ML20029C735
| ML20029C735 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, McGuire  |
| Issue date: | 12/31/1993 |
| From: | Mcmeekin T DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9404280305 | |
| Download: ML20029C735 (127) | |
Text
y%p%fi .
<c_
' '~'
(
gyh k,l q.y . L s ?l(-
h%
W" i Duke Power Company ' . .
L McGuiri Nuclear Generation Departnent V T. C Mdlem Vice President '
~
- 12700Hagen fenyRoad(MG0lVP) ' (701)875 4 %)O HuntenvWe, NC230758985 ' (701)8754909 Fax 7 ,
4e
' DUKEPOWER R
[ '
April 18,1994
'U. S. Nuclear Regulatory Commission m
Attention: Document Control Desk Washington, D.C. 20555
Subject:
. McGuire Nuclear Station Docket Nos. 50-369 and 50-370 Annual Radiological Environmental Operating Report Please find attached the McGuire Nuclear Station Annual Radiological Environmental Operating Report for 1993 pursuant to McGuire Technical Specification 6.9.1.6.
' Ouestions or problems with respect to this report should be directed to Kay Crane, at (704) 875-4306. ;
-Very truly yours, .
m ggg ,
T. C. McMeekin, Vice President
- McGuire Nuclear Station
.cc: Mr. Victor Nerses, Project Manager Mr. Dayne' Brown
' Office of Nuclear Reactor Regulation Division of Radiation Protection a .U. S. Nuclear Regulatory Commission. P.O. Box 27687 Washington, D.C. 20555 Raleigh, N.C. 27611-7687 Mr. S. D. Ebneter, Regional Administrator ANI Library
- U. S. Nuclear Regulatory Commission' Town Center, Suite 300S LRegion il _
29 South Main Street 101 Marietta Street, NW - Suite 2900 West Hartford, CT-Atlanta, Georgia ' 30323 06107-2445 0
h Mr. George Maxwell ,
' Senior Resident inspector -
.- McGuire Nuclear Site .
a
, ,3 .
9404200305 931231 PDR ADDCK 05000369
- d. -
cf -
l
- g. -
.R. PDR-- .
2 -
- newm&mww
'p'i' ' <
!' $l9:_
fIt
s l
%\. t p
th 'a s DUKE PCMER COMPANY 7, .A, 1 McGuire Nuclear Station i Units I and 2 uq 9
k 58 4
m f'h Y,.1 rj
- l. ,f %, Cl
.,M / ]
~~
l v l1;i
-}W l
- ^ - ~
l ms I d
[ ,$ff %Y {! .~
,- ~~~~~-. -
/, g{r --~._,_.__ _tm.s-- - - -
~ e n i
% /g --
. , _ .~ wa.-.w.eacom -
jd i egalim .n os_ ndJish-m w e n e C W , ~" " "'" ,..*
$ A$$ ' * *
- gg@ [] ocumusbphiaw M N # ** " " =
- -i-mmew m u m e.wa ninewm?9
~
4h
- umw w m&m muaeku.suu4 W av&,4:.w 3- 1 f 4 , *4 . ,
- .:.. m .g 3
- ,, .i.+td.i 4ty.m.P?g[.ydM,
, Ma-.- y J, ,';M, , ,Q' fwd L
~ ..
~_ ,
, l5 a' " /.; *, Y ?s>;
n m a.' f)-' n.'**.;.',a
. e .M +'A'tg-
- . . $% . f.pky,g; 3 '
,s y9 ;M t
> n:. ' ';.L < > [> Y h' "* + ' ~
- ._'b',
e "* %.,y *, ,.. ; ,; . .,n, ?
)
+g .o; q* .7 x' l
,+ t[j,' < ((N'll.,;j *$ $,b -
- j";[d s -
, g h'- "
- !.-b l
@ , p,;.,1,h?b;?Y!! . !,
A). . . .
?
m - . - - - - -'
r #
lb- ,1 yC hhah'.h.~.[ y c;);\. - ,u [ n:1;, , .:
N Y h,
- x ll gr -l'f g y
~
y g3 g g g l{
g .
7
. . . 9.993 .
.- w g zu a_ a. .d v. a.a ).. ,,g. gg, ggg ggg g, g ,7g ggg g gg 1
l l
l ANNUAL RADIOLOGICAL !
ENVIRONMENTAL OPERATING REPORT -
1 i
l l
l l
for DUKE POWER COMPANY McGuire Nuclear Station Units 1 and 2 1 January 1 - December 31 l
1993 i 1
l l
TABLE OF CONTENTS.
TITLE PAGE List of Figures . . . . . . . . . . iv List of Tables . . . . . . . . . . v
- 1. Executive Summary . . . . . . . . . 1-1
- 2. Introduction . . . . . . . . 2-1 2.1 Site Description and Sample Locations . . . 2-1 2.2 Scope and Requirements of Environmental Monitoring
. Program . . . . . . . 2-2 J 2.3 Statistical and Calculational Methodology . . . . 2-10 2.3.1 Estimation of the Mean Value . . . . 10 2.3.2 Lower Level of Detection and Minimum Detectable Activity . . . . . . . . 2-10 2.3.3 Trend Identification . . . . . 2-11 2.3.4 Test Statistic . . . . . . . 2-14
- 3. Radiological Envi: onmental Monitoring Program - Discussion, Interpretation, and Trending of Resulta . . . . . 3-1 3.1 Airborne Radiciodines and Particulates . . . . 3-2 3.1.1 Radiolodines . . . . . . 3-2 3.1.2 Particulates . . . . . . . 3-4 3.2 Drinking Water . . . . . . . . . 3-6 3.3. Surface Water . . . . . . . . 3-11 3.4 Milk . . . . . . . . . . . 3-16 3.5 Broadleaf Vegetation . . . . . . . . '3-18 1
3.6 Shoreline Sediment . . . . . . . . 3-20 3.7 Fish . . . . . . . . . . . 3-22 3.8 Direct Gamma Radiation . . . . . . . 3-26 _j
< 3.9 Food Product . . . . . . . . . 3-29 3.10 Land Use Census . . . . . . . . 3-31 l l
q l
-li 3
1 TABLE OF CONTENTS (Continued)
TITLE PAGE i
- 4. Evaluation of. Dose from Environmental Measurements Versus 4- Fatimated Dose from Releases . . . . . . . 4-1 4.1 Dose from Environmental Measurements . . . 4-1 4.2 Estimated Dose from Releases . . . . . 4-1 4.3 Comparison of Doses . . . . . . 4-1 4.4 Pathway Dose Calculations . . . . . 4-4
- 5. Quality Assurance . . . . . . . . . 5-1 5.1 Duke Power Company's Environmental Laboratories . 5-1 5.2 . Contractor Laboratory . . . . . . 5-4 G. References . . . . . . . . . . G-1 Appendix A: Environmental Sample and Analysis Procedures - Summary A-2
- 1. Change of Sampling Procedures . . . . . A-2 II. Change of Analysis Procedures . . . . . A-2 III. Sampling and Analysis Procedures . . . . . A-2 A.1 Airborne Radiolodines and Particulates . . . A-2 A.2 Drin' king Water . . . . . . . . A-3 A.3 Surface Water . . . . . . . . A-3 A.4 Milk . . . . , . . . . . A-3 A.5 Broadleaf Vegetation . . . . . . A-4 i
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 . . . . . . . A-5 IV. Sampling and.
- ualysis Improvements . . . . A-6 J
..- ~ - . . - - a. . , . ~~ . . . . , , . . .,
b l-t-
TABLE OF CONTENTS (Continued)
TITLE PAGE Appendix B: Radiological Environmental Monitoring Program -
Summary of Results . . . . . . . B-1 B.1 Radiciodines . . . . . . . . . B-2 B.2 Particulates . . . . . . . . . B-3 B.3 Drinking Water . . . . . . . . . B -4 s
B .4 Surface Water . . . . . . . . B-6 B5 Milk . . . . . . . . . . . B-8 B.6 Broadleaf Vegetation . . . . . . . B-9 B.7 Shoreline Sediment . . . . . . . . B-10 B.8 Fish . . . . . . . . . . . B-11 B.9 Direct Gamma Radiation . . . . . . . B-12 B .10 Pooc'. Products . . . . . . . . B-13' Appendix C: Sampling Deviations and Unavailable Analyses . . C-1 Appendix D: Analytical Deviations - Lower Limits of Detection . D-1 Appendix E: Radiological Environmental Monitoring Program Results E-1 1
1 l
I l
i 111
LIST OF FIGURES FIGURE TITLE- PAGE 1 Sampling Locations Map (2500 ft. radius) . . . . 2-5 2 Sampling Locations Map (ten-mile radius) . . . . 2-6 3 Concentration of Radionuclides in Drinking Water . . 3-6 4 Concentration of Radionuclides in Shoreline Sediment . 3-20 5 Concontration of Radionuclides in Fish . . . . 3-25 G TLD Exposure from Direction Radiation . . . . 3-27 7 Land Use Census Map . . . . . . . 3-34 IV
-1
LIST OF TABLES FIGURE TITLE PAGE 2.1 - A McGuire Radiological Monitoring Program Sampling i
Locations . . . . . . . . . . 2-3 2.1 - B McGuire Radiological Monitoring Program TLD Locations . 2-4 2.2-A Maximum Values for the Lower Limits of Detection . . 2-7 2.2-B Reporting Levels for Radioactivity Concentration in Environmental Samples . . . . . . . 2-8
- 2. 2-C McGuire Radiological Monitoring Program Analyses . . 2-9 3.1.1 - A Concentration of Radionuclides in Airborne Radiofodines . 3-3 3.1.1 - B Percentages of Reporting Levels for Radiolodines . . 3-2 3.1. 2- A Concentration of Radionuclides in Airborne Particulates . 3-5 3.1. 2-B Percentages of Reporting Levels for Particulates . . 3-4 3.2-A Concentration of Radit.uclides 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 l 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 . 3-18 3.0-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
- 3. 7- B Percentages of Reporting Levels for Fish . . . . 3-22 3.8-A TLD Exposure from Direct Radiation . . . . . 3-26 l 3.8-B Comparison of Inner Ring / Outer Ring TLD Results . . 3-28 3.9-A Concentration of Radionuclides in Food Products . . 3-30 l
- 3. 9- B Percentages of Reporting Levels for Food Products . . 3-29 3.10 Land Use Census Results . . . . . . . 3-32 l 4.1 1993 Environmental and Effluent Doses . . . . 4-3 5.1 U.S. E.P. A. Interlaboratory Comparison Program - 1993 Cross Check Results for the RE&S Lab. . . . . 5-5 5.2 North Carolina Department of Environmental liealth and
- Natural Resources-Environmental Dosimeter Crosscheck-1993. 5-8 l
l v
i
. - . . . ~ ,, . ,, - , - -,r. -
1.0 EXECUTIVE
SUMMARY
This Annual Radiological Environmental Operating Report describes the McGuire Nuclear Station Radiological Environmental Program and the results l of the program for the calendar year 1993. l l
Included in the report are identification of sampling locations, descriptions I of environmental sampling and analysis procedures, comparisons of present l environmental radioactivity levels and preoperational environmental data, analysh; of trends in the environmental radioactivity levels since the beginning of station operation, comparisons of doses calculated from environmental measurements and doses calculated from effluent data, a summary of the results of the 1993 program, discussion of the results, and discussion of the quality assurance activities associated with the program.
Deviations from program requirements are also included.
Sampling activities were conducted as prescribed by Selected Licensee Commitments. Required analyses were performed and detection capabilities met Selected Licensee Commitments Manual requirements. Supplemental samples also were taken in addition to the required sampling locations.
Concentrations observed in the environment in 1993 for station related radionuclides were within the ranges of concentrations observed in the past. All uositive indications of radioactivity due to plant operations were less than the reporting levels specified by the Nuclear Regulatory Commission (NRC) and given in Selected Licensee Commitments. The environmental doses also were well below specified limits.
Statistical analysis of data indicates that there are no radionuclides demonstrating high to moderate increasing trends. All possible increasing trends showed moderate to no probability. It can be concluded that the contribution of McGuire to the radioactivity in the environment is slight.
1-1
-m e -
- A.
2.0 INTRODUCTION
2.1 SITE DESCRIPTION AND SAMPLE LOCATIONS McGuire Nuclear Station is located geographically near the center of the
. highly industrialized region of the Carolinas. The land is predominantly rural non-farm with a small amount of land being used to support beef cattle and farming. Recreation in the area is confined mostly to the lake and shores of Lake Norman and Mountain Island reservoir. The McGuire site is in northwestern Mecklenburg County, North Carolina, 17 miles north-northwest of Charlotte, North Carolina. The site is bounded to the west by the Catawba River channel and to the north by the 32,510 acre Lake
, Norman. Lake Norman is impounded by Duke Power Company's Cowans Ford Dam Hydroelectric Station, which is located immediately west of the site and on the Catawba River channel. The tallwater of Cowans Ford Dam is the upper limit of Mountain Island Reservoir. Mountain Island Dam is located 15 miles downstream from the site. Lookout Shoals liydroelectric Station is at the upper reaches of Lake Norman. Marshall Coal Station is located on the western shore of Lake Norman, approximately 16 miles upstream from the site (reference 6.2 and 0.3). The sites exclusion radius is 2500 feet.
Tables 2.1-A and 2.1-B define the sampling and TLD locations for the McGuire Radiological Monitoring Program. Figures 1 and 2 illustrate these locations as compared to McGuire Nuclear Station.
l l
l 2-1
-l 2.2 SCOPE AND REQUIREMENTS OF ENVIRONMENTAL l MONITORING PROGRAM i An environmental monitoring program has been in effect at McGuire Nuclear 'l Station since 1977, four years prior to the Unit No.1 startup in 1981. The l preoperational program provided data on the existing environmental !
radioactivity levels for the site and vicinity which may be used to determine :
whether increases in environmental levels are attributable to the station.
The operational program provides surveillance and backup support of-detailed effluent monitoring which is necessary to evaluate the significance, n if any, of the contributions to the existing environmental radioactivity levels that result from station operation.
This monitoring program is based on NRC guidance as reflected in Selected Licensee Commitments Manual Section 16.11-13 with regard to sample media, sampling locations , sampling frequency , and analytical sensitivity requiremen ts . Tables 2.2-A and 2.2-B show the maximum values for LLD and the reporting levels , respectively, from Selected Licensee Commitments. Table 2.2-C shows the analysis schedule for each medium and the type of analysis required . Indicator and control locations were established for comparison purposes to distinguish radioactivity of station origin from natural or other " man-made" environmental radioactivity. The environmental monitoring program also verifies projected and anticipated radionuclide concentrations in the environment and related exposures from releases of radionuclides from McGuire Nuclear Station. This program provides surveillance of all appropriate critical exposure pathways to man and satisfies vital interests of the company, public, and state and federal agencies concerned with the environment.
4 J
1 6
,dl__
Y 2-2
- . -- . . - - _ . . . - . . _ . .~ . -
TABLE 2.1-A McGuiro Radiologic:1 Monitoring Progrcm Sampling Locations Code:
W-Weekly BW-Biweekly SM-Semimonthly M-Monthly O-Quarterly ,
C-Control SA-Semlantiually %
.aa s.,w. or.4uno sho, e room aro m d Sampling Location Description em w, w, s no e,ooms. r ua v.a.ue-120 . Site Boundary (0.4 mi NNE) W M(b) 121 Site Boundary (0.5 mi NE) W 125 Site Boundary (0.4 mi SW) W M(b) 128 Discharge Canal Bridge (0.4 mi ENE) BW 129 Discharge Canal Entrance to Lake Norman (0.6 mi ENE) SA SA 130 Hwy 73 Bridge Downstream (0.6 mi SW) SA to 131 Cowans Form Dam (0.7 mi W) BW b 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(b) 135C Plant Marshall intake Canal (12.0 mi N) BW 136C Mooresville Municioat Water Supply (12.5 mi NNE) BW 137C Pinnacle Access Area (12.0 mi N) SA SA 138 Henry Cook Dairy (2.75 mi ESE) SM 139 William Cook Dairy (2 6 mi E) SM 140 Kidd Dairy-Cows (2.8 mi SSE) SM 141C Lynch Dairy-Cows (14.8 mi WNW) SM 142 Davidson Municipal Water Supply (7.5 mi NE) BW 158 4-5 mile radius (5.0 mi NNE) M(b) 184 5 mile radius Gardens (2.5 mi ENE) M(a) 188 5 mile radius Gardens (2.8 mi N) - Special Interest M(a) 192 Peninsula Comenunity (2.8 mi NNE) - Special Interest W ;
(a) during harvest season (b) when available
Tcbb 2.1-B MCGUIRE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS (TLD LOCATIONS)
SAMPLING LOCATION DESCRIPT10N' SAMPLING LOCATION 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 MLE 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) 167 4-5 MILE RADIUS (4.9 MILES SW) 147 SITE BOUNDARY (0.4 MILES E) 168 4-5 MLE RADIUS (4.7 MILES WSW) 148 SITE BOUNDARY (0.5 MILES ESE) 169 4-5 MILE RADIUS (4.4 MILES W) 149 SITE BOUNDARY (0.6 MILES SE) 170 4-5 MILE RADIUS (4.5 M!WS VmW) w 150 SITE BOUNDARY (0.5 MILES SE) 171 4-5 MLE RADIUS (4.5 MILES NW)
E 151 SITE BOUNDARY (0 4 MILES S) 172 4-5 MLE RADIUS (52 MIWS 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) 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 M!LES WSW) 179 SPECIAL INTEREST (10.4 MLES ESE) 157 4-5 MILE RADIUS (4.8 MILES N) 180 SPECIAL INTEREST (115 MILES NNE) 158 4-5 MILE RADIUS (4.4 MLES NNE) 181 SPECIAL INTEREST (6.7 MILES NE) 159 4-5 MILE RADIUS (5.0 M!LES NE) 182 SPECIAL INTEREST (6.0 MILES NE) 160 4-5 MILE RADIUS (4 9 M!LES ENE) 183 SPECIAL INTEREST (5.5 MILES S) 161 4-5 MILE RADIUS (4.7 MILES E) 186 SPECIAL INTEREST (02 M!LES NNW) 162 4-5 MILE RADIUS (4 6 MILES ESE) 187 SPECIAL INTEREST (0.3 M!LES N) i.
163 4-5 MILE RADIUS (5.0 MILES SE) 191 SPECIAL INTEREST (2.8 MILES NNE) l l
- j All TLD samples are coflected quarterly.
l l
( _ _ _ .__ _ _ ___ _ -_______
FIGURE i Ib:-..u :
}!yg.:
.; i
+e 187 "
- j
_N
' 'ii86' i
-" -,4 g 2e .
, lWii .i../jif 146 :
156 .j .
x __
g ^
g y 0154 '
l L
',N N / -
E
(- ~
~ '
lh i_
f 2500ftRa n33 *
- g T
, 'A125 . .N tew j 153 f
d .mr%_ //
'lY
'N
. ii 30 M
g p ,_
q = __
- 151 u-. -
189
' ' 149
_s ( L_ b sse j' , ocamous
,c ,0 y s Figure B5.01 (2 of 2)
Revision 35 1/1S4
- . Tabla 2.2-A MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)
- ' " ^ I OAD LEAF WATER FISH MILK SEDIMENT
^ '
(pCill)
" ^ (pCilkg, wet) (pCill) p 3 pC g e (pCilkg, dry)
Gross beta 4 N.A. N.A. N.A. N.A. N.A.
H-3 2000* N A. N.A. N.A. N.A. N.A.
Mn-54 15 N.A. 130 N A. N.A. N.A.
Fe-59 30 N A. 260 N.A. N.A. N.A.
w 0 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-95 15 N.A. N.A. N.A. N.A. N.A.
1-131 1 7 x 10-2 N.A. 1 60 N.A.
Cs-134 15 5 x 10-2 130 15 60 150 Cs-137 18 6 x 10-2 150 18 80 180 Ba-140 15 N.A. N.A. 15 N.A. N.A.
La-140 15 N.A. N.A. 15 N.A. N A.
- 't no drinking water pathway exists, a value of 3000 pCill may be used.
Tabla 2.2-B REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS WATER
^ ^ FISH MILK BROAD N ANALYSIS (pCi/I)
^ "
(pCill) (pCl/kg, wet)
(pCi m3) (pCi/kg, wet)
H-3 N A. N.A. N.A. N.A.
2 x 10*
3 #
Mn-54 1 x 10 N.A. 3 x 10 N.A. N.A.
4 Fe-59 4 x 102 N.A. 1 x 10 N.A. N.A.
3 N.A.
Co-58 1 x 10 N.A. 3 x 10' N.A. I 2 4 Co-60 3 x 10 N.A. 1 y 10 N.A. N.A.
2 4 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.
2 1-131 2 1 N.A. 3 1 x 10 3 3 Cs-134 30 10 1 x 10 60 1 x 10 3 3 Cs-137 50 20 2 x 10 70 2 x 10 2 2 Ba-La-140 2 x 10 N A. N.A. 3 x 10 N.A.
- 4
! For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 3 x 10 pCill may be used.
.)
Tabl@ 2e2-C McGuire Radiological Monitoring Program Analysis Analyses Sample Analyses Gamma Low Level Gross l tium Medium Schedule isotopic I-131 Beta Radioiodine X
& Weekly Particulates X X Direct Radiation Quarterly X Biweekly X a
M nthly Composite X e
Ouarterly Composite X y Biweekly X
- Drinking Monthly Composite X Water Quarterly Composite X X
' " X Sem annually
- n Milk Semimonthly X X i
Fish Semiannually X Broadleaf Monthly X Vegetation (when available)
Food Monthly X Products (during harvest season)
l e
L 2.3 STATISTICAL AND CALCULATIONAL METHODOLOGY 1 1
i I
- 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 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 7
Program. The following equation was used to estimate the mean:
N -a E4
, /=1 N
i Where:
5 = estimate of the mean, 1 - = individual sample, N = total number of samples with a net activity (or concentration) xi = net activity (or concentration) for sample i.
NOTE: " Net activity (or concentration)" is the activity (or concentration) determined to be present in the sample. No
" Minimum Detectable Activity", " Lower Limit of Detection", "Less Than Level" , or negative activities or concentrations are included in the calculation of the mean.
2.3.2 LOWER LEVEL OF DETECTION. MINIMUM DETECTABLE ACTIVITY a AND
, CRITICAL LEVEL The Lower Level of Detection (LLD) and Minimum Detectable Activity (MDA)
, are used throughout the Environmental Monitoring Program, both in the .i Selected Licensee Commitments and in the implementation of the specifications.
i The LLD, as defined in the Selected Licensee Commitments Manual is the i smallest concentration of radioactive materialin a sample that will yield a net I count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. The LLD is an a priorilower limit of detection.
The actual LLD is dependent upon the standard deviation of the background i counting rate, the counting efficiency, the sample size (mass or volume), ,
the radiochemical yield, and the radioactive decay of the sample between l sample collection and counting. The '" required" LLD's' for each sample medium and selected radionuclides. are given in the Selected Licensee Commitments and are listed in Table 2.2-A.
2-10 j 1
-,, _ _. . _ _ _ . ~ . _ , .._ . . _ _ ~ , . . _ _ . . -_. _ _ _ _ _ _ _ _ _ .
d
(
)
The MDA may be thought of as an " actual" LLD for a particular sample l measurement remembering that the MDA is calculated using a sample !
background instead of a system background. In gamma spectroscopy 1 analyses, the sample background may be elevated above the system j 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 that could be positively identified in the sample. Therefore, to insure that the " required" LLD is not exceeded for any radionuclide in a sample medium, the MDA is calculated based on the actual background in the area of the identifying gamma energy and is compared to the " required" LLD.
If the MDA exceeds the " required" LLD, the sample is counted for a longer 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 requirements for the detection capability for environmental sample analysis.
For " gross" counters (such as alpha /bota proportional counters and liquid scintillation counters), the MDA is calculated using the average of batch background counts. The average is used to account for background fluctuations over longer counting periods. This MDA is then compared to the " required" LLD. If the MDA exceeds the " required" LLD, the sample is counted for a longer time period so that the standard deviation of the batch background is minimized. If the " required" LLD exceeds the MDA, then the analysis of the sample meets the requirements for the detection
- capability for environmental sample analysis.
For " gross" . counters, a critical level calculation is also performed to determine statistically significant levels of activity. The critical level is defined as the net count rate which must be exceeded before the sample is said to contain any measurable activity above background. In general, the critical level is equal to one-half of the MDA. Activities exceeding the critical level are reported for gross counters to minimize data biases, since mose detectable activities fall within this range.
2.3.3 TREND IDENTIFICATION l One of the purposes of an environmental monitoring program is to determine if there is a buildup of radionuclides in the environment due to the operation of the nuclear station. This is traditionally done by looking at historical data (including preoperational data) and determining if a trend exists.
Trends, if they exist, may be either positive or negative. Since nuclear reactor operations do not normally remove radioactivity from the surrounding environment, a negative trend in a particular radionuclide's concentration in an environmental medium does not indicate that reactor l operations are removing radioactivity from the environment but that reactor operations are not adding that radionuclide to the environment in quantities exceeding the preoperational level and that the normal removal processes .
(radioactive decay, deposition, resuspension, etc.) are influencing the concentration .
l l
l l
l 2-11 i
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. Theref re, it is desirable to obtain a single numerical value from the data which will permit a meaningful interpretation of the relationship existing between the variations in the data. .If it is assumed that a linear relationship exists between the time af ter startup of the reactor and the amount of radionuclides in a particular environmental medium, the least squares regression method may be used to define the linear relationship. To determine if the data actually correlate to the straight line assumption, the theoretical variance is compared to the actual variance.
' The numerical value that summarizes this comparison is known as the correlation coefficient. This correlation coefficient, symbolized by "r", is a determination of how cicsely the data fit a straight line and may be calculated from the following equation:
NEXY-DXE Y r =
[(NEX2 _(3y)2)(ggy2_(3y)2))$
i Where:
i 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.
l l 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:
11 lrl > 0.7 liigh to moderate probability of a trend.
0.7 2 lrl > 0.3 Moderate to poor probability of a trend.
0.32 lrl20 Poor to no probability of trend.
l 2-12 i _ _ . . _ _. . ___ _ _ _-- ~ _ _
._ _ _ . . _ _ _ . . _ _ _ ._ _ . - _ _ ~ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _
Identifying a trend by using the correlation coefficient is only useful for the time periods where the discharge from the nuclear plant is relatively stable and no other sources of radioactivity are present. Substantialincreases or decreases in the amount of a particular radionuclide's release from the nuclear plant will greatly affect the resulting environmental levels; therefore, a knowledge of the release of a radionuclide from the nuclear plant is necessary to completely interpret the trends, or lack of trends, determined from the environmental data. Other factors that may affect environmentallevels of radionuclides include prevailing weather conditions (periods of drought or heavier than normal precipitation), construction in or around either the nuclear plant or the sampling location, addition or deletion of other sources of radioactive materials (such as the Chernobyl accident), etc. . Some of these factors may be obvious while others are sometimes unknown to the plant personnel.
The recent change in the method of calculating the mean (using only not positive results) will also affect the apparent trends.
Ilecause of the above considerations, how trends are identified will depend not only on the least squares regression method, but will include some judgement by plant personnel on the factors affecting environmental levels.
2-13 3
---...-..-.-..-...-.--,--,.Y
2.3.4 TEST STATISTIC In some cases, we would not expect to observe a buildup of radionuclides in the environment, but instead would expect to see a measurable increase in levels over a short du ration . This is the case for direct radiation measurements, where the radiation level is measured over a finite period and is dependent upon whether plant discharges were occurring at that time or not. In this case, the correlation coefficient is not a sufficient indicator t 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 statistic, or t-statistic, and is calulated as fcitows:
X g - X,*
t =
sf/1/n, + 1/n2 Where :
Xi = the mean value of the first set of measurements X2 = the met value of the second set of measurements sp = the average standard deviation of the two sets of
. measurements t
I Where: 1 1
+
2
= ("i - I) S t (n2 - I)#2 s' ng + n2 - 2 l
l I
'1 "1
= the number of measurements in the first set n2
= the number of measurements in the second set 1
1 2-14 l
,. _ . _. . . . _ _ . . . ~ _ - . _ . . _ _ _ . _ _ _ _ _ _ . .
The calculated value of the test statistic is then compared to expected values of the test statistic tabulated based on the number of measurements taken and the degree of confidence required for the results. For our purposes, the expected value of the test statistic will always be chosen to give a 95% confidence level that a positive result is truly positive with only a 5%~ probability that a positive result is truly negative. This confidence i level is chosen since it is consistent with the standard confidence levels specified for similar measurements. ,
Due to the existence of naturally occurring differences in background l radiation levels over time (as a result of solar cycles and other 4 meteorological phenomena) and systematic errors due to instrument
" variability, ratios of measurements can be used to calculate the t-statistic instead ofindividual measurements. By using ratios, biases associated with the measurement process are minimized and allow us to more accurately compare results from one year to the next. Specifically, in the case of TLD measurements, the inner ring of TLD results is ratioed with the outer ring of TLD measurements in a given year and the ratio for one year is compared to the ratio for another year.
As with other environmental samples, outside factors may affect the results observed and the resulting trends identified. Therefore, the significance of trends will be based in part on judgment of plant personnel familiar with the factors affecting environmental levels, as well as the statistical results.
i.
2-15 l-L
135 o PLANT MARSHALL
$ ' f j 5Mf I AdLE A CES 7 7(1[< 4 e pp'%g
%' \ a '
i
/hys
_,' ' /. ; . . . [ s %. ',
.D. .
q
'. ', ' g,y -
I /.
A1 E j ; a Ty3- ; ,., ,
N &
'\ /
- 3 ,i (_ -
g 4 .
