATA NO OATA 1.2TE-44 2.35E-05 ALL 0.00E+00 0 00E+00 0 00E+00 0 00E+00 6 00E+00 0 00E+00 0 00E+00 0 00E+00 Co-00 NO DATA 1,44E-46 1.85E-46 NO DATA NO DATA 7.46E-04 366E-05 ALL 0 00E400 0 00E+00 0 00E+00 0.00E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 Zn-65 4 05E-oS 1.29E-05 5.28E-06 NO DATA a 62E-06 1.08E-04 628E-C6 ALL 000E+00 0 00E+00 0 00E400 0 00E+00 0 00E +00 0 00E+00 0 00E+00 0 00E+00 Nb-05 1.78E-06 9.77E-o? 526E-07 NO DATA 9 67E-47 6.31E-05 1.NE-05 ALL 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 2r-95 1.34E45 4 30E-46 2.91E-06 NO DATA 6.77E-06 211E-04 1.saE-45 ALL 0 00E+ca 0.00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 1-131 315E-06 4 47E-46 2.56E-os 1.49E-03 7 66E-06 NO DATA 7.85E-47 ALL 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 000 00 000E+00 Ce.-1;>4 4 66E-05 1.06E-44 9.10E-05 NO DATA 3 59E-45 1.22E-05 1.30E-06 ALL 000E+00 0 00E400 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Co-137 5 9'A-05 7.7BE-05 5.35E-05 NO DATA 2.78E-OS 9 40E-06 1.05E-06 ALL 0 00E+00 O M E+oo 000E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Bata-140 4 88E-06 e.1?E-09 3.20E-07 NO DATA 2.09E-os 1.59E-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 EQUIVALENT (mrsm/p). 000E+00 0 00E+00 0 00E+00 0 00E+00 0 00E400 0 00E+00 0 00E+00 s' [ ._
Blus uma tuum aus as aus sup em aus as im p me sus a sus a s sus suu Dose from Air Radiciodines Inhalation Pathway for 1991 Data Maximum Exposed Adult Usage (intaks rate)- 8000.00 (m3/yr) Highest AnnualMean Concentration Ade inhalatkm dose factor (nom por pCIingested) Air Does (wem@) Radionuclide Bone Uver T. Body Thyroid IGdney tung 06-LLI Locatkm (pCh*m3) Bcne Uver T. Body Thyroid Kdrwy Lung GB-LU un44 NO DATA 4 95E-06 7.87E-07 NODATA 113E-06 1.74E-04 9 57E-o6 T6LL 0 00E+00 0 00E+00 0 00E*00 0.00E+00 0,00E+00 0.00E+0G 0.00E+00 0 00E+00 t Cc-05 NO DAT A 1.95E-07 2.50E-07 NODATA NODATA 1.16E44 1.33E-05 ALL 0 00E+00 0.00E+00 000E+00 0 00F+00 0 00E403 0 00E+00 0 00E+00 0 00E+00 g Fe-60 1.47E-06 3.47E-os 1.32E e6 NO DATA NO DATA 1.27E-04 2.35E-05 ALL 000E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0 OOP 00 0 00E400 0 00E+00 l Co-60 NO DATA 1.44E-06 185E46 NO DATA NO DATA 7.46E-04 3.56E-05 ALL 000E+00 0 00E+00 0 00E400 0 00E+00 0 00E400 0 00E+00 0 00E+00 0 00E+00 l l l ZA-85 4 OSE-06 1.29E-05 528E-06 NO DATA 8 62E-06 1.08E-04 6OsE-06 ALL 0 00E+00 0 00E+03 0 00E400 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 \ Nb-05 1.76E-06 3.77E-o7 5.2eE-07 NO DATA 9 67E-07 6.31E-05 1.30E-45 ALL 0.00E+00 0 00E400 0 00E+00 0.00E+00 0 00E400 0 00E+00 0 00E+00 0 00E+00 f l l Zr-05 1.34E-05 A30E-06 2.91E-06 NO DATA 6.77E-06 2.21E44 1.88E-05 ALL 000E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00F+00 0 00E+00 0 00E400 l-131 315E-06 4.47E-oe 2.f4E-06 149E-03 7.e5E-06 NO DATA 7.85E-07 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 68E-05 106E44 9.10E-os NO DATA 3.50E-oS 122E-05 1.30E-06 Ali 0.GOE+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 l Co-137 5 95E-05 7.76E-05 5 35E-05 NO OATA 2.78E-05 9 40E-06 1.c5E4s ALL 000E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 f i ALL 000E+00 0 00E+00 a 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+0V O00E+00 BsLe-140 4.886 M 6.13E-09 320E-07 NO DATA 2 09E-09 1.59E-04 2.73E-oS f TOTAL DOSE EQUTVALENT(mromy). 000E.00 0 00E+00 0 00E400 0 00E+00 0 00E+00 0 00E+00 0 00E+00
E _ N _ E _ D E I U L 0 0 0 0 0 0* 0 0 0 0 0 0 0 0+ 0 0 0 0+ 0 0 0
+ + + + + + 0
+
0 0 E E E E + + E E E E E E E E IG 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 M L g n u 0 0 E
+
0 0 E
+
E 0 0
+
0 0 E
+
0 E 0
+
0 0 E
+
E 0 0
+
E 0 0
+
0 0
+
0 0
+
0 0
+
0 0
+
0 0 0 0 E E E E 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 M e n id y 0 0 E
+
0 0 E
+
0 0+ E 0 0+ E 0 04 E 0 0 E
+
E 0 0
+
0 0
+
0 0+ 0 04 0 0
+
0 0
+
0 0 0 0 E E E E E
)v K 0 0 0 0 0 0 0 0 0 0 0 0 y 0 0 0 0 0 0 0 0 g /
m e 0 0 0 0 0 0 0 0 0 0 0 0 r d 0 0 0 0 0 0 0 0 0 0 0 0 m tmary E 0
+
E 0
+
E 0
+
E 0
+
E 0
+
0
+
E 0+ E 0 E
+
E 0
+
E 0+ E 0
+
0 E
+
sh e T 0 0 0 0 0 0 0 c 0 0 0 0 o 0 0 0 0 0 0 0 0 0 0 0 0 D 0 0 0 0 0 0 Wu d y 0 0+ 0 0 0 0+ 0 0+ 0 0+ 0 0 0 0 0 0 0 0 0 0 0 0 0 0 s a B. o E E
+
E E E E
+
0 E+ 0
+
E E 0+ 0 E
+
0 E
+
E 0
+
t 0 0 0 0 0 0 0 0 0 a T 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 e D r e 0 0 0+ 0 0 0 0 0 0* 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0+ m 1 9 O v E 0 E
+
E E 0
+
E 0+ E 0 E
+
E 0
+ 0+
E E 0+ 0+ E 0+ E 9l t n 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 u i o 0 0 0 0 0 0 0 0 0 0 0 0 0 m u rd t a r n e 0 0+ 0 0 0 0 0 0+ 0 0 0 0 0 0+ 0 0 0 0 0 0+ 0 0 0 e f oA t n B o E 0 E
+
0 E 0
+
E 0 E 0
+
E 0
+
E 0 E 0
+
E 0
+
E 0 E
+
E 0
+
yed 0 e 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 s 0 0 c 0 0 0 0 0 0 0 u as wo n o k 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 s h p C l i /L M4C
)
t x n PaE p s a e r ( m om km
)
e l M l t ak ic e t L L A L L A L L A L L A L L L L L L L L L L L L L L r y i u d c A A A A A A m a Ino A e Mm u r L m s i n ( mx 5 p a n U L 0 5 0-5 0-5 4 6 0 5 0-5 4-6 0 6 0 0 6 5 0 t le n g oa frM A t s l O E-0 4 E 5 t E 0 4 E f o E-0 7 E 0 1 E 0 0 E-7 5 E-9 5 E 1 1 E-5 2 iu a v q 1 3 4 9 e 1 2 3 1 2 2 9 E s e s h g o n A T A T 6 0 A T A T A T T A A T 5 5 8 es u u A A A A A A A 0- 0- 0- o a o i H L D O D O E-5 D O D D D E 9 E 3 E 6 D f D r
)
d N N 8 2 O N N O N O O N O N 5 1 2 1 4 1 ta T o o e y A A A D n tc ts e Fa gden 6 4 E T A D T A D T A O E 5 0 9 0 E-a C-E 5 0-E 5 4 E 5 0-E 9 0-E W d a A oC s e In0 I 1 8 3 1 O N O N O N 3 0 1 2 3 4 3 5 2 0 9 7 0 7 7 6 D Pr 1 1 4 3 8 n od A A A A A A A 3 A A A o p6 o T T T T T T T 0 Y T T m d s myr A D A D A D A D A D A A - A A A u e g roh n im ( T O N O N O N N O O N D O N D O N E 5 9 1 N D O D O N D O N y 7 6 5 d M 6 6 9 9 6 4 5 6 0- 0 m o B. E E
- A E E 0
0-E 0 E E 0- 0 E 0 E-0- E 0 E-e u r y T 2 7 8 7 6 1 9 3 1 7 4 2 e 9 6 S 8 1 6 0 0 1 4 3 1 2 1 4 1 7 3 3 1 0, r 6 7 5 6 su e 5 9 9 6 4 4 8 3 v 0- 0 0 0 0 0 0- 0- 0- 0 0-U E E- E E- E- E- E E E E- E 7 5 2 4 4 6 5 5 s 9 5 5 4 0 5 s 4 7 1 2 1 1 4 3 1 9 9 5 4 1 0 1 5 2
- e A A 6 A I 9 8 5 5 5 5 n T T 0 T M
> o A A A 0 0- 0- 4 4 0 e B D
- M -
m t a O D O E 4 3 D O E 4 E-2 E 4 E 6 E-2 E-7 E 3 a S s 2 0 N N 1 2 9 0 e 4 N 4 6 3 4 6 7 2 k a t e n d n e o 6 w 4 5-8 6-0 6 0 6-5 8-5 0- 5 9 1 3 4 3 1 7 3 0 4 1 a 1 c b-n o + o n b r
~ 1
- e o
- a a
s d M C F C 2 N Z 6 C C L a a u R B s E m kI*
g gg , a gg y y up ass aus aus ese ame une M eBS BEEP 15 5 4E5 MB Dose from Drinking Water Pathway for 1991 Data Maximum Exposed Adult Usage (Intake rate)- 730 (1/yr) Highest AnnualMean Concentration Aduft ingestka Does Factor (mrom per pCIInges*ed) indkator Water Does (mrem /yr) Redkmuclide BN Uver T. Body Thyrok! 10dney Lung GI-LLI Location (pCUt) Bone Uver T.Bndy Thyroid Kidney Lung GI-til Mn-54 NODATA 4E7E-06 8 72E47 NO DATA 1.36E-06 NO DATA 1.40E-05 ALL 0 0 00E+00 0 00E+00 0 00E+00 0 00E400 C00E+00 0 00E+00 0 00E+00 3~ s M NO DATA 7.45E-07 1.67E-06 NO GATA NO DATA NO DATA 1.51E-05 ALL e o 000E+00 0 00E+00 0 00E400 0 00E+00 0 00E+00 0.00E+00 0 00E+00 Fe-69 4.34E46 102E-05 3 91E-06 NO DATA NO DATA 2.85E-ce 3 40E-05 ALL 0 0 00E+00 0 00E400 0 00E40 0 00E+00 0 00E+00 0 00E+00 0 00E+00 C > 40 NO DATA 2.14E-Os 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 ALL 0 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 2n-85 4 84E4e 1.54E-45 6.9eE46 NO D .TA 1.03E45 NO DATA 9.70E-06 ALL 0 0 00E+00 0 00E+00 0 00E400 0 00E+00 0 00E+00 0 00E*00 0 00E+00 Nb-05 6.22E-09 3.4eE-09 1.seE-09 NO DA1 A 3 42E-09 NO DATA 2.10E-05 ALL 0 0 00E+00 0 00E+00 0 00E+00 0 00E+C0 0 00E+00 0 00E+00 0 00E+00 Zr-95 3 04E-os 9 75E-09 e 80E- De NO DATA 1.53E-03 NO DATA 3 09E-05 ALL 0 0.00E+00 0.00E+00 0 00E+00 0 OLE +00 0.00E+00 0 00E+00 0 00E+00 4-131 4. tBE-OS 5 95E-06 3 41E-os 1.95E-03 1.02E-05 NO DATA 157E-06 ALL 0 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Co-134 8.22E-05 1.4aE-04 1.21E-44 NODATA 419E-05 1.59E-05 2.59E-06 ALL 0 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Co-137 7.97E-os 100E-04 7.14E-05 NO DATA 370E-05 1.23E-05 2.11E-ce ALL 0 0 00E+00 0 00E+00 0 00E400 0 00E400 0 00E+00 0 00E+00 0 00E+00 Balm-140 2 03E-05 2.55E-08 1.33E-06 NO DATA 8.876-09 1.46E-08 41aE45 ALL 0 0 00E+C0 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 N-3 NO DATA 1.0$E-c7 1.05E-07 1.05E-47 1.0'5-07 1.05E-07 105E-07 142 522 0 00E400 4 00E-42 4 00E-02 4 00E-02 4 00E-C2 4 00E-02 4 00E-02 TOTAL DOSE EOU1 VALENT (mrom/yr)= 000E+00 4 00E-02 4 00E-42 4 00E-02 4 00E-02 4 00E-42 4 00E-02
gas gew gear say_.. y sus tus eum m Sun' Eum mm 55 5 MM M W EEEE 8'E Dose from Food Products (Crops) Pathway for 1991 Data Maximum Exposed Adult Usage (intake rste) = 520 k0 Y Highest AnnualMean Concentration Adu.4
!ngsmion Does feetw (mrem per pClinoested) indicator Food Does (mrom/p)
Fladior:uefide Bone Liver T. Body Treytoid 80dney Lung O'L13 Location (pCUkg) Bone ther T. Body Thpold Gfney Lung Gs-tL Un-54 NO DATA 4 57E-06 8 72E-07 NO DATA 1.36E-08 NO DATA 1.40E-45 ALL V 0 0 00E+00 0 00E+00 0 00E+00 0 00t+00 0 00E+00 0 00E+00 0 00E+00 I Co-58 NO DATA 7.45E-07 1.s7E-06 NO DATA NO DATA NO DATA 1.51E-05 ALL 0 0 00E+00 0 00E*00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Fe-59 4.34E-06 1.02E-45 3 91E46 NO DATA NO DATA 2 85E-06 3 40E-05 ALL 0 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0.00E400 0 00E+00 0 00E+00 Co-60 NODATA 2.14E46 4.72E-06 NO DATA NODATA NO DATA 4 02E-05 ALL 0 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 2n~65 4 84E-06 154E-05 6 96E-C6 NO OAT A 103E-05 NO DATA 9.70E-06 ALL 0 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0.00E+00 Nt>-95 6 22E-49 3 48E-09 1.86E-09 NO DATA 3.42E-09 NO DATA 2.10E-45 ALL 0 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E400 0 00E+00 0 00E+00 Zr-95 3 04E48 9.75E-09 6 00E49 NO DATA 1.535-08 NO DATA 3 09E-05 ALL 0 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 % E+00 1-131 4.16E-06 5.95E-06 3.41E-06 1.95E-43 1.02E-05 NO DATA 1.57E-06 ALL 0 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Co.-134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79E45 1.59E-os 2.59E-06 ALL 0 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 Co-137 7.97E-05 1.09E-04 7,14E-45 NO DATA 3 70E-05 1.23E-05 2.11E-oe ALL o 000E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Bab-140 2.03E-05 2.55E-08 1.33E-OS NO DATA 8.17E-09 1.4eE-ce 4.1sE-05 ALL 0 0 00E400 0 00E+00 0.00E400 0.00E400 0 00E+00 0 00E+00 0 00E+00 TOTAL DOSE EQUTVALENT(mremty). 000E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+.00 0 00E+00 0 00E+00
y y ga m y sus a man gas, aus .seus aus suur met EM IEEP EME 8E85 BE:e Dose from Broadleaf Vegetation Pathway for 1991 Data Maximum Exposed Adult Usage (intake rate)- 64 kcfyr Highest AnnualMean Concentration Adut ingespan Does Factor (mrom per go ingested) Irdcator Food thdionu3de Does (mremtyr) Bone Uver T. Body Thyroid 10dney Luno GI-LLI incaten (pCUko) Bone Uver T. Body Thyroid podney Lung GI-LLI Mr>44 NO DATA 4.57E-os 8.72E-07 NO DATA 1.3nE-oe NO DATA 1.40E-05 158 95 0 00E+00 2.78E-03 S E E-04 0.00E+00 8.27E-04 0 00E+00 8 51E-43 Co-48 HO DATA 7.45E-07 1.87E-06 NO DATA NO DATA NO DATA 1.51E-05 ALL 0 0 00E+00 0.00E+00 0.00E+00 0.00E+00 0 00E+03 0.00E+00 0 00E+00 o~ g Fe-6C 4.34E-oe 1.02E-05 3 91E-on NO DATA NO DATA 2.85E-06 3 40E-45 ALL 0 0 00E+00 0 00E+00 0 00E+00 0.J0E+00 0 00E+00 0 00E+00 0 00E+00 Co40 f40 DATA 2.14E-Oe 4.72E-06 NO DATA NO OATA NO DATA 4 02E-OS ALL 0 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E<00 0 00E+00 0 00E+00 Zn-65 4.84E-os 1.54E-OS 6 96E-oe NO DATA LO3E45 NO DATA 9.70E-06 ALL 0 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E400 0 00E+00 0 00E+00 Nb-OS 622E-09 3.48E49 1.88E~o9 NO DATA 3 42E4 NO DATA 2.10E-45 ALL 0 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00*i+00 2r-95 3 04E-48 9.75509 e eCE-09 NO DATA 1.63E-48 NO DATA 3 00E-OS ALL 0 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 4-131 4.18E-os 5 95E-oe 3.41E-06 195E-03 1.02F-05 NO DATA 157E-06 ALL 0 0 00E+00 0 00E+00 0 00E*00 0 00E+0a 0 00E+00 0 00E+00 0,TE+00 Co 134 6 22E-05 1.44E44 121E-04 NO DATA 4 79E-05 1.59E-of 2 5GE-os Al.L 0 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00Ee 0 00E+00 0 00E+00 Co-137 7.97E-05 1.09E49 7.14F 35 NO DATA 3.70E-05 123E-OS 2.11E-os 125 33 1.'A E41 2mE 41 1.5 t E-41 0 00E+oo 7 81E-02 2 00E-o2 s46E-03 Bata-140 2.03E-05 2.5SE-os 133E-06 NODATA Sf70-49 1.46E-08 418E-05 ALL 0 900E+00 0 00E+00 0 00E+00 0 00E+00 00 0 00E+00 0 00E+00 Tot 21 Does Entdve!**%ef)-- 1.88E-01 2.33E-01 1.51E-41 0 00E+00 7.90E-02 2 =0E-02 1.30E42 1