AJ94
- 2
.) f -T -, - l ,
', j a .,,, , y 1
,1 =
3,1 M. \
. *N(.. NT ',, ),'>
$ + , ,,, , .t2Q4 s
f,, g o
S 44, m
, 3
,p
/
l g 'Mr y- .
175 i l C2 -
'14'
. "'mp% ,/.,)v,,L,l- ue 9" Q"" ] {q!.$ -
3i . ,
y 3 *
,1 u r( \ f l 5 h
(E.) *gy74 V; ,f } ./(- , i %, . , ~
+ ~.k [x' M *- i' y1 N, 4 . \ ... g J' _.
- 9. , . , .
^
y '"
J g
'j'[f ] 60 ,]
g d.( i 4 ,
S'd 1 7a [ ,,,, ,x ipw/
- AJ
] 6,',
- y b ,,
h' ' , I P y% / ' 2 .,
l { k
\ ./.,,,'
7bT%y '"
, I,, '
- ng , m,,$ N. , Y i a;%* l -
f ( .~ ,' 'l. .
\ ,
i ,.,u- . l %.,t s -
o,.
~,', g, .>
. , ' q'l;.,
'W
- yk!(",3' 3Af" h ,Qb h
_Y; L,4 ,,' " o x'Ih s,
' ', ,.y ,;r 't, ,,
g g .N' ,!.' b w .a < "'
. e i' f '.
1')Di
'~'
l 8
, f'
^
N 4 !
+. - --+ ,
t .,,y 2 \ ~
/ \ ,g .a r ; . a . -- . - ~
/ ' -
L. q 't[;_,L s_ . .. ,g ,- ; .140 s j ., w.. [ j!.. 3 '
E \ 9 #' "
"A \, f., ,
/ , .j -
('
[~[
! gp /vem .,, .
\ 'lca 'e .
'f l /, { ; 1Y4 V.
- i ,
,7*. '-gh +
V '
N
- J/D /k.\ / I i
i
. .i .
S . "' ' \-
%,, s ... w
./
/e 66-
,. j
/ \,-
f, 'k [
l /. 5 c,,, , -m / *> a
- m ,i (, ,
'7. j' '
.,q'((j , -
g, ,
N-/ Jrfugy " %j- . ,
"{k%~,\ 1 v 4
< .., g
,GE i ; '" '
1 - {, m ,
,". ,e3 e . . 18 #k
- 's g /;
\ , s f
) ,
N ,u s A
'M y /
, . . ..?
.) y '~ - ~;' _ , , -i i s .
f .
,4 '
,j % (*,.
'N '
.- g ,,
-(g V,-
- 7..Ol ,"...., . 3 /N -
3., ,
(
< C.N, h]9 , (,.)9 i N,.s /'
y' ' ( , / i
- p, 1, s
.y Q
). .) e .7 4770', f~' .\
tw 4 '"'mV 't 'y-g s
3
? + ..,.f.j ,
Q&
'j
' 'I fj y ,, ,
e E sw h h ? h t h ,?) , - -
132 A CHg i
1
~ ~ - . l
, ._ _ . . - _ . _ . _ _ _ _ . _ . _ _ _ _ _ _ _ - ~ . _ _ _ _ _ - _ _ _ __ . . _ _ _ _ _ _ . _ - _ . _ . _ , - _ _ . - _ _ _ . , . - - -
,1
. t-fi i
N FIGURE 2 l DORESVILLE WATER
'REATMENT PLANT '
LtGEND
. soo n
1 s . . _
gt. 4 1
- en I.4 ;; == .u . _ l 2i.-
4 m
< .s u,
q k ( .W:9C.W C.f.0
{
g -p 4 f .
_ ,.p. ,
,v e
4 +
g _. -
f- .
y . __.L
.V _T.
+---- :
@s . ~ _
.% s . _ o r'a.' .
- f. .
.<f
-s
- f. _ <p c ..
nyrs'8. ~
i A-3 , s v s ~ .===_.===.,
T
- =_-
= ;. --
c ao .- ._ ,_
. . . . t, __ ._. -
o _ _ . _ _ .
y.\,,_ , , sa .o. _ . .. _. ._ .
y- 1 s.
+
- =
l r;+ _ . . , m. g.
_ ._~ ~ . , _ _
i,; ,- 3 Q we ... a. as
. w .
3 g. . _ . _ . . _
u:. .y. ./ ,. , ,a~ . H ._
QW y , .
wv - .. .a.
e, , w , , .
/
. n A,a4bl.EC o'---
oV I APERTURE
., , 3. 3Ar;.c .
- e. .
.s a _.
'_~ _~ ~
, n
. LmARD * . . _ ,
i g ,s . . < , . .
4 1
'I k ,,' 4 Aho Availabla on 7"'~ =*
lW' g W
Aperturo Card
'. C, "_'""_' ._
k:J>
~, .
, o -
- n. .
m~
- o. _. _ _.. _ ..- _
,m w,4 ,c.s M, O'_.-l"'"**'***
178, ,
l :,.
m .cu o, ,,u, .i s __
- k. h. x.; d v p. +
- w<c . .
i
- t. _ .
3 =._.
s
- q. .s,. ,. # ,
( . .._... . ._ _
.s x. . .,. .
y ds
. Tto LOCATIONS MCGUIRE NUCLEAR STATION y[.8 ("f A ALL OTHER SAMPLING LOCATIONS MONITORING PROGRAM LOCATIONS Figure 2 Map of REMP Sampling Locations RLOTTE WATER WORKS Pg. 2 - 6 ayoq'2%O305-O,'
i - - .
3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MONITORING PROGRAM - DISCUSSION, INTERPRETATION AND TRENDING OF RESULTS The radionuclides with Selected Licensee Commitments reporting levels in the environmental media samples have been historically trended over a fourteen-year period f rom .1979 - 1993. Analyses from 1977 - 1978 have been excluded since these results were much higher than the other preoperational years due to outside influence such as weapons testing. Including these results would have produced correlation coefficients and averages that were not representative. The highest annual mean concentration of each Selected Licensee Commitments radionuclide from the indicator and control locations for each media type was used for the estimation of the mean value and correlation coefficient. The preoperational analyses from 1981 were combined with the operational analyses from the latter part of 1981 and averaged to give one concentration for each radionuclide for that year.
Ilowever, when preoperational comparisons were necessary, only the preoperational report was used.
Fifteen annual means were used to determine trends and occasionally the average concentrations reported were negative. Negative values were obtained using reported activities that were less than the assumed l background. All negative values (concentrations) were replaced with a zero to properly represent environmental conditions. Figures 3 through 6 l provide a graphical presentation of the annual mean concentrations for drinking water, shoreline sediment, fish, and TLD data. Some of these figures show both indicators and controls for significant radionuclides, while others show only indicators for clarity purposes. These media were chosen for graphical representation for special interest purposes or because l they consistently show detectable activity for a few radionuclides. In l addition, the percentages of Selected Licensee Commitments reportinglevels were calculated for each reportable radionuclide in each media type.
No Selected Licensee Commitments reporting levels woro exceeded in 1993 due to plant effluents.
Only the radionuclides with Selected Licensee Commitments reporting levels were historically trended and compared with the fourteen-year average and control levels. It is important to note that while historical trends are helpful in determining radioactivity buildup, environmental radionuclide lovels could be affected without exhibiting increasing or decreasing trends.
Many radionuclides showed decreasing trends. This can be attributed, in part, to a change of analysis equipment in 1987.
1 3-1
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - -]
[_L .
3.1 A_lRBORNE RADIOIODINES AND PARTICULATES 3.1.1 RADIOIODINES In 1993, 260 radiolodine samples were analyzed, 208 at four indicator locations and 52 at the control location.
The I-131 concentration did not significantly dif fer from the average, preoperational data, or control location levels for the fourteen-year period.
The historical trend based on highest annual mean for indicator and control location for I-131, showed decreasing trends as illustrated in Table 3.1.1 - A .
Table 3.1.1-B shows the percentages of environmental concentrations to the Selected Licensee Commitments reporting levels for the indicators at the locations with the highest annual mean for 1993.
Table _3_.1.1-B Radionuclide Concentration Reporting Percentage (pCi/m') l.cvel(pCi/m')
1-131 '
0.00E0 1.00E0 0.00 %
l
\ \
l l l l 1 l
l 1
l 3-2
Inbla11JzALC9ncentration of Radionu_cHdeLIB Airborne Radiololine_s 3
Concentration (pCi/m )
YEAR I-131 Indi;ator Control 1979
- 3.28 E-3 1.N E-3 1980
- 2.04 E-3 110E-3 1981
- 4.17E-3 6.27E-4 1982
- 1.42E-3 2.48E-3 1983
- 1.99E-3 2.O l E-4 1984 3.17E-3 -l 15E-3 l 1985 3.15 E-3 1.04 E-3 1986 1.27E-2 6.10E-3 1987 1.07E-2 6.60E-3 1988 0.(X)E0 0.00E0 1989 2.18E-2 0.tX)E0 i
l 1990 0.00E0 0.00E0 l
1991 0.(X)E0 0.00E0 l 1992 0.(X)E0 0.00E0 14 YEAR AVERAGE 4.60E-3 1.37E-3 1993 0.(X)E0 0.00E0 l
CORRELATION _
COEFFICIENT - 0.003 - 0.16 l
l l
l l
l
- ltadiciodines and Particulates analyzed together.
l NOTE: All negative values were replaced with "zero's" for calculational purposes.
3-3
1 i
1 3.1.2 PARTICULATES In 1993, 260 particulate samples were annlyzed, 208 at the four indicator locations and 52 at the control location.
The 1-131, Cs-134, and Cs-137 concentrations did not significantly differ from the fourteen-year average, preoperational data, and control location levels. I The historical trends for the indicator and control locations with the highest annual mean for 1-131, Cs-134, and Cs-137 showed decreasing trends as illustrated in Table 3.1.2-A.
Table 3.1.2-B shows the percentages of environmental concentrations to the ;
Selected Licensea Commitments reportinglevels for the indicator locations with the highest annual mean for 1993. No activity was detected and therefore no ;
reporting levels were approached. 2 Table 3.1.2-B_
i Railionuclide Concentration Reporting Percentage 3
(pCi/m ) Level (pCi/m')
l-131 0.00E0 1.00E0 0.00 %
Cs-134 0.(X)E0 1.00E l 0.00 %
Cs-137 0 00E0 2.00E l 0.(XF4 l
l l
l l
i l
l l
I l
! j l~ l 3-4 l 1 i t_ Dj
1 1
Isttile 3.1.2-A Concentration of RadionuclideJ_in Altborne PatilculateS Concentralion (pCi/m')
YEAR l-131 Cs-134 Cs-137 Indicator Control indicator Pr. trol Indicator Control 1979
- 3.28 E-3 l .04 E-3 1.19E-3 -7.64 E-4 4.40E-3 1.47E-3 1980
- 2.04 E-3 1.10E-3 -5.89 E-5 -2.45 E-4 6.70E-3 4.53E-3 1981
- 4.17E-3 6.27 E-4 1.15 E-3 2.99E-4 6.16E-3 5.32E-3 1982
- l .42 E-3 2.48E-3 4.85 E-4 2.27E-3 3.82 E-3 2.29E-3 1983
- 1.99 E-3 2.01 E-4 6.80E-4 4.98 E-4 2.93 E-3 3.2 t E-3 1984 2.72 E-3 2.08E-3 9.90E-4 8.83 E-4 1.74 E-3 8.29 E-4 1985 1.57E-3 2.0$ E-3 1.38E-3 1.05E-3 1.86E-3 1.32E-3 1986 4.42E-3 3.36E-3 2.76E-3 8.90E-4 4.98E-3 3.03 E-3 1987 9.73 E-3 0.00E0 7.25 E-3 OJX)EO 1.07E-2 7.91 E-3 1988 0.(X)EO 9.15E-3 0.(X)EO 0.(X)EO 0.00E0 0.00E0 1989 0.(X)EO OJX)E0 0.00E0 0.(X)E0 0.00E0 0.00E0 1990 OAX)EO 0.00E0 OJX)EO 0.00E0 0.00E0 0.00E0 1991 OlX)EO 01X)E0 0.00E0 OJX)EO 0.00E0 0.00E0 1992 0.00E0 0.00E0 0.00E0 0.00E0 OJX)EO 0.00E0 14 YEAR AVERAGE 2.24E-3 1.58 E-3 1.13 E-3 4.21 E-4 3.06E-3 2.14E-3 1993 01X)E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 i CORR El.ATION COEFFICIENT -0.40 -0,10 -0.12 -0.37 -0.61 -0.52 l
- Radiciodines and Particulates analyzed together.
NOTE: All negative values were replaced with "zero's" for calculational purposes.
3-5
4 3.2 DRINKING WATER ,
In 1993, 39 drinking water samples were analyzed for 1-131/LL, 2G at the two indicator locations and 13 at the control location. Tritium (H-3) analyses were performed on 12 composite samples, eight at indicator locations and four at the control location. Thirty-nine samples were analyzed for other gamma emitting radionuclides, 26 at indicator locations, and 13 at the control location. ' Analyses showed zero ranges for all indicator locations, which means no detectable activity was measu red . All radionuclides did not significantly differ from the fourteen-year average or from preoperational data.
A moderate to poor probability of an increasing trend was seen for H-3 at the indicator locations. All other radionuclide indicators and controls exhibited decreasing or no trends. Table 3.2-A and Figure 3 illustrate these trends.
FIGURE 3 CONCENTRATION OF TRITIUM IN
' DRINKING WATER pcl/l 2500 l l l Il l l 10% OF ftEPORTING LEVEL
.i i i t i l l I 1500- ; ,
l 1l 1000'
.I 2 -J 500 t
!I g i i! li l l 1979 1960 1981 1082 1983 1984 1986 1986 1987 1908 1989 1990 1991 1992 1993 Year l
I 1
3-6
1 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 1993, l Table 3.2--B Radionuclide Concentration (pCi/ll Reporting Level (pCi/l) Percentage fi-3 0.00E0 2.00E4 0.00 %
Mn-54 0.00E0 1.00E3 0.00 %
Fe-59 0.00E0 4.00E2 0.00 %
C&-58 0.00E0 1.00E3 0.00 %
Co44) 0.00E0 3.00E2 0.00 %
ZrMS 0.00E0 3.00E2 0.00%
Ntw95 0.(X)E0 4.00E2 0.00%
Zr-45 0.00E0 4.00E2 0.00 %
l-131/LL 000E0 2.(X)E0 0.00 %
Cs-134 0.00E0 3.(X)El 0.00 %
Cs-137 0.00E0 5.00E l 0.00 %
Ba/La-140 0.00E0 2.00E2 0.00 %
3-7
~
t IAble Sfd-A _ Concentration of Radiongallde_s_in Drinking Water (Page 1 of 3)
Concentration (pCi/ liter)
Year H-3 Mrt-54 Fe-59 Co-58 lixlicator Control Indicator Control Indicator Control Indicator Control 1979 1.65 E2 1.50E2 1.46EO 4.27E-l 1.29E0 5.96E-l 1.14 E0 2.01 E0 1980 1.63 E2 2.05E2 6.20 E-l -4.29 E-l 1.77E0 5.20E-1 5.62 E-l -3.72 E- 1 1981 1.88E2 1.78E2 1.40E-1 - 1.96E0 4.58E0 1.13 E0 9.36 E- l 4.33 E- 1 1982 2.41E2 1.45 E2 8.63E-1 7.05 E-2 3.50E0 -7.39 E- l 7.7 t E- 1 6.26E- l 1983 2.65 E2 1.45 E2 4.18 E-l -3.06E-2 1.44E0 7.93 E- l 6.78 E-l -2.60E-l 1984 5.77 E2 2ASE2 1.05 E0 1.42 E- l 2.15 E0 1.60E- l 8.89 F- 1 -2.57 E-l 1985 5.93E2 43M)E2 7.14 E-2 9.49E-2 7.73 E- l -4.73 E- 1 3.39 E- l 6.16E-l 1986 1.14 E3 4.37E2 9.76 E-l -4.59 E-2 2.16EO -4.92 E- l 3.82E-1 1.04E-2 1987 1.35 E3 7.75 E2 4.80E0 0.00E0 6.60E0 0.00E0 4.20E0 0.00E0 1988 9.92 E2 7. l l E2 0.00E0 2.50E0 0.00E0 0.00E0 0.00E0 0.00E0 1989 5.62 E2 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1990 7.32 E2 6. l l E2 0.(X)E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1991 5.22E2 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1992 6.73 E2 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 14 Yr.
Avg. 5.83E2 2.86E2 7.43 E-l 2.31 E- 1 1.73E0 2.29 E-l 7.07 E-l 2.M E- 1 1993 0.(X)E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 Corr.
Coef 0.33 -0.03 -0.22 0.03 -0.48 -0.68 -0.29 -0.57 NOTE: All negative values were replaced with "zero's" for calculational purposes.
3-8
Iable 3.2-A Concentration of Radionuclides in Drinkina Wale.r.__
(Page 2 of 3)
Concentration (ICi/ liter)
Year Co-60 Zn-65 NI)-95 Zr-95 Indicator Control Indicator Control Indicator Control Indicator Control 1979 2.30E0 2.Ol EO l .10E- l 2.56E- 1 2.52 E0 * -3.74 E- 2
- 2.52 E0* -3.74 E-2
- 1980 2.26E0 1.80E0 1.18 E0 -7.44 E- l 1.7tE0* 6.52 E- l
- 1.71E0* 6.52 E-l
- 1981 1.43E0 1.34 E- l 1.76E0 1.29E0 2.30E0 1.47 E0 2.42 E0 1.81E0 1982 8.25 E- l 5.98 E-l 1.16E-l 9.43 E- 1 1.35E0 1.42E0 2.49E0 2.02 E0 1983 1.26E0 1.22E0 -6.05 E-2 - 2.48 E0 -3.99 E- 1 2.32 E-l 1.82E0 1.05EO 1984 7.22 E-l -2.8 t E-l 5.03E-1 1.29 E- 1 7.4 7 E-l 1.91 E- l 2.70E0 - 1.06 EO 1985 8.44 E- l 7.09 E- l ~3.43 E- l -7.20E-2 0.32E-l 4.63 E-l 1.09E0 5.70E-l 1986 2.33 E- l -3.46E-l 2.44E-l 7.25 E-2 9.87 E-l 1.06EO 5.17E-1 -4.4 3 E- l 1987 0.00E0 0.(X)E0 0.(X)E0 0.00E0 5.30E0 0.00E0 0.00E0 7.10E0 1988 0.00E0 4.50E0 0.00E0 0.00E0 0.00E0 01X)E0 0.00E0 0.00E0
, 1989 0.00E0 0.00E0 0.00E0 OJ)0E0 0.00E0 0.00E0 0.00E0 0.00E0 l
1990 0.00E0 0.00E0 0.00E0 0.00E0 0.(X)EO 0.00E0 0.00E0 0.00E0 l
1941 0.00E0 0.(X)E0 0.00E0 0.00E0 0.00E0 0.00E0 01X)E0 0.00E0 1992 0.00E0 0.00E0 0.00E0 Ot0E0 0.3)E0 0.00E0 DJX)EO 0.00E0 14 Yr.
Avg. 7.05 E- l 7.84 E-1 2.80E-l I92E-l 1.13E0 3.92 E-l 1.09E0 9.37E-1 1993 0.00E0 OlX)EO 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 Corr.
Coef -0.90 -0.30 -0.56 -0,50 -0.46 -0.55 -0.88 -0.16 i
0 Nb-95 and Zr-95 analyzed as Nb/Zr-95 j l
NOTE: All negative values were replaced with "zero's" for calculational purposes.
l l
3-9 ,
1
1 I
l l
31able 3,2-A_C_o_n_ centration of RadionucMes in DJinking Wate_t_
I (Page 3 of 3)
Concentration (pCi/ liter)
Year 1-131 Cs-134 Cs-137 Ba/La-140 I
Indicator Control trxticator Control Indicator Control Indicabr Control 1979 4.95EO 6.97 E- l -1.09 E0 -4.12 E-l 2.55 EO 2.86E- 1 1.62E0 1.54 6-2 1980 7.39 E-l 8.96E- l -3.54 E-1 -6.24 E- 1 9.53E-l 1.73 E0 8.53 E-2 2.06E- 1 1981 1.83 E0 1.05 E0 1.46E0 4.77 E-l 1.13E0 1.16E0 1.09E0 -8.20E-l 1982 2.45E0 7.79E-2 5.38 E-l 2.64E0 1.08E0 3.50E0 8.28 E-1 -6.73 E - I 1983 4.34 E- 1 -5.57 E- l 6.29 E- 1 1.54E0 8.91 E- l 5.3 l E-l 4.26E-l 1.13E0 1984 9.46E-2* -8.65 E-2
- 6.16E-l -2.O l E- 1 2.80E0 6.07E-l 1.16E0 -7.66 E- 1 1985 - 1.84 E- l * ~l.27E-l* 1.00E0 5.55E-l 1.43E0 - 1.74 E- l 5.15 E-l 7.75 E- 1 1986 3.07 E-2
- 5.63 E-2
- 8.18 E-l - 1.45 E-2 2.58 E-l 2.83 E-l 7.53 E-l - 1. l l E- 1 1987 4. J O E- 1 000E0 0.00E0 5.90E0 4.20E0 2.80E0 0.00E0 4.00E0 1988 OJX)EO 0.00h0 0.00E0 0.00E0 OJX)EO 0.00E0 0.00E0 0.00E0 1989 0.(X)E0 0.00E0 0.(X)E0 0.00E0 0.fX)EO 0.00E0 0.lX)E0 0.00E0 1990 0.00E0 0.00E0 0.0050 01X)E0 0.00E0 0.00E0 0.00E0 0.00E0 1991 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1992 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0
( 14 Yr.
Avg. 7.52 E-1 1.98 E-l 3.62 E-l 7.94 E- l I.09E0 7.78 E- 1 4.63 E- l 4.38E-l i
1993 0.(X)EO 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 Corr, Coef -0.68 -0.69 -0.46 -0.12 -0.49 -0.46 -0.73 -0.02 j i
L C I-131/LL analysis data used.
1 NOTE: All negative values were replaced with "zero's" for calculational purposes.
3-10
3.3 SURFACE WATER In 1993, 39 surface water samples were analyzed for I-131/LL, 26 at the two indicator locations and 13 at the control location. Analyses for II-3 were performed on 12 samples, eight at indicator locations and four at the control location. Thirty-nine samples were analyzed for other radionuclides, 2G at indicator locations and 13 at the control location.
All Selected Licensee Commitments radionuelides except 11-3 showed zero ranges indicating that no other detectable activity was measured. All radionuclides , except 11 - 3 , were not significantly different from preoperational data and the control location levels. All radionuclides except 11-3 control did not differ significantly from the fourteen-year ave rage.
There is a moderate to poor probability of an increasing trend for 11-3 indicator flowever, the 1993 concentration of 11-3 resulted in only 3.43%
of the Selected Licensee Commitments reportinglevels as shown by Table
- 3. 3-B . All other radionuclide indicators and controls exhibited decreasing trends. Table 3.3-A illustrates these trends.
'r 1
3-11
Table 3.3-B shows the percentages of environmental concentrations to the Selected
- Licensea Commitments reporting levels for the indicators at the location with the highest, annual mean for 1993.
Table 3.3-B_
Radionuclide Concentration (pCi/l) Reporting Level (pCi/l) Percentage 11- 3 6.85E2 2.00E4 3.43%
Mn--54 0.00E0 1.(X)E3 0.00 %
Fe-59 0.00E0 4.00E2 b. I Co-58 0.00E0 1.00E3 0.00 %
Co-60 0.00E0 3.00E2 0.00 %
Zn-65 0.00E0 3.(M)E2 0.00 %
Nt>-95 0.00E0 4.tK)E2 0.00 %
Zr-95 0.(X)EO 4.00E2 0.00 %
l-13I/l.L 0.00E0 2.(X)EO 0.00 %
Cs-134 0.00E0 3.(X)EI 0.00 %
Cs-137 0.00E0 5.0fA1 0.00 %
Ba/La-140 0.00E0 2.00E 2 0.00 %
~.
t 3-12
Table 3.3-A Con. centration of Radionisclides in Surface Water (Page 1 of 3)
.w Concentration (pCi/ liter)
Year H-3 Mn-54 Fe-59 Co-58 indicator Control Indicator Control Indicator Control Indicator Control 1979 1.85E2 1.66E2 845E-l 6.35 E- 1 1,69E0 2.55 EO 1.47E0 1.90E- 1 1980 2.13 E2 1.93E2 2.17E0 5.81 E-1 5.21E-l 9.48 E- 1 1.17E0 -5.16E-2 1981 1.75 E2 1.70E2 4.95E-2 - 1.10E0 l.79E0 3.40E0 9.74 E- 1 - 1.35 E- 1 1982 3.30E2 1.23 E2 1.02E0 - 1.22 E- l 1.97E0 -3.99 E-2 1.63 E- 1 5.10E-l 1983 5.75E2 3.67E2 -2.30E- l 9.74E-l 1.76E0 -7.08 E- l 6.14 E- l 5.08 E-2 1984 4.10E2 2.65 E2 -7.56E-2 -4.19 E- l -4.88 E- 1 9.15 E- 1 3.30E-l 4.24 E- l 1985 7.33 E2
- 1.O'l EO -4.75 E- 1 3.9 I E- 1 I .04EO 7.6iE-I i .65 E-1 1986 2.33E3 6.13 E2 5.13E-1 3.97E-l - 1.67 E- l 4.36E-2 -2.95 E-3 3.3 t E-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.(X)E0 0.00E0 0.(X)E0 0.00E0 0.00E0 0.00E0 1990 6.77 E2 0.00E0 0.00E0 0.(X)E0 0.00E0 0.00E0 0.00E0 0.00E0 1991 7.53 E2 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1992 8.13 E2 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 14 Yr.
Avg. 7.05 E2 1.91E2 4.04 E-l 1.85E-l 1.37E0 6.35 E-l 3.92 E- 1 1.19 E- 1 1993 6.85 E2 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 Corr.
Coef 0.41 -0.30 -0.62 -0.55 -0,15 -0.66 -0.83 -0.41 0 No sample analyzed.
NOTE: All negative values were replaced with "zero's" for calculational pucposes.
3-13
i l
l Table 3.3-A Concentration of Rajugnuclides in Sudsice Water - l (Page 2 of 3) f i
Concentration (pct / liter)
Year Co-60 Zn-65 Nb-95 Zr-95 Indicator Control Indicator Control Indicator Control Indicator Control l
1979 2.45E0 2.60E0 8.62 E-l -5.33 E-l ~2.5 3 E- l
- 5.77 E- l * -2.53 E-l
- 5.77E-l
- 1980 1.36E0 1.12 E0 7.70E-l I.80E0 1.00E0 + -2.54 E-l
- 1.00E0 * -2.54 E-l
- 1981 2.47 E-l 1.54E0 -6.29 E- 1 6.93 E-1 -2.92 E- l 3.50E-2 1.98E0 9.04 E-1 1982 1.14E0 6.02 E- l 6.28E-l -3.93 E- l 2.16E0 8.89 E-l 2.23E0 8.92 E-1 1983 1.66E0 2.Ol EO - 1.20E0 4.71 E- l 3.22 E- 1 1.15E0 3.27 E-2 1,41E0 1984 1.47E0 3.38 E- 1 -9.79 d-2 5.91E-l 8.59 E-l 2.66E-2 1.67E0 - 1.45 E-1 1985 3.86E-l 9.97 E-l I.22E0 -2.43 E-2 6.10E-l 4.17 E-1 1.16E0 1.74E0 1986 - 1.36 E- 1 2.24E-2 - 1.24 E0 -1.65 EO 1.05E0 1.19E0 1.33E0 -3.91 E-1 1987 5.20E0 0.00E0 0.00E0 0.00E0 4.50E0 0.00E0 1.20El 0.00E0 1988 0.00E0 0.(X)E0 2.70E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1989 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1990 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 l
1991 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 ;
! 1992 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 l
l 14 Yr. i l
Avg. 9.94 E-l 6.59E-1 4.4 t E-l 2.54E-l 7.50E-1 3.06E-1 1.53E0 3.95 E-1 i 1993 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 i I Corr.
Coef -0.38 -0.80 -0.19 -0.54 -0.18 -0.42 -0.09 -0.49 i
Nb-95 and Zr-95 analyzed as Nb/Zr-95 NOTE: . All negative values were replaced with "zero's" for calculational purposes, j 3-14 :
i
1 l
i 4
lableA3-A Concentration olBadqauplidesJanurface WaleL.
(Page 3 of 3) 1 i
Concentration (pCi/ liter)
Year 1-131 Cs-134 Cs-137 Ba/La-140 Indicator Control Indicator Control Indicator Control Indicator Control 1979 2.66E0 -8.27 E-l -3.62 E- 1 - 1.00 E- l 2.63 E0 -2.21 E- l 2.26E-l -4.25 E-l 1980 1.13E0 1.20E0 -2.60 E- 1 -9.98 E- 1 1.97E0 1.27EO 9.70E- l -3.20E-l 1981 2.32 E0 -6.85 E- l 2.10E-2 1.88 E-l I.05 EO 2.45E0 6.98 E-l 8.66E-l 1982 -3. l l E- l -9.19 E- l -5.68 E- l 8.34E-l 1.23 E- 1 1.65 E0 4.30E-l ~4. l l E- l 1983 1.89E0 2.88 E0 7,87 E- 1 2.50 E-l 8.43 E-l 2.30 E.- l I.38E0 2.89 E- l 1984 3.02 E-2
- 1.58 E- l
- 7.36E-1 1.70E0 9.46E-l 3.30E-2 -2.84 E- l -6.81 E-3 1985 -8.69 E-2 * -7.90E-2
- 1.72E0 1.25E0 1.23E0 3.26E-l 3.79 E- l 4.53 E-1 l
1986 8.94 E-2 ' 2.13 E-2
- 7.54 E- l 1.13 E- 1 5.61 E-l 1.97 E- l 8.72 E- 1 8.29E-l l
1987 0.00E0 0.00E0 4.40E0 0.00E0 4.70E0 0.00E0 0.00E0 0.00E0 1988 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1989 OJK)EO 0.(X)EO 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1990 0.00E0 0JX)EO 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1991 0.(X)E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1992 0.00E0 0.(X)E0 0.00E0 0.00E0 01X)E0 0.00E0 0.00E0 - 0.00E0 14 Yr.