~
m aut luum ' mas em aus sus 4tmu gun aus sus aus' nun iJes use man tem aus suu Dose from Fish Pathwayfor 1991 Data Maximum Fxposed Adult usage 0ntake rate)- 21 kotyr Higimst AnnualMean Concentration Adun inoestkm Dose Fnctor (mrem per pCIingested) Indicator Floh Does (mrem /yr) RadiarPJctide Bone Uver T. Body Thyttnd IGdney Lung GI-LU Locatke (pCukg) Done Uver T. Body Thyroid Kksney Lung GI-8 Lt 8JrH54 MO D/TA 4 57E-06 S.72E-07 NO DATA 1.36E-06 NO DAT A 1.40E-05 129 6.2 0 00E+00 595E-04 1.14E-04 0.00E+00 1.77E-c4 0 00E+oo 1.82E-c3 Cn-68 NO DATA 7.45E-07 1.67E-oe NO DATA NO DATA NO DATA 1.51E-05 129 14 0 00E+00 219E44 4 91E-44 0 00E+00 0 00E+00 0 00E+00 4.44E42 d Fe-59 4.34E-os 1.02E-05 3 91E-06 NO DATA NO DATA 2 SSE-06 3.40E-05 ALL 0 0.00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0 OcE400 0 00E+00 Co40 NO DATA 2.14E-Ce 4 72E48 No DATA NO DATA NO DATA 4 02E-05 129 65 0.00E+00 2 92E-03 e44E-03 0 00E+00 0 00E+00 0 00E+00 $49E-c2 2n-65 4 8 tE-08 1.54E-05 e96E-06 NO DATA 103E-05 NO DATA 9 70E-06 ALL 0 0 00E+00 0 00E400 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00F+00 Nb-95 8 22E-09 3 48E-09 1.8eE-09 NO DATA 142E-09 NO DAfA 2.10E-05 129 35 4.57E-07 2.54E-07 1.37E-07 0 00E+00 2 51E-c7 0 00E+00 1.54E-03 2r-M 3 04E-08 9 75E-09 6SCE W NO DATA 1.53E-04 NO DATA 3 09E-05 ALL 0 0 00E+00 0 00E+00 0 00E+00 0 00E+oo 0 00E+G3 0 00E+00 0 00E400 1-131 4.18E-40 5 95E-06 3 41E-06 1.95E-03 102E-05 NO DATA 157E-06 ALL 0 0.00E400 0 00F+0e 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Co-134 6.22E-05 t.48E-04 1.21E-44 NO DATA 4.79E-05 1.59E-05 2.59E-oe 129 59 7.71E-c3 183E-42 150E-42 0 00E+00 5 93E-03 197E-43 3.21E-44 Co-117 7.97E45 1.09E-04 7. 84E-05 NO DATA 3.70E-05 1.23E-45 211E-06 129 25 4 35E-02 5 95E-02 3 90E-02 0 00E+00 2.02E-02 6 72E-43 1.15E43 Bat.m-140 2.03E4 2 55E-os 1.33E-06 NO DATA s e7E-09 1.48E-OS 4.18E-05 ALL 0 0 00E+00 0 00E*o0 0 00E*00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 TOTAL DOSE EQUtVALENT(mrem /yr)= 512E-c2 818E-02 e 10E-42 0 00E+co 2 83E-02 8 89E-03 e 42E-c2
. _ . = _
- W sua amm gau gu uns "m alus-em A9 aus m a em .m aus a sus -suu Dose from Shoreline Sediment Pathway for 1991 Data Maximum Exposed Adult Shoreline flecreation 12 hry Shore WKfth Factor = 0.3 (take shore -locatum 129; Shore Width Factor = 02 (rtver stuwn!.w-sacara 130)
Extemel Does Factor kw Stardno ilighest Annual Mean Concentration on Contaraeneted Ground . Ener(mromfyr) (mrom/hr per pCVm2) Indicator SedimerW Redonuclide T. Body thin Location (pCuko) T. Body Skin 4 C Mrt-64 5.80E-09 8 80E-09 129 28 0 2 34E-05 2.74E-05 CW 7.00E-09 8 20E-09 129 53.0 5.34E-45 e 26E-45 Fe-69 8 00E-- D9 340E49 ALL 00 0 00E+00 0.00E+00 Co-60 1.70E-08 2.00E-08 123 131.0 321E-04 3 77E+ M 4 00E-49 4.00E-49 ALL 00 0 00E+00 0 00E+00 Nb-05 510549 800E-09 ALL 00 0 00E+00 0 00E+00 Zr-05 5 00E-09 5 80E-49 ALL 00 0 00E+00 0 00E+Ca 5-131 2.80E-09 3.40E-49 ALL 0.0 0 00E+00 0 00E+00 - Co-134 1.20E-48 1.40E-08 ALL 0.0 0 00E+00 0 00E+00 Co-137 4 20E-09 4 90E-49 130 103.0 4.15E-05 4.45E-45 Balm-140 2.10E-09 2.40E-49 ALL 0.0 0.00E+00 0 00E+00 Total Does (mrem /y-) = 4 39E-04 5.18E-04 _ _ . - ________________________._____._________2
m We m W Bus WNmmW W W' Wut tem m m m una 1 I I Dose from Air Particulate Inhalation Pathway for 1991 Data l Maximum Exposed Teen Usage Ontaks rate)- 8000 (mxp) Highest AnnualMean Concentration TEEN inhalatica dose factor (mrom per pCIingested) Indicator Ak Does (mrcm/yr) Fladionuclide Bone Uver T. Body Thyroid fodney Lung G8-LLI Locanon (pcum3) Bone Uver T. Body Throod 8Gdney Lung GI-LLt , p Mn-54 NO DATA 6 39E-06 105E-06 NODATA 1E9E-06 2,48E-04 8.35E46 ALL 0 OJE+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Co-68 NO DATA 2 59E-07 3 47E-07 NODATA NODATA 1.68E-04 1.19E-05 ALL 000E+00 0 00E+00 0 00E400 0 00E400 0 00E*o0 0 00E+00 0 00E+00 0.00E+no FM 1.09E-06 4 62E-06 1,79E-06 NO DATA NO DATA 1.91E-04 2 23E-os ALL 0 00E+00 0.00E+00 0 00E+00 0 00E+oo O GJE+00 0 03E+00 0 00E+00 0 00E+00 CW NO DATA 1.89E-06 2.48E-46 NO DATA NO DATA 1.09E-03 3 24E-05 ALL 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Zn-85 4 82E-06 167E-OS 7.80E-06 NO DATA 1.08E-05 1.55E-44 5 83E-06 ALL 000E+00 0 00E+00 0 or ' 00 0 00E+co 0 00E+00 0 00E+oo 0 00E+00 0 00E+00 Nb-95 2EE-40 12eE46 7.08E-47 NO DATA 1.25E-46 9 % E-05 111E-oS ALL 000E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E400 0 00E+00 Zr-95 182E-05 5.73E-06 3 94E-06 NO DATA 8.42E-06 3 3SE-04 186E-05 ALL 000E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+a0 0 00E+00 0 00E+00 0 00E+00 1-131 4.43E46 6.14E-oe 3.30E-06 1.83E-03 105E-45 NO DATA 811E-47 ALL 0 00E+00 0 00E+00 0 00E+00 0OCE+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Ce-134 SisE-os 1.41E-64 6 86E-05 NO DATA 4 89E-c5 183E-05 1.22E-oe ALL 0 00E+00 0 00E+00 0 00E+00 0 00E+oo 0 00E+00 0.COE+00 0 00E+00 0 00E+00 Co-137 8.38 E-05 1.00E-04 3 89E-45 W DATA 3 80E-os 151E-45 1.06E-oS ALL 0 00E+00 0 00E+00 0.00E+00 0 00E*00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 BaLa-140 684E-o 8.38E-09 4 ACE-47 NO DATA 2.85E-49 2 54E-04 266E-05 ALL 000E+00 0 00E+00 0 00E+00 0 DM+00 0 00E+00 000E+00 0 00E+00 0 00E+00 Totof Does Equivalent (mrem /,9 000E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 E m i i i
'),_
m m um m aju m M M MM M M MP E - 388 " " " " Dose from Air Radiciodines inhalation Pathway for 1991 Data Maximuin Exposed Teen Usa 73 (intake rate)- 8000 (tra/p> Highest AanualMean Concentration 1EEN Inhalation does hetor (mrom per pClingested) Air Redonuctki. e Done Dose (rneem/p) Uver T. Body Thyroki Kidney tuno G8-LLI Location (pCum3) Done Uver T. Body Thyvoid IGdney Lung GI-LLI Mn44 NO DATA 6.39E-06 1.0$E46 NO t,ATA 1.59E48 . 2.48E44 8.35E-06 ALL 0.00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Co-68 t10 DATA 2.50E-07 3 47E-07 NO DATA NO DAYA 1.88E-04 1.1GE-05 ALL
- 0 00E*00 0.00E+00 0 00E+00 0 00E+00 0.00E*00 0 00E+00 0 00E+00 0 00E+00 Fe-60 1.09E-96 4 82E-06 1.79E-08 NO DATA NO DATA 1.91E-04 213E-05 ALL 000E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+03 CO-80 NO DATA 1.89E-06 2.48E-06 NO DATA NO DATA 1.09E-03 3 24E-05 ALL 000F+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Zn-05 4.82EHND 1.875-05 7.80E-ce NO DATA 1.08E-oS 1.55E44 5 83E-06 ALL 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00C+00 0 00E+00 0 00E+00 0 00E+00 Nt>-05 2.32E-06 1.29E-06 7.08 E-c7 NO DATA 1.25E-06 9.30E-05 121E-os ALL 0 00E+00 0 00E+00 0 00E*c3 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 Zr-95 1,82E-05 673E-06 3 94E-Ce PO DATA 812E-06 3 36E-04 186E-05 ALL 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 1-131 4.43E-Os e 14E-06 3 TE-oe 1.83E-03 105E-os NO DATA 8.11E-07 ALL 000E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+03 0 00E+00 Co-134 628E-45 1.41 E-04 888E-05 NO DATA 4.eeE-05 1.83E-05 1.22E-06 ALL 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+0c 0 00E+00 0 00E+00 0 00E+00 Ce-137 838E45 1DeE-04 3.89E-05 NO OATA 3 80E-05 1.51E-45 1.08E-06 ALL 000E.00 0 00E+00 0 00E+00 0 00E*00 0.00T+00 0 00E+00 0.00E+00 0 00E+00 Batm-140 6 84E-Ce a 38E-09 4 40E-47 NO DAi A 2 85E-49 2 54E-44 2 88E-45 ALL 000E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 Toral Does Equivalent (mrem /ye)=
0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00
W W W Mt W M WE M M M M M M M #EE mM M M Dose from Milk Pathway for 1991 Data u5aae ontane rate) . 400 up Maximum Exposed Teen Teen Highest AnnualMean Concentration Ingestion Dose Factor (mrom per pClinoested) lnd cator Mim Does (mecen/p) Ndionuclide Baw Uver T.Eady Thpo6d Kidney tung GI-LLI Locatiore (pCut) Bone Uver T. Body Thyroid 90dney Lung GMU Mn-64 NO DATA $ 90E45 1.17E-06 NO DATA 1.75E-06 NO DATA 1.21E-05 ALL 00 O M E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 6 00E+00 0 00E+00
> Co-68 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA 1.34E-05 ALL 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 h
W Fe-59 5 87E-oe 1.37E-05 5SE-46 NO DATA NO DATA 4.32E-Ce 3 24E-05 ALL 00 0 00E+00 0 00E+rm 0 00E+00 0 00E+00 0 00E400 0.00E+00 0 00E+00 Co-do NO DATA 2.81E-Oe e 33E-06 NO DATA NO DATA NO DATA 3 DeE-C$ ALL 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 2n-45 5.76E-os 2.00E-05 9 33E4e NO DATA 1.28E-05 PeO DATA 9.47E-Ce ALL 00 0 00E+00 0 00E+00 0 00E+00 "00E+00 0 00E+00 0 00E+00 0 00E+00 N505 8.2?E-09 4 SeE-09 2.51E-09 NO DATA 4.42E49 NO DATA 195E-OS ALL 00 0.00E+00 0OGE+00 0 00E+00 0 00E+00 0 00E% 000E+00 0 00E+00 Zr-OS 4.12E-08 1.30E-08 8 94E-os NO DATA 1.01 E-08 NO DATA 3 00E-05 ALL 00 0 00E400 0 00E+00 0 00E 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 l-131 5 86E-06 8.19E-06 4 40E-46 2.3BE-03 1.41E45 NO DATA 1.82E-05 ALL 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Co-134 8 37E-oS 1 97E-44 9.14E-45 NO DATA 6 2eE-05 2.39E-05 2.45E-OS ALL 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Co-137 1.12E-44 1,49E-04 5.19E-45 NO DATA 6 07E-45 1.97E-05 2.12E-Ce AtL 00 0 09E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+oo Bala-140 2 84E-05 3.48E-e8 1 83E-06 NO DATA 1.18E-08 2.34E-OS 4 38E-05 ALL 00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Total Does Equivalent (mrem /yr)= 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00
-___m___. _ _ _ _ _ _ _ _ _ - _
m -m W W WMM M hW W W m mM Ma m m M Dose from Drinking Water Pathway for 1991 Data usaae ont3ne rate >. 5,0 u, Maximum Fxposed Teen re.n Highest AnnualMean Concentration ingee0m Does Factor Drinking (mrem per pClin9* dad) Indacattw Wator Does (mrern/yr) Radimuende Bone Uwer T. Body Thyroid fodney Lung GI-LLI Locatkm (pC1/L) Bores ther T. Body Thyrood t5dney Lung G8-LU un-54 NO DATA 5.00E-06 1.17E46 NO DATA 1.76E-06 NO DATA 1.21E-05 ALL 0.0 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 30E+00 0 90E+oo C&58 NO DATA 9 72E-07 2.24E-06 NO DATA NO DATA NO DATA 1.34E-05 ALL 00 0 00E+00 0 00E+CJ 000E+00 0 00E+00 0 00E+00 0 00E400 0.00E+00 Fe-60 5 87E-Ot; 1.37E-05 5.29E-06 NO DATA NO DATA 4.32E-06 3 24E-05 ALL 00 0 00E400 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00c400 0.00E+00 C+o3 No DATA 2.8IE-06 6.33E-06 NO DATA NO DAYA NO DATA 3 66E45 ALL 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Zn-85 5 76E-06 2.00E45 933E-06 NO DATA 1.28E-oS NO OATA 8.47E-06 AtL 0.0 0 00E+00 0 00E+00 0 00E400 0 00E+00 0 00E+00 0 00E400 0.00E+00 Nb-95 8.22E-09 4.56E-09 2 51E-09 NO DATA 4.42E-09 NODATA 195E-05 ALL 00 0 00E+00 0 00E+00 0 00E+00 0 00E400 0 00E400 0 00E+00 0 00E*oo Zr~95 4.12E-os 1_30E-08 8.94E-09 NO DATA 101E-09 NO DAYA 3 00E-05 ALL 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+60 0 00E+00 6-131 5 85E-06 8.19E-06 4.40E-oe 2.30E-c3 1,41E-os NO DATA 1.62E-06 ALL 00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E@ Co-134 8.37E-05 1.97E-04 9.14E-OS NO DATA 6.26E-05 2.30E-05 2.45E-06 ALL 00 0.00E+00 0 00E+00 0.00E+00 0 00E400 0 00E+00 '0 00E+0C 0 00E+00 Co-137 1.12E-04 1.49E44 519E-05 NO DATA 5 07E-05 1.97E-05 2,12E-06 ALL 00 0.0GE+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Bala-140 2 84E-c5 3.48E-08 183E-06 NO DATA 1.185-08 2 34E-08 4.38E45 ALL 00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E400 0 00E+00 0 00E+00 H-3 NO DATA 1.06E-07 1.05E-07 1.06E47 1.06E-07 1.00E-or 1.06E47 142 522 0 00E+00 2.82E-c2 2.82E-42 2 82E-02 2 82E-02 2 82E42 2 82E-02 Total Does Equnra! ant (mrom/yr). 000E+00 2 82E-02 2.82E-02 2 82E-02 2 82E-02 2.82E-02 2 82E-02 l i (
M " I L t-I E 0 0
+
0 0 E
+
E 0 0+ 0 0 E
+
E 0 0+ E 0 0
+
0 0+ E E 0 0
+
E 0 0+ 0 0
+
E E 0 0
+
0 0+ E G 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 M g n o 0 04 E E 0 0+ E 0 0
+
E 0 0* 0 0 E
+
0 0 E
+
0 0 E
+
E 0 0
+
E 0 0
+
E 0 0
+
0 0
+
0 0+ L 0 0 0 E E 0 0 0 0 0 0 C 0 0 0 0 0 0 0 0 0 0 0 O 0 0 E y d 0 0 0 0 0 0 0 0 0 0 0 W t a d e n 0 0 E
+
E 0 0+ E 0 0+ 0 E 0
+
E 0 0+ E 0 0+ E 0 0
+
0 0 E
+
0 0 E
+
0 0 E
+
E 0 0+ 0 0 E
+
a ) l r o 0 0 0 0 0 0 0 0
?