Avg. 5.80 E-l 3.04 E-l 6.O l E- 1 3.10E-l 1.00E0 4.40E-l 3.54 E-1 1.74 E-l 1993 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 Corr.
Coef -0.7 l -0.33 -0.02 -0.29 -0.45 -0.58 -0.61 -0.29
- I-131/LL analysis data used.
NOTE: All negative values were replaced with "zero's" for calculational purposes.
3-15
l 3.4 MILK In 1993, 104 milk samples were analyzed, 78 at the three indicator locations and 2G at the control location.
All Selected Licenseo Commitments radionuclides showed a zero range indicating no detectable activity was measured in 1993. The I-131/LL, Cs-131, Cs-137, and Ba/Ln-140 concentrations did not significantly differ from the fourteen-year average, preoperational data, and control levels.
All radionuclide indicators and controls exhibited decreasing or no probability of a trend. These trends are illustrated in Table 3.4-A.
Table 3.4-B shows the percentages of environmental concentrations to the Selected Licensee Commitments reporting levels for the indicators at the location with the highest annual mean for 1993.
Iable 3.4-B Radionuclide Concentration Reporting Percentage (pCill) Level (pCill) 1-131/LL 0.00E0 _
3.00F0 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%
3-16
Table 3.4-A Concentration of Radionuclides in Milk Concentration (pCi/ liter)
Year 1-131 Cs-134 Cs-137 Ba/La-140 Indicator Control Indicator Control Indicator Control Indicator Control 1979 6.87 E-3 -6.13 E-2 -7.05 E- l 7.63 E- l 2.48E l 6.04E0 0.00E0 -6.15 E-l 1980 1.06E0 3.22E-2 -7.94 E-2 -6.12 E- l 1.72E l 4.13 E0 1.29E0 1.33 E- 1 1981 -3.70E-3 -6.54 E-2 1.37E0 -2.88 E- l 2.04 E l 4.15 EO 3.77E-l -7.95 E-2 1982 -3.22 E-2 -8.49 E-2 9.44E-l ~4.38 E-2 1.21 E l 5.20E0 2.31 E- l -4. l l E- l 1983 1.23 E-2 -4.57 E-2 1.26E0 1.35 E0 2.02 E l 2.82 E0 4.44 E-1 2.35 E-l 1984 1.78E-2 -4.30E-2 1.08 E0 1.80E0 1.48 E l 2.56EO 4.79 E- 1 1.43 E-1 1985 2.00E-2 -5.80E-2 9.32 E- 1 1.99E-l I .42 E l 2.72E0 5.78 E-l 5.97 E-l 1986 8.30E-l 7.55 E-l 2.36E0 9.38 E- 1 3.74 E0 3.45 E0 2.95 E- l 1.08 E- l l
1987 4.80E-l 0.00E0 5.10E0 3.60E0 5.20E0 8.60E0 0.00E0 4.40E0 1988 0.00E0 0.00E0 0.00E0 0.00E0 3.40E0 2.90E0 0.00E0 0.00E0 1989 0.00E0 0.00E0 OJX)EO 0.00E0 6JX)EO 5.60E0 0.00E0 0.00E0 1990 OJX)EO 0.00E0 0.00E0 0.00E0 5.30E0 2.60E0 0.00E0 0.00E0 1991 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1992 OJX)EO 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 OJX)EO 0.00E0 14 Yr.
Avg. 1.73E-1 5.62E-2 9.32 E- l 6.32 E-l 1.05 E l 3.63E0 2f>4 E- 1 4.01 E-1 1993 0.00E0 OJX)EO 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 Corr.
Coef -0.28 -0.02 -0. I 4 -0.I6 -0.92 -0.56 -OR) 0.03
... n -, __
l NOTE: All negative values were replaced with "zero's" for calculational purposes.
l 3-17 .
i l
1 l
3.5 BROADLEAF VEGETATION In 1993,48 broadleaf vegetation samples were analyed, 3G at the three indicator locations and 12 at the control location. The 1986 data is higher than the other years due to the Chernobyl accident.
All Selected Licenseo Commitments radionuclides except Cs-137 showed zero ranges indicating that no detectable activity was measured. Only one of 3G samples taken indicated Cs-137 activity. However, this concentration resulted in only 0.80% of the Selected Licensee Commitments reporting level.
The correlation coefficients for the location with the highest annual mean indicated a moderate to poor probability of an increasing trend for Cs-137 indicator. Since there were anomalous results in 1984 for Cs-134 and Cs-137, new concentrations for these radionuclides were calculated using the location with the highest annual mean excluding these anomalies. Ali radionuclide indicators and controls except Cs-137 exhibited decreasing trends. These trends are illustrated in Table 3.5-A.
Table 3.5-B shows the raccentage of environmental concentrations to the Selected Licensee Commitmec ts reporting levels for the indicators at the locations with the highest annual mean for 1993.
Table 3.5-B i
Radionuclide Concentration Reporting Percentage (pCi/kg) Level (pCi/kg) 1-131 0.00E0 1,00E2 0.00%
Cs-134 0.00E0 l.00E3 0.00 %
Cs-137 1.60El l 2.00E3 0.80 %
l l
l 3-18 1
Iabla15-A Concenttaion of Ralliong_cIl#es in Broadled y.ege_t.ation Concentration (pCi/kg-wet)
YEAR l-131 Cs-134 Cs-137 Indicator Control Indicator Control Indicator Control 1979 -5.82 E0 7.30E-1 - l .00E l - 1.06E l 2.19E l 1.93 El 1980 1.9 t E l 6.15E0 -2.59EO - 1.25 E l 2.30El 1.92El 1981 -1.87E0 3.16E0 1.24 E l 5.96EO 3.(M E l 2.02El 1982 1.4 ] El 6.59E0 1.50El -6.31 E- 1 2.46El I.22El 1983 1.13 El 7.19EO 4.13 E0 1.24E0 4.07EO 7.85 E0 1984 6.06E0 5.99E0 8.46E0 2.80E0 1.02 E l 1.05E l 1985 5.67E0 7.98 E- l 9.77E0 1.66El 8.05 E0 2.37E-2 1986 2.85 El 1.76E l 2.53 E l 2.07E l 4.03E l 1.27E l 1987 0 (X)EO 1.10EI 1.70E I 2.50EI 2.20E I 1.70EI 1988 0.00E0 0.00E0 0.00E0 0.00E0 3.90E l 3.40El 1989 0.00E0 0.00E0 0.00E0 0.tX)E0 9.60E l 0.00E0 1990 0.(X)E0 0.00E0 0.00E0 0.00E0 4.00El 0.00E0 1991 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1992 0.00E0 0.00E0 0.00E0 0.(X)E0 3.30El 0.00E0 14 YEAR AVERAGE 6.05E0 4.23E0 6.58E0 5.16E0 3.19El 1.09El 1993 0.00E0 OAX)EO 0.00E0 0.00E0 1.60E l 0.00E0 CORRELATION COEFFICIENT -0.40 -0.33 -0.28 -0.06 0.38 -0.55 NOTE: All negative values were replaced with "zero's" for calculational purposes, i
3-19
3.6 SHORELINE SEDIMENT in 1993, six shoreline sediment samples were analyzed, four from two indicator locations and two at the control location.
The correlation coefficient for the location with the highest annual mean indicated a moderate to poor probability of an increasing trend for Cs-137 indicator, llowever, the Cs-137 concentration only corresponds to a small percentage of the Selected Licensee Commitments reporting level
- as shown in Table 3.6-B. All other ludicators and controls exhibited decreasing trends. These trends are illustrated in Table 3.6-A and Figu re el .
Igble 3.6-B (
i Radionuclide Concentration Reporting Percentage (pCiAg) Level (pCiAg)
Cs-134 0.00E0 3.00E3 0.00 %
Cs-137 9.30E1 3.00E3 3.10 %
l l FIGURE 4 l
l CONCENTRATION OF RADIONUCUDES IN \
1 SHORELINE SEDIMENT .l pCllkg-wet 300 ,--[ j g-- j 7 - ;---~
1 t i
l l
i 200 p --+
j 100 L-- I-l 0 - - -
' I b[ -
is.o 19eo 1981 t982 tosa 1984 isso isee 19er 198a iwo tow iEt tela 103 Year . _ _
3
._ -#= Cs 137 Indicator --dr- Cs 137 Control (
L .a i
3-20
Table 16-A Cangentratton_.of Ra41omtc.lidas..lp Shoreline Sediment Concentration (pCi/kg-dry) ye;g Cs-134 Cs-137 Indicator Control Indicator Control 1979 0.00E0 1.20El 1.20EI - 1.77 E I t
1980 -3.53 E0 - 1.85 E I l.44 E I 6.88El 1981 3.97El 6.08E0 3.36El I.65E0 1982 7.67El 4.61 E I 4.40EI 2.13 El 1981 7.65El 2.78El 8.02 E I 3.28EI 1984 3.34El 1.32 El 9.13 E I 3.65 El 1985 2.02 E I 1.03 EI I.61E2 1.70E I 1986 6.35 E I 3.67El 1.53 E2 1.95 E I j 1987 4.20E I 2.40El I65E2 0.00E0 1988 9.10E0 0.00E0 2.66E2 1.70El 4 1989 5.30E1 0.00E0 6.50E I 1.40E1 j
1990 0.00E0 0.00E0 6.10El 2.10El i l
1991 0.00E0 0.(X)E0 0.00E0 0.00E0 1992 9.20E0 0.00E0 8.60E I 0.00E0 14 Year Ascrage 3.02E l 1.26El 9.54E l 1.78El 1993 0.00E0 0.00E0 9.30E1 0.00E0 l
Correlation Coefficient -0.30 --0.4 2 0.41 -0;45 NOT1?: All negative values were replaced with "zero's" for calculational purposes.
l-l 3-21
3.7 FISH In 1993.12 fish samples were analyzed, six at the indleator locations and six at the control location. All radionuclides were not significantly different from the fourteen year average. Co-58, Co-00, and Cs-137 concentrations correspond to a small percentage of the Selected Licenseo Commitments reporting level as shown in Table 3.7-B. The correlation coefficients for the location with the highest annual mean indicated a moderate to poor probability of an increasing trend for the indicator concentrations of Mu-51, Co-58, Co-60, Cs-13<l, and Cs-137. All other radionuclide indleators and controls exhibited decreasing trends. These trends are illustrated in Table 3.7-A and Figure 5.
Table 3.7-B_
Radionuclide Concentration (pCiAg) Reporting Level yCiAg) Pen.cntage Mn-54 0.00E0 3.00E4 0.00 4 Fe-59 0.(X)E0 1.00E4 0.00 %
Co-58 8.20E l 3.00E4 0.27%
Co-U) 1.30E l I,(X)E4 0.13%
Zn-65 0 tX)EO 2.00E4 0.(X)%
Cs-134 0.00E0 100E3 0.lXFt Cs-137 1.60El 2.(X)E 3 0.80 %
==
1 1
3-22 l
lable_3J-A Qongmittallqttof Radionupildes in. flab _
(Page 1 of 2)
Concentration (pCi/kg-wet)
Year Mn-54 Fe-59 Co-58 Co-60 Indicator Control Indicator Control Indicator Control Indicator Control
- * * -2.78 E- l
- 9.86E0 1979 0.(X)E-0 3.7 t El 1980 - 1.9 7 E l 1.14 E l - 1.95 E l 4.74 E l 8.36E0 8 NIE0 -2.25 E l 1.14E l 1981 -2.71 E0 2.74 E0 3.70E0 2.97 El -2.98 E0 4.25 EO -2.65 E0 -2.36E0 1982 -3.83 E0 1.28El 0.00E0 8.47 El 8.16E0 2.65 E0 -4.34E-l 2.95 E0 1983 -2.60E0 - l .84 E0 -8.68 E0 8.28E0 2.60E l -5.3 t EO l.llEl 2.42E0 1984 3.61 EO 3.87E0 -l.23El 2.21 E l I .45 E2 4.15 E0 2.82El 2.83 E0 1985 2.51E-l - l .75 E0 4.25 E0 4.49 EO 7.19 E0 1.32 E l 1.72E l 1.55 El 1986 1.03E0 -l .9 t EO - 1.2 i E0 3.77 E0 3.17El - 1.79 E0 2.96E l 5.13E0 1987 0.00E0 0.(X)E0 0.(X)E0 0.(X)E0 2.71 E2 0.00E0 1.25E2 0.00E0 1988 1.20E l 0.00E0 0.00E0 0.(X)EO 7.70E l 0 (X)EO 0.(X)EO 0.00E0 1989 9.00E l 5.40E0 0(X)E0 0.00E0 4.05 E2 0.00E0 2.99E2 0.00E0 i 1990 0.lX)EO 0.(X)E0 0.00E0 0.(X)E0 5.60E l 0.(X)E0 4.10E l 0.00E0 l l
1991 6.20E0 0.(X)E0 0.00E0 0.00E0 1.40El 0.00E0 6.50El 0.00E0 1992 0.00E0 0.(X)E0 0.00E0 0.00E0 0.00E0 01X)E0 0.00E0 0.00E0 14 Yr.
Avg. 8.70E0 2.59 E0 6.12 E-l L.70El 8.07El 2.35E0 4.74El 3.58E0 t 1993 0.00E0 0.(X)E0 0.00E0 0.(X)EO 8.20El 0.00E0 1.30El 0.00E0 l Corr.
- Coef 0.22 -0.46 -0.26 -0.72 0.28 -0.42 0.30 -0.57 l
o Ne sampic analped.
NOTE: All negative values were replaced with *zero's" for cakmlational purposet 3-23
I Iable 3.7-A C_oncenttalLOR_of RadlonucjLd_e_s in Fish (Page 2 of 2)
Concentration (pCi/kg-wen l YEAR Zn-65 Cs-134 Cs-137 l
l Indicator Control Indicator Control Inificator Control 1979 * *
- 1.73E0 -4.17 E0 2.20El 1980 -3.22 E l -2.26El -2.70El -2.10E0 -4.13 E0 8.07E0 1981 4.62E0 1.16E0 - 1.99E0 9.09E0 1.80E l 2.77E l 1982 -l.39El -9.2 t E0 -8.22 E- 1 3.57 E-l 2.69El 9.52 E0 1953 -1.07 E0 4.86E0 - 1.32 E0 -2.57E0 6.03 E l 2.08E l 1984 -2.87 E0 -3.26E0 3. l l E l -7.09 E- l 4.38E l 8.18E0 1985 -2.55 E0 3.17 E0 -l .56E0 5.22E0 1.86El 1.48 E l 1986 -8.09E0 - 1.40E l I.67E l 1.56E0 3.49El 8.64 E0 1987 0.00E0 0.00E0 2.60E l 0.00E0 5.10El 2.90El 1988 0.00E0 0.00E0 2.70E l 0.(X)E0 3.60El 2.30El 1989 0.00E0 0.00E0 1.10E l 0.(X)E0 3.50El 1.50E l 1990 0.00E0 0.00E0 0.00E0 0.00E0 3.30El I.60El 1991 0.00E0 0.00E0 5.90E0 0.00E0 2.60El 0.00E0 1992 0.00E0 0.00E0 0.00E0 0.00E0 2.90E l 1.10E l 14 Year Average 3.55E-1 7.80EI 9.05E0 1.16E0 3.17El 1.57El 1993 0.00E0 0.00E0 0.00E0 0.00E0 1.60E l 1.90El CORRELATION COEFFICIENT -0.31 -0.39 0.11 -0.32 0.28 -0.35
- No sample analyzed.
i NOTE: All negative values were replaced with "zero's" for calculational purposes.
3-24
~
I l
l l f.a.
i FIGURE 5 I
l l
CONCENTRATION OF CO-60 i PCl% wet IN FISH 600 , -
t I i i I l
$% REPORTING LEVEL l- l
[ ,
500 l 1 l t 400 p - + - - + - - - -d 300 i ! l l l I i l 200 +-+ q --
I i 100 - - - --
0 ' - a-1979 1980 1981 1982 1983 1984 1985 1906 1967 1968 1909 1990 1991 1992 1993 Year i
l 1
l l
3-25
~ 3.8 DIRECT GAMMA RADIATION 4
- In 1993,180 TLD's were analyzed,176 at Indicator locations and four at the control location. The 1993 exposure rato nt the indicator location with the highost annual mean did not algnificantly differ from the F preoperational data or fourteen-year average. Table 3.8-A and Figuro G liluntrate this summary.
Table 3.8-A TLD Exposure from Direct Radiation Exposure (mrem /> r)
YEAR Indicator Control 1979 8.76E l 8.32El 1980 1.16E2 1.05 E2 4
1981 1.45 E2 1.05E2 1982 136E2 1.10E2 1983 1.75E2 1.30E2 1984 1.20E2 9.02111 1985 1.52E2 1.27E2
.l 1986 1.40E2 1.10E2 1987 1.43 E2 1.23E2 l
1988 1.08E2 5.48EI 1989 9.77El 7.55El i 1990 8.30El 6.23El 1991' 4.60El 6.80El .)
i 1992 1.12E2 7.60E1 )
14 Year Average 1.22E2 9.43El 1993 1.00E2 7.20El NOTE: The expected background for North Carolina is 120 mrem per year -
from FSAR 11.G.1.
3-26 .
l'
(
FIGURE 6 TLD EXPOSURE mR/yr FROM DIRECT RADIATION 200 ,-- ,
i 160- - - - - - + -
p- -- L 120 -- - ~ - -
M- -*-
l l .
i > l 80 -- - -
-t- -
l 40 ~~ d--- - - --
0 - - ' --- O 1970 1980 1M1 1M2 IMS IM4 1M6 1986 1M7 1986 1984 1940 1M1 1982 1996 i Year i
-e- TLD Indicator -*~ TLD Control 7 i I
_ _ _ . - ~ . . _ _ . _ _J .
I l
l l
The test statistic, or t-test, was used to compare the TLD measurements during preoperation to those taken during 1993. In this case, ratios of results from the 1-2 mile radius and the <!-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 operations, the hypothesis was used that a significant change in the ratio from one year to another would be indicative of an environmental effect or some other phenomena requ! ring investigation. A statistically sign!ficant change in the ratio was determined by comparing the calculated t-value to the expected value of the test statistic based on the number of measurements and the desired accuracy of the results.
The value of the t-statistic was calculated by comparing preoperational results to 1993. As shown in Table 3.8-B, the t-value was -1,373. This is well within the expected value of i 2.056, based on 20 degrees of freedom and 95%
confidence in the result (a = 0.025, n = 2G). As a result, it can be concluded that the dose rates measured around McGuire in 1993 do not differ significantly from those found during preoperation.
3-27
' 1 l
l Tablo 3.8-D Comparison of Inner Ring /Outor Ring TL.D Results 1993 (mtlyr) Preop (mtlyr)
Inner Rind 56.47 79.14 Outer Ring 55.54 88.16 Ratio 0.995 0.91 Variance 0.029 0.02 t-value -1.373 t-table (95%) -2.056 Further review of the data in Figure 3.8-A shows dose rates around McGuire have decreased steadily from 1987 to 1990. An investigation into the cause of the downward trends was completed by the General Office Rartwaste Processing and Dosimetry Groups in 1993. The investigation consisted of an evaluation of TLD readout control parameters, an intercomparison study with environmental TLD's from two other utilities and a statistical comparison of DPC TLD results to colocated NRC TLD results. Ilused on the review it was concluded that the downward trend appeared to be caused by TLD readout parameters used and the manner in which controls were evaluated. This problem was corrected with the
! implementation of a new TLD reader in 1989 and a better Quality Control program . The statistical evaluation showed the results do not differ l significantly from colocated NRC results and so, no further corrective
, actions were taken. Copies of the investigation reports are available in l the station masterfile.
i l
i l
3-28
3,9 FOOD PRODUCTS In 1993,15 food products (crops) samples were analyzed, all at the two indicator locations. No control site was available for food products in 1993. All Selected Licensee Commitments radionuclides exhibited a zero range indicating no measurable activity present.
All ludicators exhibited decreasing trends. No control sites were available for 1981 through 1993; therefore, a representative correlation coefficient could not be calculated for the control data. Table 3.0-A illustrates this summary.
Table 3.9-11 shows the percentages of environmental concentrations to the Selected Licensee Commitments reporting levels for the indicators at the location with the highest annual mean for 1993. No activity was detected and therefore no reporting levels were approached.
Table 3,9-E.
Radionuclide Concentration (pCUkg) Reporting 1.esel (pCUkg) l'ercentage I-131 0,00E0 1,00E2 0.00 4 Cs-134 OJX)EO 1.00E3 OW4 Cs-137 n.00E0 2.00E3 0.009r i
l I
i 3-29 )
Ic hle_19:A._C9ncent tation_qMadJnnuclidgs_in_Eond_Etodunts l
Concentration (IC/kg-we0 YEAR l-131 Cs-134 Cs-137 Inihcator Control textic:itor Control lixlicator Coritrol 19N' -5.82 E0 7.30E-l - 1.00E l - l .06E l 2.19El 1.93El 1980* 1.9tEl 6.15 EO -2.59 EO - 1.25 E l 2.30El I.92 El 1981* - l .87 E0 3.16EO l.24El 5.96E0 3.04 El 2.02El 1982* l.41El 6.59E0 1.50El -6.31 E- l 2.46E l I.22El 1981* 1.13El 7.19E0 4.13 E0 1.24E0 9.07E0 7.85 E0 1984 -3.08 (i.-l 4.49E-l 8.45E0
" -2,4S t 0 ' 7,49 E0 "
1985 1.02 E-l
' ' 2.15E l "
1986 1.52El 1.74 E0 0,(X)EO " ** "
1987 0.(X1E0 2.90E l 1988 " 0.00E0 **
0.00E0 '
0.(X)EO 1989 0.00E0 " 0.00E0 " 0.00E0 **
1990 0.(X)EO **
0.(X)E0 " U.lX)EO **
" 0.(X)E0 " 0.(X)E0 "
1991 0.(X)E0 1992 0.(X)E0 " 0.(X)EO ** 0.00E0 "
i 14 YliAR AVERAGE 4.27E l 4.76E0 2.4 t E0 1.44E0 1.26El 1.58El
" " 0.00E0 "
1993 0.00E0 0.(X)EO l
CORREL.ATION COEFFICIENT -0.47 --
-0.45 - -0.76 --
(
- Ilroadleaf vegetation samples used for food products media.
I
- No control sito avnllable.
--- Insufficient < lata to calculato a representativo correlation coefficient.
NOTE: All negative values were replaced with "zero's" for calculational purposes.
3-30
3.10 LAND USE CENSUS The land uso consus was completed June 21, 1993 and the results are shown in Table 3.10 and Figuro 7. Currently, two irrigated gardens are being stunpled. During the 1993 census, eleven additional irrigated gardens were identified. Theso gardens were reviewed with respect to amount of irrigation, alzo, willingness to participato, crop types, and location. Ono garden will be ovaluated during the 1991 growing season to determino reliability compared to current sites. The consus also revealed five milk animal loentions that were not included in the 1992 sampling program, flowever, four of the locations do not produce sufficient volume to be added to the program and the fifth is outside the five kilometer area of participation. The nearest residence is located in the East sector at 0.16 mitos.
l 1
l l
l l
l l
3-31
p+ =
I y
1 Table 3.10 Land Use Census Results ,
Page 1 of 2 SECTOR DISTANCE N 2.5 miles Nearest Recidence Nearest Meat Animal None in 5 miles Nearest Garden 2.56 miles Nearest Cow None in 5 miles i Nearest Goat None in 5 miles NNE Nearest Residene.e 1.29 miles Nearest Meat Animal None in 5 miles Nearest Garden 2.52 miles Nearest Cow None in 5 miles Nearest Goat None in 5 miles NE Nearest Residence 1.2 miles l Nearest Meat Animal None in 5 miles Nearest Garden 2,1 miles Nearest Cow None in 5 miles Nearest Goat None in 5 miles ENE Nearest Residence G.56 mr'es Nearest Meat Animal 3.95 miles -
Nearest Garden 2.55 miles Nearest Cow 3.86 miles Nearest Goat ' None in 5 miles E Nearest Residence. 0.46 miles i
Nearest Meat Animal None in 5 miles . -
l Nearest Garden 0.47 miles I- Nearest Cow 2.46 miles
- j. Nearest Goat None in 5 miles ESE Nearest Residence ' O.82 miles Nearest Meat Animal 1.3 miles Nearest Garden 1.23 miles -
Nearest Cow 3.07 miles Nearest Goat 1.4 miles -
SE Nearest Residence 1.17 miles Nearest Meat Animal 1.6 miles l Nearest Garden 1.21 miles Nearest Cow None in 5 miles Nearest Goat None in 5 miles l SSE Nearest Residence 1.06 miles l Nearest Meat Animal 1.48 miles Nearest Garden . 1.26 miles Nearest Cow 2.76 miles Nearest Goat 2.09 miles
.S Nearest Residence 1.62 miles
- Nearest Meat Animal 3.01 miles
- 1. Nearest Garden 1.49 miles ,
Nearest Cow None in 5 miles Nearest Goat None in 5 miles 1
3-32
Table 3.10 Land Use Census Results Page 2 of 2 SECTOR DISTANCE SSW Nearest Residence 2.57 miles Nearest Meat Animal 2.75 miles Nearest Garden 2.95 miles Nearest Cow None in 5 miles Nearest Goat None in 5 miles ;
SW Nearest Residence 1.8 miles Nearest Meat Animal None in 5 miles i Nearest Garden 1.8 miles l Nearest Cow None in 5 miles i Nearest Goat None in 5 miles 1 WSW Nearest Residence 1.01 miles l Nearest Meat Animal 3.72 miles Nearest Garden 1.16 miles Nearcsl Cow None in 5 miles Nearest Goat 3.97 miles W Nearest Residence 0.82 miles Nearest Meat Animal 3.53 miles Nearest Garden 0.9 miles Nearest Cow None in 5 miles l
Nearest Goat None in 5 miles WNW Nearest Residence 0.91 miles Nearest Meat Animal None in 5 miles Nearest Garden 2.15 miles Nearest Cow None in 5 miles Nearest Goat None in 5 miles NW Nearest Residence 0.93 miles Nearest Meat Animal None in 5 miles Nearest Garden 1.37 miles Nearest Cow None in 5 miles Nearest Goat None in 5 miles NNW Nearest Residence 1.53 miles Nearest Meat Animal 3.67 miles Nearest Garden 1.78 miles Nearest Cow None in 5 miles Nearest Goat 1.78 miles 3-33 l
I
f ,
g A- 4 '~
'N ; \ .<
f 4
y4- j - ]+
St: tion ^1993 Land
,3 use census Map
'N g I 4+
p;f^
r ~ q -(%.-
!p j ,
- M ilk cow
_ g -War ,, -
\ [ j ,h[ ~a n $. s
' + G oat
/ +
f
[ -
f A trrig a te d g a rd en y f gtw s4~ k aJeg ,ge f
- j . . _ rr,..t.d carden
' p- 1
. t
'3 A (/. #
1},y-y ., a,,,,,,,,
3
,.q j G
[/ Beef cow I /'
,b N / r
. }Jy ,
/ ,-
19 ? y
\[ .,
,, g streams and
/1 d ,MQ 7 '
T fs -
S h o relin e s Y
)[ /3 g,\
1 W 3 I
j kg e "/ -
.p -
x -
rn Roads
_(\
county iin e.
~
sp L l .f x
ma w -t Fy +e . 4 ,,. / . J ' >. R,g , 4y y s
- 2-
{ J s t6 n m i
@5\;& -
% -x 7NJA t p (M@ ,,) "\"
l' xes t -
f4 c
x ; s sc_ m s_
s y,; e i
\A r,oi.c io. u.c. si. . ei.e.
s s/
be m c"h i
N / b M - r '-.. V ^=au=t '993 let 02/2 6464 g
_ __- -___--.-_ _____ x_
4.0 EVALUATION OF DOSE FROM ENVIRONMENTAL MEASUREMENTS VERSUS ESTIMATED DOSE FROM RELEASES 4.1 DOSE FROM ENVIRONMENTAL MEASUREMENTS Doses were estimated for measured concentrations of radionuclides in direct pathways to man using NRC Regulatory Guide 1.109 methodology.
The highest annual mean values for each sample type and radionuclide were used after the background concentrations, as measured at the controllocation, had been subtracted. The maximum exposed individual doses are summarized in Table 4.1.
4.2 ESTIMATED DOSE FROM RELEASES
- Doses were estimated for release concentrations of radionuclides in direct pathways to man using NRC Regulatory Guide 1.109 methodology.
The doses were cale 11ated using GASPAR and LADTAP computer programs. The maximum exposed individual's doses are summarized in Table 4.1.
4.3 COMPARISON OF DOSES Comparisons of environmental and effluent doses are shown in Table 4.1.
In general, estimated doses from releases are higher than calculated environmental doses. This comparison demonstrates the conservative methodology used in projecting effluent doses.
In the liquid pathway, no' environmental doses were evaluated for the bone, thyrold, kidney, and lung due to the dose factors not available for the media which indicated activity in 1993.
In the gaseous pathway, all the environmental data doses e.re the result l of one Broadleaf Vegetation sample that contained Cs-137. The doses were conservatively calculated based on only that one sample.
The doses, as calculated using the environmental sample results, are well below the limits specified in Selected Licensee Commitments Manual ,
Section 16.11-12. 1
'l 4 -- I
TABLE 4,1 (Page 1 of 2)
- j. 1993 ENVIRONMENTAL AND EFFLUENT DOSES Llauld Rc:sase Pathway 1
i r
l Environmental Critical l Organ or Effluent Critical Pathway Dose Age Data (mrem) l Skin Environ. Teen Shoreline Sediment 1.77E-3 Skin Effluent Teen Shoreline Sediment 2.33E-3 Bone Environ. - -
0.00E0 l Bone Efiluent Child Fish 7.15E-2 l Liver Environ. Adult Fish 1.87E-3 j Liver Efiluent Child Dr.nking Water 1.38E-1 T. Body Environ. Teen Fish 4.26E-3 T. Body Efiluent Adult Drinking Water 1.01 E-1 Thyroid Environ. - -
0.00E0 Thyroid Effluent Infant Drinking Water 8.72E-2 i
Kidney Environ. - -
0.00E0 Kidney Effluent Child Drinking Water 8.61 E-2 Lung Environ. - - 0.00E0 Lung Effluent Child Drinking Water 7.11 E-2 l
GI-LLI Environ. Adult Fish 3.70E-2 GI-LLI Effluent Adult Drinking Water 9.15E-2 l
l l
1 4-2
1 TABLE 4.1 (Page 2 of 2) 1993 ENVIRONMENTAL AND EFFLUENT DOSES Gaseous Release Pathway Noble Gas Exposure Environmental Maximum I
Organ or Effluent Critical Pathway Dose Data (mrem)
Skin Environ. - -
Noble Gas Not Sampled Skin Effluent N/A Noble Gas Exposure 1.38E0 T. Body Environ. - -
Noble Gas Not Sampled T. Body Effluent N/A Noble Gas Exposure 6.86E-1 lodino, Particulate. and Tritium Exposure Environmental Maximum I
Organ or Effluent Critical Pathway Dose Data (mrem)
Bone Environ. Child Broadleaf Vegetation 1.36E-1 Liver Environ. Child Broadleaf Vegetation 1,30E-1 T. Body Environ. Adult Broadleaf Vegetation 7.31 E-2 Thyroid Environ. - - 0.00Et l Thyroid Effluent Infant Goat Milk 2.68E-1 _
Kidney. Environ. Ch!id Broad 8aaf Vegetation 4.24E-2 l
Lung Environ. Child Broi:dleaf Vegetation 1.53E-2 GI-LLI Environ. _
Adult Broadleaf Vegetation 2.16E-3 4-3
4.4 PATHWAY DOSE CALCULATIONS Dose calculations for each age and pathway can be found on the following pages.
I l
1 l
l l
l l \
i l
i l
4-4
9 Dose from Air Radioiodine Inhalation Pathway for 1993 Data Maximum ExposedInfant Breathino rate = 1400 m3tyr Highest AnnualMeen Concentration INFANT
].
inhalatimr he Factor (mrom per pCl hhaled) Air Dome (mromtyr)
Radionuctide Bone tsvor T, Body ThyrM IGdmy Luno O'-LLI Location (pCi/m3) Bone Uver T. Body Thyroid Kidney Leig GI-LLI Mn-54 NO DATA 1.81E-45 3.5eE-06 NO DATA 3.56E-oe ( 14E-04 5.04E-06 ALL 0 00 0.00E+oo 0 00E+00 0.00E+00 0.00E+00 0 00E+00 0.00E+00 0 00E+00 Co-58 NO DATA 8.71 E-07 1.30E-06 NO DATA NO DATA 5.t BE44 7.95E-06 ALL 0 00 0 00E+00 0.00E+00 0.00E+00 0.00E+00 0 00E+00 0.00E+00 0 00E+00 4
Fe-Se 9 00E-06 t esE-05 6.77E-06 NO DATA NO DATA 7.25E-04 1.77E-05 ALL 0.00 0.00E+00 0.00E+oo 0 00E*00 0 00E*00 0 00E+00 0.00E+00 0 00E+00 A
C&-60 NO DATA 5.73E-oe 8.41E-06 NO DATA NO DATA 3.22E43 2 28E-05 ~ AtL 0 00 0 00E+oo 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0.00E+00 0 00E+00 Zn45 1.38E-05 4.47E-OS 2 22E-05 NO DATA 2.32E-05 4.82E-04. 3 67E "3 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 1.12E-oS 4 5eE-06 2 70E-os NO DATA 3.37E-06 3 42E-04 9.05E-46 ALL 0 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 000E+00 I Zr-05 8.24E-05 190E 1.45E-45 NO DATA 2.22E-45 1.2E-03 1.55E-os ALL 0 00 0 004+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 1-131 2,71E-05 317E-05 140E-45 1.00E-02 3.70E-05 NO DATA 7.58E-07 ALL u % 0.00E+00 0 00E400 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Cs-134 2 83E-04 5 02E-04 5.32E-05 NO DATA 1.3eE-04 5 00E-05 9 53E-07 ALL 0.00 0.00E+00 0 00E+00 0 00E400 0 00E+oo 0.00E+00 0 00E+00 0.00E+00 Co-137 3 92E-04 4.37E-44 3.25E-05 NO DATA 1.23E-04 5.00E-05 9.53E-47 ALL 0.00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Bala-140 4.00E-os 4 00E-08 2.07E-Oe NO DATA 9 5eE-49 1 14E-03 2.74E-05 ALL 0.00 0.00E+00 0 00E+00 0.00E+00 ~0.00E+00 0 00E+00 . 0.00E+00 0.00E+00 TW Does Equivalent (mromtyr) = 0.00E+00 0.00E+00 0 00E+00 0.00E+00 0.00E+00 0 00E+00 0 00E+00 '
___c _______m_ _ _ _ _ _ _ _ _ . _ _ _ _ _ ___._______m _ _ _ $r
.eu Dose from Air Particulate Inhalation Pathway for 1993 Data Maximum Exposed Infant Breathing rate = 1400 m3.y Highest AnnualMesn Cancentration INFANT Inhalation Dose Factor imrom per pCi inhaled led) indicator Air Dose (mromhr)
Radionucide Bone Uver T. Body Thyroid 10dney Luno GI-LLI Location (pCi/m 3) Bone Uver T. Body Thyroid Kidney Lung GI-LLI 8An-54 NO DATA 1.8IE-05 3.58E-06 NO DATA 3 56E-ce 7.14E-04 5 04E-oe 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-58 NO DATA 8.71E-07 1.30E-06 NO OATA NO DATA 5.55E-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-se 9 eeE-Oc 1esE-05 6 77E-06 NO DATA NO DATA 7.25E-04 8.77E-05 ALL 000E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+0C 0ccE+00 0 00E+00 0.00E+00
.b s
c) CW NO DATA 5.73E-46 s 41E-ce NO DATA NODATA 3.22E-03 2.28E-45 ALL 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0ocE+00 0 00E+00 0.00E+00 Zn-45 1.38E-05 4.47E-05 2 22E-05 NO DATA 2.32E-05 4 82E44 3 67E-45 ALL 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Nb-05 1.12E-05 4 5eE-06 2.70E-06 NO DAT A 3.37E-oe 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 00E40 0.00E+00 2r-95 8.24E-oS t ooE-05 1.45E-05 NO DATA 212E45 1.25E43 1.55E45 ALL 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00teuo 0.00E+00 6-131 2 71E-05 317E-05 140E-05 1.osE-02 3.70E-05 NO DATA 7.5eE-C7 ALL 000E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0fv4+00 0 00E+00 Cs-134 2 83E44 5.02E-04 5.32E-05 NO DATA 1.3eE-04 5 80E-05 9 53E-07 ALL 0.00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 ,0.00E+00 0 00E+00 0 00E+00 Co-137 3 92E44 4.37E-04 3.25E-05 NO DATA 1.23E-04 5 09E-45 9 53E-07 ALL 000E+00 0 00E+M 000E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 Bate-140 4.00E-05 4 00E-os 2.07E-06 NO DATA 9 SOE-Os 1.14E43 2.74E-05 ALL 000E+co 000E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E*oo Total Does Equhralent (mremtyr)= 000E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00
Dose from Drinking Water Pathway for 1993 Data Maximum ExposedInfant usage (intake rato) - 330 vyr Highest AnnualMean Concentration INFANT Ingeehan Does Factor (mrom per pClingested) Indicator Water Does (mrom/yr)
Radkmuchde Bone Liver T. Body Thyroid IGdney Lung GI-LLI Location (pCi/L) Bone t.Jver T. Body Thyroid IGdney Lung GI-LLI L1n-54 NO DATA 190E-45 4 5tE-OS NO DATA 4 41E-os NO DATA 7.31E-06 ALL 0 00 0 00E+00 0.00E 00 0 00E+00 0 00E+00 0 OK+00 0.00E+oo 0.00E+00 Co-Sa NO DATA 3 00E-06 8 98E-06 NO DATA NO DATA NO DATA 8.97E-06 ALL 0 00 0 00E+oo 0.00E+oo 0 00E+00 0 00E+00 0.00E+00 0.00E+00 0 00E+00 Fe-59 3 08E-05 5.38E-05 2.12E-05 NO DATA NO DATA 1.5GE-05 2 57E-05 ALL o 00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00
.4 CW NO DATA 1.08E45 2 55E-05 NO DATA NO DATA NO DATA 2.57E-05 ALL 0 00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+co 0 00E+00 0 00E+00 Zn-45 1.84E-05 e3tE-oS 2.91E-05 NO DATA 3.06E-05 NO DATA 5.33E-05 ALL 0 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Ntt-95 4 20E-os 1.73E-os 100E-08 NO DATA 1.24E-08 NO DATA 14eE-05 ALL 0.00 0 00E+.00 0.00E+00 0 00E+oo 0.00E+00 0 00E+00 0 00E+00 0 00E<co Zr-OS 2 08E-47 5 02E-os 3 SSE-08 NO DATA 5 41E-08 NO DATA 2.50E-45 ALL 0 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0.00E+00 t-131 3 59E-45 4.23E-05 1 bee-05 1.39E-02 4 94E-05 NO DATA 1.51E-06 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-134 3 77E-04 7.03E-04 7.10E-05 NO DAT A 1.81E-04 7.42E-05 1.91 E-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 Ce-137 5.22E44 611E-04 4.33E-05 NO DATA 1 61E-44 664E-05 191E-46 ALL 0 00 0.00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 Bala-140 1.71E-04 1.71E-07 8 81E-os NO DATA 4 DeE-os 105E-07 4 20E-05 ALL 0 00 0 00E+00 0 00E+00 0 00E+00 0 00E+40 0 00E+00 0.00E+00 0.00E+00 H-3 NO DATA 3 08E-07 3.08E-07 3.0 iE-07 3.08E-47 3 08E-47 3 08E-47 ALL 0.00 0 00E+00 0 00E+oo 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 Total Does Equivalent ( nremlyr) = 000E+00 c +00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0.00E+00
Dose from Milk Pathway for 1993 Data Maximum ExposedInfant Usage (intake rate)- 330 Uyr Highest AnnualMean Concentration INFANT Ingesten Does Factor (mrom per pC2 in0ested) Indscator Milk Does (nwsm/yr)
Radenuclide Bone 1.iver T. Body Thyrad 80dney Lung G8-LLI Locahon (pCVL) Bone Over T. Body Thyroid K)dney Lung GI-LLt Mn-54 NO DATA 199E45 4 51E-06 NO OATA 4 41E-06 NO DATA 7.38E-06 ALL 0 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 Co-58 NO DATA 3 60E-06 8 98E-06 NO DATA NO DATA NO DATA 8 97E-06 - ALL 0 00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 Te-59 3 OsE-05 5.3sE-os 2.12E-05 NO DATA NO DATA 1.59E-05 2.57E-05 ALL 0 00 0.00E+00 0.00E+00 0 00E+00 0 V L+00 0 000+00 0OCE+00 0 00E400 Co-e3 NO DATA 108E-os 2 55E-05 NO DAT A NO DATA NO DATA 2 57E-05 ALL 0 00 0 00E+00 0uuc . ... +00 0 00E+00 0 00E+co 0 00E+00 0 00E+00 Zn-e5 184E-os 6.31E-05 2 91E-05 NO DATA 3.06E-05 NO DATA 5 33E-05 ALL 0 00 0 00E+00 0.00E+00 0 00E+00 0 00E+oo 0 00E+00 0 00E+00 0.00E+00 Nb-95 4 20E-os 113E-08 1.00E-08 '40 DATA 1.24E-os NO DATA 1.46E-05 ALL 0 00 0 00E+oo 0 00E+00 0 00E+00 0.00E+co 0 00E+00 0 00E+00 0.00E+00 Zr-95 2.06E-07 5 02E-08 3 56E-08 NO DATA 5.41E-o8 NO DATA 2 50E-05 ALL 0 00 0 00E+00 0 00E+00 0 00E+00 0.00E+oo 0.00E+00 0.00E+00 0.00E+00 6-131 3 5GE-OS 4 23E-os 1.s6E-05 130E-02 4 04E-05 NO DATA 1.51 E-06 ALL 0 00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0.00E+00 0 00E+00 0.00E+00 Ca-134 3 77E-04 7.03E-04 . 7.10E-05 NO DATA l 81E-04 7.42E-05 101E-os Att 0 00 0 00E+00 0 00E+oo 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 Co-137 5.22E-04 t.t 11E-44 4.33E-oS NO DATA 1.64E-04 664E-05 191E-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 Bala-140 1.71E-44 1.71E-47 881E-06 NO DATA 4.06&cs 105E-07 4 20E-05 ALL 0 00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 Total Does Equevalent (mrem /yr) = 0.00E+00 0 00E+00 0 00E400 0 00E+00 0 00E+00 0 00E+0c 0.00E+oo
- _ . _ _h
l Dose from Inhalation Air Radioiodines Pathway for 1993 Data Maximum Exposed Child Breathing rate = 3700 m3 /yv Highest AnnualMean Concentration CHILD inhalation Does Factor (mrom per pCi inhaledt Indicator Air Does (mrom/yr)
Radtonuclide Bone Liver T. Body Thyrood 1Gdney Lung GI-LLI Location (pCVm3) Bone tJver T. Body Thyrood Kidney tung GI-LLI Mn-54 NO DATA 1.16E-05 2 57E-06 NO DATA 2.71E-06 4 26E-04 619E-06 ALL 000E+00 0 00E*o0 0 00E+00 0 00E*00 0 00E+00 0 00E+00 0.00E-00 0 00E+00 Co-58 NO DATA 419E-07 8 55E-07 NO DATA NO DATA 2 99E-04 9 29E-06 ALL 0.00E+00 0 00E+00 0.00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 y Fe-59 5 59E-06 9 04E-06 4.51 E-06 NO DATA NO DATA 3 43E-04 191E-05 ALL 000E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 w
CM NO DATA 3 55E-06 612E-46 NO DATA NO DATA 191E-03 2.60E-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 Zn-65 1.15E-os 3 06E-05 190E-05 NO DAYA 1.93E-05 2 69E-04 4 41E-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 Nb-05 6.35E-06 2 48E-06 117E-06 NO DATA 2 33E-06 1.66E-04 1.00E-os ALL 0 00E+00 0 00E+00 0OGE+00 0.00E+00 0 00E+00 0 00E+00 C.00E+00 0 00E+00 Zr-95 513E-05 1.13E-os 1.00E-oS NO DATA 1.61E-05 6 03E-04 1.65E-05 ALL 000E+00 0 0CE+00 0 00E+00 0 00E 00 0 00E,00 0 00E+00 0 00E+00 0 00E+co l-131 1.30E-OS 130E-os 7.37E-oS 4.39E-03 2.t 3E-05 NO DATA 7 68E-07 ALL 0 00E+00 0 00E+00 0 00E+00 0 00E+co 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Co-134 1.76E-04 2 74E-44 607E-OS NO DATA 8 93E-OS 3 27E-05 104E-06 ALL 000E+00 0 00E*oo 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Co-137 2.45E-04 2 23E-04 3.47E-OS NO DATA 7 63E-05 2.81E-OS 9.78E-47 ALL 000E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+oo 0.00E+00 BaLa-140 2 00E-05 175E-08 1.17E-06 NO DATA 511E-09 411E-04 2 75E45 ALL 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E400 0 00E+00 0 00E+00 0.00E+00 Total Does Equivalent (mromtyr)= 0 00E+00 0 00E+00 0 ocE+00 0 00E+00 0 00E400 0.00E+co 0.00E+00
Dose from Inhalation Air Particulate Pathway for 1993 Data Maximum Exposed Child Breathitig rate = 3700 (m3/yr)
Highest AnnualMean Concentration CHILD inhalation Does Factor (mrom per pCiinhaled) Indicator Air Does (mrom/yr)
Radionuclide Bone Uver T Body Thyroid Kidney Lung GI-LU Location (pCum3) Bone Uver T. Body Thyrcid IGdney Lung GI-LLI Mn-54 NO DATA 1.16E-05 2 57E-06 NO DATA 2,71E-oe 4 26E44 619E-oe ALL 0.00E+00 0 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0 00E+00 Co-58 NO DATA 4.79E-07 8.55E-07 NO DATA NO DATA 2 99E-04 929E-06 ALL 000E+00 0 00E+00 0 00E+00 0.00E+00 0.00E+co 0.00E+00 0 00E+00 0.00E+00 A Fe-50 5 5OE-os 9 04E-06 4.51 E-06 NO DATA NO DATA 3 43E-04 191E-05 ALL 000E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E*oo 0 00E+00 0.00E+00 b
o CW NO DATA 3 55E-oe 6.12E-os NO DATA NO DATA 1.91E-43 2 00E-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 Zn-85 1.15E45 3 DeE-05 190E-oS NO DATA 1.93E-45 2 00E-04 4 41E-oe ALL 000E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+oo 0 00E+00 0.00E+oo 0 00E+00 Nt m e.35E-06 2.4aE-06 1.77E-46 NO DATA 2 33E-os 1 eeE-44 1.00E-05 ALL o00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0.00E+00 Zr-95 5.13E-os 1.13E-05 100E-05 NO DATA 1.61E-os e 03E-04 1.65E-05 ALL 000E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 1-131 1.30E-05 1.30E-05 7.37E-oe 4.30E-c3 2.13E45 NO DATA 7.68E-47 ALL 0 00E+00 0.00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 Co-134 1.7eE-04 2.74E-04 607E-05 NO DATA 8 93E-05 3.27E-oS 1.04E-06 ALL 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Co-137 2.45E-04 2.23E-04 3 47E-05 NO DATA 7.93E-oS 2.s t E-oS 9.7aE-07 ALL 0.00E+00 0 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+oo 0 00E+00 0 00E+00 Ba u-140 2.00E45 175E-os 1.t7E-oe NO DA? ' 5.71E-09 4 71E-04 2.75E-05 ALL 000E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+co 0 00E+00 0 00E+00 0.00E+00 Total Does Equivalent (mromtyr} = 0.00E+00 0 00E+00 0.00E+00 0 00E+co 0 00E+00 0 00E+00 0.00Eeo0
Dose from Drinking Water Pathway for 1993 Data Usage { intake rate) = 510 (vy) Maximum Exposed Child Cmx Highest AnnualMean Concentration ingesexy* * - Factor (mrom per pu angested) Indicatar Water Doom (mrom/p)
Ndxmuctede Bone Uver T. Body Thpc'd PGoney Lung GB-LLI Locatum (pCi!!) Bone Over T. Body Thyroad IGdney Luno GI-LLI Mn-54 NO DATA 1.07E-05 2 85E-06 NO DATA 3 00E-06 NO DATA 8.9aE-06 ALL 0 00 0 00E+00 0 00E+00 0.00E+00 0.00E.00 0 00E+00 0 00E+00 0 00E+00 Co-58 NO DATA 180E-06 5 51E46 NO DATA NO DATA NO DATA 105E-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-59 185E-05 2 67E-05 1.33E-05 NO DATA NO DATA 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 A Co-co NO DATA 5 29E-oS tSeE-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+oo 0.00E+00 0.00E+00 d
Zn-05 1.37E-OS 3 e5E-05 2.27E-05 NO DATA 2.30E-OS 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 2 25E-08 8 7eE-09 626E-09 NO DATA 5.23E-09 NO DATA 162E-OS ALL 0 00 0 00E+co 0 00E+00 0OcE+00 0 00E+oo 0 00E+00 0 00E+00 0 00E+00 Zr-95 1.18E-07 2.55E-03 2 27E-08 NO DATA 3 65E-08 NO DATA 2 eeE-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 1.72E-OS 1.73E-OS 9 83E-46 5 72E-03 2 84E-05 NO DATA 1.54E-06 ALL 0 00 0.00E+00 0 00E+00 0.00E+oo 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Co-134 2 34E-04 3 84E-04 8 tDE-05 NO OATA 1.19E-04 4 27E-05 2 07E-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-137 3.27E-04 3.13E-04 4 62E-05 NO DATA 102E-04 3 67E-05 19eE-06 ALL 0 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0.00E+00 BaLa-140 8 31E-OS 7.28E-08 4 85E-06 NODATA 2.37E-08 4 34E-08 4.21E-05 ALL 0 00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 N-3 NO DATA 2 03E-07 2 03E-or 2 03E-o? 2.03E-07 2 03E-07 2 03E-07 ALL 0 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Total Does Equivalent (mromtyr) = 0 00E.00 0 00E+00 0 00E+00 0.00E+00 0.00E+00 0 00E+oo 0.00E+00
Dose from Milk Pathway for 1993 Data Usage (intake rate) = 330 00 tuyr) Maximum Exposed Child CHILD Highest AnnualMean Concentration ingesnon Does Factor (mrem per pClingested) indicator Mith Does (mromtyr)
Radionuchde Bone Liver T. Body Throid IQdney Lung GI--LU Location (pCul) Bone Uver T. Body Thyroid IQdney Lung GI-LU Mn-54 NO DATA 107E-05 2 85E-06 NO DATA 3 00E-06 NO DATA 8 98E-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-58 NO DATA 1.80E-06 5 5 t E-os NO DATA NO DATA NO DATA 1.05E-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 Fe-59 1.65E-05 2.67E-05 1.33E-05 NO DATA NO DATA 7.74E-oe 2 7aE-05 ALL 0 00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0.00E+00 0 00E+00
.A 1
to CO-40 NO DATA 5 29E-06 1.5eE-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 2n-45 1.37E-05 3 e5E-oS 2 27E-OS NO DATA 2.30E-45 NO DATA 6 41E-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 Nb-95 2.25E-08 8.7eE-09 e2eE-09 NO DATA 8.23E-09 NO DATA 182E-OS ALL 0 00 0 00E+00 0 00E+00 0 00E+co 0 00E+00 0.00E+00 0 00E+00 0.00E+00 Zr-95 1. t 6E-47 2 SSE-os 2 27E-48 NO DATA 3.65E-os NO DATA 2 esE-45 ALL 0 00 0 00E+00 0 00E+00 0 00E+00 0 03E+00 0 00E+00 0 00E+00 0 00E+00 1-131 1.72E-05 1.73E-05 9 83E-oe 5.72E-03 2 84E-05 NO DATA 1.54E-06 ALL 0 00 0.00E+00 0 00E440 0.00E+00 0 00E+00 0.00E+00 0.00E+00 0 00E+00 Co-134 2.34E-04 3 84E-44 s.10E-45 NO DATA 1.19E-44 427E-05 2 07E-oe ALL 0 00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0.00E+00 0.00E+00 0 00E+00 Co-137 3.27E-44 3.13E-04 4 62E-05 NO DATA 1.02E-04 3 87E-05 1.9eE-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-45 7.28E-os 4 85E-ce NO DATA 237E-os 4.34E-os 4.21E-c5 ALL 0 00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tdal Does (meemtyr) = 0 00E+00 0.00E+00 0.00E+00 0 00EW 0.00E+00 0 00E+00 0 00E+00
Dose from Broadleaf Vegetation Pathway for 1993 Data Usage (intake rate) = 2e kyp Maximum Exposed Child CHiw Highest AnnualMean Concentration inoestion Does Factor (mrem por pCiincested indicator Food Does (mremlyr)
Radionuclide Bone Liver T. Body Thyrced Kidney Lung GW Location (pClikg) Bone Liver T. Body Thyroid Kidney Lung GI-LU L4n-54 NO DATA 107E-05 2 85E-06 NO OATA 3 00E-06 NO DATA 8.98E-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-58 NO DATA 180E-os 5 51E-46 NO DATA NO DATA NO DATA 105E-05 ALL 0 00 0 00E+co 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 DATA 7 74E-06 2.78E-oS ALL 0 00 0 00E+00 0 00E+00 0 00E+co 0 00E+00 0 00E+00 0 00E+00 0 00E+00 A
8 CO-ec NO DATA 5 29E-06 156E-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 u
Zn-85 137E-05 3 65E-05 2 27E-05 NO DATA 2 30E-05 NO DATA 6 41E-os ALL 0 00 0 00E+00 0 00E+00 0 00E+00 0.00E+oo 0 00E+00 0 00E400 0 00E+00 Nb-95 2 25E-os 8 76E-09 626E-09 NO DATA 8.23E-09 NO DATA t 62E-05 ALL 0 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Zr-95 1.16E-07 2 55E-08 2.27E-08 NO DATA 3 65E-08 NO DAl A 2 66E-05 ALL 0 00 0 00E+00 0 00E+00 0 00E+.00 0.00E+00 0 00E+co 0 00E+co 0 00E+00 1-131 1.72E-05 1.73E-05 9 83E-06 5 72E-03 2 84E-05 NO DATA 154E-06 ALL o 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 Cs-134 2.34E-04 3 84E-04 8.10E-os NO DATA 1.1GE-04 4.27E-05 2.07E-06 ALL 0.00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 Co.-137 3 27E-04 313E-04 4 62E-05 NO DATA 102E-04 3 67E-05 196E-06 120 16 00 136E-01 1.30E-41 192E-02 0 00E+oo 4.24E-02 1.53E-02 8.15E-04 Bata-t40 8.31E-05 7 28E-08 4 85E-06 NO DATA 2.37E-08 4 34E-48 4.21E-05 ALL 0.00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0.00E+00 0 00E+00 Total Does (mrom/p) = 136E-01 1.30E-o1 192E-02 0 00E+00 4.24E-42 1.53E-02 815E-04
Dose from Shoreline Sediment Pathway for 1993 Data Maximum Exposed Child Shoreline Recreation 14 hetyr Shore Wdth Factor = 0 3 (take shore - socanon 129)
Shore Wdth Factor = 0.2 (river shoreline -locane 130)
Externe? Dose Factor kr S:andmo on Highest Annual Mean Concentraaon Cataminated Ground Does (mremlyr)
(mremnw per pC1/m2) Indicator Sediment Radeonuchde T. Body %n Location (pCukg) T. Body Skin Mn-54 5.80E-09 e80E-09 ALL 00 0 00E+00 0.00E+00 A Co-58 7.00E49 8 20E49 129 22.0 2.59E-05 3 03E45
" Fe-59 8 00E-40 9 40E-c3 ALL 00 0.00E+00 0 00E+00 Co-eo 1.70E-c8 2 00E-08 130 88 0 2.46E-04 2 89E-04 Zn-65 4.00E-09 400E 4 ALL 00 0 00E+00 0 00E+00 Nb-es 5.10E-09 e 00E-49 ALL 00 0 00E+00 0 00E+00 Zr-95 5 00E-09 5 80E-09 ALL 00 0 00E+00 0 00E+00 5-131 2 80E-09 3 40E-09 ALL 00 0 00E+00 0 00E+00 Co-t34 1.20E-08 140E-ca ALL 00 0 00E+00 0 00E+00 Co-137 4ME-09 4 90E-09 *10 93 0 4.37E-05 5.10E-05 Ba W 140 2.10E-49 2.40E-09 ALL 00 0.00E+00 0 00E+00 Total Dose (meem/yr) r 315E-44 3.70E-04
" - =
Dose from Fish Pathway for 1993 Data usaae ontane ras,> - 6 9 norp Maximum Exposed Child CHILD Highest AnnualMean Concentration InDesden Does Factor (mrem per pCiingested) Indecator Fish Does (nuem/p)
Radionuclide acne Uver T. Body Thpoid IGdney Lung GI-LLI Location (pCa/kg) Bone Uver T. Body Thyroid Kidney Lung Gl-LLI un-54 NO DATA 1.07E-05 2 85E-06 NO OATA 3 00E-06 NO DATA 8.98E-06 ALL 0 00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 Co-58 NO DATA 1.80E-06 5.51E-06 NO DATA NO DATA NO DATA 1.05E-05 129 82.00 0 00E+00 1.02E-03 3.12E-03 0 00E+00 0 00E+00 0 00E+00 5.94E-03 Fe-se 165E-os 2 67E45 1.33E-OS NO DATA NO DATA 7.74E-46 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 OATA 5.29E-06 156E-45 NO DATA NO DATA NO DATA 2 93E-os 129 13 00 0 00E+00 4.75E-04 1.40E-03 0 00E+00 0 00E+00 0 00E+00 2 63E-03 Zn-65 1.37E-05 3 35E-45 2 27E-05 NO DATA 2.30E-05 NO DATA 6 41E-46 ALL 0 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Nb-95 2.25E-48 8.76E M 626E-09 NO DATA 8 23E-os NO DATA 1.62E-45 ALL 0 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 71 - 9 5 1.18E-07 2.55E-08 2.27E-08 NO DATA 3 65E-08 NO DATA 2 66E-05 ALL 0 00 0 00E+00 0 00E+oo 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 4-131 1.72E-OS 1.73E-05 983E-oC ".32E-03 2 84E-05 NO DATA 1.54E-06 ALL 0 00 0 00E+00 0 00E+00 0 00E+co 0 00E+00 0.00E+00 0.00E+00 0 00E+00 Co-134 2.34E-04 3 84E44 810E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 ALL 0 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Co-137 3 27E-04 3.13E-04 4 62E-05 NO DATA 102E-04 3 67E-05 196E-06 ALL 0 00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Bala-140 8.31E-05 7 28E-os 4 85E-06 NO DATA 2.37E-08 4.34E-08 4.21E-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 Total Dose (mrem!p) = 0 00E+00 149E-03 4 52E-03 0 00E+00 0 00E+00 0 00E+00 8 57E-03
t-9 Dose from Food Pathway (Crops) for 1993 Data usaoo oniano rare)- 520 acer Afaximum Exposed Child Cwto Highest AnnualMean Concentration ino. w Do r aor
<=... p.r pCono...m e rood De. <= .mw RadonucHd. Bon. Liver T. Body Thyroid IGdney Lung 08-LLI Location (pCUkg) Bone Liv.r T. Body Thyrced Kh2ney Lung Cl-LLI Mn~54 NO OATA 107E-05 2 85E-06 NO DATA 3 00E-06 NO DATA 3 GSE-oe 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 1.30E-os 5 51E-06 NO DAYA NO DATA NO DATA 1.CSE-05 ALL 0 00 0 00E+00 0 00E+00 0 00E+c0 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Fe-59 1.esE-05 2 67E-05 1.33E-oS NO DATA NO DATA 7.74E-06 2.7tE-05 ALL 0 00 0 00E+00 0 00E+00 0 00E+00 C.00E+00 0 00E+00 0 00E+00 0.00E+00 A
e CO-60 NODATA 529E46 1.5eE-o$ NO DATA NO DATA HO DATA 2.93E-45 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
Zn-85 I.37E-OS 3 obE-05 227E-05 NO DATA 2.30E-05 NO DATA 6 41E-06 ALL 0 00 0 00E+co 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+oo 0.00E+oo Nb-95 2.25E-08 8.78E-ce 5.20E-09 NO DATA S.23E-09 NO DATA 182E-05 ALL 0 00 0.00E+00 0 00E+00 0 00E+oo 0 00E+00 0 00E+00 400E+00 0.00E+00 Zr-95 1.1SE-07 2 55E-04 2 27E-OG NO DATA 3 85E-04 NO DATA 2.86E-05 ALL 0.00 0 00E+00 0 00E+00 0 00E+oo 0.00E+00 0 00E+00 0 00E+00 0.00E+00 6-131 1.72E-oS 1.73E-oS 9 83E-06 5.72E43 2 84E-05 NO DATA 1.54E-06 ALL 0 00 0 00E+co 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+oo 0.00E400 Co-134 2.34E44 3 84E-04 8.10E-OS NO DATA 1.19E-04 4.27E-05 2.c7E-oe ALL 0 00 0 00E+00 0 00E+00 0.00E+00 0.001i400 0 00E+00 0.00E+00 0.00E+00 Co-137 3.27E-04 3.13E-04 4 82E-05 NO DATA 102E44 3 57E-05 19eE-06 ALL 0 00 0 00E+00 0 00E+00 0 00E+00 0 00E+co 0 00E+co 0.00E+00 0 00E+00 Bata-140 s.3t E45 72sE-os 4.25E-06 NO DATA 2.37E-OS 4.34E-04 42t E-05 ALL O.00 0.00E+00 0 00E+00 0 00E+00 0 00E400 0 00E+00 0.00E*00 0.00E+00 Total Does Equtwel.r(mr.mty). 000E+00 0OcE+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00
-w - n n ,a --&
l l
3 V V V V % 9 9 % V V V s sO ss O O sO s@ssssss O O O O O O O E
O ssssssssiii O O O O O O O C ' O O O sO 8 g 5 %
o i
o s
o so s o
so so
- s. s. so so so a oeeeeeeeeeee e
~
y ilsssssssssss 5 o O o o o o o o o o o so
> fk k k k k k k k k a i ssssssssss k k k sO O O O O O O O O O O O Ee e !!!!!!!!!!! !