C 0 0 0 0 0 0 0 0 0 0 0 0 0 0 D y
/ 0 0 0 0 0 0 0 0 0 0 0 0 m
1 ed 0 0 0 0 0 0 0 0 0 0 0 o M 9 ( s r i mo r y E 0
+
E 0
+
E 0
+
E 0
+
0+ E 0 E
+
E 0
+
E 04 0 E
+
E 0
+
E 0
+
E c
+
9 1 eh oT 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 D 0 0 0 0 0 0 0 0 0 0 0 0 r y 0 0 0 o 0 0 0 0 0 0 0 0 A f o d o B 0 E
+
0 E
+
E 0
+
E c+ E 0
+
E 0
+
E 0
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ygg gas y aammW M W W W "5 W 8 E W Dose from Broadleaf Vegetation Pathway for 1991 Data usaae tintane rate). 42 (nam Maximum Exposed Teen Teen Highest AnnualMean Concentration Ingestion Does rector (mrom per pCl ingested) indicator Fond Ocee (mrem /yr) 51ad6anuchde Bone Uver T. Body Thyroid IQdney . Lung GRU Location (kg/p) Bone Uver T. Body Thyroid 80dney Lung GHU Mn~54 NO DATA 5 00E-oe 1.17E-06 NO DATA 1.78E-06 NO DATA 1.21E-05 158 95 0 00E+00 2.35E-03 4 87E-04 0 00E+00 7 02E o4 0 00E+00 4 83E-43 . Co-58 NO DATA 9 72E-07 2.24 E-06 NO DATA NO DATA NO DATA 1.34E-os ALL 00 0 00E+00 0.00E400 0 00E+00 0 00E+00 0 00E+00 0.00E*oo 0 00E+00
$ Fe-59 5 87E-oe 1.37E-05 '5.29E-oe NO OAYA NO DATA 4.32E-oe 3 24E-05 ALL 00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Co-40 NO DATA 2 81E-46 e 33E-06 NO DATA NO OATA NO DATA 3 e6E-05 ALL 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Zn-85 S.78E-08 2.00E-05 k33E-06 NO DATA 1.28E-05 NO DATA 8.47E-oe ALL o0 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+0L N1'-05 8 22E-ow 4.56E-09 2.51E-09 NO DATA 4.42E-09 NO DATA 1.95E-05 ALL 00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E400 0 00E+00 0 00E+00 Zr-er 4.12E-08 L30E-03 8 94E-09 NO DATA 1.01E-08 NO DATA 3 00E-05 ALL 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 1-131 .5E-06 819F-os 4 40E-06 2.39E-03 1.41E-05 NO DATA 1.82E-ce ALL 00 0 00E+00 0 00E+oo 0 00E+00 0 00E+0u 0 00E+00 0 00E+00 0 00E+00 Co-134 8.37E-05 t ie7E 44 914E-05 NO DATA 0 2eE-05 2.39E-05 2.45E-06 ALL 00 0 00E+00 0 00E400 0 00E+00 0 00E+00 0 00E*00 0 00E+00 0 00E7A Co-137 1.12E-44 1.4eE-04 8 19E-oS NO DATA 5 07E-05 1.97E-05 2.12E M 125 33 0 1.55E-41 2 07E-of 719E-42 0 00E+00 7 03E-02 2 73E-02 2 94E-43 B*La-140 2.84E-45 a 48E-08 183F-os NO DATA 1.rE-48 2.34E-OS 4.38 E-05 ALL 00 0 00E+00 0 00E+00 0 00E+00 0 00E400 0 00E+00 0 00E+00 0 00E+00 l
Tote. Doea Equivalent (mrom/p)= 1 SSE-of 2 09E-01 7 24E-02 0 00E+00 7.10E-02 2.73E-02 7.77E-03
g ggay a mm m em W Wim Dose from Fish Pathway for 1991 Data usaga < intake rato)- 26 (5 0ryr> Maximum F_xposed Teen TEEN Highest AnnualMean Concentration IngsWkm Dose Factor) (mrom per pciingewed) indicator neh Radkmuctide Dose (mruntyr) Bone Uver T. Body Thyroid 90dney Lung G6-tLI Location (kg/yr) Bone Uvet T. Body Thyro 6d 4Gdney Lung GI-LU Mn-64 NO DATA 5 90E-06 1.17E-os NO DATA 1.7613-06 NO DATA 1.21E-OS 129 6.2 0.00E+00 5.85E-04 1.10E-04 0 00E400 17bE-04 5.00E+oc 120E-03 p Co-58 UO DATA 9.72E47 2.24 E-06 No t;ATA NO )ATA NO DATA 1.34E-05 129 b 14 0 0 00E+00 2.18E-04 5 02E44 0 00E+00 0 0cc+00 0 00E+00 3 00E-c3 N Fe-se 5 87E46 1.37E45 5.29E-OS NO DATA NO )ATA 4.32E-06 3.24E-oS ALL 00 0 00E+00 0 00E+00 0 00E+00 0 00E+oo 0 00E+00 0 00E+00 0 00E+00 t Co-40 NO DATA 2.81E-06 6.33E-46 HO DATA No t ATA NO DATA 3 0eE-os 129 e5 0 0 00E+00 2 92E-03 658E-03 0 00E+00 0 00E+00 0 00E+00 3 8 t E-62 2n-65 5.7eE-06 2.005-05 9 33E-06 NO DATA 1.211 M5 NO DATA 8 47E-o6 ALL o0 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Nt>-95 8 22E-09 / ioE-00 2.51E-09 NO DATA 4.42E-os NO DATA 1.95E45 129 35 4 60E-07 2.55E-47 141E-47 0.00E+00 2 4sE-07 0 00E+00 1.09E-03 Zr-95 4.12E-08 1.30E-os 8 94E-09 NO DATA 101E48 NO DATA 3 00E-05 ALL 0.0 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+no 0 00E+00 1-131 5 85E-06 6.19E-06 4.40E-06 2.30E-43 1.41E-05 NO DATA 1.62E-o6 ALL 00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+ao 0 00E+00 0 00E+00 Co-134 8.37E-05 197E-04 9.14E-oS NO DATA 6 26E-OS 2.30E-os 2.45E-06 129 59 7 90E-03 186E-02 8 63E-03 0 00E+00 5 91E-03 22eE-03 2.31E-04 Co-137 1.12E-44 1.40E-44 5.19E-05 NO DATA 5 07E-05 197E-05 2.12E-06 129 26 0 4 66E-02 6 20E-02 lt.16E42 0 00E+00 2.11E-02 8 20E-03 8 82E-04 Bala 140 2 54E-05 3 48E-08 1.83E-06 NO DATA 1.180-08 2.34E-08 4 38E-oS ALL 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00Ee(/) 000E+00 TotalDoes Equivaler.;(mremtyr). 5.45E-02 8 43E-42 3.74 E-42 0 00E+00 2.72E-42 1.05E-02 4 45E-42 i
-m m M Was eemeam ae a m 'm m W W W Dose from Shoreline Sediment Pathway for 1991 Data Maximum Erposed Toen Shoreline R0 creation 87 Sr/rr Snors Width Factor = ' O.3 (!ake shore-locatkm 129)
Shore W.dth Factor .- 0.2 (ther shorenne-scent 6on 130) l External Does Fac*or Ibr Standing on H!ghest Annual Mean Concentration , contaminated Orrmnd Doop (mremfyr) (mrerrJhr per pCthn?) Indicator Sedement Radionuctido T. Body Skin Locatke (pCuhg) T. Body Skine l l f Mn-Sa 680E-09 e 80E-09 129 28 0 1.31E-04 1.53E-04 5 CW 7.0GE-09 s 20E-09 129 53 0 2 0eE-04 3.49E-04 l l F -69 8.00E -09 9.40E-09 ALL 00 0 00E+00 0 00E+00 CM 1.70E-OS 2 00E-08 129 131 0 1.73E-03 2.11E43 2%-85 4 00E-oQ 4.00E-09 ALL 00 0 X)E+00 0 '#E+00 9 Nb-05 510E-?e e 00E-09 ALL 00 0coti+00 0c0E+00 Zr-95 .* 00E-09 580E-09 ALL 00 0 00E+00 0 00E+00 I-131 2.SCE-09 3.a0E-09 ALL 00 0 00E+00 0 00E+00 Co-134 1.20E-08 1 40E-08 ALL 00 0 00E+00 C00E+00 Co-137 4 RE-09 4.90E-09 130 103 0 2.3?E-44 2.71 E-0. Bata-140 2.10E-09 2 40E-09 ALL 00 0 00E+00 0 00E+00 Total Does Equhralent (mrom/yr)= 2.45E-03 2 88E-03 l
m ?ca W -m- W JW M M M M M M mam M W WW ' l i Dose from Inhalation Air Particulate Pathway for 1991 Data l Maximum Exposed Child l Breathing rate - 3700 (m3/yr) Highest AnnualMean Concentration CHILD inhalatkm Does Factor i (mrom per pCiinhaled) Indicator Ak Drwe (mrem /yr) t Radionuclide Done Uver T. Body Thyro 6d Kkiney Lung G1-LLI Location (pClim3) Bone Uver T. Body Thyroid fGdnef , Lung GI-LU Mn-54 NO DATA 1.16605 251E-06 NODATA 2.71E46 4.26E44 619E46 ALL 000E+00 0 00E+00 0 00E+00 000E*00 0 00E+00 0 00E+00 0.00E+00 0 00E+00
- 1. E' Co-68 NO DATA 4.79507 8.55E-07 NO OATA NO DATA 2.99E-04 9.29E-o6 ALL 000E+oo 000E+00 0.00E+00 0 00E400 0 00E+0u o00E+00 0 00E+00 000E+0c Fe-50 5.59606 9 04E-06 4 51E-oe NODATA NODATA 3.43E44 1.01 E45 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 l
l CW NO OATA 3.55 Goo 6.12646 NO DATA NO DATA 191503 2.00605 ALL 0.00EW D00E+00 0 00E+00 0 00E+00 0 00E400 0 00E+oo 0 00E+00 0 00E+00 Zn-85 1.15605 3C6E-05 190E-05 NO r ' TA 1.93E-05 2.69E-04 4 41E-06 ALL 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 000600 0 00E+00 Nt>-95 6356 00 2.43600 1.TTE-06 NO DAfA 2.33E-06 1.6sE-04 1.00605 ALL 0.00E+oo 000E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 000600 0 00E@ Tr45 513GCS 1.13605 1.00605 NO DATA 1.61E-05 603E-04 1.e5E-c5 ALL 000E*00 0 00Doo 0 00E+oo 0 00E 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 6-131 1.30605 1.30E45 7.37E-06 4.39E-03 2.13E-45 NO DATA Te2E-67 ALL 0 00E+00 0 00E+00 0 00E+00 0.00E +00 0 00E+00 0 00E+0V 000*+00 0 00E+00 Co-134 1.76E-04 2.74E44 607E-05 NO DATA s 93E-c5 3.27E45 1.04E-06 ALL 000E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+oo 0 00E+00 Co-137 2.45E44 223E-04 3 47E-05 NO OATA 7 23E-os 2 stE-oS 9 78E-c7 ALL 0 00E+00 0 00E+00 0 00E+03 0 00E+00 0 00E+00 0 00Doo 0 00E+1m 0 00E+00 Bata-140 2 00E45 1.75E4s t.17E-40 NO DATA 5716 09 4.71 E44 2.75E-c5 ALL 000E+co 000E+C0 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+co Total Dose Equrvalent (mrenvyr) = 000E+00 0OcE+00 0 00E+oo 0 00E+00 0 00E+00 0 00E+0) 0 00E+00 l r l
mm m m W- m m SWB m M M M m m m m Mm m: Dose from inhalation Air Radiciodines Pathway for 1991 Data Maximum Fxposed Ch!id BraatNng rate = 3700 m3 ty Highest AnnualMean Concentration CHILD tr.Sa;spon Doos Factor (mrom per pClinhaled) indicator Air Duse(mvem/F) fladionuc4de Bon, Liver T. Body Thyroid IGdney Lung G6-LLI Location (pC1/m3) Bona L)wer T. Body Thyroid Kidney Lung Gl -LLI e Un41 NODATA 1.18E45 2.57E-06 NO DATA 2.71E-48 4.2eE44 619E-oe ALL 0.00E+00 0.00E+00 0 00E+oo 0.00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+oC b O Co-58 NO DATA 4.79E47 8 56E-07 NO DATA NC DATA 2 99E44 9.29E46 ALL 0"#4 40 0 00E+oo 0 00E+00 0 00E+00 0 00E+00 0 00E+oo 0 00E+00 0.00E+00 F6-59 5 59E-06 9 04E-06 4 S1E-c6 NO DATA NO DATA 3 43E44 191 E-05 ALL 0OCE+00 0 00E+oO O00E+00 0 00E+00 0 00E+00 0.00E*oo G 00E+00 0 00E+00 Co-60 NO DATA 3 56E-os 612E46 NO DATA NO DATA 191E-03 2.00E-05 ALL 000E+00 0 00E+00 0 00E +00 0 00E+00 e00E+00 0OGE+C0 C00E+00 0 00E+00 Zn-65 1.1M-05 3 06E-oS 1.90E-OS NO DATA 1.93E-05 2.osE-04 4.41E~oe Ill. 0.M E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Nb-05 635E-0$ 2.4aE-06 1.77E-06 NO DATA 211E-06 1e6E-04 100E-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 Zr-95 513E-05 1.13E-05 1.00E-05 NO DATA 161E-05 0 03E-04 185E-05 ALL 000E+00 0 00E+oo 0 00E+00 0 00E400 0 00E+00 0 00E+00 0 00E+00 0 00E+00 4131 1.30E-05 1.30E-45 7.37E-oe 4 39E-03 2.13E-05 NO DATA 7.esE-07 ALL 0 00E+00 0 00E 00 0 00E+00 0 00E+00 0 00E+00 0oCE+00 0 00E+00 0 00E+00 Co-134 1.76E-04 2.74 E-04 9 07E-OS NO DATA 8 93E-05 3.27E-05 1.04 E-06 ALL 000E+00 0 00E+00 0 00E+00 0 00E+oo 0 00E+00 0 00E+00 0Ot5+00 0 00E+00 Co- 137 2 45E-04 2.23E-04 3 47E-05 NO DATA 7 635-05 2 S1E-05 9 78E-07 ALL 0 00E40 0 00E+00 0 00E+00 0 00E+00 0 00E+oo 0 00E+00 0 00E+00 0 00E+00 Bale-14t' 2.00E-05 1.75E-os 117E-os NO DATA 5 71E-09 4.71E-04 2.75E-4 i ALL 000E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+oo o 00E+00 0 00E+00 Total Dooo Equivalent (mreerdyi). 000E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+oo 0 00E+00 0 00E+00
g y gg gg g a m -m m em e um m m Em ~ 'm3 W W l>ose from Milk Pathway (Or 1991 Data Usage (intakc rate) = 330.00 (uyr) Maximum Exposed Child Cmto Higtmst AnnualMean Concentration inoemian Does r.ctor (mrom per pClingested) Indicator Milk Goes (rmem/yr) Radeonuctide Boni Uwer T. Body Thytold K)dney Lung GB-LU Locathm (pCan) Bone Liver T. Body Thyroid IGdnay Lung GI-LU Mn-64 NO DATi t 107E-05 2 85E-ce NO DATA 3 00E-06 NODATA s eeE46 V ALL 0 00 0 00E+oo 0.00E+00 0 00E400 0 00E+00 0.00E+00 d.00E+00 0 00E+00 C<>68 NO DATA 1.80E-ce 5.51E-06 NO DATA NO DATA NO DATA 1.05E-os ALL 0 00 0 001+00 0 00E+00 0 00E+00 0 00E+co 0.00E+00 0 00E+00 0 00E+00 Fe-60 1.65E-05 2 67E-05 1.33E45 NO DATA NO DATA 7.74E-46 2.78E-05 ALL 0 00 0 00E+00 0 00E400 0 00E+00 0 00E+00 0.00E400 0 00E400 0 00E400 Co-c0 NO DATA 529E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 ALL 0 00 0 00E+00 0 00E+00 0 00E400 0.00E+00 0 00E@ 000E+00 0 00E+00 Zn-65 1.37E-05 3 0$E-45 2.27E-05 NO DATA 2.30E-05 NO D#TA e 41E-Oe ALL 0 00 0.00E400 0 00E+00 0 00E+00 0 00E+00 0 00E*00 0 00E+00 0 00E+00 NtHE 2.25E-os 8.76E-oe 826E-09 NO DATA 423E-09 NO DATA 1.e2E-05 ALL 0 00 0 00E+00 0 00E400 0 00E+00 0 00E400 0 00E+00 0 00E+00 0.00E+00 Zr-95 1.16E-07 2.55E-08 227E48 NO DATA 3 85E-OS NO DATA 2 06E-oS ALL 0 00 0 00E+00 0 00E+co 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 l-131 1.72E-05 1.73E-05 es3E 4 672E-03 2.84E-05 NO DATA 1.54E-c6 ALL 0.00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Ce-134 2.34E-04 3 84E-44 810E-oS NO DATA 1.19E-04 417E-05 2.07E-06 ALL 0 00 0 00E+00 0 00E+00 0ceE+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Co-137 3.27E-04 3.13E-44 4 82E-05 NO DATA 1.02E-04 3 67E-os 196E-46 ALL 0 00 0 00E+00 0.00E+00 0 00E+00 0 00E400 0.00E+00 0 00E+00 0 00E+00 BaLa-140 a 31E-05 72sE-08 4 85E46 NO DATA 2.37E-os 4 34E-08 4 21E-05 ALL 0 00 0 00E+00 0 00E+00 0 DOE +00 0 00E+00 0 00E+00 0 00E+co 0 00E+00 Total Does (mrom/yr) == 0 00E400 0.00E+00 0 00E+00 0 00E400 0 00E+00 0.00E+00 0 00E+00
g gum a m . ggs - m m m em m mW m W W m Ed W 'W
-1 l
Dose from Drinking Water Pathway for i991 Data u5aae ontare rate > - 5,0 m Maximum Fxposed Child Cuan Highest AnnualMean Concentration inGe.uon Does r.cu, (mrom per pCiingested) indicator Water Dose (meem/p) Ndionuclide Bone Uver T. Bod r Thpold IGdney Lung GI-LLI Locatmn (pCut) Bone ther T.Jody Thyroid IGdney Lung Gt-LLI Mn-64 NO DATA 1.07E-45 2 85E-O1 NO DATA 3 00E-06 NO DATA 8 esE-Ce ALL 0.00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Co-58 NO DATA 1.80E-os 5.51E-os NO DATA NO DATA NO DATA 1.05E-05 ALL 0.00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 f to " Fe-60 1.85E-05 2.67E-05 1.33E-45 NO DATA NO DATA 7.74E-46 2.78E-45 ALL O.00 0.00E+00 0 00E+00 0 00E+00 0.00E+00 0.00E+00 0 00E+00 0 00E+00 CO-60 N0 DATA 6.29E~oe 1.5eE-05 NO OATA NO DATA NO DATA 2.03E-05 ALL 0.00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Zn-45 1.37E-05 3 85E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 9 41E-06 ALL 0 00 0.00E+00 0.00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0.00E+00 M - Mi 225E-08 8 76E-09 62eE-09 NO DATA 8.23E-00 NO DATA 1.82E-05 ALL 0 00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 03E+00 0 00E+00 0 00E+00 Zr-OS 1.18E-07 2 55E-48 2.27E-os NO DATA 3 esE48 NO DATA 2.06E-05 ALL 0 00 0 00E+00 0 00E400 0 00E+00 0 00F+00 0 00E+00 0 00E+00 0 00E+00 1-131 1.72E-05 1.73E-c5 9 83E-oe 5 72E-03 2 84E-45 NO DATA 151E-06 ALL 0 00 0 00E*00 0 00E+00 0 00E+00 0 00E+00 0 00E400 0 00E+00 0 00E+00 Co-134 2.34E-04 3 84E-C4 f.10E-05 NO DATA 1.19E-44 4.27E-05 2 07E-06 ALL 0 00 0.00E+00 0 00E+00 0.00E+00 0 00E+00 0.00E+oo 0 00E+00 0 00E+00 Ca-137 3 27E-04 3.13E44 4 82E45 NO DATA 1.02E-04 3 87E-05 1seE-06 ALL 0 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Bata-140 8.31E-os 7.2sE48 4 85E-46 NO DATA 2.37E-48 4.34E-08 4,21E-45 ALL 0 00 0 00E+00 0 00E+00 0 00E400 0 00E+00 0 00E+00 0 00E+00 0 00E+00 H-3 NO DATA 2 03E-07 2.03E47 2 03E-47 2.03E -47 2.03E-47 2 03E-07 142 522 0 00E+00 5 40E-02 5 40E-02 540E-02 5 40E-02 5 40E-c2 5 40E-42 Total Does Equivalent i mremtyr) = 0.00E+00 5 40E-02 540E-02 5.40E-02 5 40E-02 540E-02 5.40E-02
s ~ g g m gg mm m m e as m - am m M W _ W M- W M i -- Dose from Food Pathway (Crops) for 1991 Data usaae oma rata) 520 w e Maximum Exposed Child Cwtn Highest AnnualMean Concentration in0estiori Dose Feetor (rneem per pCl hegested) bdicator Food Doce (mrem /p) Radionuc!ide Bone Uver T. Body Thymed IGdney Lung GB-LU Loca6on (pCIAg) Bone Uver T. Body Thyroid IGdney Lung GI-LLI Mn-54 NO DATA 1.07E-05 2.85E-os NO DATA 3 00E46 NO DATA 8 98E-06 ALL 0 00 0.00E+00 0.00E+00 0 00E+co 0 00E+00 0.00E+00 600E+00 0 00E+00 f Co-68 NO DATA 1.80E-06 5.51E-06 NO DATA NO DATA NO DATA 1.05E-05 ALL 0.00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E400 0 00E+00 0 00E+00 l u ' w j Fe-59 1 65E-05 2.67E-05 1.33E-oS NO DATA NO DATA 7.74E-06 2.78E-05 ALL 0.00 0 00E+00 0 00C+00 0 00E+0C 0 00E400 0 00E+00 0 00E+00 0 00E+00 CO-60 NO DATA 5.29E-oe 1.56E45 NO DATA NO DATA NO DATA 2.93E-OS ALL 0 00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 l Zn-85 1.37E-oS 3 65E-05 2.27E-05 NO DATA 2.3cE45 NO DATA 6.41E46 ALL 0 00 0 00E+co 0 00E+oo 0 00E+00 0 00E+00 0 00E+oo 0 00E400 0.00E+00 Nb-05 2.25E-os 8.76E-09 62SE-09 NO DATA 823E-09 NODATA 182E-05 ALL 0 00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E400 0 00E+00 Zr-45 1.18E-o? 2.56E48 2.27E-08 NO DATA 3 65E-08 NO DATA 2 66E-05 ALL 0 00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0 0aE+00 0.00E+00 0 00E+00 1-131 1.72E-05 1.73E-os 9 83E-06 5 72E-os 2 84E-05 NO DATA 1.54E46 ALL 0 00 0 00E+00 0 00E+00 0 00E+00 0 00E400 0 00E+00 0 00E+00 0 00E+00 Co-134 2.34 E-04 3 84E-04 810E-45 NO DATA 1.19E-04 4.27E-45 2 07E-06 ALL 0 00 0 00E+co 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 Co-137 3 27E-o4 3.13E-04 4 62E-05 NO DATA 102E-04 3 87E-05 1.9eE-os ALL o 00 0 00E+co 0 00E+00 0 00E+00 0.00E+00 0 00E400 0 00E400 0.00E+00 BaLa-140 8.31E-oS 7.2sE48 4 35E-06 NO DATA 2.37E-08 4.34E43 4 21E-oS ALL 0 00 0 00E+00 0 00E+00 0 00E+00 0OCE+00 0 00E+00 0 00E+00 0 00E+00 i l Total Does Equivalent (mremfyrp 9 00E400 0 00E+00 0 00E+00 0 00E400 0 00E+00 0 00E+00 0 00E+00 l l l mA -
.m gm . m?m amm Q gmI y y .m m ma m , Dose from Broadleaf Vegetation Pathway for 1991 Data usage ent3ne 13te). 2e uwy, Maximum Exposed Child Cwt 0 Highest AnnualMean Concentration waenion Do.o reciar (mtem por gc incested Irwilestor Formf Does(meemtyr) Redknuclide Bone Uver T. Body Thyroid lOdney Lung GI-LU Location (pCUkg) Brne Over T.Dody Thyroid IGdney Lung G8-LLI Mn-54 NO DATA 1.07E-05 2.85E-06 NC DATA 3 00E-06 NO DATA $ 98E46 158 9 50 0.00E+00 2.64E-03 7.04E-04 0.00E+00 7.41 E44 0 00E+00 222E-03 Co -58 NO DATA 1.80E-06 5.51E-OS NO DATA NO DATA NO DATA 1.05E-05 ALL 0 00 0.00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0 00E*00 0 00E+00 Fe-50 1.65E-05 2.67E-05 1.33E-05 NO DATA NO OATA 7.74E-06 2.78E-OS ALL 0 00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0 00E+00 0.00E+00 0 00E+00 CO-00 NO DAYA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 ALL 0 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Zn-05 137E45 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41E-06 ALL 0 00 0.00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0.00E+00 Nb-95 225E-08 8.7eE-09 62eE-09 NODATA 8.23EMMD NO DATA 1.82E-05 ALL 0 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Zr-95 1.t eE-07 2.55E-08 2.27E-08 NO DATA 3 85E-08 NO DATA 2.66E-05 ALL 0 00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 1-131 t72E-05 1.73E45 9.83E-06 5.72E-03 2.84E-45 NO DATA 1.54E-06 ALL 0 00 0.00E*00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 Co-134 2.34 E-04 3.84E-44 8.10E-05 NO DATA 1.19E-04 4.27E-05 2 07E-Oe ALL 0 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 COE+00 0 00E+00 Co-137 327E-04 3.13E-04 4 62E-05 NO DATA 102E44 3 67E-05 196E-06 125 33 00 2.81E-01 2 00E-01 3 0eE-02 0 00E+00 8 75E-02 315E-02 188E-03 BaLa-140 8 31E-05 7.28E-08 4.35E-06 NO DATA 2.37E-08 4.34E-08 4.21E-05 ALL 0 00 0.00E+00 0 00E400 0 00E+00 0 0JE+00 0 00E+00 0 00E+00 0 00E+00 4 Total Does (mrom/yr) = 2 81E-01 2.710-01 4 03E-02 0 00E+00 8.83E-02 315E-02 3 90E-03
m . _ . , _ _ m a m .m :m' m m me e e e m mM M mW m' W Dose from Fish Pathway for 1991 Data usage onlane rate > - 9 e .,ry, . Maximum Exposed Child CHfLD High0St AnnualMean Concentration ingestien Dose Factor (mrom per pCllegested) indicator Flah Does(mrom/p) Radionucfkle Bone Uver T. Body Thyro 6d 90dney Lung G8-LU Location (pCUkg) Bone Over T. Body 1hyroid Kkiney Lung GS-LU Mn-54 NO DATA 1.07E45 2.85E-ce NO DAT A 3.00E-46 NO DATA 8 9sE-oe 129 6 20 0 00E+00 6 37E-04 1.70E-04 0 00E+00 1.79E~o4 5 00E+oo 5.34E-04 f M Co-58 NO DATA 1.80E-Oe 5.51506 NO DATA NO D ATA NO DATA 1.05E45 129 14.00 0 00E+00 2.42E44 7.41E-04 0 00E+00 0 00E400 0.00E+00 1.41E-03 tn Fe-69 1.85E-05 2.67E-05 1.33E-05 NO DATA NO DATA 7.74E-oe . 2.78E-05 ALL 0 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 CO-60 NO DATA 5 29E-06 1.5eE45 NO DATA NO DATA NO DATA 2.93E-OS 129 85 00 0 00E+00 3 30E-03 9 73E-03 0 00E+00 0 00E+00 0 00E+00 183E-02 Zn-65 1.37E-45 Se5E-05 2.27E-05 NO DATA 2.30E-05 NO DATA e 41E40 ALL O.00 0.00E+00 0 00E+00 0.00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 Nb-95 125E-08 8.76E4e e 2eE-09 NO DATA 8.23E-09 NO DATA 1.8'E45 129 3 50 7 56E-07 2 94E-07 2.10E-07 0 03E+00 2.77E-07 0 00E+00 5 44E-04 Zr-OS 1.16E-07 2.56603 2.27E-08 NO DATA 3 66E-08 NO DATA 2 erSoS Att 0 00 0.00E+00 0 00E+00 0 00E+oo 0 00E+00 0.00E+oo 0 OnE*oo 0.00E+00 6-131 1.72E-e5 1.73E45 9 83E-ofi 5 72E-c3 2 84E-os NO DATA 1.54E-oe ALL 0 00 0 00E400 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Co-134 2.34E-04 3.84E44 810E-45 NO DATA ta&E-04 427E-45 2 07E-06 129 5 90 1.33E-02 2.17E-02 4 59E-43 0 00E+00 6 74E-03 2.42E-03 1.17E44 Co-137 3 27E-04 3.13E-04 4.82E-oS NO DATA 1.02E-04 3 67E-05 1.95E 129 20 00 81eE-o2 7 8 t E-c2 1.15E42 0 00E+00 2 55E-02 9. t eE-43 4s9E-04 Bata-1*C 8 31E-05 7.28E-08 4 85E-OS NO DATA 2.37E-08 4 34E48 4 21E-05 ALL , 0 00 0 00E+oo 0.00E+00 0 00E400 0.00E+00 0 00E+00 0 00E400 0 00E+00 Total Oces (mrem /yr) = 9.49E-02 104E-01 2 68E-02 0 00E+00 3.24E-02 1.16E-02 2.14E-02
as WR - - M W .M M M M M M M M E " " " " " Dose from Shoreline Sediment Pathway for 1991 Data Maximum Fxposed Child Shoreline Hocreation 14 hr/yr Shore Width Factor = 0.3 cake shore-socation 129) Shore Width Factor = 0.2 (rtver shoretir.e-socation 130) External Does Factor for standing on Highest Annual Mean Coricentration Contaminated Ground Does barem/yr) (mrom/hr per pCi/m2) Iruficator *ediment R adiorwclide .T.Bndy Skin Location (pCIA9) T. Body Skin w Mn-54 580E-00 6 80E-09 129 28 0 2.73E-05 3.20E-05 Co-68 7.00E-49 8 20E-49 129 53.0 823E-05 7.30E-05 Fe-59 8 00E-09 9 40E-09 ALL 00 0.00E+00 0 00E+00 C&40 1.70E-os 2 00E-08 129 131 0 3.74E-04 4 40E-04 In-es 4 00E-Os 4 00E-09 ALL 00 0 00E+00 0 00E+00 P4b-95 5.10E49 a00E 49 ALL 00 0.00E+00 0 00E+00 Zr-OS 5.00E49 580E-09 ALL 00 0 00E+00 0 00E+00 1-131 2.80E-09 3.40E-09 ALL 00 0rmE400 0.00E+00 - Co-134 1.20E-48 1.40E-08 ALL 00 0 00E+00 0 00E+00 Co-137 4.20E-09 4 90E-09 130 1030 4.85E-05 5 65E-05 Bals-140 2.10E-09 2.40E-09 ALL 0.0 0.00E+00 0 00E+00 Total Does (rnrem/yr) = 512E-04 6 02E-04
g m e m . m m m - p;m m -m m e e W 'M M M M M _~- _ Dose from Air Particulate Inhalation Pathway for 1991 Data Maximum ExposcdInfant Breathing rate - 1400 maryr . Highest AnnualMean Concentmtion INFANT Inhafauan Dose Factor (mrom per pClinhaled fed) Indicator Air FladlenucGde Does (miow/p) Bone Uvor T.Dody Thpoid IGdney Lung GI-LLI Location (pCW.-3) Done Uver T. Body Thro 6d #Gdoey , Lung GI-LLI h 54 NO DATA 1.81E-05 3 56E-06 NO DATA 3 56E-06 7.14E44 504E-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 Co-68 NO DATA 8.71E-07 1.30E46 NO DATA NO DATA 5 55F-04 7.95E-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 Fe-69 9 69E-06 1.68E-05 6.77E-06 NODATA NODATA 7.25E44 1.77E-05 ALL 0.00E400 0.00E+00 0 00E*00 0 00E+00 0.00E+00 0 00E+00 0 00E q 000E+00 Co-80 No DATA 5.73E-06 4.41E-06 NO DATA NO DATA 322E-03 2.28E-05 AtL 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+0v Zn-05 1.38E-05 4 47E-05 2.22E45 NO DATA 2.32E-05 4 62E-04 3.67E-05 ALL 0 00E+00 0.00E+00 0 00E+00 0.00E400 0 00E+00 0 00E+00 0 00E+00 0 00E+ 4 Nb-05 1.12E-05 4.59E-46 2.70E-06 NO DATA 3.37E-06 3.42E-04 9 05E-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+0r Zr-95 2.24E-05 199E-05 1.45E-05 NO DATA 2.22E-05 1.2SE-03 1.55E-05 ALL 0 00E+00 0.00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E400 0.0cE+00 0.00E+00 1-131 2.71E-45 3.17E-OS 1.40E-05 1.06E42 3.70E-05 NO DATA 7.56E-07 ALL 0.00E+00 0.00E+00 0.00E+oo 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Co-134 2 83E-04 5 02E44 5.325-05 NO DATA 1.36E-04 6 69E-OS 9 53E-07 ALL 000E+00 0 00E+00 0 00E+00 nn0E+00 0 00E+00 0 00E+00 'O 00E+00 0 00D00 Co-137 3.92E-04 4.37E-44 3 25E-05 NO DATA 1.23E-04 5,09E-05 9.53E-07 ALL 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Ba b-140 4 00E-05 4.00E-03 2.07E-06 NO DATA 9 59E-09 f.14E-03 2.74 E-05 ALL 0 00E+00 0 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0 00E+00 0 00E+00 Totat Does Equivalent (mrem /p)= 000E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00
- asas! e m : 1 ==:: .. ==ms =m m aus e ~ ges '
m asas a m aus- m e e m 7 Dose from Air Radiciodine Inhalation Pathway for 1991 Data Maximum ExposedInfant Breathing rate . 1400 m3ryr V HighestAnnualMean Cmration ~ INFANT Inha;eter. Dese Factrw (mreen por S IrW Aar Radionuclue Dome (mremnpr) Bone. Uwr T. Body Thyrted Kunoy Luno . G8-LLI Leeenan (pCUm3) Bor= Over T. Body Thyrtzd Krtrwy Lung GS-LLt Mn-64 NODATA 121E45 15eE-os NODATA 15eE46 7.14E4M 5 04E46 ALL 0 00 0 00E+00 0 00E+00 0 00E40 0 00E+Go 0 00E+00 0 00E*00 0 00E+00 p Co-58 NO DATA 8.71E-47 130E-09 NODATA NODATA 555E-04 7.esE-os ALL 0 00 0 00E+00 0 00E+00 0 00E+00 0 00E*00 0 00E+00 0 00E+00 0 00E+00 iFe-59 9.89E4C 1.08E-05 0.77E-06 NODATA NODATA 7.25E-04 1.77E-05 ALL 0 00 0 00E+00 0.00E+oo 3 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Cc40 NO DATA 5 73E-OS S4*E-OS NOOATA NODATA 322E-03 21sE-05 ALL 0 00 0 00E+00 0 00E+00 0 00E+00 0 00E+co 0 00E+00 0 orc +00 0 00E+00 Zn-45 1.3eE-05 4 47E-05 2.22E-05 NO DATA 2.32E-c5 4 e2E-04 387E-05 ALL 0 00 0 00E+00 0 00E+00 0 00E+00 0 00E+co 0 00E+00 0 00E+00 0 00E*00 Nb-95 1.12E-os 4 SeE4e 2.70E-oe NO DATA 337E-06 3 42E-04 0 0$E-oe ALL t 0 00 0 00E+00 0 00E+oo 0 00E+00 0 00E+00 0 00E+00 0 00E+co 0 00E+00 27-05 824EWS 1.99E-05 1.45E-05 fC DATA 2.27E-05 125E-03 155E-05 ALL 2 0 00 0 00E+00 0 00E+oo 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 b131 2.71F '4 317E-os 1.40E-05 1.0eE-02 3 70E-OS NO DATA 7 SeE-07 ALL 0 00 0 00E+co 0 00E+C4 000E+00 0 00E+co 0 00E+00 0 00E.00 0 00E+00 .. Co-134 I 2 83E-04 E 02E-04 532E-05 NO DATA 138E-44 5 eeE-05 953E-07 i ALL 0 00 0 00E*00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+co 0 00E*oo l Co-137 3 9?E-44 4.3 TE-44 32SE-05 NO DATA 1.23E-04 SN 25 9 53E-07 ALL 0 00 0 00E*00 0 00E+00 0 00E+00 0 00E+0; o00E+00 0 00E+co 0 00E+00 Belm-140 4 00E-05 4 D)E-OS 2.07E-oe NO DATA 4 SeEA. 1 i4E-43 4 WE-os ALL 0 00 0 00E+00 0OcE+00 0 00E*c0 0 00E+00 0 00E+00 0 00E+00 0 00E 00 fn. 4,ose leurvalent (rammeyr) = 0 coE+00 0 00E+00 0 00E+00 0 00E+00 0 00E.00 0 00E+00 0 00E+00 I T s
g a - g m e e e e e e e m 3 M M M M M Dase from Milk Pattiway for 1991 Data Maxtmum ExposedInfant usago ontake rate)- 330 ur Highest AnnualMean Concentration INFANT IngeW6an Does Factor (mrom w pCs snowed) andcaww im Radionuch Bone ther . T. Body Throid Doe.(mrom w sodney Luno Gs-tu Loesnan ecut) sono uver T.sody Thym d Kidney Luno us-tu M9-64 NO DATA 1.esE-os 4 51E-os NO DATA 4.41E-06 NO DATA 731E-48 ALL ' 0 00 0 00E+oo 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 d Co-68 NODATA 3190E-46 8ptE-08 NODATA NODATA NODATA e 97E-ce 1 ALL m 0 00 0 00E+00 0 00E+00 0 00E+% 000E+00 0 00E.oo 0 00E+00 0 00E+00 Fe-50 3 OLE-05 5.38E-05 2.12E-C5 NO DATA NO DATA 1.5eE-45 2 57E-45 ALL 0 00 0 00E+00 0 00E+co 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Co-eo NO DATA 1.ceE-05 2.56E-05 NO DATA NO DATA NO DATA 2.57E4 ALL 0 00 0 00E+00 0DaE+00 0 00E+co 0 00E+00 0 00E.00 000E+00 0 00E+00 Zn-e5 1.84E-c5 6.31E-05 2 91E-05 NO DATr 3 ceE-05 NODATA 533E-05 ALL 0 00 0.00E+00 0 N E+00 0 00E+00 0 00E400 0 00E+00 0 00E+40 0 00E+00 Nte-@5 4 2cE-08 1.73E-ce 1.00E-08 NO DATA 124E-os NO DATA 14eE-05 ALL 0 00 0 00E+co 0 00E+00 0 00E+00 0 00E*00 0 00E+00 0 00E+co 0 00E+00 Zr-95 2.ceE-07 5.02E-et 3 seE-os NO DATA 5 41E-os NO DATA 2.50E-05 I ALL 0 00 0 00E+oo 0 00E+00 0C'OE*c0 0 00E+00 0 00E+00 0 00E+00 0 00E*c0 ' l-131 3 500-05 4.23E-05 1.86E-05 1M-42 4 94E-05 NO DATA 1.51E-06 ALL 0 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Co-134 3 77E-04 7.03E-04 7.10E-05 NC,DAYA 1.stE-04 7.42E-os 191E-06 ALL 0 00 0 00E+00 0 00E*oo 0 00E+00 0 00E+00 0 00E+oo 0 00E+00 0 awc Co-137 5.22E-os e.11E-04 4.33E-45 NO DATA 1e4E-04 8 64E-45 1.91E-OS ALL 0 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+oo 0 00E400 0 00E+co Bala-140 1.71E-04 1.71E-07 4 StE-OS NO DATA 4 DeE-os 1.05E-47 4.20E-45 ALL 0 00 0 00E*C0 C.00E 00 0 00E+00 0 00E+co 0 00E+00 0 00E+00 0 00E+co Toest Do e Eedvekm immvyr) = 0 00E+oo 0 00E+00 0 00E+00 0 00E+00 0 00E*o0 0 00E+00 0COE+oo
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I l 5.0 QUALITY ASSURANCE l I l 5.1 DUKE POWER COMPANY'S RADIOLOGICAL ENV!RONMENTAL LABORATORIES 5.1.1 SAMPLE COLLECYlON The Radiological and Environmental Services Group and the Fisheries work I group oorform the environmental sample collections as specified by appnwes sample collection procedures. I Modifications and improvements made to the environmental sampling program during the past year can be found in Appendix A. 5.1.2 SAMPLE ANALYSIS The Radiological and Environmental Services Group performed the I environmental sample ana!yses as specified by approved analysis procedures. In 1989, reviewed data indicated detection of Cs-137 in airborne radiolodine cartridges, but not in associated airborne filters for the same sampling period and location. An extensive investigation was ccnducted in 1990 to I determine reasons why low level Cs-137 activity, approximately 1 to 8 picoeuries per total cartridge, was being detected on a low percentage basis of all cartridges counted by the Duke Power Radiological and Environmental Services Group. The possibility of detecting low-level actJvity was increased due to the installation of low background shields for gamma spectroscopy. In addition to the new shields employed, analysis techniques I in some instances used extended count times. Experimental results determined that the Cs-137 activity was due to the activated carbon medh and was present prior to placement into field sampling units. Various airborne radiolodine cartridges were obtained from different vendors nationwide which had similar characteristics as the cartridges that ware in current use by the Duka Power Environmental Collection Team. Findings support that low-level Cs-137 is a fallout product that is incorporated into the carbon media. I It is anticipated that continual observance of low activity Cs-137 will be detected on a random basis in airborne radiolodine cartridges and any trending of this data will be reported by the Radiological and Environmental Services Group to appropriate nuclear station personnel for consideration. 1
5.1.3 DOSIMETRY ANALYSIS The Dosimetry I2iboratory performed environmental dosimetry measumments as specified by approved dosimetry analysis procedures. I 5.1.4 INTRALABORATORY OUALITY ASSURANCE Radiological and Environmental Services has an internal quality assurance program which monitors each type of instrumentation for reliability and 3 acc. racy. Daily quality control checks en.are that instruments are in 5 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 ns unknowns at various frequencies ranging from weekly to annually to verify that I i efficiency calibrations are valid. The frequency is dependent upon instrument use and performance. Investigations are performed and documented should calibration verification data fall out of limits. I 5.1.5 INTERLABORATORY OUALITY ASSURANCE 5.1.5.1 DUKE POWER'S AUDIT DIVISIO3 The Radiological and Environmental Services Group participated in a Quality Assurance audit in 1991, performed
- i. by Duke Power Company's Audit Division. Followup items pertaining to the environmental sampling program were 3 identified in the audit and resulted in the placement of two E specialinterest TLD's inside the site boundary at the N and NNW secars.
The follow-up items were later closed out by the Audit Division. I 5.1.5.2 DUKE POWER'S NUCLEAR PRODUCTIOJ INTERCOMPARISON PROGRAM The Radiological and Environmental Services Group participated in the Duke Power Nuclear Production Intercomparison Program during 1991. Interlaboratory cross-check body burden standards, marinelli beakers, air filters, air cartridges, gross alpha /bota on I smears, and tritium in water samples were analyzed at various times of the year by the four counting laboratorios in Duke Power Company for this program. 5.1.5.3 KS. NUCLEAR REGULATORY COMMISSION INSPECTIONS Radiological and Environmental Services was audited by the NRC in 1991. No follow-up items were identified by the 5-2
4
; E inspector- A non-cited violation was identified concerning E the failure to employ a sampling motbod which resulted in a specimen that was representative of liquid flow at drinking water site #132. A new sample location was found where the I pump would continue to operate even during periods of low demand. This location was placed in service on 01/25/91.
5.1.5.4 UNITED STATES ENVIROJMENTAL PROTECTION AGENCY INTERCOMPARISON PROGRAM l The Radiological and Environmental Services Group
, participated in the Environmental Protection Agency (EPA) l
- Environmental Monitoring Systems Laboratory l Intercomparison Program. Thn EPA sample types included I mixed gamma in water (3 times per year), mixed gamnia in milk l (2 times per year), gamma in air filters (2 times per year),
I iodine in milk (2 times per year), tritium in water (3 times per year), iodine in water (2 times per year), gross alpha / beta in air filters (2 times per year), and gross alpha / beta in water (2 times per year). Radiological and Environmental Services prepared and analyzed each sample as quickly as possible. Should the data I obtained be out of EPA limits, Radiological and Environmental Services would have performed and documented follow-up investigations. The Radiological and Environmental Services EPA Intercomparison Report code is "CP". A summary of , B the EPA Intercomparison Reports for 1991 is documented in Table 5.1. Of the thirty-seven (37) analyses performed in i 1991, one analysis (Gross Alpha / Beta in Air Filter cross-check, reference date 3/29/91) was out of EPA acceptance limits. An investigation was performed to find out why these results were not within statistical limits. The following areas were investigated in an effort to resolve these poor results: I 1. Geometry of the sample
- 2. Gas flow
- 3. Efficiency calibration files
- 4. Errors in the activity calculation
- 5. X-checks and calibration checks counted at about the same time of the analysis
- 6. Trends of past EPA Alpha / Beta X-checks
- 7. Recounting the EPA X-Check Air Filters
- 8. McGuire Nuclear Station air filter results for 1991 5-3
I In the first area of investigation, geometry, it was noticed that the air filter media the EPA uses is considerably thicker than that of our regular air samples, therefore the sample will be placed closer to the counting window during the time of I analysis. This closer placement of the samplo will then produce a higher alpha count rate than that of a sample that is more distant from the window. This would in turn produce I a higher activity ' reported for alpha, but the beta results would not necessarily change, because of the high energy of the Cs-137 beta. Frr a the review of the logbooks it was noticed that these samples were analyzed about 2 months before the end of a gas cycle. The gas flow was normal during this time, therefore this could not have adversely affected the results. The efficiency calibration files were checked and they were up-to-date at the time of the analysis. This was shown by comparing the efficiencies used in calculating the activities for this x-check to those used for previous samples with the same weights. The activity calculations were also reviewed again very thoroughly to see that all data input was correct, and they were found to be satisfactory. The x-checks and verifications performed at about the same time ( April 1991) of the EPA x-check analysis were also reviewed to see if they were indicating a problem with the instrument. It was found that two x-checks, one EPA Drinking Water and one G.O. smear, were analyzod at about the same time of the analysis of this x-check. The results of both were within acceptable I limitsi therefore the system wts operating properly. The results of the EPA X-Checks for Air Filters and Drinking I Water since 1984 were gathered and plotted to see if there were any trends in the results. The EPA started using a new uisk media tc simulate an air filter in April of 1987. By I studying these graphs it was seen that the alpha results, from 1988 to present, start to trend high. This trend can be related to either the change in filter media or change in g calibration standa!.'ds (new standards made in October 1987) . g By comparing the graphs it was seen that the change in
- results is due to the change in filter media, because the l Drinking Water restats did not trend in the same manner as
- ' those of the Air Filters.