E
! .$ $ $ ]!!!!!!!!!!!
8 8 8 8 8 8 8
!8 a g 8
8 8
8
. . O E N 9 9 9 9 1 V V 4 4 1 3 6 *{e sasisssisss V
g g o o o o o o o O o o O C g I
f= $$kk$kk$Nkk 8 oe 2D ee E e
3 4*]mk4 99 9 i V Zg %
2 o w-n K um& I. m m
4 s f
e xe fi s.
s s
s k
- s. s. ; a
{e ,-
i a g
-jg i*g;2 sas.is,8 m e -
8 susssssss jg#% C O O O O O O
- es O O O 11 2 9 9 9 9 9 9 . 9 9 9 Il
! l !. !8 ! ! !a s$s$ 'i, 1 - - - - - ,a . C ,
V) a
. n. .
a sn C
8 a
- ! 9 9 5
9 55235!!
l 4 .
h 1 k k 8 E g
= 1 ah- a as ss3 1
I l
4-17
! l
Dose from Air Particulate Inhalation Pathway for 1993 Data Maximum Exposed Teen Usage (Intake rate)- 8000 (m3/yr)
Highest AnnualMean Concentration TEEN Inhalatum does tactor (mrom per pCJ inhaled) Indacator Air Does (mrom/yr)
Radionuctide Bone Liver T, Body Thpoid Kidney Lung Gl-LLI Location (pCi/m3) Bone tiver T.Eody Throid IGdney Lung GI-LLI Mews 4 NO DATA 6 39E-06 105E"06 NO OATA 1.59E-06 2 48E-04 8.35E-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-53 NO DATA 2 59E-07 3 47E-o7 NO DATA NO DATA t 68E-04 1.t 9E-45 ALL 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+co 0 00E+oo 0 00E+00 0 00E+00 Fe-50 1.09E-06 4 62E-c6 1.79E-ce NO DATA NO DATA 191E-04 2 23E-05 ALL 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+co 5 Co-60 NO DATA 189E-06 2.48E-oo NO DATA NO DATA 1.00E-03 3 24E-05 ALL 0 00E+00 0 00Ee00 0.00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+co 0 00E+00 Zn-65 4 82E-06 167E-45 7 80E-46 NO DATA 108E-45 155E-04 5 83E-06 ALL 000E+00 0 00E+00 0 00E.00 0 00E+00 0 00E+0c 0 00E+00 0OCE+00 0 00E+00 Nt>-95 2.32E-oS t20E-oo 7.08E-07 NO DATA 125E-06 9 3eE-05 121E-05 ALL 0 00E+00 0 00E+00 0 00E+oo 0 00E+00 0 00E+oo 0 00E+00 0 00E+00 0 00E+00 Zr-95 182E-05 5 73E-os 3 94E-06 NO DATA 8 42E-oe 3 36E-04 1 SeE-05 ALL 0.00E+00 0.00E*oo 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+oo 0 00E+oo I-131 4.43E-46 614E-46 3.30E-oo 1.83E-o3 1.05E-05 NODATA 8.11E-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 6.28E-OS 1.41E-04 6 86E-45 NO DATA 4 69E-45 183E-05 122E-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-137 8 38E-05 1.06E-04 3 89E-OS NO DATA 3 80E-45 151E-05 1.06E-06 ALL 000E+00 0 00E+oo 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Bala-140 684E-06 838E-oe 4 40E47 NO DATA 2.85E-00 2.54E-04 2 86E-05 ALL 000E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 Total Dome Equavelent (mromty). 000E+00 0 00E+00 0 00E+00 0.00E+00 0.00E+.00 0 00E+00 0 00E+00
Dose from Drinking Water Pathway for 1993 Data usage ontaue rate)- 5,o uyr Maximum Exposed Teen reen Highest AnnualMean Concentration ingestion Does Factor Drinksng (mrom per pCE ingested) indicator Water Dome (mremlyr)
Radxmuclide Bone t.iver T. Body Throid IGdney Lung GI-LLI Location (pCL/L) Bone Uwer T. Body Thecsd IGdney Lung GI-LLI Mn-54 NO DATA 5 90E-06 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21E-05 ALL 0.0 0 00E+00 0 00E+00 0.00E+00 0.00E+00 0 00E+00 0 00E+00 0.00E+00 Co-58 NO DATA 9 72E-47 2.24E-06 NO OATA NO DATA NO DAT A 134E-05 ALL 00 0 00E 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Fe-50 5 87E-c6 1.37E-oS 5 29E46 NO DATA NO OATA 4 32E-06 3 24E-05 ALL 00 0 00E400 0 00E+00 0 00E+00 0 00E+oo 0.00E+00 0 00E+00 0.00E+00 4
CW NO DATA 2 81E-46 633E-06 NO DATA NO DATA NO DATA 3 66E-45 ALL 00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 i
e Zn-45 5.76E-06 2 00E-o5 9 33E-06 NO DATA 1.2SE-oS NO DATA 8 47E-os ALL 00 0 00E+00 0 00E+00 0 00E+00 0 00E+oo 0 00E+00 0 00E+00 0 00E+00 Nb-05 8 22E-09 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 00E+00 0 00E+00 0 00E+00 Zr-95 4 12E-os 1.30E-o8 8 94E-09 NO DATA 1.01E-08 NO OATA 3 00E-05 ALL 00 0 00E+00 0 00E400 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+oo 1-131 5 85E-06 8.19E-oS 4 40E-06 2.30E-c3 141E-05 No DATA 1.62E-06 ALL 00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+oo 0 00E+00 Co-134 b37E-oS 197E-04 9.14E-05 NO DATA 6 26E-05 2.39E-05 2 45E-oe ALL 00 0.00E+00 0.00E+00 0 00E+oo 0 00E+oo 0.00E+00 0 00E+00 0 00E+00 Co-137 1.12E-04 1.49E-04 519E-45 NC DATA 5 07E-OS 197E-45 2.12E-os ALL 00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0.00E+00 0 00E+00 0 00E+00 Bala-140 2 84E-05 3 4aE-48 183E-06 NO DATA 1.18Eas 234E-08 4.3aE-oS AtL 00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0.00F+00 H-3 - NO DATA 1.06E-07 106E-07 1.06E-07 1.06E-47 106E47 106E-07 ALL 0 00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0 DOE +00 0 00E+00 0 00E+00 Total Does Equivalent (mromtyr)= 0 00E+00 0.00E+co 0 00E+00 0.00E+00 0.00E+00 0 00E+00 0.00E+oo
Dose from Milk Pathway for 1993 Data usaae ontake rate > - 400 up Maximum Exposed Teen Te.n Highest AnnualMean Concentration Ingeerion Does Factor (mrom per pCiincessed) Indicakw Mdk Dome (meendy)
Redumuchde Bone Uver T. Body Thpoid Kidney Lung Gl-LLI Location (pCUL) Bone Uwer T. Body Throid IGdney Lun0 Cl-LU Mm64 NO DATA 5 90E-06 1 17E-06 NO OATA 1.76E-06 NO DATA 111E-45 ALL 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 9 72E-07 224E46 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 G00e*
Fe-59 5 87E-06 137E-OS 5 29E-06 NO DATA NO DATA 4 32E-06 3 24E45 ALL 00 0 00E+00 0 00E+00 0 00E+oo 0 00E+00 0 00E+00 0.00E+00 0 00E400
.h e Co-60 NO DATA 2 81E-06 6 33E-06 NO DATA NO DATA NO DATA 3 SeE-05 ALL 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+oo 0 00E+00 0 00E+00 90 O
2n-65 5.76E-os 2 00E-05 9.33E-06 NO DATA 128E-05 NO DATA 8.47E-06 ALL 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+co 0 00E+00 Nb-95 8 22E-09 4 56E-09 2 51 E-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 00E+00 0 00E+00 0 00E+00 Ze-95 412E-ca 130E-os a 94E-09 NO DATA 1.01E-os NO DATA 3 00E-OS ALL 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+co 0 00E+co 0 00E+co 8-131 5 85E-06 819E-06 4 40E-06 2 39E-03 1.41E-05 NO DATA 1.62E-06 ALL 00 0 00E+co 0 00E+00 0 00E+00 0 00E+oo 0 00E+00 0 00E+00 0 00E+00 Co-134 S.37E-OS 197E-04 9.14E-05 NO DATA 626E-05 2.39E-OS 2.45E-06 ALL 00 0 00E+00 0.00E+00 0 00E.co 0 00E.00 0.00E+00 0 00E+co 0 00E+00 Cs-137 1.12E-04 1.49E-04 5.t9E-os NO DATA 5 07E-05 1 G7E45 212E-46 ALL 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Bata-140 2 84E-05 3.48E-08 1.83E-06 NO DATA 1.18E-08 2.34E-os 4.3aE-05 ALL 0.0 0 00E+co 0.00E+00 0 00E+00 0.00E+oo 0 00E+00 0 00E+00 0 00E+00 Total Does Equhralent (mrevn/p). 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00
Dose from Broadleaf Vegetation Pathway for 1993 Data Usage (intake rate) = 42 (ko np> Maximum Exposed Teen T~ Highest AnnualMean Concentration ingeanon Does Factor (mrom per pCiirgoemd) In&cator Food Does(wom/p)
Radionuclide Bone Uver T Body Thyroid Kidney Lung GI-LLI Location (ko rp) Bone Uver T. Body Throat 10dney Lung GI-LLI MrHM NO DATA 5 90E-oe t.17E-os NO DATA 1.7eE-ce No DATA 1.21E-45 ALL 0.0 0 00E+00 0 00E+00 0 00E+oo 0 00E+00 0 00E+00 0 00E+co 0 00E+00 i
Co-58 NO DATA 9 72E-c7 224E-os NO DATA NO DATA NO DATA t.34E-05 ALL 00 0 00E+co 0.00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+oo 0 00E+00 Fe-59 5 8TE-oe t.37E-c5 5.29E46 NO DATA NO DATA 4.32E-06 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 I Co-oo NO DATA 2 81E-ce 6 33E-06 NO DATA NO DATA NO DATA 3 eeE-05 ALL 00 0 00E+00 0 00E+00 0 DOE +00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 e 2n-e5 5 7eE-06 2 00E-05 9.33E-oe NO DATA 138E-c5 NO DATA 8 47E-os ALL 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 Nb-e6 8.22E-09 4 5SE-os 2.51E-oe NO DATA 4 42E-09 NO DATA t95E-45 ALL 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 _
r Zr-95 4.t2E-os t.30E-os a 94E-49 NO DATA 1.01E-os 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 l-131 5 SSE-os s.1oE-os 4.40E46 2.3eE-43 1.41E-oS NO DATA 1.62E-48 ALL o0 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 I Co-134 8.37E-05 197E-04 914E-05 NO DATA e.2eE-05 2.39E-OS 2.45E48 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-04 1.40E-44 5.19E-05 NO DATA 5 07E45 1.97E-05 2.12E-oe 120 to o 7.53E-02 100E-01 3 40E-02 0 00E+00 3 4 t E-02 1.32E-02 1.42E-o3 4
Bala-t40- 2.54E-05 3 48E-os t.33E-os NO DATA 1.1SE-os 2.34E-os 4.3aE-05 ALL o0 0.00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 t
I Total Oces Equive6ent(mrom/yr). 753E-42 1.00E-o1 3.49E-02 0 00E+00 3 41E-02 1.32E-02 1.42E-03
. r I
4 w-~e#v~ e -
Dose from Shoreline Sediment Pathway for 1993 Data Maximum Exposed Teen Shoreline Recreation 57 hrlyr Shore width Factor = 0.3 (take shore-m tre)
Shore Width Factor - 0 2 (river ahosenne - socation 130)
External Dome Factor kw Standmo on Highest Annual Mean Concentration Contammated Ground Does (mrem /yr)
(mrom/hr per pCi/m2) Indicator Sedirnent Radumuchde T. Body Siun Locatwns (pCi/kg) T. Body Skm Mn-54 5 80E-09 6 80E-49 ALL 00 0 00E.00 0 00E+00 CW 7.00E-09 8 20E-09 129 22 0 1.24 E-04 1.45E-04 to Fe-59 8 OGE-09 9 40E-09 ALL 00 0 00Eun 0 00E+00 N
Cm 1.70E-os 2.00E-os 130 86 0 118E-03 1.38E-03 Zn-85 . 4 00E-09 4 60E-09 ALL 00 0 00E+00 0 00E+00 Nb-95 51OE-09 600E-09 ALL 00 0 00E+00 0 00E+00 Zr-05 5.00E-09 5 80E-09 ALL o0 0 00E+00 0rAJE+00 5-131 2 80E-09 3 40E-09 ALL 00 0 00E+00 0 00E+co C -134 1.20E-08 1.40E-Ca ALL 00 0 00E*06 0 00E+00 Co-137 420E-09 4 90E-49 130 93 0 2 00E-04 2.44 E-04 Bala-140 2.10E-09 2 40E-09 ALL 00 0 00E+00 0 00E+00 Total Dome Equivalent (mrom/yr)= 1.51E-03 1.77E-03
f.
i.
o sisiisisi8 o - o N o o o o o o o
N Jfssf V V V V ssssss1s V 4 4 1 9 s
9 o o o o o o o o o o o o f4 4 4 1 6 9 9 9 9 V V V s s s s s 1 1
- s. s. s. s. s o o
{3 m3 o
4 o
V o
V o
V 6
V V V V V V 9 9
~
gEsssssasssss o o o o o o o o o o o s6 5
g jt s ia o
!sWsssssss o
4 o
99
- o 4
o 4
o 4
o 4
o 9
o 9
o W
9 c
1!!!!!!!!!!!
8 2 8 3 8 8 8 8 8 8 8 4
@m g o . . . o o o o o -
,]9 j9 4 4 V V 1 1 9 V 1 4 1 e' $ e i ssssssss1s s A o o o o o o o o o o o o E
6 5
- 5*E*******
s el 5 s ljWB 1B $WWWWWW l te$ B 1 i E $ 9 o
!a ! ! i ! 9 s
!8 !a !, ! !n
~
t
%o - a- .a s, . . - ~ ~ ,
l
[
j GG9 i GGGGVV 4 O O W O Q O Q O W ]
_ 9 9 99 9 9 9 9 E. WB* !
il 9iiGV 9 4 494 4 s"I5
-jq i j j j W 5, %. i . s. !. i l
l 1 13 55 io GGGGG59iG5 o o o o o o o o 8 8
11 9 9 9 9 2 5 9 5.>9 9 9 j 99 5x] *9 {a l 9 9 9 9 9 9 l 1 a
- ~ . . A. : s. s s. s 1-j 9 9 99 9 9 9 9 39i
- s. W.W i s, s, A E e 1 jii!!9 9 9 9 99 9 l $
3 ll.z s. W. t. 0
,- W.s-i
~
5 f $ $ $
- N y
}sdd a
$$$$533j j 4-23
l l
l l
aeeeaeeaeeee e saasayasata e
t i
i O O O O O O O O O O O O l j w vvvvvvvvvvv a
v !
1
- s. s. a. a. s. s. a a a o O O O a. s. \
8 i V V U V V 4 1 1 V 9 9 4 n asiaissasssi sO i g g O O O O O O O O O O O l
- oeeeeaeaeaee a w jasaaassssias O O O O O O O O O O O s
O j4 9 9 9 V 4 9 % 4 9 1 1
- aassssssstu O O O O O O O O O O O i
O E
xete e j eevvvvvvvvg e a ssasssssis8 O O sO p g O O O O O O O O O s =
g jmt t m
9 m
9 9 9 m
4 m
4 m
4 m
9 m
9 m m 9
E e !!!ym!!!!!!!
O !
aR 0 a : : : : : : : : : : :
oa e gs S
s m
5 .
tg s ~Ifssassassass a
g 13 i
1 kg
- 5 4 i V4g4i i i gV 2 e
3 e
- x. s. e. ssss=w
. - ~ a ,
i a
S $ "
$54 55555V O O W O O O O O V 4 W ]
8 saeaa9 s a ! W:5 3 i j}I*visiV 8 9 3 g V 4 g
-jq - i i ;
- 5, a-r s.
O n
l 11 g#
555555i O O O O O O O 555 O O O fl 2 9 9 9 9 9 9 . 9 9 9 j r; *9-V g
.sWag9s. g 9 i V V 9 1 O O -
i O
ws a g 4 4 4 4 4 4g 14a. n O
95 s s. *. *.ss
- 4 i i i i !!!!l!!!!
! sa5sES: : 5~E 5
3 s a 8 s a !
u
@ kbibn 9 kk 1 B B hbj 4-24
- Dose from Air Radiciodines Inhalation Pathway for 1993 Data Maximum Exposed Adult Usage (intake rate) = 8000.00 (m3tyr)
Highest AnnualMean Concentration Adus hti=8afw=i does factor (wom par pClinhaled) Ar Does (mromtyr)
Bone Uver T. Body Thyrosd IGoney L.ang Gktd Rad onuchde Bone tiver T. Body Thycond IGdney Lung GbLLs Locanari (pce,w3)
Un-54 NODATA 4 95E46 7 87E-07 NO DATA 123E-OS 1_74E-04 9 EPE-o6 ALL ocoE+oo oocE+00 0 00E+00 0 00E+00 0 00E+oo o coE+00 0 00E 00 0 00E*oo Co-58 NO DATA 194E-07 2.5eE-07 NO DATA NO DATA 1.16E-04 1mE-45 ALL o00E+co 000E+00 0 DCE+00 0.00E+00 0OcE 00 0.00E+oo 0 00E+00 0 00E+00 Fe-59 1.47E-oe 3 47E46 132E-46 NO DATA NO DATA 127E44 2.35E-OS ALL oocE+00 0 00E+00 0 00E+00 0 00E.00 0 00E+oo 0 00E+00 0.00E+00 ch0E+00 h
CM NO DATA 144E-oS 1.45E-06 NO DAT A NO DATA 7 46E-04 3 56E-05 ALL o00E+00 0 00E+00 0 00E+oo 0 00E+oo 0 00E+oo 0 00E 00 0 oCE+00 0OCE+oo 4
ci Zn-65 4 05E-06 129E-05 578E-06 NO DATA s 62E-46 1osE-04 6saE-06 ALL 000E+00 0OcE+00 0ocE 00 oocE+00 0 OcE+oo 0 00E+00 o ocE+oo 0 00E 00 Nt>-95 t76E-06 9 77E47 5 26E-07 NO DATA 9 67E-07 6.31E-05 1.30E-05 ALL 000E+00 0OcE+oo 000E+oo 000E+00 0 00E+oo 0 00Enoo 0 00E+oo 0 00E+00 Zr-95 t 34E-os 4 30E-os 2 91E-46 NO DATA 6 77E46 221E44 SaE-05 ALL o00E+00 0 00E+00 0ooE.co ocoE+00 0 ooE+.00 0coE+oo ocoE+oo 0 00E.co b131 31SE-06 4 47E-46 2 56E46 1 49E--03 7 66E-os NO DATA 7 85E-07 ALL 0coE+oo 000E+00 0 00E+oo 0 00E+oo o coE+oo o 00E+oo 0 00E+00 0OCE+00 Co-134 4 66E-05 106E44 910E-05 NO DATA 3 50E-05 1.22E-05 t.30E-06 ALL 0 00E+00 0 00E+00 0oCE+00 0 00E 00 0 00E+00 0ocE+00 0 30E+oo 0 00E+00 Co-137 5 95E-05 7.76E-os 535E-05 NO DAT A 2 78E-OS 9 40E-06 *05E-06 ALL o00E+00 0 00E+oo 0 00E+00 0 00E+co 0 00E+00 0 00E+00 0 00E+oo 0 00E+oo Bata-140 4 88E-06 613E-09 320E-07 NO DATA 2 OGE-09 159E-04 2 73E-05 ALL 000E+00 0 00E 00 0OcE+oo 000E+00 0 00E+00 0 00E+oo 0 coE+00 0 00E+oo TOTAL DOSE EQUtvALENT(nuendyr)= 0 00E.00 0 00E+00 0 00E 00 0 00E+00 0coE+00 0coE 00 0 00E+00
Dose from Air Particulate Inhalation Pathway for 1993 Data Maximum Exposed Adult Usage (intake rate) = 8000 (m3fvr)
Highest AnnualMean Concentration Inhalataan does factor (mrom per pCiinhaled) Ar Does (mrom/yr)
Radmuclide Bone Uver T. Body Thyroid IGdney Long GI-LLI Locanon (pCi/m3) Bone Uver T. Body Thyrood Kidney Lung GI-LU Mn-54 NO DATA 4 95E-06 7.87E-47 NO DATA 1.23E-06 1.74E-04 967E-06 ALL 0.00E+00 0 00E+00 0 00E+oo 0 00E+00 0.00E+00 0 00E+00 0.00E+00 0 00E+C0 Co-54 NO DATA 198E-07 2.59E-07 NO DATA NO DATA 1.16E-04 1.33E-05 ALL 000E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Fe-59 1.47E-OS 3 4TE-06 1.32E-06 NO DATA NO DATA 1.27E-04 2.35E-05 ALL 000E+00 0 00E+oo 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 A
m CM NO DATA 1.44E-06 t.25E-06 NO DATA NO DATA 7.46E-04 3.58E-05 ALL 000E+00 0OcE+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+oo 0 00E+00 In45 4 05E-06 129E45 5 28E46 NO DATA 8 62E-06 1.08E-44 6 SaE-OS ALL 000E+00 0 00E+00 0 00F+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Nb-95 1.76E-06 9 77E-07 5.26E-o? NO DATA 9 67E 47 8 31E-45 1.30E-05 ALL 0 00E400 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+oo 0 00E+00 Zr-95 1.34E-45 4 30E-06 2 91E-06 NO DATA 6.77E-06 2.21E-04 188E-05 ALL 000E+00 0 00E+00 0 00E+oo 0 00E+00 0 00E+oo 0 00E+00 0 00E+00 0 00E+00 1-131 3.15E-06 4 47E-06 2 56E-os 149E43 7.66E-06 NO DATA 7 85E-07 ALL C00E+00 0 00E+00 0 00E+C0 0 00E+oo 0 00E+00 0 00E+00 0 00E+00 0 00E+oo C >134 4 66E-05 106E-04 9.10E-oS NO DATA 3.59E-05 122E-05 1.30E-06 ALL 0 00E+00 0.00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00EW Co-137 5 95E-05 7.76E-05 5.35E-05 NO DATA 2.7sE-oS 9 40E-06 105E-06 ALL 0 00E+oo 0 0cE400 0 00E+00 0.00E+00 0 00E+00 0 00E+oo 0.00E+00 0 00E+00 Bala-140 4 88E-06 8.13E-09 3.20E-07 NO DATA 2.03E-49 1.59E-04 2.73E-05 ALL 0.00E+00 0 00E+00 0.00E+00 0.00E+00 0 00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL DOSE EOUIVALENT(mrem /yr)= 000E+00 0 00E+00 0 00E40 0.00E+00 0.00E+00 0 00E+00 0.00E+00
5 Dose from Drinking Water Pathway for 1993 Data Maximum Exposed /dult Usage (intake rate)- 730 (tryr)
Highest AnnualMean Concentration Adua
' Ing*asson Does Factor i (mrera r. Clingested) Indicator Water Does (mrom/p)
Hadeonuclide Bone Uver T. Body Throid rGdney Lung GI-LLI Lacanon (pCM) Bone Uver T, Body Throid Kidney Lung- GS-Ett
.Mn~54 NO DATA 4.57E-06 4.72E-07. NO DATA 1.3sE-06 NO DATA 1.40E-05 ALL 0 0 00E+00 0.00E+00 0.00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 Co-58 NO DATA 7.45E-07 f.67E46 NO DATA NO DATA NO DATA 1.51E-05 ALL 0 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 Fe-Se 4.34E-es t.02E-45 , 3 01E-06 ' NO DATA NO DATA 2.45E-06 3 40E-05 ALL 0 0 00E*00 0 00E*00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E400 I CW NO DATA 2.14E-08 4.72E-06 NO DAYA NO DATA NO DATA 4 02E-05 alt 0 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0.00E+00 m
- Zn-85 4 84E-06 1.54E-05 8eeE-06 NO DATA 1.03E-05 NO DATA 9 70E-06 ALL 0.000E+00 0 00E+00 0.00E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 Nb-95 6.22E-00 : 3 deE-oe t JeE-Oe NO DATA 3 42E-OS NO DATA 2.10E-05 ALL 0 0.00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00
- Zr-e5 3 04E-44 9 75E-Oe 6.00E-09 NO DATA 1.53E-08 NO DAYA 3 DeE-05 ALL 0 0 00E+00 0 00E+00 0.00E @ 000E+00 0 00E+00 0.00E+00 0 00E+00 1-131 4.t eE-06 5.96E-06 3 41E-oe 1.95E-03 1.02E-05 . NO DATA 1,57E-06 ALL 0 0 00E+00 0 00E+00 0.00E+00 0.00E+00 0.00E+00 0 00E+00 0 00E+00 -
Co-134 822E-05 1.4aE-04 1.21E-04 NO DATA 4.79E-05 1.5eE-05 2.5eE-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 ~t0eE-04 7.14E-05 NO DATA 3.70E-06 1.23E-05 2.11E-Os ALL 0 0 00E+00 0 00E+00 0 00E+00 0.00E+00 ' O.00E+00 0 00E+00 0 00E+00 s
Bala-t40 ' 2 03E-05 2.55E-08 1.33E-06 NO DATA S.87E-Oe 1.4eE-os 4.t85 M ALL 0 0.00E+00 ' O.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 t
H-3 NO DATA .1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-47 1.05E-07 ALL 0 0.00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0.00E+00
- TOTAL DOSE EOEVALENT(mromty). 0.00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 4
- . . _ _ _ _ _ - _ - _ _ - - _ _ _ . , - . _ _ - _ ._ _ _ :-- - , _- _ - . . - . - . -_.=
_ - _ . . _ . -: a, . . _ _ = _ - . -- 2
\ll {ll ]1' , I o 0 0 o IL 0 0 0 0+
0 0
o o+
0 0
0 0
0 0 o+ 0 0 o+ _
0 0+ + + + + + +
L +
E E E E E E E E _
E E E E c o o S
c o c c c o 0 o o c 0
o.