The EPA Air Filters were an dyzed again under the new
- & calibration that was performed in June 1991. These results
- E were satisfactory for Bo'.a activity, but were at the warning timit for Alpha. _ The Air Filters were also counted while
- placed directly in the holders (i.e. not in planchets), and these results were within statisticallimits (Alpha Normalized Deviation =2.46 and Beta Normalized Deviation =-1.58). These
, results would support #1 of this investigation for Alpha, g because the results were produced with the sample being further away from the counting window and closer to being 5-4
i the geometry used prior to April 1987. Ilowever, this does I not support #7 for Beta, because even though the results are within statistical limito, the activity had dropped. I The final part of this investiga' tion was to determine if there was a change or trend in the results of the routine air filter samples for 1991. This study was done by printing all of the I alpha and beta res'ults for McGuire Nuclear Station for 1991, and visually checking to see if there was a noticeable change in the results. By doing this, there appeared to be no I adverse changes or trends in the activities that were reported; therefore, our countiag systems were still operating properly. .in the conclusion of this intestigation, i it appeared that just one reason for the poor results could not I be identified. The instruments will continue to be checked on a quarterly basis to ensure they are within calibration limits. I Additional documentation of this investigation is available from Radiological and Environmental Services. I 5.1.5.5 NRC/ STATE OF S.C. ENVIRONMENTAt. MONITORING PROGRAM i The ONS Chemistry Section and Radiological and Environmental Services routinely participate with the State of South Carolina in their NRC/ State Contract Environmental Monitoring Program. The ONS Chemistry Section spilts water, milk, vegetation, sediment, and fish samples with the Bureau of Radiological Health of the State's Department of Health and Environmental Control (DHEC) for analysis. I 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 Radiological and Environmental Services Group and DiiEC Laboratory are compiled by DilEC 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 Radiological and Environmental Services, and the Dosimetry Laboratory routinely participate with the State of North Carolina Department of Environmental Health and Natural I Resources (DEHNR) in an intercomparison program. Health and Radiological Projects sends air, water, milk, vegetation, sediment, and fish samples which have been collected to the i 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 irradiates environmental dosimeters and sends them to the Dosimetry Laboratory for analysis of the unknown estimated delivered exposure. A summary of the I State of North Carolina Environmental Dosimetry Intercomparison Report for 1991 is documented in Table 5.2. 5-5
- I 3 The Dosimetry Laboratory results were withlu 8.13% of tho l 5 State of North Carolina r<mults (excluding Standard Deviation l values) for the March If*91 cross-check and 3.79% (excluding Standard Deviation values) for the December 1991 cross-check.
5.1.5.7 U.S. DEPARTMENT OF ENERGY INTERCOMPARISQU PROGRAM There was no DOE Intercomparison program during calendar i year 1991. t 5.2 CONTRACTOR LADORATORY ,l No contractor iahoratories were used during 1991. . I
.I
,I l I . 1 I I-I I I s.e
em aus e amE MEE M SEE BER M WWE 6 NED 859 W IM M EEE W TAELE 5.1 (Page i of 2) U.S. ENVIRONMENTAL PROTECTION AGENCY INTERLABORATORY COMPARISON PROGRAM 1991 CROSS-CHECK RESULTS FOR THE RADIOLOGICAL AND ENVIRONMENTAL SERVICES LABORATORY CONTROL LIMITS ANALYSIS DATE NUCLIDE(S) rJ00WN VALUE (3 SIGMA N=3) REPORTED VALUE_ Gama in Water 2/08/91 Ba-133 75 pCi/L 61.1 - 88.9 pCi/L 76.3 pCi/L Co-60 40 pCi/L 31.3 - 48.7 pCi/L 42.3 pCi/L Zn-65 149 pCi/L 123.0 - 175.0 pCi/L 158.0 DCi/L Ru-106 186 pCi/L 153.0 - 219.0 pCi/L 212.3 pCi/L Cs-134 8 pCi/L 0.0 - 16.7 pCi/L 8.3 pCi/L Cs-137 8 pCi/L 0.0 - 16.7 pCi/L 9.3 pCi/L 6/07/91 Ba-133 62 pCi/L 51.6 - 72.4 pCi/L 65.0 pCi/L T Co-60 10 pCi/L 1.3 - 18.7 pCi/L 11.0 pCi/L Zn-65 108 pCi/l. 88.9 - 127.1 pCi/ L 112.7 pCi/L Ru-106 149 pCi/L 123.0 - 175.0 pCi/L 159.0 pCi/L Cs-134 15 pCi/L 6.3 - 23.7 pCi/L 15.0 pCi/L Cs-137 14 pCi/i 5.3 - 22.7 pCi/L 15.3 pCi/L ' 10/04/91 Ba-133 98 pCi/L 80.7 - 115.3 pCi/L 100.7 pCi/L Co-60 29 pCi/L 20.3 - 37.7 pCi/L 32.7 pCi/L Zn-65 73 pCi/L 60.9 - 85.1 pCi/L 83.3 pCi/L Ru-106 199 pCi/L 164.3 - 233.7 pCi/L 218.0 pCi/L Cs-134 10 pCi/L 1.3 - 18.7 pCi/L 10.3 pCi/L Cs-137 10 pCi/L 1.3 - 18.7 pCi/L 11.0 pCi/L i i 2/15/91 I-131 75 pCi/L 61.1 - 88.9 pCi/L 78.7 pCi/L 8/09/91 1-131 20 pCi/L 9.6 - 30.4 pCi/L 20.7 pCi/L Air Filter 3/29/91 Cs-137 40 pCi/ Filter 34.2 - 45.8 pCi/ Filter 39.3 pCi/ Filter Gross Alpha 25 pCi/ Filter 18.1 - 31.9 pCi/ Filter 41.7 pCi/ Filter Gross Beta 124 pCi/ Filter 117.1 - 130.9 pCi/ Filter 108.0 pCi/ Filter
p M m mmm M m Mm mm mM M M m M. p TABLE 5.1 (Page 2 of 2) U.S. ENVIRONMENTAL PROTECTION AGENCY INTERLABORATORY COMPARISON PROGRAM 1991 CROSS-CHECK RESULTS FOR THE RADIOLOGICAL AND ENVIRONMENTAL SERVICES LABORATORY CONTROL LIMITS ANALYSIS DATE NUCL1DE(5) KNOWN VALUE (3 SICMA; N=3) REPORTED VALUE_ Air Filter 8/30/91 Cs-137 30 pCi/ Filter 21.3 - 38.7 pCi/ Filter 31.7 pCi/ Filter Gross Alpha 25 pCi/ Filter 14.6 - 35.4 pCi/ Filter 35.0 pCi/ Filter
. Gross Beta 92 pCi/ Filter 74.7 - 109.3 pCi/ Filter 93.0 pCi/ Filter w Tritium in Water 2/22/91 H-3 4418 pCi/L 3651.2 - 5184.8 pCi/L 4676.0 pCi/L a
6/21/91 H-3 12480 pCi/L 10314.8 - 14645.2 pCi/L 12387.7 pCi/L 10/18/91 H-3 2454 pCi/L 1843.3 - 3064.7 pCi/L 2839.0 pCi/L Gama in Milk 04/26/91 1-131 60 pCi/L 49.6 - 70.4 pCi/L 67.0 pCi/L Cs-137 49 pCi/L 40.3 - 57.7 pCi/L 49.7 pCi/L 9/27/91 I-131 108 pCi/L 88.9 - 127.1 pCi/L 110.7 pCi/L Cs-137 30 pCi/L 21.3 - 38.7 pCi/L 31.0 pCi/L Alpha-Beta 1/25/91 Gross Alpha 5 pCi/L 0.0 - 13.7 pCi/L 7.7 pCi/L in Water Gross Beta 5 pCi/L 0.0 - 13.7 pCi/L 9.3 pCi/L i l 9/20/91 Gross Alpha 10 pCi/L 1.3 - 18.7 pCi/L 10.7 pCi/L Gross Beta 20 pCi/L 11.3 - 28.7 pCi/L 21.3 pCi/L 1
p W m .m' W W W WW mm um W W W m m alps TABLE 5.2 STATE OF NORTH CAROLINA DEPARTMENT OF ENVIRONMENTAL HEALTH AND NATURAL RESOURCES ENVIRONMENTAL DOSIMETER CROSS-CHECK 1991 STATE OF N.C. DOSIMETRY LABORATORY FSTIMATED VALUE FSTIMATFE VALUE Date Fatimated , g Exposure FAimated Uncertainty Faposure a Cross-Check (mR) (IS.D. mR) (mR) 3/91 49.6 i 1.2 47.72 1 1.91 l 12/91 49.3 1 0.7 45.75 g 3,39
t .. m- _ .- m_ _;_ _-
6.0 REFERENCES
I ' I i
- 1. Final Safety Analysis Report, McGuire 1 & 2, Section 1.2.1.
I 2. Final Safety Analysis Report, McGuire 1 & 2, Section 2.1.
- 3. Final Safety Analysis Report, McGuire 1 & 2, Section 2.1.1.
t 4. Final Safety Analysis Report, McGuira 1 & 2, Section 11.6.1.
- 5. Final Safety Analysis Report, McGuire 1 & 2, Section 11.6.3.
G. Final Safety Analysis Report, McGuire 1 & 2, Section 11.6.4.
- 7. Selected Licensee Commi'ments Manual Section 16.11-13.
t 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 I Evaluating Compliance with 10CFR Part 50, Appendix I", U.S.
Nuclear Regulatory Commission, Rev.1, October 1977. I 10. Probability in Statistics in Engineering and Management i 11. Science, liines and Montgomery,1969, pp. 287-295. Practical Statistics for the Physical Sciences, American Chemical Society,1988, pp. 84-100. I i l 6-1 _ _ _ - _ _ _ . - . - _ - - - - - - - - - - - - - - ~ - - - - - " ~ ~ - ^
g _- !I I l - I I APPENDIX A I I I ENVIRONMENTAL I SAMPLING AND I ANALYS/S PROCEDURES
.I I
I . I I I
l i APPENDIX A I ENVIRONMENTAL SAMPLING AND ANALYSIS PROC _EDURES I ' Adherence to established procedures for sampling and analysis of all environmental media at McGuire Nuclear Station was required to ensure compliance with Station I Selected Licensee Commitments. Analytical procedures were employed to ensure that Selected Licensee Commitments detection capabilities were achieved. a I Environmental sampling and analyses were performed by the Duke Power Generation Services Department Radiological and Environmental Services Group, the Dosimetry Laboratory, and the Fisheries work groups. Starting at Section A.1, this appendix deceribes the environmental sampling frequencies and analysis procedures by media type. I 1. CHANGE OF SAMPLING PROCEDURES The Land Use Census identified an additional food products location at the Austin Residence. The Austin Residence was assigned as location number 188, and is located 2.8 miles from the station in the North sector. Sampling i at the Austin Residence began October 10, 1991. Location 188 will replace location 185 (Brewer's Residence) for future food products sampling. Two new TLD locations were added a s "SPECIAL INTEREST" monitoring sites. These locations were designated as location 186 (0.2 mi. NNW) and location 187 (0. 3 mi. N) . Two additional TLD's were added as site boundary sites in December,199.1 as a result of the GPS Project (see page A-5). These locations were designt..ed as location 189 (0.4 miles SSE) and location 190 (0.5 miles WSW) . The results of these TLD's will be summarized in the 1992 Annual Report. I II. CHANGE OF ANALYSIS PROCEDURES During 1991, a change in the counting procedure was made for gross beta samples. The samples were counted in replicate, three times each, and a mean result was used in the calculation of activity. The value used to determine if the gross beta activity is less than the critical level was re-evaluated ar charged to be 50% of the MDA value rather than 100%. This value is indicated on the activity calculation printout for each i sample. I A-2
- _E
E It!. SAMPLING AND ANALYSIS PROCEDURES l A.1 AIRBORNE PARTICULATE AND RADif)lpDINE Airborne particulate and radiolodine samples at each of five locations were composited continuously by means of continuous air samplers . Air particulates were collected on a particulate filter and radiolodines were collected in a charcoal cartridge situated behind the filter in the sampler. The samplers are designed to operate at a constant flow rate (in order to compensate for any filter loading) and are set to sample approximately 2 cubic feet per minute. Filters and cartridges were collected weekly. A weekly 5 gamma analysis and gross beta analysis was performed on each filter and a weekly gamma analysis was performed on each charcoal cartridge. The filter and charcoal cartridge were analyzed independently. The continous composite samples were collected from the locations listed below. I Location 120 = Site Boundary (0.4 mi. NNE) Location 121 = Site Boundary (0.5 mi. NE) Location 125 = Site Boundary (0.4 mi. SW) Location 133 = Cornelius, NC (6.2 mi. NE) Location 134 = East Lincoln Junior High School (8.7 mi. WNW) A.2 DRINKING WATER Biweekly composite samples were collected. A low-level Iodine-131 analysis
. was performed on each corrposite sample. A gross beta and gamma analysis was performed on monthly composites. Tritium analysis was performed on the quarterly composites. The composites were collected biweekly from the I locations listed below.
Location 132 = Charlotte Municipal Water Supply (11.2 mi. SSE) Location 136 = Mooresville Municipal Water Supply (12.5 mi. NNE) Location 142 = Davidson Municipal Water Supply (7.5 mi. NE)
'I A.3 SURFACE WATER I Biweekly composite samples were collected. A low-level Iodine-131 analysis was performed on each composite sample. A gamma analyris was performed on the monthly compositen. Tritium analysis was perf ormed on each sample. The composites were collected from the locations listed below.
Location 128 = Discharge Canal Bridge (0.4 mi. ENE) Location 131 = Cowans Ford Dam (0.7 mi. W)
,I Location 135 = Plant Marshall Intake Canal (12.0 mi. N)
A.4 MILK Biweekly grab samples were collected at each dairy and a gamma and low-level Iodine-131 analysic was performed on each. The biweekly grab samples were collected from the locations listed below. Location 138 Henry Cook Dairy (2.75 mi. ESE)
~
=
Location 139 = William Cook Dairy (2.6 mi. E) Location 140 = Kidd Dairy - COWS (2.8 ml. SSE) Location 141 = Lynch Dairy - COWS (14.8 mi. WNW)
A.5 BROADLE AF VEGE.TATION Monthly sampics were collected and a gamma analysis was performed on each, The samples were collected from the locations listed below. Location 120 = Site Boundary (0.4 mi. NNE) Location 125 = Site Boundary (0.4 mi. SW) I Location 134 :
=
East Lincoln Junior High School (8.7 mi. WNW) 4-5 Mile Radius (5.0 mi. NNE) Locat' ion 158 A.6 SHORELINE SEDIMENT ! Samiannual samples were collected and a gamma analysis was performed on eaca following the drying and removal of rocks and clams. The samples were collected from the locations listed below. Location 129 = Discharge Canal Entrance to Lake Norman (0.6 mi. ENE) l Location 130 = liighway 73 Bridge Downstream (0.6 mi. ENE) Location 137 = Pinnacle Access Area (12.0 mi. N) A.7 FISH Semiannual samples were collected and a gamma analysis was performed on the I . edible portions of each sample. Boney fish such as Shad were prepared whole minus the head and tail portions. The samples were collected from the locations listed below. Location 129 = Discharge Canal Entrance to Lake Norman (0.6 mi. ENE) Location 137 = Pinnacle Access Area (12.0 mi. N) A.8 plRECT G AMMA RADIATION (TLD) Thermoluminescent dosimeters (TLD) were collected quarterly at forty-two concentric locations. A gamma dosa rate was determined for each TLD. The TLDs were placed as indicated below.
- An inner ring of 14 TLDs at the site boundary, one in each available meteorological sector. The site boundary locations in I the N and NNW sectors are over water; however, two special interest TLD's were placed in these sectors inside the site boundary in March,1991.
- An outer ring of 16 TLDs, one in each meteorological sector in the B to 8 kilometer range.
- The remaining TLDs were placed in SPECIAL INTEREST areas such as population centers, residential areas, schools, and CONTROL locations.
A-4
I - A.9 EOOD PRODUCTS Samples were collected monthly when aval;able during the harvest season and a gamma analysis was performed on each. The samples v'ere collected at the , locations listed below. Location 184 = 5 Mlle Radius (2.5 mi . ENE) - Gardens I Location 185 = (Davenport'3 Residence) . 5 Mile Radius (4.9 mi. N) - Gardens (Brewer's Residence) I Location 188 = 5 Mlle Radius (2.8 mi. N) - Gardens ( Austin's Residence) A.10 ANNUAL LAND USE CENSU) I An annual Land Use Census was conducted to identify within a distance of 8 kilometers (5.0 miles) from the station, the nearest location from the site boundary in each of the sixteen meteorological sectors, the following: 1 E'
- The Nearest Residence
* "'he Nearest Meat Animal
- T!m Nearest Garden
- greater than 50 square meters or 500 square feet The Nearest Milk-giving Animal (cow, goat, etc. )
E
, IV. SAMPLING AND ANALYSIS IMPROVEMENTS <g' 9
m Several enhancements were made to the environmental monitoring program in 1991. Focus was centered on reducing the number of sampling deviations by researching equipment upgrades, establishing acceptance criteria for equipment replacement, implementing equipment labelling and serial number documentation, and carefully reviewing deviations by site location and sample type. Also, the Global Positioning System (GPS) Project was implemented to more accurately determine distance and sector for each sampling location. GPS is a satellite - based radio navigation system which provides precise positioning data. I -
.. 1, t
, A-5
I l 3 1 1 APPENDIX B 8 I I I RADIOLOGICAL ENVIRONMENTAL E IAONITORING I PROGRA.M i g
SUMMARY
OF RESULTS Summary sheets for each media have been included in this Appendix. I I I I I I e.1
I !.1 rat!Dl0 DINES Environeratal Rac2elegatal Monstering Prograa Su ur, base of facility : ht6uire Natitar Statien Lottet husber : 50 4 69.370 Location of Facility : Mettlenburg tourity. 4.C. Eroertirg Per2od : 1-JAh 1991 through 31 MC 1991 Database mane : 1D1511 ll'5ER. ASC)MN591.!AF.4 B.....Tjee. . . . . .lieeert
. . - - . - - - .Generated
- - - - - - - - - - - - - -i JAt
~ . ~ - ~ ~ - 199213:33:32 ---------------------------~~-~------- - - - - ~ - - - - - - - ~ ~ - - - - ~
- Location eith Nghest Nean '
he. ci
?ediu or : Tver 6 total : Leser
- All Inga rator I Pathny Sasoled tttnitsi Nuaber ci Analvses Liest oi :
4tettien ' rean tirattlun) Locations
- ---~~~---~-------~~-~
hate. Distante anc Dirtttaen :
- Location mean (frattioni '
[cettel Lt;tatacos Fran if raction)
. Non-hotine
' Secort Perfornec fttD)
- Range : Code Aange sange atas,
~~~~~~~~~~~~~~~^~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~^~~~~~~~~~~~~~~~~~~~~~~~~
l.~~IRRADIDlDtlNIS: A : : : : ' iPCl/M31 : : : : . 138 19.7 Mi thW) I5 Lotatsoris : MN 54 261 : 0.0 0.00E+001 0/ 209) : 0.0M +00 f 0/ 51) : 0.ME*001 0/ 52) : 0
- : : 0.00E+00-- 0.ME*00 : 0. 00E
- 00-- 0. 0M
- 00 ' O.00E+00 - 0.00E+00 '
- i : : : :
- CD 5B 261 : 0.0 : 0.0M
- M t 0/ 209) : 0.0M+00i 0/ $1) ' O.00E + 00( 0/ $21 : 0
- : 0.0M+00~ 0.00E +00 :
0.00E+M~ 0.00E +00 : 0.00E*00~ 0.00E+00 :
. g g
- FE-59 261 : 0.0 : 0.00E*001 0/ 209) :
3 0.00E*001 0/ $11 : 0.00E+001 0/ 52) : 0
- : : 0.00E+00~ 0.ME+00 : 0.0M +00~ 0.0M +00
- 0.00E+00- 0.00E +00 :
- CD-60 261 : 0.0 : 0.00E +001 0/ 209) : 0. ME + 001 0/ $1) : 0.00E*00( 0/ 52) : 0 I :
- 0.00E+00~ 0.00E+00 : 0.0M *M- 0.0M+00 : 0.00E+M~ 0.00E*00 :
l l : .
' 2n 65 261 : 0.0 : 0.00E*00t 0/ 2091 :
I l
- kB-95 261 :
0.0
- 0.00E+00-- 0.ME+00 :
0.0M
- 001 0/ Sal : 0.00E*001 0.0M+M- 0.0M *00 : 0.00E+00 ~ 0.00E+00 :
0/ 52) : 0
- 0.00E+001 0/ 209) : 0.0M +001 0/ 51) : 0.00E+001 0/ 52) : 0
- : : 0.00E
- 00-- 0. 00E +00 : 0.00E+00-- 0.ME+00 : 0.00E+00-- 0.00E+00 :
I : : : : : :
- IR-95 261 : 0.0 : 0.00E+00f 0/ 209) : 0.0M + 001 0/ 51) : 0.00E *001 0/ $21 : 0
- : : 0.00E+00-- 0.00E+00 : 0.00E+00-- 0.00E+00 : 0.00E+00-- 0.00E+00 :
5 :
- 1 131 261 : 7.00E-02 : 0.00E+001 0/ 209) : 0.00E+00( 0/ 51) : 0.00E*00( 0/ 52) : 0 I :
l CS-134 261 : 5.00E-02 : 0.00E+001 0/ 2091 : 0.00E*M-- 0.00E+00 : 0.0M*00-- 0.00E *00 : 0.00E+MI
- 0. ME*00-- 0.00E+00 :
0/ SI) : 0.00E+001 0/ 52) : l 0
- 0.00E+00-- 0.00E+00 : 0.00E+00~ 0.00E*00 : 0.00E*00 - 0.ME*00 :
- ! : : 120 10.4 Mi NME) :
I : C5-137 261 : 6.00E-02 : 2.31E-021 3/ 209) : 3.56E-021 1/ 51) : 0.00E+001 0/ 52) : 0
- : 1.?BE 02-- 3.56E-02 l 3.56E 3.56E-02 0.00E *M-- 0.00E*00 :
I BALA-140 261 ! 0.0 : 0.00E+001 0/ 209) : 0.0M+001 0/ $1) : 0.00E+00( 0/ 52) : 0
- 0.00E+00-- 0.00E+00 : 0.00E *M-- 0.00E +00 : 0.00E+00~ 0.00E+00 :
E n na ran0 0 i a can a t <ta$i r nti ani, Mattion of detettat>le measuresents at sottified locations is indicated in carentheses. (Fraction) Jero range indicates no detectable activitt seasurteents LLD is esual to 0 then LLD is not reevired by Technical Soetifications e LLDs listed above are the values required by Station 1 ethnical Soetifications I Location 120 Site Boundart (0.4 Ri ItNE) Lotation 121
- Site Boundary 10.5 Ri NE)
Location 125
- Site Boundarv 10.4 R1 SW)
Location 133 : Corrielius. NC 16.2 Mj NE) Location 134 = East lintoln Junior High School (B.7 Mi WhW) 5-2
9.2 PARilCULATE Environeental Radiological Monitorino Prograe $cesar, Nase of Facility : Pt6uire Rutlear Station 8 Location of Facility : Mettlenburg Countr. N.C. Dottet hueter : 50 369.370 Feocriang Feriod i 1 J Ah l'.91 through 31-MC-1H1 time Fenert Generated 14 An 19 92 13 : 33 : 32 tatabase use : SCISil slv5ER. A$t mS91.5M :1
...............................-J. . . . . . . . . ~ . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ~ - - - . . - ~ . . . . ~ . - - . ~ . - . - - . . - - . ~ . - - - - - - . . . - - - -
I Medaue er Tree I icial : Lower
- All Indicater
.etation eith H2pt,est *te
-~~--~-~"--~~~~---~~:
No, cf ha-Pathear : heter ci : Liest of ' L oc a ts t+s use. Dantante and Direction Contrtl Lecaiaors E cut a r.e SaaDied Arialists ' Deletiton Pean (Tractioni ' Letat2on Mean (f rattat'ni mean (FrattaoM ' Errort iunits) : Pericreed ; iltt) Ra6p : Coce Range Gange Peas.
....................--.......................~.................-.....~...--....~...---.--..---..~.------...-~....~.....~...
!?4 10.7 '!1 thul IAIRPARiltutATE (PC1/M3) l l l l .
l MN-54 261 : 0.0 : 0.0M + 001 0/ 209) : 0.00E*001 0/ 51) : 0.00E+001 0/ 521 0
- : 0.00E*00- 0.00E*00 : 0.0M *00 - 0.00E*00 ' O.00E*00 - 0.00E+00 5 5 tocations l l l l l l CD-58 261 : 0.0 : 0.ME
- 001 0/ 209) : 0/ $1) 0.0M + 00( 0.00E + 001 0/ 52) : 0
- : : 0.0M *00- 0.00E +00 0. 00E + M- 0.00E
- 00 : 0.00E *00- 0.00E *00 '
l I ! FE-59 l 261 : 0.0 l 0.00E+00I 0/ 209) : l l . 0.00E *00t 0/ 51) : 0.00E+00( 0/ 52) ' 0 l l : 0.00E *00- 0.0M *00 0.0M *M-- 0.0M +00 : 0.00E*00 I
*.0M+00 :
C0 60 261 : 0.0 0.00E+001 0/ 209) : 0.00E*00t 0/ $11 : 0.00E*001 0/ 52,: 0
- : 0.00E + 00- 0.ME + 00 :
' 0.00E+00-- 0.00E+00 : 0.00E*00~ 0.ME+00 :
l l l ' l I : l IN-65 261 : 0.0 l 0.00E+001 0/ 209) l 0.00E +001 0/ 51' : 0.00E+00( 0/ $2) : 0
- 0.00D00- 0.ME+00 : 0.00D00~ 0.00D00 l 0.00D00~ 0.00E *00 '
l l l l
'I l :
- W145 261 l 0.0 l 0.00D001 0/ 209) : 0.00D00( 0/ 51) : 0.00D001 0/ 52) ' 0 l l l 0.00E+00- 0.ME+00 l 0.00D00~ 0.00E+00 l 0.00E*00 - 0.00E*00 l l l l l l l 1R-95 261 : 0.0 l 0.0M+00( 0/ 209) : 0.ME +001 0/ 5tl l 0.00D001 0/ 52) :
8- l l l 0.00D00 - 0.ME+M l 0.00D00-- 0.00D00 : 0.00D00~ 0.00D00 l 0 l l l l l l
- 1-131 260 l 7.0M-02 0.00D00( 0/ 208) : 0.00E*00( 0/ 51) : 0.00E *00f 0/ 52) : 0 5 l l
l l l 0.ME+M-- 0.00E*00 0.00D00-- 0.MD00 : 0.00D00~ 0.MD00 l l l l
- CS-134 261 5.0M-02 l 0.00D00( 0/ 209) : 0.00D001 0/ SI) : 0.%E *001 0/ 52) : 0
'5 .
0.00D 00-- 0.000 00 : 0.00E*M~ 0.00D00 l 0.00D00- 0.00E+00 . l l CS-132 261 6.00E-02 l 0.00D001 0/ 209) : 0.00D001 0/ Sin l 0.00E+001 0/ $2) . O
'I l l
- BALA-140 261 l l
l 0.0 l l 0.00E+00-- 0.00D00 l l 0.00D001 0/ 209) : l 0.00E+00-- 0.00E+M l 0.00D00-- 0.00D00 0.00D001 0/ 51) : 0.00D001 0/ 52) : 0 I :
- BETA l
l 0.00D 00~ 0.0M +00 : 261 l 1.00E 02 : 2.11E-02t 207/ 209) : 0.00D00-- 0.00D00
' 133 16.2 Mi NE) 0.00E +00-- 0.00E *00 l 2.16D021 52/ 53) l 2.15E 021 52/ 52) :
0
........l ................l .. .. . .. 3. 04 E 6.9 7E -023.04E-03--
l 5.09E-02 l 7.14E-03-- 3.79E-02 l Ie.. . based noon detectable seasurements..............................
.. range en and only Frattion of detectable seasurteents at scetified locations is indittitd in parentheses. (Frattion)
. E 're rea9' ia'itat's aa d'tertable acti it' >'**ats
- Ef LLD is ecual to 0. then LLD is not renuired 'ov Technical Soetifications The LLDs listed above are the va. lues freuired by Station 1 ethnical Soecilitations Location 120 = Site Boundarv 10.4 Mi NNE) location 133 = Corrielius. NC (6.2 Mi *El Location 121 = Site Boundary 10.5 Mi NE) location 134 = East Lintion Junior High School 19.7 Mi WWW) location 125 : Site Boundary 10.4 Mi SW) B-3
I I.3 DRictlNG WATER in+1 rot.nental Radiological Monitoring Progras $uasar? Doce ci Facility : Ps6vare Nutlear Station Dottet hueber : 50-369.370 Location et Facilstr : Mittlenburg County, n.t. Repertang Perayd i 1 JAN 199] through 31-MC-1991 I .....fjee Report 6tnerated 114 JAN-199213:33:32 Estabase kaer l
- ID!Sil s (L'$ER. A$C Ph591.5 AF:1 Location with Highest Mean ' he of I Redius or Pathue+
$aeoler
- 17De & Totti : Loser :
ht:6ber cf Analyses
- Laett of :
- Detection l Ai! It: citator locations Mean (Frattioni
- Lotetton hate. Distante and Direction ' Control Locations : Routier f.ean (Frattson) l Mean (Frattient hon.
' Pecort
- Ferforsed : (LLD) l Range Code Range tange ' meas.
I.......(Units) ...................................................-...........--.......---.....-------.....----........--------.------....... DRiesthG kATER l : ' l
- 136 112.5 Mi hh!) :
(FCl/LliERI l l l
- AhAL1-LL 31 : 1.0 0.00E+00( 0/ 261 : 0.00E + MI 0/ 13) : 0.0M + 001 0/ 131 l I3Letations : 0.00E +M-- 0.00E+00 0.00E+00- 0.00E+00 l 0.00E+00-- 0.00E*00 0
l l l l l AkAL2-LL 39
- 1.0 : 0.00E+001 0/ 26) : 0.0M
- 001 0/ 13) : 0.00E+001 0/ 131 l 0
- : : 0.0M +00-- 0.00E+00 :
0.0M+M-- 0.00E+00 0.0M*00- 0.00E+00 :
- : : l ; '
- m-54 39
- 15. : 0.ME + 00 f 0/ 261 : 0/ 13) : 0.00E+MI 0.00E +001 0/ 131 l 0 l E l : 0.00E*M-- 0.00E *00 : 0.00E
- M-- 3.00E
- 00 l 0.00E*00-- 0.00E*00 :
- : l l l l l CD-58 39 : 15. : 0.00E +001 0/ 261 l 0.00E*001 0/ 131 l 0.00E +001 0/ 13) : 0 0.ME+00-- 0.00E+00 0.00E*00~ 0.00E+00 l 0.00E +00-- 0.00E*00 l 0 l l l l l l l FE49 39 , 30. : 0.00E +001 0/ 26) : 0.00!*MI 0/ 13) : 0.0M *00( 0/ 13) : 0
- : : 0.00E+00-- 0.00E+00 : 0.ME+00- 0.00E *M 0.00E+00 - 0.00E*00 :
. : l l l l l CD-60 39 l 15. : 0.00E+001 0/ 26) : 0. 00E + 00( 0/ 13) : 0.ME *00( 0/ 13) : 0
- : : 0.00E+00 - 0.00E*00 l 0.00E+00-- 0.00E+M l 0.0M+00-- 0.0M60 :
I : IN-65 39 : 30. : 0.ME*001 0/ 26) : 0.00E *001 0/ 13) : 0.ME
- MI 0/ 13) :
0
- l l 0.00E*M-- 0.00E+00 : 0.00E+00- 0.00E+00 : 0.0M+00-- 0.00E+M :
'I l kB-95 39 l 15.
- 0.00E +001 0/ 26) :
; P 00E+00-- 0.00E+00 :
0.00E*001 0/ 13) : 0.00E+001 0/ 13) : 0 0.00E+00-- 0.0M*00 : 0.00E+M- 0.00E+00 :
- IR-95 39 : 15. : 0.0M+001 0/ 26) :
0.00E+001 0/ 13) : 0.00E+001 0/ 13) : 0
- 0.00E+M-- 0.0M*00 0.00E*00-- 0.00E +00 l 0.00E+00- 0.00E+00 .
- l l :
I l I-131 39 l 15. : 0.0M+00t 0/ 26) : 0.00E*001 0/ 13) : 0.00E+001 0/ 13) : 0
- : 0.00E+00-- 0.00E+00 : 0.00E*00-. 0.00E+00 : 0.00E*00- 0.00E*00 l l .,! .
l l M: I : CS 1?
- 15. ; s.00E+001 0/ 26) :
; 0.0M+00-- 0.00E*00 :
0.00E+001 0/ 131 l 0.00E+00( 0.00E*00-- 0.00E+00 0/ 131 : 0.00E+00-- 0.0M+00 0
.en and range based untr, a f < :e seasuresents only rattien of detectable seasurmts at sottified locations is indicated in carentheses. (Fraction) loro range indicates no detectable activity seesarements
! If LLD is toual to 0. then (to is trot reovired by itthnical Soetifications The LLDs listed above are the values receired by Station Technical Sectifications Location 02 f. 6 te Munitical Water Supplr 111.2 Mi $5!)
Location ID oc die Nnitical Water Supolt (12.5 Mi NME) Lotation 1 4 + E daunitical Water Suppli (7.5 Mi NE) B-4 5
I Entsroneental Radiological Constering Frograe Suenar, I Wase of Facilitt Location of Facilitt Tiet Report Generated : 14
- McGuire Nuclear Station Mettlenturg Countt. N.C.
Dottet husber 50-369.370 Reportino Ptraod : 1-JAh 1991 through 31-0EC-1991 Catabase Nase t IDISil:[ USER.ASCinhS91.SAFi l 3 I .. .................... Cedive or Troe 8 Total : Lo er
...... AllJIr.ditator l AN i f 92 13 : 3 3 : 32 l lstation =str. Highest F.ean '
No. of
- -----~.~~..-~~.--~~..-:
gen. Pathwar : busber of '
- Lisit ci Locations haer. Distante and Direttson Analyses Contro! Lotations : Routine S c led : ' Detettien : hean (Frattsoni : location nean (Frattson) : N an (Frattsoni ' Report tunits) : Perforced (LLD) : Range : Code Range : : Peas,
- ..............................................................................................................ge...................
Ran j ,l0RlWKINGkATER : : : : : ' WIPCl/LliER) ! '
- ' )
136 (12.5 Mr NhEl l l l CS-137 39 : 18. : 0.00E40f 0/ 26) : 0.00E+00f 0/ 13) : 0.00E+00f 0/ 13) : 0 ,
- : 0.00E40~ 0.00E+00 : 0.00E+00-- 0.00E+00 : 0.00E*00 - 0.00E*00 : I 13 Locations : : : : : :
BAL A-140 39 : !$. : 0.00E+001 0/ 26) : 0.00E40f 0/ 13) : 0.00E40f 0/ 13) : 0
- : : 0.00E*00-- 0.00E 40 : 0.00E+00-- 0.00D00 : 0.00E 40-- 0.00E+00
- l l l l 132 (11.2 Mi SSEl : ;
; BETA 39 : 4.0 l 2.3 f 24/ 26) : 2.4 1 12/ 13) : 2.5 i 13/ 13) : 0
- : 1.0 --
4.3 : 1.8 -- 3,0 ; 0.97 -. 6.4 :
- gWTRITIUM : : : : : ;
- m PCl/LITERI
- : : : : :
- : : : 142 17.5 Mi NC) ; ;
- H-3 12 l 2.00E+03 : 5.22E+021 2/ 8) : 5.22E+02f 2/ 4) : 0.00E*001 0/ 4) : 0 ILocations .
- 4.7BE+02-- 5.67E*02 : 4.7BE*02- 5.67E+02 : 0.00E+00 - 0.00E*00 :
enn a:d range based voon detettable seasuresents only rattien of detectable seasurteents at soetaffed locations is indicated in oarentheses. (Frattion)
.ere range indicates no detectable activity staturements If LLD is enval to 0, then LLD is not recuired by fethnical Soetifications he LLDs listed above are the valers reovired tv . Station iethnical Sortifications 132 = Charlotte thinicipal Water Supsir (!!.2 Mi SSE)
I 136 = Mooresville Nnicioal Water Seppir I!2.5 Mi NME) 142
- Davidson Municipal Water Sappir (7.5 Mi NE)
'I
- I-
!I
- g I
B-5 I
3.4 $URFACE WATER Environeental Radiological Monitsring Prograa Sunear, Maee et f acility : McGuire hotlear Station Dottet hunber I Location of Fatility : Mettlenburg County, N.C. 50-369.370 Reporting Period 1-JAN 1991 through 314EC-1991 Tier Report beterated : 14 JAh 19*? 13:33:32
- SelSti t t USER. ASC)RN591.SAF:1 lg.............................................................~Databasehaee
'g : : : totation eith highest Pean : : he, of Medius or Irpe & Total : Loser : All indicator -- ~ - ~ ~ ~-~---------- - --- '
; hen-Pathsa, l hwaber of
- Liait of : tctations : hase. Distante and Darettion : Control Locations : Routine Sasoled : Analyses : Ortettson : Reen (frattion) ' location mean (Frattion) : Mtan (Frattlon) ' Report (Units) : Performed * (LLD) : Range : Code Range Range
. Meas.
ISURfACE (Pfl/LliER) WATER ; ; ; 135 (12.0 ni N)
- AhAll-LL 39 : 1.0 0.00E*00( 0/ 26) : 0.00E
- 00( 01 13) : 0.00E+00( 0/ 13)
- 0 I 3 Losations : : 0.00E+00-- 0.00E*00 : 0.00E+00- 0.00E*00 0.00E+00- 0.00E*00 :
! ANAL 2 Li 39 : 1.0 : 0.00E
- 00( 0/ 26) : 0/ 13) : 0.00E*00(
0.00E+00( 0/ 13) : 0 0.00E*00~ 0.0M +00 0.00E*00-- 0.00E+00 : 0.00E+00 - 0.00E*00 :
; MM-54 39
- 15. : 0.00E+00( 0/ 26) : 0/ 13) : 0.00E+00(
I 0.00E*00( 0/ 13) : 0
- : : 0.00E+00-- 0.00E+M : 0.00E+00 ~ 0,00E+00 : 0.00E*00-- 0.00E+00 :
- CD 58 39 : 15. : 0.00E+00( 0/ 26) : 0.00E+00f 0/ 13) : 0.00E
- 00( 0/ 13) : 0
- I
- : :
0.00E*00- 0.00E+00 0.00E+00- 0.00E+00 : 0.00E+00- 0.00E+00 : FE-59 39 : 30. : 0.00E*00( 0/ 26) : 0/ 13) : 0.00E+00( 0.00E *00( 0/ 13) : 0 0.00E+00~ 0.00E+00 : 0.00E*00-- 0.00E+00 : 0.00E+00-- 0 30E+00 : !I : CD-60 39 :
- 0.00E *00( 0/ 26) :
0.00C+00( 01 13) : 0.00E*00( 0/ 13) : 0
- : 0.00E*00-- 0.0M+00 : 0.00E +00-- 0.00E *00 0.00E+00-- 0.00E+00 :
- R
- : : : : :
?W : Ik-65 39 : 30. : 0.00E+00( 61 26) : 0.00E *00( 0/ 13) : 0.ME+00( 0/ 13) : 0
- : : 0.00E*00-- 0.00E*00 : 0.00E+00-- 0.00E+00 : 0.00E+00-- 0.00E*00 l lg : : : :
g h!-95 39 : 15. : 0.00E+00( 0/ 26) : 0.00E+00( 0/ 13) : 0.00E*00( 0/ 13) : 0
- : 0.00E*00~ 0.00E+00 : 0.00E+00 ~ 0.00E+00 0.00E*00-- 0.00E+00 :
- IR-95 39 : 15. : 0.00E*00( 0/ 26) :
0.00E+00( 0/ 13) : 0.00E*00( 0/ 13) : 0
- : 0.00E+00-- 0.00E+00 : 0.00E+00-- 0.00E*00 : 0.00E+00 ~ 0.00E*00 :
I
- 1-131 39 : 15. : 0.00'+00( 0/ 26) : 0.00E+00( 0/ 13) : 0.00E+00( 0/ 13) : 0
. . 0.00E+00-- 0.00E+00 :
0.00E+00-- 0.00E+00 0.00E +00~ 0.00E+00 : CS-134 39 : : 0.00E*00( 0/ 26) :
'I 15.
0.00E*00( 0/ 13) : 0.0M *00( 0/ 13) : 0
- : 0.00E+00~ 0.00E+00 : 0.00E+00-- 0.00E*00 : 0.00E+00-- 0.00E*00 :
=
'hanacdrangebasedupondetectablemessarementsonly Wraction of detettable nessurements at specified locations is indicated in parentheses. (Fractioni fero range indicates no detectable activity seasurements LLD is roual to 0, then LLD is not required by Techr, ital Specifications LLh listed above are the values reovired tiv Station itthnical Specifications Location 128 Discharge Canal Eridge (0.1 Mi ENE) location 131 = Comans Ford Das (0.7 Mi W) location 135 Plant Marshall latake Canal (12.0 Mi N)
B6 I
I Environmental Radiological Monitoring Prograe Suasart Kaoe of Facilite : Mt6uire hurlear Station Dettet husber 1 50 369.370 Location of Facility : Mettlenburg Countr, k.C. Pecorting feriod : 1-JAh-1991 through 31 DEC-1991 14-JA8i-1992 13:33:32 Database W4 e : tDISil:! USER.ASC)MNS91.SAF:1 I....TimeReportGenerated
- : : Location eith Highest Mean : ho, of Medius.or Tree t ictal : Lower : All Infatator :----- --------- -----~ --------: : h on .