G o c o o o c 0 c 0 o o o o o o o o c o o 0 o o 0 o o o o o 0 0 oo _
g o c o+ c+ 0+ 0 n o+ o+ c
+
0
+
o+ c+ + +
E
+
u E E E E E E E E E E c
L E c o c o o o o o o
0 0 0 o c 0
0 o c o c o -
c 0 o o o o -
o o 0 o o o o o 0 o 0 o o 0 0 0 y 0 0 0 0 0 e 0+ 0 0 0 0+ o+ 0
+
c+ o+ 0+ 0
+ +
n + + + E E E E E E E E E E E E d
G 0 0 0 o o o o c
o c
0 0
o c
o c
0 0
) #
0 0 0 c c c r o 0 o o o o o o 0 o o 0 w '
r o o o o o 0 0 0 o 0 -
ef r u o 0
0 0
0 o+ c+ o+ o+ 0
+
0+ 0
+
o+ 0+
(mory E
+
E
+
E E E E E E E E E E c
sh c c o 0 c o c c C oT c o o 0
0 o c 0 o o o c o o C
o o o 0 o o o o o o o o o y o 0 o 0 o o o 0 o 0 0 do 0
0 o+ 0 o+ 0+ o+ o+ o+ 0
+
o4 0+ 0
+
+ E a
t B.
T E
0 E
0 0
E c
o E
0 0
E o
o E
o c
E o
c E
0 0
E o
c E
o c
E o
c o
o a 0 o 0 o o o o o o o o o o D r e
v 0
0 0
0 o
o+
o c+
0 0
+
0 0+
0 0
+
0 0
+
o c+
0 0
+
o o+
o o+
+ +
3 L a
E E c
E o
E E E o
E c
E c
E 0
E c
E o
E 0
9 t n 0
0 o c 0
0 0
0 c o o 0 c c 0 o
9l 1 u io o o o 0 o o o o o o o t e 0 o o 0 o 0 0 0 0 0 o rd oA a
t r n o
B 0
0 E
+
0 E
+
C E
+
E o +
0 E
+ c.
E E 0
E 0
o
+
0 E
o
+
E 0
+
0 E
o
+
E o+
o f n c o
c o
0 0
c o
C o
oc C
o c c 0
0 c c ye d e c o o 0 o o o o o o 0 o o a s n o o o o o o o o o 0 o wo h p C o k uat) ti o o o o o o o o o 0 o aEx C
t n (p a .
P e ra no a
)
y km M L L L s
L L L L L L L L L L L L vn l l a na c L A
L A
L A
L A
L A
L A
L A A A A A e i u a d c n o r
m Mm u I L (
w i n 5 5 5 5 6 S 5 6 6 6 5 r mx oa A n tL L
k G
0 E
0 0
E 1
0 E
0 4
0-E 2
0 E
0-C 7
O E
C 0
E 9
0 E
7 5
0- 0-E 9
5 0-E 1
1 0-E 5
2 6v w
a u
frM t 4 5 I q
s 1 1 3 4 9 2 3 1 2 2 9 E e A A A A A se e
s h
g g
n A
T A
A T
A 6
0 T A
T A
T A
T A
T A
S O-5 4-6 0
D o
u E
D D D D D E E 66 o i H
L D O
D O
5 8 O O O O O G 5
3 2 4 la t
o D )
d N N 2 N N N N N 1 1 1 T o emey r
t 6 A T
A T
A T
5 0
9 0-8 4-5 C
5 0-5 0-s o-c 0- A A A a e n -
E E E E E E E
au Fs igd i r i K E
6 D D D 3 2 3 2 9 0 7 s
3 O O O 0 4 5 0 7 7 d
A ec o
D p 1 N N N 1 3 1 1 4 3 a r s A A A A A A A A A A n
o e s pu o T A
T A
T A
T A
T A
T A
T A
3 0- T A
T A
T A
mmy r D D D D D D D E 5
D D D e oh g O O O O O O O 9 O O O v r T N N N N N N N N N .
h m (
N 1 _
y 7 6 6 6 6 9 e 6 4 S 6 d
o 4- 0- 0- 0- 0- 0- c- 0 0- O- 0 E E E E E E E E E E 4
63 B. 2 7 1 2 6 6 0 1 1 2, 3 T 7 6 9 7 9 8 6 4 1 w s 1 3 4 6 1 6 3 1 7 1 r 6 7 5 6 5 9 9 6 4 4 4 0, e 0- 0 0- 0- 0 0- 0- 0- 0 3 w
> 4 4 E
E E E E E E E t E E E a e 5 7 5 2 4 4 5
s 4
5 7
5 9 4 o 5 5 4 0 1 4 7 t 2 1 3 9 5 1 t 2 e A A S A s 9 8 e 5 5 5
- n Y T o T o- 0- 0 o- 0 0 0
> o A A - A - - -
e B D D E D E E E E E E- E t 4 4 2 4 6 2 7 3 a
r O O 3 O 8 2 0 1 2 9 0 N N N 4 6 3 4 6 7 2 _
e 4 s
t d e 0 -
n 7 4 -
h 4 o 5 5 4 8 0 5 3 3 o c 5 6- 5 e- e 9 9 1
3 1 1 1
e g
mr & o e o n t
F -
r 1
s o t
a .
a M C F C 2 N Z l C a -
a m C s a B u R Adao l 1 >i f, lt
Dose from Broadleaf Vegetation Pathway for 1993 Data Maximum Exposed Adult Usago (intake rate) = 64 kg/yr Highest AnnualMean Concentration Adult inges6on Does Factor trwficator Food Dome (mrem /p)
(mrom per pCIIngested)
GI-LLI Locanon (pCUkg) Bone Uver T. Body Thyroid Kidney Lung Gf4LI h hoe Bone Over T. Body Thyrmd Kidney LunC Mn-54 NO DATA 4 57E-06 8.72E-07 NO DAT A 136E-06 NO DATA 1.40E-05 ALL 0 0.00E+00 0 00E+00 0.00E+00 0.00E+00 0 00E+00 0 00E 00 0ccE+00 Co-- C NO P ATA - 7.45E-o7 167E-oS NO DATA NO DATA NO DATA 1.51E-05 ALL 0 0 00E+00 0 00E+00 0.00E+00 0 00E+M 0 00E+00 0 00E+00 0 00E+00 Fe-50 4 34E'-06 1.02E-of 3.91E-06 NO DAT A NO DATA 2 85E-OS 3.40E-05 ALL 0 0 00E+00 0 00E+00 0 00E+00 0.00E+oo 0 00600 0 00E+00 0 00E+00 4
Co00 NO DATA 2.14E-06 4.7 E-06 NO DATA NO DATA NO DATA 4 02E-05 ALL 0 0 00E+co 0 00F+00 0 00E+00 0 00E+00 0 00E+00 000E+00 0 00E+00 Zn-65 4 84E-06 1 54E-05 6 960-06 NO DATA 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 Nb-95 622E-09 3 46E-09 1.86E-09 NO DATA 3.42E-09 NO DATA 2.10E-OS ALL 0 0 00E+oo 0 00E+oo 0 00E+00 0 00E+00 0 00E+00 0 00E+oo 0 00E400 Zr-05 3 04E-08 9.75E-09 6 00E-09 NO D ATA 1.53E-08 NO DATA 3 09E-05 ALL 0 0 00E+00 0 00E+00 0 00E+oo 0 00E+00 0 00E 00 0 00E+oo o 00E40 6-131 416E-06 5 95E-06 3.41E-06 195E-03 1.02E-oS NO DATA 157E-06 ALL 0 0 00E+00 0 00E+00 0 00E+oo 0.00E+00 0 00E+00 0 00E+00 0 00E+00 Co-134 622E-05 1.48 E-04 1.21 E-04 NO DATA 4.79E-05 1.5sE-os 2 50E-06 ALL 0 0.00E+00 0 00E+00 0 00E+00 0 00E+oo 0 00E+00 0 00E*C0 0 00E+co Co-137 7 97E-05 109E-04 7.14E-05 NO DATA 3 70E-05 123E-05 2.11E-co 120 16 816E-02 1 12E-01 7 31E-42 0 00E+00 3.79E-02 1.26E-o2 2.18E-o3 Bala-140 2.03E-45 2 SSE-os 1.33E-06 NO DATA 8 67E-09 1.46E-oS 4.18E-05 ALL 0 0 00E+00 0 00E+00 0 00E+00 0 00E+oo 0 00E+00 0 00E+00 0 00E+00 Total Does Equevalent(mromtyr)= 8.16E-02 1.12E-o1 7.31E-02 0 00E+oo 3.79E-02
- 26E-o2 2.18E-03
Dose from Shoreline Sediment Pathway for 1993 Data Maximum Exposed Adult Shoreilne Recreation 12 twtyr Shore W4th Factor = 0 3 cake stume-socanon 129)
Shore Wdth Factor - 0.2 (w shoreline-locanon 130)
Externei Does Factor for Sts%ng Highest AnnualMean Concentration on Contam#nated Ground Does (mremlyr)
(mrom/hr per pC1/m2) andu:ator Sediment fladionuchde T. Body 6 kin Locaban (pCiAL9) T. Body Skin Mn-64 5 80E-09 6.80E-09 ALL 0.0 0 00E+00 0 00E+00 Co-68 7.00E-00 S 20E-09 129 22.0 2.22E-OS 2 00E-05 A
b O
Fe-50 100E-09 9 40E-09 ALL 00 0 00E+00 0 00E+00 Co-e0 1.70E-08 2.00E-08 130 se C 2.1IE-04 2.48E-04 Zn-os 4 E E-49 4 00E-09 ALL 00 0 00E+00 0 00E+00 Nb-05 5.10E-09 6.00E-09 ALL 0.0 0 00E+00 0.00E+00 Zr-95 5.00E-09 5 80E-09 ALL 00 0 OcE+00 0 00E+00 1-131 2.30E-09 3 40E-09 ALL 0.0 0 00E+00 0 00E+00 Co-134 1.20E-08 1.40E-oe ALL 00 0 00E+00 0 00E+00 Co-137 4.20E-09 4.90E-09 130 93 0 3 75E-05 4.37E-05 Belm-140 2.10E-00 2.40E-09 ALL 00 0 00E+00 0.00E+00 Total Does (mram/yr) = 2 70E-04 317E-04
Dose from Fish Pathway for 1993 Data Maximum Exposed Adult usage (intake rate)- 21 kotyr Highest AnnualMean Concentration Adult ingesnon Dose Factor (mreen per pct ingested) h Fieh Does(mromtyr)
Lung GI-LLI Locatscri (pC1tg) Bone Liver T. Body Thyroid IGdney Lung G8-LLI Radmuchde Bone Uver T. Body Thyrod IGdney Mn-54 NO DATA 4 57E46 8 72E47 NO DATA 1.36E-46 NO DATA 1.40E45 ALL 0 0ooE+00 0 00E+00 0 coE+00 0 coE+oo o coE+oo 0.coE+00 0coE+00 CW NO DATA 7.45E-oT 1.67E-os NO DATA NO DATA NO DATA 15tE-OS 129 82 DooE+00 12aE-03 2 88E43 G ooE+00 0 00E+00 0 00E+oo 2 eoE-02 Fe-59 4 34E-o8 102E-os 3 91E-09 NO DATA NO DATA 2 85E-06 3.40E-45 ALL 0 0 ooE+oo 0coE+00 000E.00 0ocE+oo 000E+oo o coE+00 0coE+00
- t. toe-02 p CoM NO DATA 214E-46 4 72E-06 NO DATA NO DATA NO DATA 4 02E-05 129 13 0 00E+00 5 84E-44 129E-03 0 00E+oo o coE+oo o coE+00 w
~
Zn-65 4 84E46 1.54E-45 696E-o6 NO DATA 103E-05 NO DATA 9 70E-oe ALL o ocoE+00 0coE+00 ocoE+00 0coE+00 0 coE+oo 000E+00 ocoE+00 Nt>-95 6 22E-09 3 46E-09 1.86E-09 NO DATA 3 42E-09 NO DATA 2.10E-os ALL L 0coE+00 0 00E+oo o coE+00 0coE+00 0 00E+00 0coE+oo o 00E+00 Zs-95 3 04E-os 9 75E-09 6SoE-09 NO DATA 153E-48 NO DATA 3.09E-oS ALL 0 0coE+oo o00E+00 0ooE*oo oooE+00 0 ooE+0c 0coE+oo ocoE+00 8-131 4 tSE-06 5 95E-06 3 41E-06 195E-03 1.02E-OS NO DATA 157d-06 ALL o 000E+00 0 00E+00 0 00E+oo 0 00E+03 0 00E+00 0 00E+00 0 00E 00 Co-134 622E-05 1.48E-44 121E44 NO DATA 4,79E-05 1.50E45 2.50E-oS ALL o 000E+00 0ooE+00 0coE+00 0 coE+00 0 coE+00 ocoE+co 0 00E+00 Co-137 7 97E-os 1 ME-04 7.14E-OS NO DATA 3 70E-o5 1.23E-45 2.11 E-06 ALL 0 0 ocE+oo o coE+oo o coE+00 0coE+00 0coE+00 0 00E*00 033E+00 BaLa-140 2.03E-c5 2 55E-os 133E-06 NO DATA 8 67E-oe 1.46E44 4 taE-45 ALL 0 ocoE+00 0ooE+00 0ooE+oo 0.ocE+00 0coE+oo o coE.co o coE+00 TOTAL DOSE EQUIVA .ENT{mromtyr)= cooE+00 187E-03 4.18E-43 0.00E.co c.coE+co c ooE+00 3.70E42 i
I
Dose from Food Products (Crops) Pathway for 1993 Data Maximum Exposed Adult use0. ontake me)- 520 *0y Highest AnnualMean Concentration Ada ingeshon Does f actor (rneem per pc ingested; indicator Food Does (mrom/yr)
Radionuchde Bone Liver T. Body Thyroid Kkiney Lun0 G5-LLI Locanon (pCWkg) Bone Liver T. Body Thyroid IGdney Lung G5-LLI Mn-54 NO DATA 4 57E-06 8 72E-o? NO DATA 1.36E46 NO DATA 1.40E-05 ALL 0 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+oo Co-58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.58E-os ALL 0 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 A Fe-59 4.34E-06 1.02E-oS 3 91E-46 NO DATA NO DATA 2 85E-06 3 40E-c5 ALL 0 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 a
fwJ M CW NO DATA 2.14E-46 4 72E-06 NO DATA NO DATA NO DATA 4 02E-OS ALL 0 0 00E+00 0 00E+00 0 00E+00 0 00E*.00 0 00E+oo 0 00E+00 0 00E+00 Zn-65 4 84E-06 1.54E-oS 696E-06 NO DATA 1.03E-OS NO DATA 9.70E-06 ALL 0 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+oo 0.00E+00 0 00E400 Nb-95 6 22E-09 3.46E-09 186E-09 NO DATA 3 42E-09 NO DATA 2.10E-05 ALL 0 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+co 0 00E+00 0 00E+00 Zr-95 3 04E-08 9 75E-09 660E-og NO DATA 1.53E-os NO DATA 3 09E-05 ALL o 000E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 0 00E 00 0 00E+oo 1-131 4.16E-06 5 95E-oe 3.4IE-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 ALL 0 0 00E+00 0 00E+oo 0 00E+co 0 00E+00 0.00E+00 0 00E+00 0 00E+00 Cs-134 6.22E-05 1.48E-44 121 E-04 NO DATA 4 79E-05 1.59E-oS 2.59E-06 ALL 0 0 00E+00 0 OCE+00 0 00E 00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 Co-137 7.97E-05 109E-04 7.14E-05 NO DATA 3.70E-05 1.23E-os 2.11E-06 ALL 0 0.00E+00 0 00E+00 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0.00E+00 BaLa-140 2.03E-05 2.55E-48 1.33E-06 NO DATA 8.67E-09 1A6E-08 418E-05 ALL 0 0 00E+00 0 00E+00 0.00E 00 0.00E+00 0.00E+00 0 00E+00 0 00$+00 TOTAL DOSE ECUtVALENT(mesm/yr)= 0.00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00 0 00E+00
5.0 QUALITY ASSURANCE 5.1 DUKE POWER COMPANY'S RADIOLOGICAL ENVIRONMENTAL LABORATORIES 5.1.1 SAMPLE COLLECTION The Radiological and Environmental Services Group and the Fisheries work group perform the environmental sample collections as specified by approved sample collection procedures.
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 environmental sample analyses as specified by approved analysis p rocedu res .
5.1.3 DOSIMETRY ANALYSIS The Dosimetry and Records Group performed environmental dosimetry measurements as specified by approved desimetry analysis procedures.
5.1.4 INTRALABORATORY OUALITY ASSURANCE Radiological and Environmental Services has an internal quality assurance program which monitors each type of instrumentation for reliability and accu racy. Daily quality control checks ensure that instruments are in proper working order and these checks are used to monitor instrument performance.
Additionally, National Institute of Standards and Technology (NIST) standards that represent counting geometries are analyzed as unknowns at various frequencies ranging from weekly to annually to verify that efficiency calibrations are valid. The frequency is dependent upon instrument use and performance. Investigations are performed and l documented should calibration verification data fall out of limits.
5-1
. .. - . . .. .. . .- . . . . ~
5.1.5 INTERLABORATORY QUALITY ASSURANCE l 5.1.5.1 DUKE POWER'S AUDIT DIVISION Radiological and Environmental Services participated in a Quality Verification audit in 1993. One McGuire recommendation was given and the REMP. quarterly data evaluation procedure was revised. One Environmental Center finding, two follow-up items, one observation, and three recommendations were identified during this' audit. Based on these items , actions were taken to enhance laboratory operations.
5.1.5.2 DUKE POWER'S NUCLEAFl PRODUCTION INTERCOMPARISON PRO, GRAM The Radiological and Environmental Services Group ,
participated in the Duke Power Nuclear Production Intercomparison Program during 1993.
Interlaboratory cross-check standards including marinelli beakers, air filters, air cartridges, gross alpha / beta on smears, and tritium in water samples were analyzed at various l times of the year by the four counting laboratories in . Duke l~ Power Company for this program.
L l
5.1.5.3 U.S. NUCLEAR REGULATORY COMMISSION INSPECTIONS Radiclogical and Environmental Services was not audited by l
the .NRC in 1993.
5.1.5.4 UNITED STATES ENVIRONMENTAL PROTECTION AGENCY
- INTERCOMPARISON PROGRAM The Radiological and Environmental Services . Group participated in the Environmental Protection Agency (EPA)
Environmental Monitoring . Systems Laboratory Intercomparison Program. The EPA sample types included .
mixed gamma in water (3 times per year), mixed gamma in milk L (1 time per year), gamma in air filters (1 time per year),,
lodine in milk (1 time per year), tritium in water (2 times per year), iodine in water (2 times per year), gross beta in air filters (1 time per year), and gross betain water (3 times per year).
l 5-2 L
i Radiological and - Environmental Services prepared and analyzed each sample as quickly as possible. Should the data obtained be out of EPA limits, Radiological and Environmental Services would have performed and documented follow-up investigations. The Radiologica;and Environmental Services EPA Intercomparison Report codo is."CP". A summary of l the EPA Intercomparison Reports for td93 is documented in Table 5.1. of the twenty-six (2G) analyses performed in 1993, none of the analyses were out )f limits.
5.1.5.5 NRC/ STATE OF S.C. ENVIRONMENTAL MONITORING PROGRAM-l 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 splits -
! water, milk, vegetation, sediment, and fish samples with the Bureau of Radiological llealth of the State's Department of llealth and Environmental Control (DilEC) for analysis.
DilEC 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 DilEC Laboratory are compiled by DilEC and provided to the NRC. TLDs are also co-located with the
. State and NRC at various environmental sites.
l 5.1.5.6 NRC/ STATE OF N.C. INTERCOMPARISON PROGRAM t-L Radiological & Environmental Services and the Dosimetry &
Records Group routinely participate with the State of North Carolina Department of Environmental llealth.and Natural Resources (DEHNR) in an intercomparison program.
Radiological and Environmental Services sends air, water, milk, vegetation, sediment, and fish sa'mples which have been collected to the State of North Carolina. Radiation Protection:
Section for intercomparison analysis. TLDs. are also co-located with the -State and NRC at various~ environmental sites. Also, every six to eight months, the State of North Carolina Radiation Protection Section irradiates environmental dosimeters and sends them to the Dosimetry Laboratory for analysis of the unknown estimated delivered exposure. A' summary of the State of North Carolina Environmental Dosimetry Intercomparison Report-for 1993 is documented in
' Table 5.2. The Dosimetry Laboratory results were within an average of 1.51% of the State of North Carolina results
~
(excluding Standard Deviation values) for the July and December 1993 cross-checks. .
i l
-]
1
~5-3 !
~
h
5.1.5.7 U.S. DEPARTMENT OF ENERGY INTERCOMPARISON PROGRAM There was no DOE intercomparison program during calendar year 1993.
5.2 CONTRACTOR LABORATORY No contractor laboratories were used during 1993.
1 4
l I
l t
(
l l
l 5-4
TABLE 5-1 (Page 1 of 3)
U.S. ENVIRONMENTAL PROTECTION AGENCY INTERLABORATORY COMPARISON PROGRAM-1993 CROSS-CHECK RESi)LTS FOR THE RADIOLOGICAL AND ENVIRONMENTAL SERVICES LABORATORY E
ANALYhlS l l NUCNDE(S)1 . KNOWN VALUN
( iREPORTED VALUE
<[7_ i. ,,, Oe,I I,93 e.-i33 ee.0 pCi,i si.7 - lie.3 pCi,, 103.0 pC1,i Co-60 15.0 pCi/l 63 - 23.7 pCiA 15.7 pCi/l Zn-65 103.0 pCill 85.7 - 1203 pCill 112.7 pCi!!
Ru-106 119.0 pCiA 98.2 - 139.8 pCi/l 100.7 pCiA m Cs-134 5.0 pCi/l 0.0 - 13.7 pCia 5.7 pCi/l m
Cs-137 5.0 pCiA 0.0 - 13.7 pCi/l 5.0 pCi/l 10/19/93 Co-60 10.0 pCi/l 1.3 - 18.7 pCia 10.7 pCi/l i
Cs-134. 12.0 pCi/l 33 - 20.7 pCiA 103 pCi/l Cs-137 10.0 pCill 1.3 - 18.7 pCill 103 pCi/l 11/12/93 Ba-133 79.0 pCia 65.1 - 92.9 pCia 80.3 pCi/l Co-@ 30.0 pCiB 213 - 38.7 pCi/l 31.0 pCill Zn-65 150.0 pCill 124.0 - 176.0 pCia 162.0 pCia
, I Ru-106 201.0 pCi/l 1663 - 235.7 pCi/l 1903 pQ1 F
Cs-134 59.0 pCi/l 503 - 67.7 pCi/l 54.7 pCi/l Cs-137 40.0 pCia 313 - 48.7 pCill 413 pCi/l-
TAELE 5-1 (Page 2 of 3)
U.S. ENVIRONMENTAL PROTECTION AGENCY INTERLABORATORY COMPARISON PROGRAM 1993 CROSS-CHECK RESULTS FOR THE RADIOLOGICAL AND -
ENVIRONMENTAL SERVICES LABORATORY CO R O L I. S ANALYSIS NUCLIDE(S) KNOWN VALUE REPORTED VALUE DT Gamma in Water 02/02 S 3 1-131 100.0 pCi/l 82.7 - 117.3 pCill 103.0 pCi/l 10/08 S 3 I-131 117 0 pCill 96.2 - 137.8 pCi/l 118.0 pCill Air Filter 08/27B3 Cs-137 9.0 pCUI 0.3 - 17.7 pCi/1 11.0 pCill Gross Beta 47.0 pCi/l 38.3 - 55.7 pCi/l 48.0 pCi!! ;
Tritium in Water 06/07 S 3 11- 3 9844.0 pCill 8136.8 - 11551.2 pCi/l 9267.3 pCill I1/05S3 H-3 7398.0 pCi/l 6114.1 - 8681.9 pCi/l 6787.0 pCi/l e
i
TABLE 5-1 (Pagc 3 of 3)
U.S. ENVIRONMENTAL PROTECTION AGENCY INTERLABORATORY COMPARISON PROGRAM 1993 CROSS-CHECK RESULTS FOR THE RADIOLOGICAL AND ENVIRONMENTAL SERVICES LABORATORY O I S KNOWN VALUE ANALYSIS NUCLIDE(S) - REPORTED VALUE DT 3 3 Gamma in Milk 09/24N3 1-131 120.0 pCi/l 99.2 - 140.8 pCill 122.0 pCi/l Cs-137 49.0 pCill 40.3 - 57.7 pCi/l 48.0 pCill Beta in Water 1/29N3 Gross Beta 44.0 pCi/l 353 - 52.7 pCill 39.0 pCi/l en E
7/23N3 Gross Beta 43.9 pCill 31.0 - 55.0 pCi/l 373 pCi/l 10/1983 Gross Beta 58.0 pCill 40.7 - 75.3 pCi/l 463 pCa/l 10/2933 Gross Beta 15.0 pCi/l 63 - 23.7 pCill 17.0 pCi/l I
\ .
l l
L
TABLE 5.2 STATE OF NORTH CAROLINA ,
DEPARTMENT OF ENVIRONMENTAL HEALTH AND NATURAL RESOURCES ENVIRONMENTAL DOSIMETER CROSS-CHECK - 1993 STATE OF N.C. RD&R ESTIMATED ESTIMATED VALUE VALUE Y
oo Date of Exposure Estimated Exposure Estimated Uncertainty Cross-check (mR) Uncertainty (mR) (IS.D. mR)
(IS.D. mR)
Jul-93 60 t 1.81 57.66 2.20 Nov-93 40 t 1.91 39.58 1 0.82 l
l
6.0 REFERENCES
- 1. Final Safety Analysis Report, McGuire 1 & 2, Section 1.2.1.
- 2. Final Safety Analysis Report, McGuire 1 & 2, Section 2.1.
- 3. Final Safety Analysis Report, McGuire 1 & 2, Section 2.1.1.
- 4. Final Safety Analysis Report, McGuire 1 & 2, Section 11.6.1.
- 5. Final Sa'ety Analysis Report, McGuire 1 & 2, Section 11.6.3.
l G. Final Srfety Analysis Report, McGuire 1 & 2, Section 11.6.4. l
)
- 7. Selected Licensee Commitments Manual Section 16.11-13.
- 8. McGuire Nuclear Station Technical Specification 6.9.1.6.
l
- 9. Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I", U.S. Nuclear Regulatory Commission, Rev.1, October 1977.
- 10. Probability in Statistics in Engineering and Management Science, Illnes and Montgomery,1969, pp. 287-293.
- 11. Practical Statistics for the Physical Sciences, American Chemical Society, 1988, pp.84-100.
6-1 t- _ - - _ - . - _ - _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _
APPEND /X A ENVIRONMENTAL SAMPLING AND ANALYS/S PROCEDURES
'I
APPENDIX A
_ENVIRCNMENTAL SAMPLING AND ANALYSIS PROCEDURES Adherence to established procedures for sampling and analysis of all environmental media at McGuire Nuclear Station was required to ensure compliance with Station Selected Licensee Commitments. Analytical procedures were employed to ensure that Selected Licensee Commitments detection capabilities were achieved.
Environmental sampling and analyses were performed by the Duke Power Generation Services Department Radiological and Environmental Services Group, the Dosimetry and Records Group and the Fisheries work groups.
Starting at Section A.1, this appendix describes the environmental sampling frequencies and analysis procedures by media type,
- l. CHANGE OF SAMPLING PROCEDURES Two special sampling sites were added in 1993. Descriptions are given under applicable media headings.
II. CHANGE OF ANALYSIS PROCEDURES No changes were incorporated to the sample analysis procedures in 1993.
Ill. SAMPLING AND ANALYSIS PROCEDURES A.1 AIRBORNE PARTICULATE AND RADIOlODINE Airborne particulate and radioiodine samples at each location were composited continuously by means of continuous air samplers. Air particulates were collected on a particulate filter and radioiodines were collected in a charcoal cartridge situated behind the filter in the sampler. The samplers are designed to operate at a constant flow rate (in order to compensate for any filter loading) and are set to sample approximately 2 cubic feet per minute.
A-2
l I
1 Filters and cartridges were collected weekly. A weekly gamma analysis and l 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 liigh School (8.7 mi. WNW)
In addition, a special location (192) was added in 1993 at the nearest community located 2.81 miles NNE at the Peninsula development.
A.2 DRINKING WATER :
Biweekly composite samples were collected. A low-level Iodine-131 analysis was performed on each composite aample. A gross beta and gamma analysis was performed on monthly composites. Tritium analysis was performed on the quarterly composites. The composites were collected biweekly from the locations listed below.
Location 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)
A.3 SURFACE WATER Biweekly composite samples were collected. A low-level Iodine-131 analysis was performed on each composite sample. A gamma analysis was performed on the monthly composites. Tritium analysis was performed on each sample. The composites were collected from the locations listed below.