Pathma, : tueber of Li it of : Locatiens : hase. Distante and Direction : Control Locations ' Routine Saanled : Analeses lDe 'on : Mean (Frattlon) ' Location Mean (Frattion) : Mean fFrattson)
- Pecort lunits) : Perfereed : fLtc)
- Range Code Fange : Rar:ge Meas.
B SURFACE: WATER: : (PC1/ LITER) : : : : 135112.0 f's NI
, CS-l?7 39 : 18, l 0.00E+00f 0/ 261 : 0.00E+00( 0/ 13) : 0.00E+00f 0/ 13) : 0 I3 Locations
- : 0.00E+00 - 0.00E+M : 0. 00E +M - 0.00E +M : 0.00E+00-- 0. NE+00 '
- BALA 90 39 : 15. : 0.00E+00I 0/ 26) : 0.0^(+001 0/ 13) : 0.00E*00f O' 13) : 0
- : 0.ME+M-- 0.00E+00 : 0. 44 40-- 0.00E+00 : 0.00E*00- 0.00E+00 :
SW TRil!UM : : : : 129 ;0.4 Mt ENE) * (PCl/LliER) : H-3 12 l 2.00E+03 : 7.22E+021 4/ 01 7.53E+02( 3/ 4) : 0.00E+001 0/ 4) : I3 Locations : : : 4.03E+02-- 9.66E+02 : 4.63E+02 - 9.66E+02 : 0.00E+M- ..ME *00 : 0 Mean and range t'ased upon detectable seasurteents on' IFractionofdetectableseasurteentsatsortifiedlot.sionsisindicatedinparentheses.(Fraction) 2ero range indicates no detectable activity seasurements if LLD is coual to 0, then LLO is not reevired try Technical Soetifications The LLDs listed atieve are the values required by Station itthnical Specificattoes E Location 126 = Discharge Cerial Bridge 10.4 Mi ENE) location 131 = Comans Ford Das 10.7 fii W) location 135 : Plant Marshall Intate Canal 112.0 Mi N)
. I I
I I - I E .> I
B.5 Milt Environeental Radiological Monitoring Progroa Suenarv kase of Facility : McGujre Notlear $tation Dottet hveber 50-36).170 Location of Facility : mettlenburg County, N.C. Feoorting Period : 1.1H-1991 through 31-MC-1991 fine Feoort Generated : 14 19 92 13 : 33 : 32 Catatase hase : Silillt!!!SER. ASC)ntS91.5Af t1 I ..............~.............#N Pedius or
........~.............................................................................. ............
- Ivpe 4 icial : toetr l l
- All Indicator l Location eith Highest Pesh :
- ----------~~--~~------l
- ho, of gen.
I Patheaf Sasoled it) nits) h.aber of
- Performed
- Limit of Analv r,es : Detection (LLD) :
Locations Mean (Fractiou Range
..................................................................~......................................~...ge
- Nase. Distante and brettion '
l tocation
- Code Mean (Frattion)
R+nge Con rol Locations ! Routine Mean (fractatal Ran
' Secort
- Meas.
I nJLt (PCl/ LIT [R) : : :
- : 138 12.75 Mi ESE)
- EN-54 1H : 0.0 : 0.00E+001 0/ 81) : 0. 0M
- 00( 0/ 27) ' O.00E+00t 01 27) : 0 l : 0.00E+00~ 0.ME*00 : 0.00E*M~ 0.ME+M : 0.0M+00~ 0.00E*00 '
I4 Locations : '
- CD-58 108 : 0.0 0.ME
- 00( 0/ B1) : 0.00E +001 0/ 27) : 0.00E+001 0/ 27) : 0 l l l 0.ME+00~ 0.ME*00 : 0.00E +00-- 0.0M+M : 0.ME +00~ 0.00E+00 .
l l l FE-59 108 : 0.0 0.00E*001 01 81) : 0.00E+001 0/ 27) : 0.00E *00( 0/ 27) l 0
- : : 0.00E+M-- 0.00E *00 :
I :
- C0-60 108 l 0.0
- 0.00E +001 0/ B1) :
0.0M +00~ 0.00E
- 00 : 0.ME*00~ 0.00E+00 l
- 0. 00E +00(
01 27) : 0.ME+A 4 0/ 27) : 0
)
l l l 0.00E+00-- 0.0M*00 : 0.00E*00~ 3.00E+M : 0.00E*00~ 0.00E+00 : I : l IN-65 108 : 0.0 : 0.00E+001 0/ B1) :
- 0.00E *M-- 0.00E*00 l l l 0.00E+001 0/ 27) : 0.0M + 001 0/ 27) :
0.00E+00~ 0.00E*00 l 0.00E+00~ 0.ME*00 : l 0
- kB-95 1 08 : 0.0 0.00E*001 0/ 81) : 0.00E*001 0/ 27) l 0.00E*001 0/ 27) : 0
- : 0.00E*00-- 0.00E+00 0.00E+00~ 0.00E*00 l 0.0M+00~ 0.00E+00 l l l l l I
l l l IR 95 108 : 0.0 0.00E*001 0/ B1) : l 0.00E+001 0/ 27) : 0.00E*001 0/ 27) : 0 l l 0.0M+00-- 0.00E*00 : 0.00E+00-- 0.ME+00 : 0.0M *M-- 0.00E+00 : l l I : 1-131 l 108 l l
- 15. : 0.00E+001 0/ B1) :
l 0.00E+00 ~ 0.0M +00 :
- 0. 0M +001 0/ 27) l 0.00E +Mt 0.00E+00 ~ 0.00E+00 : 0.00E+00~ 0.ME+00 :
0/ 27) : 0 LL1-131 108 t' I 1.0 l 0.ME*001 0/ B1) : l 0.00E+00f 0/ 27) : 0.00E*001 0/ 27) : 0
- 0.00E*00~ 0.00E+00 : 0.M+04- 0.0M +00 : 0.ME*00~ 0.0M*00 :
- : : : l l CS 134 108l 15. : 0.00E+001 0/ 81) : 0,00E+001 0/ 27) : 0.ME+001 0/ 27) :
I l l CS-137 108 l l 18. l 0.ME+M-- 0.00E*00 :
- 0.00E+001 0/ 81) :
v.00E+M-- 0.0M+00 l 0.00E+M- 0.00E+00 :
- l 0
0.00E*00( 0/ 271 l 0.ME +MI 0/ 271 : 0 I : ; l 0.00E*00~ 0.0M+00 l 0.00E*M-- 0.00E+00 l 0.00E* 00~ 0.0M +00
, i : : l l l BALA 140 108 l 15. l 0.ME*00( 0/ 81) : 0.0pi+001 0/ 27) : 0.00E*00(
l l 0/ 27) : 0 l 0.00E+M- 0.00E+00 : 0.00E*00~ 0.00E*00 : 0.00E+M- 0.ME*00 : an and range based upon detectable menurteents on!v Fraction of detectable acasurteents at specified locations is indicated in parentheses. (Fraction) BroLLD range indicates no detectable activitt seasurewets is coual to 0. then LLD is not reovired by Technical Specifications The LLDs listed abovt are the values reewared by Station fathnical Soetifications Location 138 = Hent, Coot Dair, 12.75 Ri ESE) Location 140 = ti6d Cairt - COWS 12.8 Ri SSEl Latation 139 = Willf as Coot Cairy 12.6 Ri El Location 141 Lynth Dairy - CDt$ (14.8 Mi WNW) I 88 I l
l.6 BROADLEAF VECETAT10m Emirnnsental Raniological Monitor r.a Progras Suseart I hase of Facility : McGuire Nelear Station Location of Facility : Mettl e bur 0 Countr, N.C.
% e Report Benerated 14 JAN-It92 13:13:32 Dorset hunter 50-369.370 Reporting Perand : 1 JAh-It91 through 31-tEC-1991 tatabase Naer r
i Ol$tliltfSER.ASC)MNS91.SAFil
- l l l Location with Highest Mean ' he. of Medits or : Tree 4 lotal : LP er : All incitator :---------- ~ ~ ~ --------- -----: : hen-Pathwer : hunber of l Liait at : Locatior s : haar. Dattante and D2rettice l Ctmtrol locations
- 80 utee II $assied (Units) l Analyses : Detett20n
- Periorsed : f LL" :
Mean (Frattioni bnge
- totation Eofe Mean (Tract)on)
Range nean (Frattioni Pange
- Reoert
' Meas.
IBROAD LEAF VEGET : IPC1/ WET /tG) l : : : 134 18.7 Mi ths) l l l 15S 15.0 Mi NNEl : :
- MN 54 48 : 0.0 l 9.5 1 1/ 36) : 9.5 ( 1/ 12) : 0.00E+00t 0/ 121 : 0 ItLocations: l l 9.5 --
9.5 : 9.5 - 9.5 : 0.00E+M- 0.00E+00 :
- CD-58 48 ' O.0 0.00E+00( 0/ 36) : 0.00E+00f 0/ 121 l 0.00E+MI 0/ 121 l 0 l l l 0.00E +00-- 0.0M+00 : 0.00E*00-- C.00E+00 l 0.00E+00-- 0.00E+00 :
l l l l l l l FE-59 48 : 0.0 0.0M *001 0/ 36) : 0.00E*001 0/ 12) : 0.00E+00f nl 12) : I 0
- l l 0.00E+00-- 0.00E+00 l 0.ME+00-- 0.ME +M l 0.00E + 00- 0 ME
- H :
l l l l l l l CD-60 48 l 0.0 0.00E+001 0/ 341 l 0.00E+001 0/ 12) : 0.00E+001 0/ 12) 0 I :
- IN-65 48 l 0.0 l 0.ME
- 00-- 0.ME +00 l
- 0.ME + 001 01 36) :
0.00E*00- 0.00E+00 l 0.00E*00-- 0.00E+00 : 0.00E + 00( 0/ 121 l 0.00E+001 01 12) : 0 l l l 0.00E+M- 0.00E+00 0.00E*00-- 0.00E+00 : 0.00E +00-- 0.00E +00 l l l l l l l l ha-95 48 l 0.0 : 0.00E+001 0/ 361 : 0.00E*00( 0/ 121 : 0.00E*00f 0/ 12) : 0
- : : 0.00E+00- 0.ME*00 l 0.0M*00- 0.ME+00 l 0.00E+00-- 0.00E+00 :
I l IR-95 l 48 l l 0.0 l l 0.00E+001 0/ 361 : l 1.00E+00-- 0.00E+00 : l 0.00E+001 0.00E*00-- 0.00E+00 l 0/ 12) : 0.00E*0' l 0/ 12) : 0.ME+% ; 0
- 0. M.
l l l l l l t
-I l l 131 48 60. : 0.00f+00( 0/ 36): 0.00E+001 0/ 12) : 0.wE +v01 0/ 12) : 0 l l l 0.00E*00-- 0.00E+00 0.00E*00 - 0.00E+00 l 0.00t +00- 0.ME+00 l
!C5134 48 h 60. h0.ME+001 0/ 361h 0.e,I*001 0/ 121 h 0.0M*00101 121h 0
- l l 0.00E+00 - 0.00E*00 : 0.00E*00- 0.00E+M 0.00E+00-- 0.00E+00 l l l l l 125 10.4 Ri SV) :
I l l CS-137 41 ! l E0. l 33. 33. I 11 361
- 33. l l
33. 33. I 1/ 12) : 0.00E+001 01 12) :
- 33. l 0.00E+00-- 0.ME +00 l 0
I l 84LA 140 48 : 0.0 0.00E*00( 0/ 36) : 0.0M *00-- 0.00E*00 0.00E+001 0/ 12) : 0.00E+MI 0.0M +00-- 0.00E*00 : 0.00E+00 - 0.00E*00 0/ 12) : 0 an and range based uoan detectable seaserteents only action of detirttable nessurteents at sortified locations is indicated in parentheses. (Frattion) to range indicates no detettable attivity ne61urteents 11 LtD is ecual to 0, then LLD is not reevired by Technical Soetificatiens LLDs listed above are the values reevired by Station 1 ethnical Soetifications location !?0 = S2te Boundary 10.4 Ri NME) Location 125 = Site Boundary 10.4 Mi SW) location 134
- East lintcln Junior High Schocl 18.7 Mi WhW)
Location 158 = 4 $ Rile Radius (5.0 Mi NMEl B-9
8.7, $HORELINE SEDIMENT favaronmental Radiological Monitorine Progras Ssesar, , I case of Facility Location of Facilitr i ntSuire Nuclear Station nettlenburg Counts. N.C. line Report Benerated i 14 JAN 199213:33:32 Dociet Number i 50 369.370 Risorting Period : 1-J At-1991 0 ; ugh 31-DEC 1"1 tatabase Nant 'IDl$t1?!LSER.ASC)%kS91.5AF:1 I Mefius or
- Tree 4 Total : Loner
- All ladatator
- tecatjor, eith Hjahrst Mean :
I he. et l han. I Patheat : hunt.er of : Lielt of l
- Locations '
Sasoled Analyses hase. Distante a.e Direttion l Control Locat' ens : Ecuttne
- : Detettion : Mean (Frattions : it ation Mean (Frattion) : Mean IFrattaon) : Report it) nits) l rerferard l ILLD) : Range Coce Range '
Range : Prag. i lSEDlMENT l l l l . ; sa (PCl/0Ry/tB) l l l l l 137 112.0 Mi N) :
- 129 (0.6 Mi ENE) : :
- MM-54 6l 0.0 l 28. I 1/ 4) : 26. I 1/ 2) : 0.00E +001 I S Locations : : : 28. -
- 29. ; 28. -
20. 0/ 2) :
- 0.00E+00-- 0.MD00 l 0
- l l l 129 : .
- C0-58 6: 0.0 : 53. 2/ 41 l I 53. I 2/ 2) : 0.00E+001 0/ 2) : 0
'3.
B3. l 23. -
- 83. : 0.00D00- 0.00E*00 :
FE-59 6: 0.0 0.00E+001 0/ 4) : 0.00D001 0/ 2) : 0.ME +001 0/ 2) : I : CD 60 6: l 0.0 l 0.00DH- 0.00D00 l 1.31D021 2/ 4) : 129 0.00D00- 0.00D00 l 0.00D00- 0.00D00 : 0 4 1.31E+021 2/ 2) : 0.00D001 0/ 21 : I 0
- : 93. -- 1.70D02 l 93. -- 1.70D 02 l 0.00E+ % 0.00D 00 :
- : l l l l In 65 6: 0.0 l 0.00DMI 01 4) :
0.00D001 0/ 2) : 0.00E*001 0/ 2) : 0 l l 0.00E+M-- 0.ME 00 0.00DM-- 0.0CD00 : 0.00DM- 0.00E+00 : I- : l NH-95 6l 0.0 0.ME+001 0/ 4) : 0.00D001 01 2) : 0.MD001 0/ 2) : 0 l l l 0.00000-- 0.MD00 ; I :
! IR-95 6l 0.0 0.00E *001 01 4) :
l 0.00E* M-- 0.00E+ M l 0.MDM-- 0.00D00 l 0.00D00- 0.00E+00 : 0.MD001 0/ 21 l 0.00D001 0/ 2) : 0 0.00E+M-- 0.00000 : 0.00D00-- 0.00D00 l I !
- 1-131 6l 0.0
- 0.00D001 01 4) :
'. J.00E*00-- 0.00E+00 :
0.00D001 0/ 21 l 0.00E+001 0,00D 00-- 0.000 00 0/ 2) : 0.00DM-- 0.00D00 : 0 I l l l l l l CS-134 6: 1.50E+02 i 0.00D001 01 4) : 0.00D001 01 2) : 0.00E+001 0/ 21 l 0
! 0.00E*M- 0.00E+00 : 0.MD00- 0.00E*00 ; 0.00DM-- 0,ME+00 l l l 130 10.6 Mi SW) '
I : = l CS-137 6l 1.90E+02 l 2B. I 4/ 4) : 1.03E+021 2/ 2) : 0.000001 0/ 2) : 0
- 37. -- 1.04E*02 l 1.03D02- 1.04E+02 : 0.00D00-- 0.00D00 l l l l l l I : BALA-140 6:
0.0 l 0.00D001 0/ 4) : 0.00E+00- 0.00D00 : 0.00D001 0/ 2) : 0.00E+001 0/ 21 : 0.00D 00-- 0.00E+00 : 0.00DM-- 0.ME+M l 0 an and range based upon detectal,lr measurteents only rattian of detectable measurestets at scetified locations is indicated in sarentheses, IFraction) era range indicates no detrttable activity measurements if LLD is ecual to 0, then LLD is not reouired by Technical Specifications he LLDs listed above are the values rtovired by Station Technical Soetifications Location 129 Distharge Canal Entrance to take horaan 10.6 Ri ENE)
.I Location 130 s Highway 73 Bridge Downstreaa 10.6 Mi SW)
Location 13; e Pinnacle Actess Area (12.0 Ri NI
9.6 FISH Esvironmental Radiologirol Monitore.e Progran Sweaary haae et facility stSuire Nuclear Station Dettet husber i 50-369.370 Location of Facilitt : nettlenburg County, k.C. Re:orting Feriod : 1-JAh-1991 through 31-DEE-1991 k ..... Time Report Eenerated i 14-JAN-199213:33:32 Database Name : SD15ti (USER. ASC)MNS91.SAF:1 l l Location eith Highest Mean l Medius or l Iver & Total : Lorer ' ho. ci { : A!] Indicator l*-- --- ----- -----*--- - - --- Pathsay l hon-Naaber of : Limit of I .'.....it) nits).......................... l Sanoled : Analyses
- Performed :
- Detection l (LLD) l Locations Mean (Fraction)
Range
- hane. Distante and Direction l
- Location
! Eoce Mean (Frattion)
Range
...................................................................-.. ~ .......ge Controllocations
- Routine Mean (Frattion)
Ran
' Reoort
' meas.