I Location 128 = Discharge Canal Bridge (0.4 mi. ENE) l Location 131 = Cowans Ford Dam (0.7 mi. W) i Location 135 = Plant Marshall Inta'ke Canal (12.0 mi. N) l A.4 MILK Biweekly grab samples were collected at each dairy and a gamma and low-level i Iodine-131 analysis was performed on each. The biweekly grab samples were collected from the locations listed below.
Location 138 = lienry Cook Dairy (2.75 mi, ESE)
Location 139 = William Cook Dairy (2.6 mi, E)
Location 140 = Kidd Dairy - COWS (2.8 mi. SSE) l-Location 141 = Lynch Dairy - COWS (14.8 mi. WNW) l
[
A-3
f A.5 BROADLEAF VEGETATION Monthly samples were collected and a gamma analysis was performed on each.
The samples were collected from the locations listed below.
Location 120 = Site Boundary (0.4 mi. NNE)
Location 125 = Site Boundary (0.4 ml. SW)
Location 134 = East Lincoln Junior High School (8.7 mi. WNW)
Location 158 = 4-5 Mile Radius (5.0 ml. NNE)
A.6 SHORELINE SCOIMENT Semiannual samples were collected and a gamma analysis was performed on each following the drying and removal of rocks and clams. The samples were collected from the locations listed below.
Location 129 = Discharge Canal Entrance to Lake Norman (0.G mi.SW)
Location 130 : Highway 73 Bridge Downstream (0.,6 mi. SW)
Location 137 = Pinnacle Access Area (12.0 mi. N)
A.7 j*lSH Semiannual samples were collected and a gamma analysis was performed on the 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 ml. ENE)
Location 137 = Pinnacle Access Area (12.0 mi. N)
A.8 DIRECT GAMMA RADIATION (TLD)
Thermoluminescent dosimeters (TLD) were collected quarterly at thirty concentric locations. A gamma dose rate was determined for each TLD. The TLDs were placed as indicated below.
A-4 .
l
- An inner ring of 14 TLDs at the site boundary, one in each available meteorological sector. The site boundary locations in the N and NNW sectors are over water; however, two special interest TLD's are located in these sectors inside the site boundary.
- An outer ring of 16 TLDs, one in each meteorological sector in the 6 to 8 kilometer range.
- The remaining TLDs were placed in SPECIAL INTEREST areas such as population centers, residential areas, schools, and CONTROL locations. One TLD location was added in 1993 at the nearest community to McGuire. Site 191 is located 2.81 miles NNE at the Peninsula development.
A.9 FOOD PRODUCTS Samples were collected monthly when available during the harvest season and a gamma analysis was performed on each. The samples were collected at the locations listed below.
Location 184 = 5 Mile Radius (2.5 m! . ENE) -
Gardens (Davenport's Residence)
Location 188 = 5 Mile Radius (2.8 mi. N) - Gardens ( Austin's Residence)
A.10 h.NNUAL LAND USE CENSUS An annual Land Use Census was conducted to ifentify within a distance of 8 kilometers (5.0 miles) from the station, the nearest location from the site boundary in each of the sixteen meteorological sectors, the following:
- The Nearest hesidence
- The Nearest Meat Animal
!
- The Nearest Garden
- greater than 50 square meters or 500 square feet
- The Nearest Milk giving Animal (cow, goat, etc. )
L This census was completed on June 24, 1993 and the results are shown in Table 3.10 (pages 3-32 and 3-33).
l l
l l
V l A-5 l
1 l
l 1
IV. SAMPLING AND ANALYSIS IMPROVEMENTS I In 1993, efforts were continued to reduce the number of sampling deviations, focusing on equipment upgrades, research of other equipment, increasing the !
frequency of checking on sites which incur a greater number of deviations, and providing better documentation of those deviations. New carbon vano air samplers were placed in the field in 1993 at all air locations .to replace the older oil lubricated pumps. In addition, better fuses were installed in an attempt to decrease " blown fuse" deviations. Surface water sites were also improved in 1993. A platform was built at Location 135 (Plant Marshall) to maintain sampler 18 inches below the water line. This design should reduce deviations and provide a more consistent sample at this location. At Location 131 (Cowan's Ford Dam), the water line length from supply to collection tank was decreased to reduce deviations and dead leg collection. Also, the Global Positioning System (GPS) Project was completed for McGuire Nuclear Station to more accurately determine distance and sector for each sampling location.
GPS is a satellite - based radio navigation system which provides precise positioning data.
t i
l l
l l
i i
A-6
APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING l
PROGRAM
SUMMARY
OF RESULTS Summary sheets for each media have been included in this Appendix.
l B-1
1 0.1 RADIO 100lNES Environmental Radiological Monitoring Program si.srnary Name of Facility : McGuire Nuclear Station Docket Ntster : 50 369,370 Location of Facility Mecklenburg County, N.C. Reporting Parlod : 1-JAN 1993 through 31 0EC 1993 l flme Report Generated 26 JAN.1994 09:40:25 Database Name : $0lSK1:(USER.ASC]McGuire Nuclear Station 93.SAF;)
................................................."............" ..... 4.........................................................
l l l l Location with Highest Mean l lNo.of Medlun or l Type & Total l Lower l All Indicator l".""""-"""""."".l l Won.
Psthwsy l Nuter of l Limitofl Locations l Name,OlstanceandOfrectionl Control Locations l Routine sag ted l Analysee l Detection l Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) l Report (Units) l Performed l (LLO) l Range l Code Range l Range l Meas.
RADIO!ColNES l l l l l l
!/M3) l l l l l134(8.7MiWW) l l I I I l ocations l MN 54 260l 0.0
- 00E+00( 0/ 208) l 0.00E*00( 0/ 52) l 0.00E+00( 0/ 52) l 0 l l J 00E+00 " 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l l I I I I l CO 58 260l 0.0 l 0.00E+00( 0/ 208) l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52)l 0 l l l 0.00E+00 " 0.00E*00 l 0.00E*00-0.00E*00l 0.00E+00 " 0.00E+00 l l l l l l 1 lFE-59 260l 0.0 l 0.00E+00( 0/ 208) l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52) l 0 l l l 0.00E+00' 0.00E+00 l 0.00E+00 " 0.00E+00 l 0.00E+00.0.00E+00l 1 I I I I I lCo60 260l 0.0 l 0.00E*00( 0/ 208) l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52) l 0 l l l 0.00E+00 " 0.00E+00 l 0.00E+00.0.00E+00l 0.00E+00. 0.00E+00 l l l I I . I I l2N65 260l 0.0 l 0.00E+00( 0/ 208) l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52) l 0 l l l 0.00E+00 " 0.00E+00 l 0.00E+00 0.00E+00l 0.00E+00" 0.00E+00 l 1 I I I I I lN895 260l 0.0 l 0.00E+00( 0/ 208) l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52) l 0 l l l 0.00E+00 " 0.00E+00 l 0.00E+00 " 0.00E+00 l 0,00E+00 " 0.00E+00 l l 1 I I I I l2R95 260l 0.0 l 0.00E+00( 0/ 208) l 0.00E+00( 0/ 52) [ 0.00E+00( 0/ 52) l 0 l l l 0.00E+00 0.00E+00 l 0.00E+00-0.00E+00l 0.00E+00 " 0.00E+00 l l i l i I I i 1 lt131 260l 7.00E02l 0.00E+00( 0/ 208) l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52) l 0 l l l 0.00E+00 " 0.00E+00 l 0.00E*00" 0.00E+00 l 0.00E+00 " 0.00E+00 l I I I I I l lCS134 260l 5.00E02l 0.00E+00( 0/ 208) l 0.00E+00( 0/ 52) l 0,00E+00( 0/ 52) l 0 l l l 0.00E+00 " 0.00E+00 l 0.00E+00" 0.00E+00 l 0.00E+00' 0.00E+00 l l l l I I I l CS 137 260l 6.00E02l 0.00E+00( 0/ 208) l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52)l 0 l l l 0.00E+00 0.00E+00 l 0.00E+00" 0.00E+00 l 0.00E+00' 0.00E+00 l l 1 1 I I I lBALA140 260l 0.0 l 0.00E+00( 0/ 208) l 0.00E+00( 0/ 52) [ 0.00E+00( 0/ 52) l 0
.l l l 0.00E+00" 0.00E+00 l 0.00E+00 " 0.00E+00 l 0.00E+00" 0.00E+00 l n ....................................................... ......... ...u..........o............ ...............................
% and range based mon detectable measurements only ,
htionofdetectablemeasurementsatspecifiedlocationsisindicatedinparentheses,(Fraction)
$rcngsirdicatesnodetectableactivitymeasurements kl0isequalto0,thenLLOisnotrequiredbyTechnicalSpecifications tion 120 = Site Boundary (0.4 Mi kNE) tion 121 = Site Bom dary (0.5 Mi NE) ption125=SiteBoundary(0.4MiSW) .
ption 133 = Cornelius, NC (6.2 Mi NE) btion 134 = East Lincoln Junior High School (8.7 Mi WNW) B2 l l
l l
l l
8.2 PARilCULATES Environmental Radiological Monitoring Program Sumery Name of Facility : McGuire Nuclear Station Docket Nunt>er t 50 369,370 Location of Facility : Mecklenburg Ccunty, N.C. Reporting Period 1 JAN 1993 through 31 DEC 1993 flee Rsport Generated 26 JAU 1994 09:40:25 Database Name t $0lSX1t[ USER.ASC)McGuire Nuclear Station 93.SAF;)
........................................................ ............. u ..... u ..................................................
l l l l Location with Highest Mean l l No. of Kedius or l Typ A Total l Lower l All Indicator l""""""a"l l Non.
Pathway l Nunber of l Limitofl Locations l Name, Distance and Direction l Control Locations l Routine Sampled l Analyses l Detection l Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) l Report (Units) l Performed l (LLD) l Range l Code Range l Range l Meas.
........u.......... .........................................................................................................u.
< PARTICULATE l l l l l l l/M3) l l l l l134(8.7MlWNW) l 1 I I I I I 23stions lMN54 260l 0.0 l 0.00E+00( 0/208)l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52) l 0 l l l 0.00E+00" 0.00E+00 l 0.00E+00 " 0.00E+00 l 0.30E*00 " 0.00E+00 l l 1 I I I I lCO-58 260l 0.0 l 0.00E+00( 0/ 208) l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52) l 0 l l l 0.00E*00 " 0.00E+00 l 0.00E+00" 0.00E+00 l 0.00E+00 " 0.00E+00 l l l I I I i l FE 59 260l 0.0 l 0.00E+00( 0/ 208) l 0.00E+00( 0/ 52) l 0.00E+00( 0/ $2) l 0 l l l 0.00E+00-0.00E+00l 0.00E+00 ' 0.00E+00 l 0.00E+00.0.00E+00l 1 I I I I i lCO60 260l 0.0 l 0.00E+00( 0/ 208) l 0.00E*00( 0/ 52) l 0.00E+00( 0/ 52) l 0 l l l 0.00E+00" 0.00E+00 l 0.00E+00- 0.00E+00l 0.00E+00 " 0.00E+00 l 1 I I I I l lZN65 260 l 0.0 l 0.00E+00( 0/ 208) l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52) l 0 l l l 0.00E+00- 0.00E+00l 0.00E+00 0.00E+00 l 0.00E+00 " 0.00E+00 l 1 I i l i I lNS95 260l 0.0 l 0.00E+00( 0/ 208) l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52) l 0 l l l 0.00E+00.0.00E+00l 0.00E+00" 0.00E+00 l 0.00E+00 " 0.00E+00 l l I I I I I l2R95 260l 0.0 l 0.00E+00( 0/ 208) l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52) l 0 l l l 0.00E+00" 0.00E+00 l 0.00E+00 0.00E+00 l 0.00E+00 " 0.00E+00 l 1 l I I I I ll131 260l 7.00E02l 0.00E+00( 0/ 208) l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52) l 0
, l l l 0.00E+00 0.00E+00 l 0.00E+00" 0.00E+00 l 0.00E+00 " 0.00E+00 l l l l ,l l l lCS134 260l 5.00E02l 0.00E+00( 0/ 208) l 0.00E*00( 0/ 52) l 0.00E*00( 0/ 32) l 0 l l l 0.00E+00 " 0.00E+00 l 0.00E+00" 0.00E+00 l 0.00E+00" 0.00E+L0 l l 1 I I I I lcs137 260l 6.00E02l 0.00E+00( 0/ 208) l 0.00E+00( 0/ 52)l 0.00E+00g 0/ 52) l 0 l l l 0.00E+00 0.00E+00 l 0.00E+00" 0.00E+00 l 0.00E+00 " 0.00E+00 l l l l l l l lBALA140 260l 0.0 l 0.00E+00( 0/208)l 0.00E+00( 0/ 52) l 0.00E+00( 0/ 52) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00 " 0.00E+00 l 0.00E*00" 0.00E+00 l l l l l121(0.5MiNE) l l l BETA 260l 1.00E02l 1.88E 02( 208/ 208) l 1.93E 02( 52/ 52) l 2.04E 02( 52/ 52) l 0 l l l 5.67E 03" 3.30E*02 l 8.26E 03" 3.27E 02 l 8.90E*03 " 4.34E 02 l
..u..............................................................................u............................................
p and rsngt based upon detectable measurements only htlon of detectable measurements at specified locations is indicated in parentheses, (Fraction) hrangsindicatesnodetectableactivitymeasurements
'LD is equal to 0, then LLD is not required by Technical $pecifications j tion 120 = Site Boundary (0.4 MI NNE) I tion 121 = site Soundary (0.5 MI NE) I htlon125=siteBoundary(0.4MiSW) l
) tion 133=Cornelius,NC(6.2MiNE)
) tion 134 = East Lincoln Jtrif or High School (8.7 Mi WNW) B+3 l
1
I a.3 DRit:ElNG WATER Envircrvnental Radiological Monitoring Program Stmnery Name of Fecility : McCulte Nuclear Station Docket Ntrt)er 50 369,370 l Locstion of facility : Mecklenburg County, N.C. Reporting Period 1 JAN 1993 th*ough 31 0EC 1993 1 tima Report Generated 26 JAN 1994 09:40:25 Database Nemo : $0lSK1 (USER.ASCIMcCulre Nuclear Station 93.SAF;1 ,
................................o..~.........................................................o................o u............
l l l l Location with Highest Mean l lNo.of !
Medlun or l Type &fotall Lower l All irrilcator l'"""'*"""""""l l Non-Pathway l Ntrt>er of l Limitofl Location $ l Name, Olstance and Direction l Control Locations l Routine Sarrpled l Analyses l Detection l Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) l Report (Units) l Performed l (LLD) l Range l Code Range l Range l Meas.
........................................... ............ .................... o ..................................................
NKitG WATER l l l l l l
<!/ lifer) l l l l l136(12.5MINNE) l l 1 1 I I I
.ocations l ANAL).LL 39l 1.0 l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13)l 0 l l l 0.00E+00 " 0.000 00 l 0.00E+00' 0.00E+00 l 0.00D 00" 0.00E+00 l 1 I I I I i l ANAL 2LL 39l 1.0 l 0.00D 00( 0/ 26) l 0.00E*00( 0/ 13) l 0.00D00( 0/ 13) l 0 l l l 0.00E+00 " 0.00D 00 l 0.00E+00 " 0.00E+00 l 0.00E+00 " 0.00 D 00 l 1 I I I I i lMN54 39l 15. l 0.00E+00( 0/ 26) l 0.00D00( 0/ 13) l 0.000 00( 0/ 13) l 0 l l l 0.00D 00' 0.00 D 00 l 0.00D00--0.00E+00l 0.00D0a" 0.00E*00l l l I I I I l Co 58 39l 15. l 0.00E+00( 0/ 26) l 0.00D00( 0/ 13)l 0.00E*00( 0/ 13) l 0 l l l 0.00E+00 " 0.00E+00 l 0.00D 00 " 0.00E+00 l 0.00D 00 " 0.00 D 00 l l l l l 1 I lFE59 39l 30. l 0.00D 00( 0/ 26) l 0.00D00( 0/ 13) l 0.00D00( 0/ 13) l 0 l l l 0.00C+00 " 0.00E+00 l 0.00D 00' 0.00D 00 l 0.00E+00 " 0.00D 00 l l l I I I l lCo60 39l 15. l 0.00E+00( 0/ 26) l n.00E*00( 0/ 13)l 0.00E+00( 0/ 13) l 0 l l l 0.00E*00-0.00000[ 0.09:+00- 0.00D00 l 0.00E+00' 0.00E+00 l 1 I I I I I lZN65 39l 30. l 0.00D00( 0/ 26) l 0.00000( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00 " 0.00D 00 l 0.00D00 0.00E+00 l 0.00 D 00 " 0.000 00 l l l 1 1 I I lks95 39l 15. l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 13) l 0.00E*00( 0/ 13) l 0 l l l 0.00E+00 0.00D00 l 0.00D 00 " 0.000 00 l 0.00E+00 " 0.000 00 l l I I I I I l2R95 39l 15. l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 13)l 0.00E*00( 0/ 13) l 0 l [ l 0.00 D 00 " 0.00E*00 l 0.00E*00' 0.00D 00 l 0.00E+00' 0.00E+00 l l l l 1 1 I ll131 39l 15. l 0.00E+00( 0/ 26) l 0.00E*00( 0/ 13) l 0.00E*00( 0/ 13)l 0 l l l 0.000 00" 0.00E+00 [ 0.000 00 " 0.00E+00 l 0.00E+00 " 0.00D00 l 1 1 I I I I lCS134 39 l 15. l 0.00D00( 0/ 26) l 0.00D 00( 0/ 13) l 0.00D 00( 0/ 13) l- 0 l l l 0.00D 00 " 0.00E*00 l 0.00D 00 ' 0.00E+00 l 0.00E+00 " 0.00 0 00 l l l 1 I I I lC$a137 39 l 18. l 0,00D00( 0/ 26) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00. 0.00E+00 l 0.00D 00 " 0.00D 00 l 0.00D 00" 0.00E+00 l 1 I I I I I l lBALA.140 39l 15. l 0.00000( 0/ 26) l 0.00D00( 0/ 13) l 0.00D 00( 0/ 13) l 0 l l l l 0.00E+00 0.00E+00l 0.00E*00 0.00000l 0.00000" 0.000 00 l L....................................................."................................"...........................................
&nd rcngs based upon detectable measurements only tion of detectable measurements at specified locations is indicated in parentheses, (Fraction)
) rcngs irdicates no detectable activity measuremente LD is equal to 0, then LLD is not required by Technical Specifications tion 132 = Charlotte Municipet Water supply (11.2 Mt SSE) location 142 = Davidson Municipal Water Supply (7.5 MI NE) stlon 136 = Mooresville Municipal Water sumly (12.5 Mi NNE) 84
, - _ _ - - - - , - - . ._ ~ _ , - -, ,
i i
l 1
I i
Envirorvrental Redlological Monitoring Progeom $uvery Name of Pscllity 1 McGuire Nuclear Station Docket Ntetwe 50 369,370 Location of Facility : Meckletturg Comty, N.C. Reporting Period 1.JAN.1993 through 31*0EC 1993 Time Report Generated t 26 JAN 1994 09:40:25 Database Name : SOISK1t(U$ER.ASCIMcCulre Nucteer Station 93.SAF;)
l l l l Location with Highest Mean l lNo.of Medlue or l Type & Total l Lower l Alt Indicator l*******************************l l Nen*
Psthway l Nurtser of l Limitofl Locations l Name, Distance and Olrection l Control Locations l Routine
$eepted l Analyses l Detection l Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) l Report (Unite) l Performed l (LLD) l Range l Code Range l Range l Mees.
utito VATER l l l l l l l/ lifer) l l l l l136(12.5MINNE) l l l l l 142 (7.5 Mi NE) l l socations l BETA 39l 4.0 l 2.5 ( 26/ 261l 2.8 ( 13/ 13)l 2.4 ( 13/ 13)l 0 l l l 0.68 ** 10. l 0.84 ** 10. l 0.68 ** 7.2 l TRIT!UM l l l l l l
$1/LlfER) l l l l l l 1 1 I I I I lH3 12l 2.00l!+03l 0.00E*00( 0/ 8) l 0.00E+00( 0/ 4) ' 0.00E+00(
, 0/ 4) l 0 l l l 0.00E*00**0.00E+00l 0.00E+00**0.00E+00l 0.00E+00-*0.00E+00l erd range based upon detectable ressuremente only tion of detectobte measurements et specified Locations is indicated in perentheses, (Fraction)
'o range Irdicates no detectobte activity measurements LLO la equel to 0, then LLO la not required by Technical specifications atten 132 = Charlotte Municipal Water surply (11.2 Mi ssE) etion 136
- Mooresvitte Municipal Water supply (12.5 MI NME) ctico 142 = Davidson Municipal Water surpty (7.5 Mi NE)
I l
l l 85 i I l . - - - _ . - .. .. . - --
1 I
S.4 $URFACE WATER Enviroreental Radiological Monitoring Program tunury l Name of facility i McGuire Nucteer station Docket Nwtaer 50 369,370 Location of PeclLity : Mecklenburg Comty, N.C. Reporting Period a 1* JAM 1993 through 3t+0EC 1993 flee tiport Generated 26 JAN 1994 09:40:25 Database Name t $0lS(li(USER.ASC)McGuire Nucteer Stetton93 tAF)1
...........o..................................................o........ o.................................o..... o.............
l l l l Location with Highest Mean l l No. of M: dim or l Type &fotell Lower l Alt Indicator l"""'""""""*"l l Won.
Pathwsy l Nwtwr of l Limitofl Locations l Nam, Olstence ord Of rection l control Locations l Routine tagled l Analyses l Detection l Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) l Report (Units) l Performed l (LLO) l Range l Code Range l Range l Meas.
.,.............o........................................................u...................... o........u....................
FACE WATER l l l l l l t/ liter) l l l l l135(12.0 min) l l 1 l I I I
,ocations l ANAL 1LL 39 l 1.0 l 0.00E+00( 0/ 26) [ 0.00E*00( 0/ 13) l 0.00E+00( 0/ 13)l 0 l l l 0.00E+00 0.00E+00 l 0.00E+00.0.00E+00l 0.00E+00 " 0.00E*00 l l l l 1 I l l ANAL 2 LA 39 l 1.0 l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 13)l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00 " 0.00E+00 l 0.00E+00 " 0.00E*00 l 0.00E*00 ' 0.00E+00 l l l I I I l lMW54 39 l 15. l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E *00" 0.00E *00 l 0.00E+00" 0.00E+00 l 0.00E+00 " 0.00E+00 l l l l 1 1 I 15, l 0.00E+00( 0/ 26) l l C0 58 39 l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13)l 0 l l l 0.00E+00 " 0.00E+00 l 0.00E+00 " 0.00E+00 l 0.00E+00 " 0.00E+00 l l 1 I I I I lFE59 39l 30. l 0.00E+00( 0/ 26) l 0.00E*00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00 " 0.00E+00 l 0.00E+00' 0.00E+00 l 0.00E+00 " 0.00E+00 l l 1 I I I I l Co 60 39 l 15. l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00 " 0.00E+00 l 0.00E+00 " 0,00E*00 l 0.00E+00 " 0.00E+00 l 1 l i I I I lZM65 3v l 30. l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 13)l 0.00E+00( 0/ 13)l 0 l l l 0.00E*00 " 0.00E+00 l 0.00E+00" 0.00E+00 l 0.00E+00 " 0.00E*00 l 1 I I I I I lNa95 39 l 15. l 0.00E+00( 0/ 26) l 0.00E*00( 0/ 13) [ 0,00E+00( 0/ 13) l 0 l l l 0.00E+00" 0.00E*00 l 0.00E+00" 0.00E+00 l 0.00E+00 " 0.00E+00 l 1 I I I I I l2R95 39 l 15. l 0.00E+00( 0/ 26) l 0.00E*00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00 " 0.00E+00 l 0.00E+0C. 0.00E+00 l 0.00E *00" 0.00E+00 l l l l l l 1 lt131 39] 15. l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 13)l 0.00E+00( 0/ 13)l 0 l l l 0.00E*00 " 0.00E+00 l 0.00E+00 " 0.00E*00 l 0.00E+00" 0.00E+00 l 1 I I I I l lC1134 39l 15. [ 0.00E+00( 0/ 26)l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00" 0.00E+00 l 0.00E*00 " 0.00E+00 l 0.00E+00" 0.00E*00 l l l l l 1 l lCS137 39 l 18. l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 13)l 0.00E+00( 0/ 13) l 0 l l l 0.00E+00 " 0.00E+00 l 0.00E+00 " 0.00E+00 l 0.00E*00.0.00E+00l 1 I I I I I lBALA.140 39 l 15. l 0.0CE+00( 0/ 26) l 0.00E+00( 0/ 13) l 0.00E+00( 0/ 13)l 0 l l l 0.00E*00 " 0.00E+00 l 0.00E+00 " 0.00E+00 l 0.00E+00 " 0.00E+00 l
...........o...............................................o.....o.......................................o................... l yandrengtbasedupondetectablemeasurementsonly 3 tion of detectobte measurements et specified locations is indicated in parentheses, (Fraction) 3 rangs Indicates no detectobte activity measurements lLO is equal to 0, then LLO is not reqJired by Technicet specifications 3 tion 128
- Discharge Canal Orldge (0.4 MI ENE) Location 135
- Plant Marshelt Inteke Canal (12.0 Mi N) )
Dtion 131 a cowans ford Dam (0.7 Mi V) B6
Environmental Radiological Monitoring Program Sumery tame of Facility ? McGuire Nuclear Station Docket Nurber : 50-369,370 Location of Facility : Mecklenburg County, N.C. Reporting Period : 1 JAN-1993 through 31-DEC-1993 Time Report Generated
- 26 JAN-1994 09:40:25 Database Name : $0lSK1:IUSER. ASC]McGuire Nuclear Station 93.SAF;1 l l l l Location with Highest Mean l lNo.of Medium or l Type & Total l Lower l All Indicator l"~~~~~--~.~.-~'-~~l l Won-Pathwty l Nurber of l Limitofl Locations l Name,DistanceandDirectionl Control Locations l Routine Sanpled l Analyses l Detection [ Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) l Report
/ _( Units) l Performed l (LLD) l Range l Code Range l Range l Meas.
3.................................................................................................................................
TRITIUM l l l l l l sI/ LITER) l l l l l135(12.0 MIN) l l l l l128(0.4MiENE) l l (ocstions lN3 12l 2.00E+03l 6.85E+02( 3/ 8) l 6.85E+02( 3/ 4) l 0.00E+00( 0/ 4) l 0 l l l 5.31E+02" 9.44E+02 l 5.31E+02" 9.44E+02 l 0.00E+00- 0.00E+00 l snd rence based upon detectable measurements only tion of detectable measurements at specified locations is indicated in parentheses, (Fraction) o rtngs indicates no detectable activity measurements LLD is equal to 0, then LLD is not required by Technical Specifications stion 126 = Discharge Canal Bridge (0.4 Mi ENE)
<ation 131 = Cowans Ford Dam (0.7 Mi W) ation 135 = Plant Marshall Intake Canal (12.0 Mi N) 1 l
- l. I l
l 1
\
I l
[
r B7 l
R.5 NILK Environmental Radiological Monitoring Program Sumary name of Facility : McGuire Nuclear Station Docket Nwber : 50 369,370 Locstion of Facility Mecklenburg County, N.C. Reporting Period : 1-JAN 1993 through 31-DEC-1993 Time Rrport Generated : 26 JAN-1994 09:40:25 Database Name : $0lSK1:(USER. ASC]McGuire Nuclear Station 93.SAF;1 l l l l Location with Highest Mean l lNo.of Medium or l Type & Total l Lower l All Indicator l-------'-~~-----"'""'"l l Non-Nthwiy l Nu h of l Limitofl Locations l Name,DistanceandDirectionl Control Locations l Routine SarnpM l Analyses l Detection l Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) l Report (Units) l Performed l (LLD) l Range l Code Range l Range l Meas.
K I I I I I I 1/ LITER) l l l l l141(14.8MiWNW) l l l l l l 1 tocations lMN54 104l 0.0 l 0.00E+00( 0/ 78) l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 26) l 0 l l l 0.00E+00 " 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00" 0.00E+00 l l l I I I I lCo-58 104 l 0.0 l 0.00E+00( 0/ 78) l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 26) l 0 l l l 0.00E+00- 0.00E+00l 0.00E+00- 0.00E+00 l 0.00E+00 " 0.00E+00 l l l l l l l lFE-59 104l 0.0 l 0.00E+00( 0/ 78) l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 26) l 0 l l l 0.00E+00 " 0.00E+00 l 0.00E+00" 0.00E+00 l 0.00E+00-0.00E+00l
! I I I I i lCo60 104l 0.0 l 0.00E+00( 0/ 78) l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 26) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00- 0.00E+00l 0.00E+00--0.00E+00l I I I I I I l2N-65 104l 0.0 l 0.00E+00( 0/ 78) l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 26) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00" 0 00E+00 l l l l l l l lN895 104l 0.0 l 0.0M + 00( 01 78) l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 26) l 0 l l l 0.00E+00" 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00" 0.00E+00 l 1 I I I I I lZR95 104 l 0.0 l 0 10E+00( 0/ 78) l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 26) l 0 l l l OE+00' 0.00E+00 l 0.00E+00 " 0.00E+00 l 0.00E+00--0.00E+00l l l l l 1 l ll131 104l 15. l 0.00E+00( 0/ 78) l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 26) l 0 l l l 0.00E+00 " 0.00E+00 l 0.00E+00" 0.00E+00 l 0.00E+00-0.00E+00l 1 1 I I I I lLLI-131 104l 1.0 l 0.00E+00( 0/ 78) l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 26) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l 0.00E+00- 0.00E+00 l l l l l I I lCS134 104l 15. 0/ 78) [ 0.00E+00(
l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 26) l 0 l l l 0.00E+00" 0.00E+00 l 0.00E+00 " 0.00E+00 l 0.00E+00 " 0.00E+00 l l 1 1 I I I lCS-137 104l 18. l 0.00E+00( 0/ 78) l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 26) l 0 l l l 0.00E+00" 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00 " 0.00E+00 l l l l l l l lBALA-140 104l 15. l.0.00E+00( 0/ 78) l 0.00E+00( 0/ 26) l 0.00E+00( 0/ 26) l 0 l l l 0.00E+00 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00" 0.00E+00 l cnd range based upon detectable measurements only tion of detectable measurements at specified locations in indicated in parentheses, (Fraction) rongs frdicates no detectable activity measurements LD is equal to 0, then LLD is not required by Technical Specifications tion 138 = Henry Cook Dairy (2.75 Mi ESE)
, tion 137 = William Cook Dairy (2.6 Mi E) i tion 140 a Kidd Dairy - COWS (2.8 Mi SSE) stion 141 = Lynch Dairy COWS (14.8 Mi WNW) B8 l
l 1
l 8.6 BROADLEAF VEGETAfl0N Envirorenental Radiological Monitoring Prograrn Swynary Name of Facility ? McGuire Nuclear Station Docket Nunber : 50 369,370 Locstion of Facility : Mecklenburg County, N.C. Reporting Period
- 1-JAN-1993 through 31 DEC 1993
' Time Riport Generated : 26-JAN-1994 09:40:25 Database Name : $0!SK1:(USER. ASC)McGuire Nuclear Station 93.SAF;1 l n................................................................................................... ............. ............... l l l l l Location with Highest Mean l lNo.of Medlun or l Type & Total l Lower l All Indicator l--~"---""-~~--~---"-l l Non-Psthwty l N w ber of l Limitofl Locations l Name, Distance and Direction l Control Locations l Routine Sarrpt ed l Analyses l Detection l Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) l Report (Units) l Performed l (LLD) l Range l Code Range l Range l Mees.
p............. ....................................... ...... ....... .. ......... ............... ..............................
DADLEAFYECETl l l l l l Ct /WE T/KG) l l l l l134(8.7miWNW) l 1 1 I I l 1 Locations lMN54 48 l 0.0 l 0.00E+00( 0/ 36) l 0.00E+00( 0/ 12) l 0.00E+00( 0/ 12) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00 ~ 0.00E+00 l 0.00E+00- 0.00E+00 l l l l l l l lCo-58 48l 0.0 l 0.00E+00( 0/ 36) l 0.00E+00( 0/ 12) 1 0.00E+00( 0/ 12) l 0 l l l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l 0.00E+00 " 0.00E+00 l l l l 1 1 I lFE-59 48l 0.0 l 0.00E+00( 0/ 36) l 0.00E+00( 0/ 12) l 0.00E+00( 0/ 12) l 0 l l l 0.00E+00- 0.00E+00l 0.002+00~ 0.00E+00 l 0.00E+00 ~ 0.00E+00 l l l l I 1 l lCo60 48 l 0.0 l 0.00E+00( 0/ 36) l 0.00E+00( 0/ 12) l 0.00E+00( 0/ 12) l 0 l l l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l l l l l 1 l l2N65 48l 0.0 l 0.00E+00( 0/ 36) l 0.00E+00( 0/ 12) l 0.00E+00( 0/ 12) l 0 l l l 0.00E+00~ 0.00E+00 l 0.00E+00 ~ 0.00E+00 l 0.00E+00 " 0.00E+00 l 1 I I I I I lNS95 48l 0.0 l 0.00E+00( 0/ 36) l 0.00E+00( 0/ 12) l 0.00E+00( 0/ 12) l 0 l l l 0.00E+00~ 0.00E+00 l 0.00E+00--0.00E+00[ 0.00E+00 ~ 0.00E+00 l l 1 1 I I l l2R95 48 l 0.0 l 0.00E+00( 0/ 36) l 0.00E+00( 0/ 12) l 0.00E+00( 0/ 12) l 0 l l l 0.00E+00" 0.00E+00 l 0.00E+00" 0.00E+00 l 0.00E+00 ~ 0.00E+00 l l 1 I I I I lI-131 48 l 60. l 0.00E+00( 0/ 36) l 0.00E+00( 0/ 12) l 0.00E+00( 0/ 12) l 0 l l l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l. 0.00E+00 ~ 0.00E+00 l l l 1 I I i lCS134 48 l 60. l 0.00E+00( 0/ 36) l 0.00E+00( 0/ 12) l 0.00E+00( 0/ 12) l 0 l l l 0.00E+00 ~ 0.00E+00 l 0.00E+00 ~ 0.00E+00 l 0.00E+00 ~ 0.00E+00 l l l l l120(0.4MiNNE) l l lCS-137 48 l 80. l 16. ( 1/ 36) l 16. ( 1/ 12) l 0.00E+00( 0/ 12) l 0 l l l 16. "
- 16. l 16. --
- 16. l 0.00E+00 ~ 0.00E+00 l l l 1 I I I lBALA-140 48l 0.0 l 0.00E+00( 0/ 36) l 0.00E+00( 0/ 12) l 0.00E+00( 0/ 12) l 0 l l l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l 0.00E+00 " 0.00E+00 l a 6nd rsnge based upon detectable measurements only stfon of detectable measurements at specified locations u is indicated in parenthes 4, (Fraction) 3 ranga indicates no detectable activity measurements lLD is equal to 0, then LLD is not required by Technical Specifications btion 120 = Site Boundary (0.4 Mi NNE)
Jtion 125 = Site Boundary (0.4 Mi SW)
Jtion 134 = East Lincoln Junior High School (8.7 Mi WNW)
Dtion 158 = 4 5 Mile Radius (5.0 Mi NNE) )
89 j
1
-l B.7 SHC2ELINE SEDIMENT En irorinental Radio agical Monitoring Program Swmary Name of Fac lity : McGuire huclear Station Occket Nwber 50 369,370 Location of Facility : Mecklenburg County, N.C. Reporting Period : 1*JAN-1993 through 31 DEC 1993 Time R gort Generated : 26-JAN 1996 09:40:25 Database Name + S0lSK1:(USER.ASC)McGuire Nuclear Station 93.SAF;1 j l l l Location with Highest Mean l lNo.of Medius or l Type & Total l Lower l All Indicator l-----......--..-.........-..l l Non-Pathway l Ntrber of l Limitafl Locations l Name,DistanceandDirectionl Control Locations l Routine Sanpl>ed l Analyses l Detection l Mean (Fraction) lLocatien Mean (Fraction) l Mean (Fraction) l Report (Units) l Pe' formed l (LLO) l Range l Coc<e Range l Range l Meas.
IMENT l l l l l l I/ORY/KG) l l l l l137(12.0 min) l 1 I I l 1 I ocStions l NN 54 6l 0.3 l 0.00E+00( 0/ 4) l 0.00E+00( 0/ 2) l 0.00E+00( 0/ 2) l 0 l l l 0.00E+00-- 0.00E+00 l 0.00E+00.0.00E+00l 0.00E+00--0.00E+00l l l l l129(0.6MiENE) l l l0058 6l 0.0 l 22. ( 1/ 4) l 22. ( 1/ 2) l 0.00E+00( 0/ 2) l 0 l l l 22. -- 22. l 22. --
- 22. j 0.00E+00--0.00E+00l l l l l l l lFE59 6l 0.0 l 0.00E+00( 0/ 4) l 0.00E+00( 0/ 2) l 0 00E+00( 0/ 2) l 0
[2 l l l 0.00E+00--0.00E+00l 0,00E+00--0.0C4+00l 0.00E+00" 0.00E+00 l 1 l l l l130(0.6MiSV) l l 6[ 0.0 2/ 4) l 0/ 2) l lCo-60 l 63. ( 86. ( 1/ 2) l 0.00E+00( 0 l l l 40. -
- 86. l 86. - 86. l 0.00E+00--0.00E+00l 1 1 I I I I l2N65 6l 0.0 l 0.00E+00( 0/ 4) l 0.00E+00( 0/ 2) l 0.00E+00( 0/ 2) l 0 j l l 0.00E400- 0.00E+00l 0.00E+00--0.00E+00l 0.00E+00-.0.00E+00[
I I I I I I lNS95 6l 0.0 l 0.00E+00( 0/ 4) l 0.00E+00( 0/ 2) l 0.00E+00( 0/ 2) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00 " 0.00E+00 l l l l l 1 l lZR95 6l 0.0 l 0.00E+00( 0/ 4) l 0.00E+00( 0/ 2) l 0.00E+00( 0/ 2) l 0 l l l 0.00E+00 0.00E+00 l 0.00E+00' 0.00E+00 l 0.00E+00 " 0.00E+00 l l 1 I I I I ll-131 6l 0.0 l 0.00E+00( 0/ 4) l 0.00E+00( 0/ 2) l 0.00E+00( 0/' 2) l 0 l
l l l 0.00t.+00.0.00E+00l 0.00E+00 " 0.00E+00 l 0.00E+00" 0.00E+00 l l l l l 1 I I 0/ 4) l 0/ 2) l lCS134 6l 1.50E+02l 0.00E+0C 0.00E+00( 0/ 2) l 0.00E+00( 0 l l l 0.00E+00" 0.00E+00 l 0.00E+00 " 0.00E+00 l 0.00E+00 " 0.00E+00 l l l l l 130 l l lCS-137 6l 1.f,0E+02l 93. ( 2/ 4) l 93. ( 2/ 2) l 0.00E+00( 0/ 2) l 0 l l l 89. " 97. l 89. ~ 97. l 0.00*+00 " 0.00E+00 l i l I I I I l I
lBALA.140 6l 0.0 l 0.00E+00( 0/ 4) l 0.00E+00( 0/ '$
' O.00E+00( 0/ 2) l 0 l l l 0.00E+00 0.00E+00l 0.00E+00 0.i 0.00E+00 " 0.00E+00 l l
(..................................................."..............................."..... ..................................
pandrcngebasedupondetectobtemeasurementseily
$tionofdetectablemeasurementeatspecified(bcationsisindicatedinparentheses,(Fraction) brsngsindicatesnodetectableactivitymeasurements hl0isequalto0,thenLLOisnotrequiredbyTechnicalSpecifications ption129eDischargeCanalEntrancetoLakeNormon(0.6MiENE) tion 130 m Highway 73 Bridge Downstream (0.6 Hi W)
Dtion 137 s Pinnacle Access Area (12.0 Ml N)
B-10
'B.8 FitH Envirorrnental Radiological Monitoring Program SLmnary Name of Facility : McGuire Nuclear Station Docket Nurrber : 50 369,370 Locstion of Facility : Mecklenburg County, N.C. Reporting Period : 1-JAN 1993 thruugh 31 0EC-1993 Time Rtport Generated : 26-JAN-1994 09:40:25 Database Name $0!$K1 (USER.ASC]McGuire Nuclear Station 93.$AF;1 l l l l Location with Highest Mean l lNo.of Medium or l Type & Total l Lower l All Indicator l----------------- ------ --
-l l Non-Psthw:y l Nteter of l Limitofl Lccations l Name,DistanceandDirectionl Control Locations l Routine Earpled l Analyses ! Detection l Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) l Report (Units) l Performed l (LLD) l Range l Code Range l Range l Meas.
H l l l l l l I/ WET /KO) l l l l l137(12.0 min) l l l 1 I I I kocations l MN 54 12 l 1.30E+02l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0 l l l 0.00E+00. 0.00E+00 l 0.00E+00-. 0.00E+00 1 0.00E+00. 0.00E+00 l l l l l 129 (0.9 MI ENE) l l lCo58 12 l 1.30E+02l 82. ( 2/ 6) l 82. ( 2/ 6) l 0.00E+00( 0/ 6) l 0 l l l 75. -- 90. l 75. -- 90. l 0.00E+00--0.00E+00l l l l l l l lFr59 12l ?.60E+02?l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0 l l l 0.00E+00-0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l l l l129 l l lCo-60 12l 1.30E+02l 13. ( 1/ 6) l 13. ( 1/ 6) l 0.00E+00( 0/ 6) l 0 l l l 13. --
- 13. l 13. -- 13. l 0.00E+00-0.00E+00l l 1 I I I I lZN-65 12l 2.60E+02l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0 l l l 0.00E+00--0.00E+00l 0.00e+00. 0.00E+00 1 0.00E+00.- 0.00E+00 l l l l l l l lNS95 12l 0.0 l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0 l l l 0.00E+00-0.00E+00l 0.00E+00- 0.00E+00 l 0.00E+00--0.00E+00l l l l l l l lZR95 12l 0.0 l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0 l l l 0.00E+00- 0.00E+00 l 0.00E+00-- 0.00E+00 l 0.00E+00-0.00E+00l l l 1 1 I I lI131 12l 0.0 l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00 0.00E+00 l 0.00E+00- 0.00E+00 l I I I I I I lC$134 12 l 1.30E+02j 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0 l l l 0.00E+00- 0.00E+00 l 0,00E+00--0.00E+00l 0.00E+00- 0.00E+00 l l l l l129 l l lC$137 12l 1.50E+02l 16. ( 2/ 6) l 16. ( 2/ 6) l 19. ( 1/ 6) l 0 l l l 11. -- 21. l 11. -- 21. l 19. --
- 19. l I I I I I I lBALA-140 12 l 0.0 l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0.00E+00( 0/ 6) l 0 l l l 0.00E+00- 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00- 0.00E+00 l and rcngs based upori detectable measurements only tion of detectable measurements at specified locations is indicated in parentheses, (Fraction) e ranga indicates no detectable activity measurements LLD is equal to 0, then LLD is not required by Technical Specifications ation 129 = Discharge Canal Entrance to Lake Norman (0.6 Mi ENE) tion 137 s Pinnacle Access Area (12.0 Mi N) '
l B 11
8.9 DIRECT GAMMA RADIATION Environmental Radiological Monitoring Program Sunnary
- Stame of Facility
- McGuire Nuclear Station Docket Nunber : 50-369,370
- Location of Facility : Mecklenburg County, N.C. Reporting Period : 1 JAN 1993 through 31 DEC 1993 I
Time Report Generated : 25 JAN 1994 14:43:36 Database Name : $0lSX1:(USER.ASC)MNS93.SAF;1
.............................................................................. l l l l l Location with Nighest Mean l lNo.of l
' Medlun or l Type & Total l Lower l Att Indicator l-- ----------------- " --*- --l l Non. !
Pathway l Nunber of l Limitofl Locations l Name, Distance and Direction l Control Locations l Routine )
Sanpled Analyses Mean (Fraction) l l Detection l l Location Mean (Fraction) l Mean (Fraction) l Report (Units) l Performed l (UD) l Range l Code Range Range l Meas.
........................................................................................................................l........ 1 CT RAD TLD l l l l l l r/Qutrter) l l l l l175(12.7MiWNW) l l l l l180(11.5MiNNE) l l lMR/Qtr 180l 0.00E+00l 14
( 176/ 176) l 25. 4/ 4) l l 3.0 -- 27
( 18. ( 4/ 4) l 0 l l l 21. ~
- 27. l 15. -- 20.
l and range based upon detectable measurements only tion of detectable measurements at specified locations is indicated in parentheses, (Fraction) renge indicates no detectable activity measurements LD is equal to 0, then LLD is not required by Technical Specifications a SITE BOUNDARY (0.3 MI NW) 163 = 4 5 MILE RADIUS (5.0 MI SE)
= SITE BOUNDARY (0.4 MI NNE) 164 = 4 5 MILE RADIUS (4.5 Mt SSE) e SITE BOUNDARY (0.5 MI NE) 165 = 4-5 MILE RADIUS (5.0 Mt S)
.m SITE BOUNDARY (0.5 Mt ENE) 166 = 4 5 MILE RADIUS (5.2 MI SSW)
= SITE BCUNDARY (0.4 MI E) 167 = 4 5 MILE RADIUS (4.9 M1 SW)
= SITE BOUNDARY (0.5 MI ESE) 168 = 4-5 MILE RADIUS (4.7 MI WSW) m $1TE BOUNDARY (0.6 Mt SE) 169 = 4-5 MILE RADIUS (4.4 M! W)
= SITE BOUNDARY (0.5 MI SE) 170 = 4-5 MILE RA01US (4.5 MI WNW) a SITE BOUNDARY (0.4 Mt S) 171 = 4 5 MILE RADIUS (4.5 MI NW) s SITE BOUNDARY (0.5 Mt SSW) 172 = 4-5 MILE RADIUS (5.2 MI NNW)
= SliE BOUNDARY (0.5 MI SW) 173 = SPECIAL INTEREST (8.5 MI NNW)
'e $1TE BOUNDARY (0.5 MI W) 174 = SPECIAL INTEREST (8.7 Mt WNW) e SITE BOUNDARY (0.5 MI WNW) 175 = CONTROL (12.7 M! WNW) la $1TE BOUNDARY (0.5 MI WNW) 176 = SPECI AL INTEREST (11.0 Mt SW) to 4 5 MILE RADIUS (4.8 MI N) 177 s SPECIAL INTEREST (8.6 M! S) o 4 5 MIL.E RADIUS (4.4 HI NNE) 178 = SPECIAL INTEREST (9.2 Mt SE) o 4 5 MILE RADIUS (5.0 MI NE) 179 = SPECIAL INTEREST (10.4 MI ESE) a 4 5 MILE RADIUS (4.9 MI ENE) 180 = SPECIAL INTEREST (11.5 MI NNE) ja 4 5 MILE RADIUS (4.7 Mt E) 181 = SPECIAL INTEREST (6.7 M! NE) b 4 5 MILE RADIUS (4.6 MI ESE) 182 3 SPECIAL INTEREST (6.0 MI NE) 183 = SPECI AL INTEREST (5.5 MI S) 186 3 SPECIAL INTEREST (0.2 MI NNW) 187 = SPECIAL IW!EREST (0.3 MI N) 189 = SITE BOUNDARY (0.4 MI SSE) 190 = SITE BOUNDARY (0.5 MI WSW) 191 m SPECIAL INTEREST (2.8 MI NNE) l l
l i
8 12 w
I
' C.10 FOCD PRCDUCTS Environmental Radiological Monitoring Program Stmnary 1 Nam? of Facility . McGuire Nuclear Station Docket Ntrber : 50 369,370 Location of Facility . Mecklenburg County, N.C. Reporting Period : 1 AN 1993 through 31 0EC-1993 Tire Rtport Generated : 26 JAN-1994 09:40:25 Database Name S'ilSK1:(USER. ASClMcGuire Nuclear Station 93.SAF;1 l l l l Locatl9n with Highest Mean l lNo.of Medit.rn or l Type & Total l Lower l All Indicator l------ ------------ ------
---l l Non-Pathwsy l Nteter of l Limitofl Locations l Name,DistanceandOfrectionl Control Locations l Routine Sanpled l Analyses l Detection l Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) l Report (Units) l Performed l (LLD) l Range } Code Range l Range l Meas.
S- l l l l l l I/ WET /KG) l l l l lNoControlLocationsl l l l 1 1 I
,ocations lMM54 15l 0.0 l 0.00E+00( 0/ 15) l 0.00E+00( 0/ 12) l 0.00E+00( 0/ 0) l 0 l l l 0.00E+00-0.00E+00l 0.00E+00- 0.00E+00 l 0.00E*00--0.00E+00l l I I I I I lCO58 15l 0.0 l 0.00E+00( 0/ 15) l 0.00E+00( 0/ 12) l 0.00E+00( 0/ 0) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l l l 1 I l l lFE59 15l 0.0 l 0.00E+00( 0/ 15) l 0.00E+00( 0/ 12) l 0.00E+00( 0/ 0) l 0 l l l 0.00E+00-0.00E+00l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l I I I I I i lCO-60 15l 0.0 l 0.00E+00( 0/ 15) l 0.00E+00( 0/ 12) l 0.00E+00( 0/ 0) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l l l l 1 I lZN65 15l 0.0 l 0.00E+00( 0/ 15) l 0.00E+00( 0/ 12) l 0.00E+00( 0/ 0) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l 0.00E+00- 0.00E+00 l 1 I I I I I
! l NB 95 15l 0.0 [ 0.00E+00( 0/ 15) l 0.00E+00( 0/ 12) l 0.00E+00( 0/ 0) l 0' l l l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l 0.00E+00 0.00E+00 l 1 I I I I 1 lZR-95 15l 0.0 l 0.00E+00( 0/ 15) l 0.00E+00( 0/ 12) l 0.00E+00(' 0/ 0) l 0 l l l 0.00E+00--0.00E+00l 0.00E+00 0.00E+00 l 0.00E+00-0.00E+00l l l 1 1 I I ll131 15l 60. l 0.00E+00( 0/ 15) l 0.00E+00( 0/ 12) l 0.00E+00( 0/ 0) l 0, l l l 0.00E+00 0.00E+00 l 0.00E+00 0.00E+00 l 0.00E+00- 0.00E+00 l 1 I I I I I lCS-134 15l 60. l 0.00E+00( 0/ 15) l 0.00E+00( 0/ 12) l 0.00E+00( 0/ 0) l 0 l l l 0.00E+00- 0.00E+00 l 0.00E+00-0.00E+00l 0.00E+00 0.00E+00 l l 1 1 I I I l CS 137 15l 80. l 0.00E+00( 0/ 15) l 0.00E+00( 0/ 12) l 0.00E+00( 0/ 0) l 0 l l l 0.00E+00 0.00E+00 l 0.00E+00-0.00E+00l 0.00E+00--0.00E+00l l l 1 I i l lBALA140 15l 0.0 l 0.00E+00( 0/ 15) l 0.00E400( 0/ 12) l 0.00E+00( 0/ 0) l 0 l l l 0.00E+00- 0.00E+00l 0.00E+00 0.00E+00 l 0.00E+00-0.00E+00l l....................... ................... .....................................................................................
handrengsbasedupondetectablemeasurementsonly
$tionofdetectablemeasurementsatspecifiedlocationsisindicatedinparentheses,(Fraction) hrangsindicatesnodetectableactivitymeasurements
%LO is equal to 0, then LLO la not required by Technical Specifications btion164=5MileRadius(2.5MiENE)-Gardens (Davenport'sResidence) l otion 188 = 5 Mlle Radius (2.8 Mi N) Gardens (Austin's Residence)
B 13 I'
y q I. I l !
)
APPENDIX C L
^
SAMPLING DEVIATIONS AND UNAVAlLABLE I
l ANALYSES 1-l l
l C-1
APPENDIX C MCGUIRE NUCLEAR STATION SAMPLING DEVIATIONS AND UNAVAILABLE ANALYSES
- 1. SAMPLING DEVIATIONS The following deviations from sampling requuements occurred dunng 1993.
- e e u., _
Sampic : Yneation ! LNded [ ._ Actual Collectics Deviation Acten S
? Reason ~
g.p,;
%;% w. - c pote, y Air Paniculates 121 2/2-2/9/93 2/2-2/6/93 Sampler did not nm for full 7 day Blown Fuse Replaced sampler with #2199 due to and period broken rotometer.
125 9/21-9/28/93 9/21-9/23/93 Sampler did not run for full 7 day Blown Fuse Changed fuse on sampler #16.
penod. Sampler would not start due to broken fuse holder. Replaced with sampler #14.
12/21-12/28/93 12/21-12/27/93 Sampler did not nm for full 7 day Blown Fuse Replaced fuse.
O penod. Re-taned air sampler.
to Air Radiciodmes 133 6/l-6/8/93 6/I-6/4/93 Sampler did not nm for full 7 day Blown Fuse Replaced fuse.
period. Restaned air sampler.
12/21-12/28/93 12/21-12/22/93 Sampler did not nm for full 7 day Blown Fuse Replaced fuse.
period. Restaned air sampler.
I34 3/2-3/9/93 3/2-3/4/93 Sampler did not nm for full 7 day Blown Fuse Replaced fuse.
period R.estarted sampler #2518 5/4-5/11/93 5/4-5/6/93 Sampler did not nm for full 7 day Blown Fuse Replaced fuse.
period Restaned sampler #2547.
Surface Water 128 3/2-3/16/93 3/2-3/14/93 Sampler did not collect for full 14 Cold weather caused intake to freeze Notified mamtenance.
day period. Here un no flow to solenoid valve. Collected abbrev. sample.
3/16-3/30/93 3/17-3/30/93 Sampler did not collect for full 14 Cold weather afrected sampler - Lines thawed and samplir4 resumed day period. lines froze. Collected abbrev. sample.
_ _ _ _ __- _____ ____ _ ___ _ _ _ _ _ _ _ __ _ - _ . .~ _ _ _ - -
1 Sample Le n on Scheduled Actual Collecten Deviation Reason Action Tme Collection Dates Dates ;
Surface Water - 128 4/27-5/11/93 5/11/93 Sampler did not collect for full 14 Pump failure Notified maintenance.
day period. Collected grab sample.
5/11-5/25/93 5/17-5/25/93 Sampler did not collect for full 14 Wire shorted on switch from motor Repaired wiring i day periaal to pump. Collected abbrev. sample.
5/25-6/8/93 6/4-6/8/93 Sampler did not collect for full 14 Sampler out of service to repair Collected abbrev sample.
day penod. plumbing.
131 3/2-3/16/93 3/16/93 Sampler did not collect for full 14 Assume intake Ime is clogged from Contacted maintenance and collected day penod. the jordan valve to the solenoid grab sample.
valve. ,
10/26-1I/9/93 11/9/93 No composite available at time of Pump out of senice. Pump repair will be initiated ,
collection. Collected etab.
I1/9-11/23/93 11/23/93 No composite available at time of Pump out of service. Pump repair has been scheduled collection. Collected grab.
O No composite available at time of Pump out of senice. Pump was placed back in service on i l1/23-12n/93 12D/93
" collection. 12n/93 Collected grab.
135 3/30 4/13/93 4/13/93 Sampler did not collect for full 14 Lmes are clogged or pump failed Secured power to solenoid and
- day period. pump. Collected grab sample. ;
4/13-1/27/93 4/22-4/27/93 Sampler did not collect for full 14 Bypass salve, solenoid valve, and Pipmg and valve were removed '
day period. associated piping clogged with sitt. New overtlow and piping were added. Collected abbrev. sample l
6/18-6/22/93 6/22/93 Sampler did not collect for full 14 Probably clogged imes. Notified commodities and facilities day period. personnel Collected grab.
t 6/22-7/6/93 7/6/93 Sampler did not collect for full 14 Out of service due to repairs on Collected grab Placed sampler back dav period. pump. in senice Collected erab.
10/12-10/26/93 10/26/93 No composite available at time of The overload on the pump kicked Maintenance retified on 10/27/93 collection. the breaker out due to electrical for repairs. Collected grab.
problem.
10/26-11/9/93 11/9/93 No composite available at time of Pump out of senice. Maintenance notified on 10/27/93 collection. for repairs. Collected grub.
! 11/9-11/23/93 11/23/93 No composite available at time of Pump out of service. Maintenance notified on 10/27/93 collection. for repairs. Collected grab. ,
! 11/23-12n/93 12n/93 No composite availsble at time of Pump out of service. Maintenance nortfied on 10/27/93 -
collection. for repair 2. Collected grab. ,
i
~
Sample . Locatim ~ Scheduled Actual Collectica Deviation :Rdasen Actice
' Tvpe
~
Collecuan Dates - Dates Dnnking Water 132 .
2/16-3/2/93 2/16-3/2/93 Sampler dd not collect for full 14 Power interrupted to sampler while Pow restored after piping installed.
day period. installing hard piping. " Abbrev.* sample collected.
10/12-10/26/93 10/12-10/26/93 Composite tank overflowei Timer was adjusted too far open Timer was adjusted down to pwide causing tank to overflow. less sample.
!~ l36 10/12-10/26/93 10/12-10/26/93 Composite tank overflowed. Solenoid timer malfunctioned Timer was adjusted.
causing valve to open every 20 Replaced on 10/29/93 '
. seconds.
TLD 161 3/29-6/29/93 3/29-5/15/93 TLD not in lield for full monitonng Found on ground 3 miles from Recovered and placed back in field ,
< 5/27-6/29/93 period. momtonng location. on 5/27/93.
'O
.1 t
t t
i s
e s
MCGUIRE NUCLEAR STATION II. UNAVARABLE ANALYSES The following unavailable analyses occurred during 1993:
- .r.n ' w . - -.
Sample' Loccuon i *bdni d Deviatum f
_ Reasoa: ~ ' Actimt gy ' CaterGa Dates TLD 157 6/29-9/27/93 Not available for analvsis. Missing Placed 4th Qtr. TLD in field 159 6/29-9/27/93 Not available for analysis. Missing due to utility pole removed Placed 4th Qtr. TI.D on a new pole bv Marina Construction. near original location.
166 3/294/29/93 Not available for analysis. Missing Placed 3rd Qti TLD in field.
O Si
d APPENDIX D ANALYTICAL DEVIAT/ONS LOWER LIMITS OF
, DETECTION l
l-i l
No analytical deviations were Incurred for the 1993 environmental sampling program.
I 1
s l
1 i
l l l
!' D-1 l
APPENDIX E
- l l RADIOLOGICAL ENVIRONMENTAL MON /TORING PROGRAM RESULTS This appendix Includes all of the sample analysis reports generated from each sample medium for '1993.
i Appendix E is located separately from this report and is permanently archived at Duke Power Company's Environmental Center radiological environmental data master file, located at Huntersville, NC at the AfcGuire Nuclear Station Site.
l E-1
F;; ,
\
k
( ; DUKEPOWER d
f, i
i d
1
-1 li
__ j
- ~ ~ - =
- e av.+-- % .._,y . , ,- ,#,#, ,,, ,