FISH : l l l : tPCl/WE1/tB) : l l ' l 137 (12.0 Ni N) l l : l 129 (0.6 Mi ENE) l l 2 Locations : MM-54 12 : 1.30E*02 : 6.2 ( 1/ 6) : 6.2 1 1/ 6) : 0.00E+00( 0/ 6) : 0
- : 6.2 --
6.2 6.2 -- 6.2 : 0.ME+00- 0.00E +00 l l l l 129 l l lC0-50 12 ' 1.. n2 l 14. I 1/ 6) : 14 ( 1/ 6) : 0.00E+00( 0/ 6) : 0 l l 14. -- 14 14. -- 14. l
- 0.0CE+00-- 0.00f+00 l l l l l l lFE-59 12 l 2.60E+02 0.0M
- 00( 0/ 6) l 0.00E+00( 0/ 6) l 0.00E+001 0/ 6) : 0 l l 0.00E +00- 0.0M *00 0.0M+00- 0.00E*00 0.00E+00-- 0. ME*00 :
- : : 129 : :
- CD-60 12 1.30E*02 : 65. I 1/ 6) : 65. I 1/ 61 l 0.00E+001 01 6) : 0
- ; 65. --
- 65. l 65. -- 65. 0.00E*00-- 0.00E+00 :
- : : : : l l IN-65 12 l 2.60E*02 0.00E *001 01 6) : 0.00E+001 0/ 6) : 0.00E+00( 0/ 6) : 0 l l 0.00E+00- 0.00E*00 0.00E+00-- 0.00E*00 0.00E +00-- 0.00E +00 :
- : : 129 : :
NE-95 12 : 0.0 l 3,5 ( ll 6) : 3.5 ( ll 6) : 0.00E*001 0/ 61 : 0
- : 3.5 -- 3.5 *
+b -- 3.5 : 0.00E+00-- 0.00E+00 :
- : l l l l 2R-95 12 : 0.0 l 0.00E+00( 0/ 6) :
0.00E+001 0/ 6) : 0.0M*001 01 6) : 0 0.0M*00-- 0.00E+00 0.00E+00 - 0.00E*00 l 0.00E*00-- 0.00E+00 : l l l l l ll-131 12 l 0.0 0.00E+001 01 6) : 0.00E+001 0/ 6) : 0.00E+001 0/ 6) : 0
- 0. A '00- 0.0M +00 0.00E+00-- 0.00E*00 l 0.00E*00- 0.00E+00 l l l l l 129 l l CS-134 12 : 1.30E+02 : 5.9 f 8* ^) : 5.9 ( 1/ 6) l 0.0M + 001 0/ 6) : 0
- 5.9 h,i : 5.9 --
5.9 l l 0.00E+00-- 0.00E*00 l l l l ?? l l l CS-137 12 1.50Ed2l 26. I 6/ H: 26. I 6/ 61 l 0.00E*00( 0/ 6) : 0
- : : 11. --
- 45. I 11. -
- 45. : 0.cM *00-- 0.00E+00 :
BALA-140 12 0.0 : 0.00E+001 0/ Ml 0.ME+MI
; l 0/ 6) : 0.00E+00( 01 6) : 0 l 0.00E+00-- 0.00E+M : 0.00E+00-- 0.00E+00 0.00E+00-- 0.0M+00 l aan and range based upon detettalle seasurements only action of detectable seaswesents at specified locations is imitated in carentheses, (Fractioni ro range indicates no detectable attavity seasureaeots 11 LLD is toual to 0, then LLD is not reonired by Techn. cal Specifications e LLDs listed above a;e the values reonired by Station 1 ethnical Spet'fications location 129 = Discharge Canal Entrante to Late Norman (u.6 Mi ENE) location 137 = Pinnacle Acetts Area 112.0 Ri N) 8-11
lI B.9 slEEtt SAMMA RADIAllCO Environnental Radioltrgical Moni *.ing Frogran Sueeary Name of facility : McGuire Nuclear Station Lottet Number i 50-369.370 I .................................................................................................................................... Location c.f Facility : Mettlenburg County, N.C. Time Recort Generated 21-JAN 1992 16:09:49 Reporting Period : 1-JAN-1991 through 31-DEC 1991 Datatate Naee : SDlSrl:(USER.Ast)*NS91.SAFil l l l l Location eith Highest =ean ho, of iI Medius or Fathuay
- Tree & Total Loser l All Indicator :---- ------------------------- * '
Non. f Nunber of L2 sit 01 : Locations ; hase. Distance and Direction l Control totations : Routarie l Sansled : Analyses : Detett2Da l Mean (Fraction) ' Location %.n (Frac tion) : Frport
- Mean (Frattson)
(Units) : Ferformed l (LLD) l Range : Code Range : Range ' Peas. t I BIRECT RO-TLD l : jleR/03arter) l l l l l 175 (12.7 M2 DNW) l l3 : : : : 180 (11.5 M2 NNE) ' 43 Locations l aR/0tr 170 : 0.00E+00 l 14. I 166/ 166) : 24 ( 4/ 4) : 17 ( 4/ 4) ' 0
- l ; 6.0 -- 31. : 16. --
- 31. : 12. -- 23. :
I........ = .......... ...................................................................................................... Mean and range based upon dettttable seasurteents only Frattion 01 detectable seasurements at speti12rd letations is indicated in cerentheses. (Fraction) Blerorangeindicatesnodetectableattivityseasurteents if LLD is toual to 0, then LLD is not recuired by lechnical Specifications I I 143 = Site Boundary (0.3 Mi NW) 163 = 4-5 Mile Radius (5.0 Mi SE) ist = Site Boundary (0.4 Mj WE) 164 = 4-5 Mile Radius (4.5 Mi SSE) b) = Site Boundary (0.5 Mi HE) 165 = 4-5 Mile Radius (5.0 h1 S) 2s = Site Boundary (0.5 Mi ENE) 166 = 4-5 Mile Radius (5.2 Mi SSW) I H = Site Boundary (0.4 Mi E) P = Site laundary (0.5 Mi ESE1 i4 s Site Boundarv (0.6 Mi SE) 167 = 4-5 Mile Radius (4.9 Mi SW) 168 = 4-5 Mile Radius (4.7 Mi WSW) 169 = 4 5 Mile Radius (4.4 Mi W) I 6 = Site Boundary (0.5 Mi SE) 251 = Site Boundary (0.4 Mi S) 152 = Site Boundary (0.5 Mi SSW) 170 = 4 5 Mile Radius (4.5 M2 kNW) 171 = 4-5 Mile Radius (4.5 Mi NW; 172 = 4-5 Mile Radius (5.2 Mi NNW) 153 = Site Boundary (0.5 Mi SW) 173 = Sortial laterest (8.5 Mi NNW) 154 = Site Boundarr (0.5 Ri W) 174 = Special laterest (B.7 M2 nW) 155 = Site Boundary (0.5 Mi WNW) 175 = CONTRDL (12.7 Mi WW) 156 = Site Bour.dary (0.5 Mi nW) 176 = Scetial interest *11.0 Mi SW) I 157 = 4-5 Mile Radius (4.9 Mi N) 150 = 4-5 Mile Radius (4.4 Mi KNE) 159 = 4-5 Mile Radius (5.0 Mi NE) 177 = Special Interest (8.6 Mi S) 178 = Scecial Interest (9.2 Mi SE) 179 = Special laterest (10.4 Mi ESE) I 160 = 4-5 Mile Radius (4.9 Mi ENE) 161 = 4-5 Mile Radius (4.7 Mi El 162 = 4-5 Mile Radius (4.6 Mi ESE) 150 = Sortial Interest (!!.5 Mi HE) 181 = Special interest (6.7 Mi NE) 182 = Special interest (6.0 Mi hE) I 183 = Seccial Interest (5.5 Mi S) 186 = Soetial laterest (0.2 Mi NNW) 187 = Special Interest (0.3 Mi N)
.I g.12 I
8.10 FOOD PRO M IS (CROPS) Environmental Radiological Monitoring Progree Suenarv Nant of facility : McGuire Nuclear Station Dociet Number : 50-369.370 Location of Facility : Mecklenburg County, k-C. Reporting Period 1 . LAM 1991 threugh 31 DEC-1991 time Report Generated : 14 JAN-199213:33:32 Database hane : lDISti:(USie.ASC]MNS91.SAf1 I t
- l l : Location with Highest Mean : ' he, of Medius or : Type & Total : Loser All Indicator l------------------------ ; hon.
I Pathear Sanoted
-(Units) l Number of
- Performed l (LLD) l Lisit of l Analyses : Dettelion :
' Loc ations Mean (Fractioni Range
- Name. Distante and Direction ' Control Locations l Routine
- Location Code mean (fractioni Range Mean (Frattion)
Range
' Heoort
' Meas.
l lpps (PCl/ WET /I61 l l l : : ' ')- l l l
- ho Eontrol locations
- l l l
I '""' : ""~ : ' ' 0. 00E + 00-- 0. 00E +00 : 0.00E+00-- 0.ME +00 : 0.00E+00-- 0.00E+00 :
' CD-58 17 : 0.0 : 0.00E+001 0/ 17) : 0.00E*00: 0/ 71 : 0.00E+00f 0/ 01 :
I- l l l 0.00E+00 - 0.00E+00 : l 0.00E+00-- 0.00E+0a : 0.00E*00-- 0.00E+00 : 0 l l l FE-59 17 : 0.0 l 0.00E*00( 0/ 17) : 9 I :
- CD-60 17 l l
0.0 l 0.00E+00~ 0.00E+00 l l 0.00E+001 0/ 7) : 0.00E+001 0.0M+00- 0.00E+00 l 0.00E+00- 0.00E+00 : l 0/ 01 : l 0 0.00E*001 0/ 17) : 0.00E+001 0/ 7) : 0.00E+001 I 0/ 0) : 0
- l l 0.0M+00- 0.00E+00 l 0.0M+00-- 0.0M*00 : 0.00E+00- 0.00E+00 :
? l l l l l l In-65 17 : 0.0 1 0.00E+00t 0/ 17) : 0.0M *001 0/ 7) : 0.00E+001 0/ of l 0 I Na-95 17 :
0.0 0.00E+00-- 0.0M*00 : 0.ME *001 0/ 17) : 0.00E+M-- 0.0M+00 : 0.00E*00-- 0.00E+00 : 0.00E*001 0/ 7) : 0.00E+001 0/ 01 : 0 l l l 0.00E+00-- 0.00E+00 : I : l 1R-95 17 l 0.0 l
- 0.00E+001 0/ 17) :
l 0.00E+M-- 0.0M +00 : 0.00E+001 l 0.0M+M-- 0.00E+00 : 0/ 7) l 0.00E +001 0/ 01 : l 0
- 0.00E+00 - 0.00E+00 : 0.0M+00-- 0.00E*00 l 0.00E+00-- 0.00E+00 l I ll-131 17 :
60. l 0.00E+001 01 17) :
- 0.00E+00-- 0.00E+00 :
l 0.00E+00( l 0/ 7) : 0.00E*00f 0.00E+00 - 0.00E+00 : 0.00E+00-- 0.00E*00 : 0/ 01 : l 0 I
- : : l l l l CS-134 17 60. : 0.00E*001 0/ 17) l l
0.00E*001 0/ 7) : 0.00900( 0/ 0) : 0 l 0.00E+W-+ 0.00E*00 : 0.00EvM-- 0.00E+00 0.00E+00-- 0.00E+00 l l l l l l :
-l l C5-137 17 l 90. : 0.00E+00( 0/ 17) :
W 0.00E+001 0/ 7) 0.00E +001 0/ 01 0 l l l 0.C0E+00-- 0.00E+00 : 0.00E+00-- 0.00E+00 : 0.00E+00-- 0.00E+00 l l l l l l l I_ .. l BALA-140 17 . 0.0 ! 6.00E+001 0! 17) :
- 0.Ml +00 0.00E*00 :
0.00E+001 0/ 7) : 0.0M+001 0.00E+00 0.00E*00 0.00
.....................E+00--
0/ 01 : 0.00E+00 l 0 an and range based upon ettertable seasureeents only sction of detectable acasurements at specified legations is indicated in carentheses. (Frattion) ro range indicates no detectable activity measurements 11 LLD is couz) to 0. then LLD is not reovired by Technical Specifications LLDs listed above are the values recuired by Station Technical Specifications Location 184 = 5 alle radius 12.5 Mi ENE) - Gardens (Davenport's Residentel I Location 185 = 5 mile radius 14.9 Mi N) - Gardens (Brewer's Residence) Location 188 = 5 mile radius 12.8 fli N1 - Gardens (Autsin's Residente) B 13
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I APPENDIX C I I ^I SAMPLING I DEVIATIONS AND I UNAVAlLABLE l ANALYSES I I I I ~I . .I L I LI c.1
I g; APPENDIX C SAMPLING DEVIATIONS AND UNAVAILABLE ANALYSES
- 1. SAMPLING DEVIATIONS The following deviations from sampling requirements occurred during 1991:
g A. AlRBORNE RADIOlODINES AND PARTICULATES I 1. Incation #134,1/8/91 to 1/15/91 I R2ason: Due to power having been cut off at the breaker box, the sampler ran only 124.3 hours out of a normal 168 hour sampling period. Action: Power was resto1+d and sampler was restarted. Actual sampling period was 1/8/91 @ 10:45 to 1/15/91 @ 15:03.
- 2. Location #133,1/15/91 to 1/22/91 Reason: Due to part of the filter not covering the full center of the sample I head, air was able te pass through unfiltered, reducing the CPM and Net Weight (mg) which may have affected the analysis. The sampler ran 167.1 hours out of a normal 168 hour sampling period.
Action: Filter and cartridge were changed for new sampling period. All LLD's were met. No nuclides were found on the cartridge attributed to having missed the filter. Actual sampling period was 1/15/91 @ 08:54. to I 1/22/91 0 08:53.
- 3. Location #134, 3/12/91 to 3/19/91 Reason: Due to the power to the sampler being turned off by vandals, the sampler ran for only 102.5 hours out of a normal 168 hour sampling period.
Action: Restored power and used a tie-wrap to secure breaker box lever in stationary position. Actual sampling period was 3/12/91 @ 11:32 to 3/16/91 @ 18:02.
- 4. Location #133, 5/7/91 to 5/14/91 Reason: Due to the plug having been disconnected, the sampler only ran 23.7 hours out of a normal 168 hour sampling period.
.I Action: Plugged in sampler and secured it with a tie-wrap. Actual sampling period was 5/7/91012:28 to 5/8/91012:10. C-2
- 5. Location #120, 5/14/91 to 5/21/91 Reason: Due to an apparent power failure during the sampling period , the I' sampler only ran 84.8 hours out of a normal 168 hour sampling period. The sampler was running at the time of collection.
I Action: Collected p&C and restarted sampler. Actual sampling period was 5/14/01014:38 to 5/21/91 @ 14:38. I 6. Location #120, 5/28/91 to 6/4/91 I Reason: Due to a blown fuse, sampler only ran 142.5 hours out of a normal 168 hour sampling period. I Action: Replaced fuse and restarted sampler. Actual sampling period was 5/28/91 @l4:40 to 6/3/91013:10. I 7. Location #120,10/8/91 to 10/15/91 I Reason: Due to a blown fuse, the sampler only ran for 11.9 hours out of a normal 168 hour sampling period. g Action: Replaced fuse and restarted sampler. Actual sampling period was g 10/8/91 @11:25 to 10/8/9123:15.
- 8. Location #120,10/15/91 to 10/22/91 I Reason: Due to a blown fuse, the sampler only ran for 85.2 hours out of a normal 168 hour sampling period.
I Action: Replaced fuse and restarted sampler. Actual sampling period was 10/15/91 @l5:02 to 10/19/910 04:14. I 9. Location #133,10/29/91 to 11/5/91 Reason: Particulate from recent forest fires clogged the particulate filter, preventing air flow and causing the pump to overheat and malfunction. Also, the actual run time was not available due to an inoperable timer on I the air sampler. A calculated run time was estimated to be 17.78 hours out of a normal 168 hour sampilng period. Action: Collected sample and replaced sampler. Actual sampling period was calculated to be 10/29/910 09:22 to 10/30/91003:09. I l C-3 o
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- 19. Location #12511/5/91 to 11/12/91 Reason: In order to prevent the air sampler pumps from forest fire I' damage, the Radeco samplers were checked after 2.69 days for flow rate.
The sampler only ran 64.4 hours out of a normal 168 hour sampling period. I Action: Cellected particulate and charcoal after 2.69 days. sampling period was 11/5/91 @ 15:50 to 11/8/91 @08:17. Actual
- 11. Location #12511/5/91 to 11/12/91 Reason: In order to prevent the air sampler pumps from forest fire damage, the Radeco samplers were checked after four (4) days for flow rate. Sampler only ran 97.0 hours out of a normal 168 hour sampung period .
Action: Collected particulate and charcoal after 4.04 days and replaced with new particulate and charcoal. Actual sampling period was 11/8/91 @ 08:18 to 11/12/91 @ 09:18. l
- 12. Location #133,11/5/91 to 11/12/91 Reason: In cedor to prevent the air sampler pumps from forest fire damage, the Radeco samplers were checked after 2.8 days for flow rate.
Sampler ran for only 67.3 hours out of a normal 168 hour sampling period. Action: Collected particulate and charcoal after 2.8 days. Actual sampling period was 11/5/91 @ 14:08 to 11/8/91 @09:28. I
- 13. Location #133,11/5/91 to 11/12/91 Reason : In order to prevent the air sampler pumps from forest fire damage, this sample was collected after running only 3.95 days (94.8 hours).
Action: Collected sample earlier than normal. Actual sampling period was 11/8/91009:30 to 11/12/9108:19. I B. SURFACE WATER
- 1. Location #128, 2/5/91 to 2/19/91 Reason: Due to a malfunctioning pump, a full composite sample was unavailable. ,
Action: MNS personnel were notified for corrective maintenance. An abbreviated sample was collected. Actual sampling period 2/5/91 @ 12:00 to 2/19/91 @l4:50. I C-4
- 2. Location #128, 2/19/91 to 3/5/91 Reason: Due to a malfunctioning pump, no composite sample was available.
I Action: MNS personnel were notified for corrective maintenance. A " grab" sample was collected., Actual sampling period 3/5/91 0 14:30.
- 3. Location #128, 3/5/91 to 3/19/91 Reason: Due to a broken intake line, the sampler did not run for the full sampling period. A full composite was unavailable.
Action: Appropriate personnel were notified for repairs. An abbreviated sample was collected. Actual sampilng period was 3/7/91010:45 to 3/19/91 014:50.
- 4. Location #128, 3/19/91 to 4/2/91 Reason: Due to a clogged intake line, no composite sample was available.
Action: Technical Services were notified for repair. An abbreviated sample was collected. Actual sampling period was 3/19/91014:50 to 4/2/91 0 13:45.
- 5. Locatiou #128, 4/2/91 to 4/16/91 Reason: Due to a malfunctioning pump, a full composite sample was not available.
Action: Pump was repaired. An abbreviated sample was collected. Actual sampling period was 4/9/91013:20 to 4/16/91014:30.
- 6. Location #128, 6/11/91 to G/25/91 Reason: Due to main feed line being redirected. a full composite sample was not available.
Action: An abbreviated sample was collected. Actual sampling period was 6/13/91013:00 to 6/25/91013:30. I E I c-5
C. DRINKING WATER
- 1. Iocation #132,1/8/91 to 1/22/91 Reason: Due to water sample being drawn from a " dead water leg", no composite sample was available. It was determined that the composite sampler was not providing a representative sample due to periodic interruption of flow, due to pump location.
Action: Composite sampier was relocated. A " grab" sample was collected I from the new location after the intake line was purged. Actual sampling period was 1/22/91 @ 11:00.
- 2. Location #132,1/22/91 to 2/5/91
, Reason. Due to the water sampler being moved, a full ecmposite sample was not available.
- i. tion: An abbreviated sample was collected. Actual sampling period was
, 1/25/91014:00 to 2/5/91011:25.
- 3. Location #13G, 3/19/91 to 4/2/91 I Reason: Due to a reduction of water flow, there was not enough pressure to operate the solenoid. No composite sample was available.
' Action : Water flow was increased and a " grub" sample was collected.
Actual sampling period was 4/2/91 @ 09:35. I 4. Incation #142, 3/19/91 to 4/2/91 I Reason: Due to the water flow being reduced in the sample line, there was no composite sawple available.
'g Action: Water flow was increased. A " grab" sample was collected. Actual 3 sampling period was 4/2/91 @ 09:05.
- 5. Location #136, 4/2/91 to 4/16/91 Reason: Due to a lack of water flow in the lines, no composite sample available.
Action: Water flow was increased. A " grab" sample was collected. Actual sampling period was 4/16/91 @ 09:40.
- 6. Location #142, 4/2/91 to 4/16/91 Reason: Due to a lack of water flow, no composite was available.
I Action: Water flow was increased. A " grab" sample was collected. Actual sampling period was 4/16/910 09:15. C-6
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- 7. Location #142, 4/30/91 to 5/14/91 Reason. Due to a lack of water pressure, no composite sample was available.
Action: Water flow was adjusted. A " grab" sample was collected. Actual sampling period was 5/14/91 0 09:00. 4
- 8. Location #136,11/12/91 to 11/26/91 Reason: Due to water supply valve having been cut off by pN.t 3
. personnel, no composite sample was available.
Action: Water supply was turned on and a " grab" ssmple was collected. Actual sampling period was 11/26/91 @ 03:15. D. DIRECT G AMMA RADIATION (TLD) l
, 1. Location #166, 9/5/91 to 12/5/91
, Reason: TLD was not in the field for the entire 4th quarter. TLD was found on the ground 'oy Riverbend Plant personnel and turned into the Laboratory. Action: A new TLD was placed in the field. Actual sampling period was I 9/5/91 to 10/17/91 and 10/18/91 to 12/5/91. 1
- 2. Location #178, 9/5/91 to 12/5/91 Reason: TLD was found to be missing on 11/5/91 due to unknown reacons.
- 3 Action
- A new TLD was placed in the field on 11/6/91. Actual sampling
.E period was 11/6/91 to 12/5/91. The abbreviated sample period was converted'to 672 hours of field monitoring. The normal collection period I for the fourth quarter 1991 was 91 days. The collection period of 91 days converted to 2,184 hours of field monitoring. The following action was taken in order to provide a more realistic and representative dose per quarter for this location:
The dose rate of site #178 for the sampling period of 11/6/91 to 12/5/91 was determined to be 0.006 mR/ Hoar by the Dosimetry Lab. Multiplying 0.006 I mR/ Hour by 672 hours yielded a quarterly dose of approximateiy 3.9 mR/ Quarter The doso rate 0.006 mR/ Hour for location #178 was next multiplied by 2,184 hours which was the normal collection period ft all I remaining TLDs. This calculation yielded a dose of 13.1 mR/ Quarte. I _ C-7
I I - II. UNAVAILABLE ANALYSES The following unavailable analyses occurred resulting from inappropriate samples during 1991:
.I A.' AIRBORNE RADIOlODINES AND PARTICULATES
- 1. Location #120, 6/4/91 to 6/11/91 Reason: Due to a blown fuse, the sampler ran for only 2.6 hours out of a normal 168 hour sampling period. Because of short span of run time, it was technically impossible to meet required LLD's.
Action: Replaced fuse and restarted sampler. Actual sampling period was 6/4/91 @l4:35 to 6/4/91 @ 17:11. E I I I I 13 I LI LI
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APPEND!X D I I I g ANALYTICAL DEVIAT/ONS LOWER LIMITS OF I DETECTION I ll l (_- No analytical deviations were incurred for the l 1991 environmental sampling program. lI
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