ML20107L904
| ML20107L904 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 12/31/1995 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20107L888 | List: |
| References | |
| NUDOCS 9604300075 | |
| Download: ML20107L904 (110) | |
Text
_ - -
I DUKE POWER Catawba Nuclear Station Units 1 and 2 1
i l-n j
r 4
1
+
a
- w..,
x
. Ik)Q[.:?[htM5Nik ',,'TJ:
N -;.-
k
..... ly. ;
c
+Y. +s 1
b
~
- -,-[/.'3 2;.gyv.,wo g m w y 4,.',,....-~
i
- yrf,.
j' l'h 4 ' f
,h/ : Ih ( j6I.f j 7
1
. m a..
s.
c,
,., 1-
. - Q, q-N.p.:.ags ~g g;gmdg, jyn.
.;...a.
4
- gjqr
~
,,e g
m s:w s,,
g, vc *, s r..
' q,,,-;
...+ :.
4
'm s
[
A f f:,3.. /J r?.,&p[e.ln
?
~,~
- ' w' l.
g,:, : ?J $& ;
i s
{g
- M,
4 y
4
- . ; u,,f ' A;.2g.:$, L'. W_~jWy b;.#? * ' '
s, y y #.
kh?'.
e a
, J_
..e..
Jn
. s_
..__ m s.
., g.'(Mtmq:;~,:~y~ dl 2l;;-;p:;: m 'E_ j' _._$h j
9 m_,
uR T
L
,., c...g..g. g.m..... :
s y.
4 7
i
-~
l
-.y g i
i 1
4 1
i
]
i
)
4 i
Annual l
Radiological Environsnental
)
Operating Report 4
l 1995 c..
9604300075 960422 PDR ADOCK 05000413
}
PDR f
j R
1 l
l DUKE POWER l
Catawba Nuclear Station l
Units 1 and 2 i
3, e
e
=
ggw:$en$39' i j
.!Ui. i;. _
f l'$sh$ [Oglk
.,.x en,e
?"? % $ t. 7 M
F i
9 w
- w n;v wun a
, m; wfp ~w :m# ?a: W~E J n~w
~
.c if i
3 Q
p a m. A
\\a g m.w>ge,P, w,
= rn)m..m=w.:.+_+, r_.-
- b. ei a
a
- .;A..
mp
.. iC.....,; 3., -
4, s
. m_,
r..a-.
4
- f. =;.g y p ;--sp h.di'" _
g i
~Q-.
1;. w.,.-%< '
c!gfyrta::
wgt -c.
q t. :..%
,er.
,s 9
,;3,,,,,,.
y%
. 4
.,g.~ 51
.?
~~
- ,-n
,p,pg_
j pgg_,,
amo e
Annual RadiologDcal Environmental Operating Report 1995 9604300075 960422 PDR ADOCK 05000413 PDR R
r
i i
i i
i i'
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT for DUKE POWER COMPANY CATAWBA NUCLEAR STATION Units 1 and 2 January 1 - December 31 1995
l TABLE OF CONTENTS l
TITLE PAGE List ofFigures iv List of Tables y
List of Acronyms.
vii 1.
Executive Summary 1-1 2.
Introduction 2-1 2.1 Site Description and Sample Locations 2-1 2.2 Scope and Requirements ofEnvironmental Monitoring Program 2-1 j
2.3 Statistical and Calculational Methodology 2-2 2.3.1 Estimation of the Mean Value 2-2 2.3.2 Lower Level of Detection, Minimum Detectable Activity, and Critical Level 2-3 2.3.3 Trend Identification 2-4 2.3.4 Test Statistic.
2-4 3.
Radiological Environmental Monitoring Program - Discussion, Interpretation, and Trending of Results 3-1 3.1 Airborne Radiciodines and Particulates.
3-3 3.1.1 Radiciodines.
3-3 3.1.2 Particulates 3-3 3.2 Ground Water 3-3 3.3 Drinking Water 3-3 l
3.4 Surface Water 3-4 3.5 Milk 3-6
3.6 BroadleafVegetation 3-6 3.7 Shoreline Sediment 3-7 3.8 Fish 3-10 3.9 Direct Gamma Radiation (TLD) 3-13 3.10 Food Products.
3-16 3.11 Bottom Sediment 3-16 3.12 Land Use Census 3-20 4.
Evaluation of Dose from Environmental Measurements Verses Estimated Dose from Releases 4-1 4.1 Dose from Environmental Measurements 4-1 4.2 Estimated Doses from Releases 4-2 4.3 Comparison ofDoses 4-3 5.
Quality Assurance 5-1 5.1 Duke Power Company Environmental Laboratories 5-1 5.2 Contractor Laboratories 5-4 6.
References 6-1 Appendix A: Environmental Sample and Analysis Procedures - Summary A-1 I.
Change of Sampling Procedures A-1 II. Description of Analysis Procedures A-1 III. Change of Analysis Procedures.
A-2 IV. Sampling and Analysis Procedures A-2 A.1 Airborne Particulate and Radiciodine A-2 A.2 Drinking Water A-2 A.3 Surface Water A-2 A.4 Milk A-3 A.5 BroadleafVegetation A-3 o
i A.6 Shoreline Sediment A-3 A.7 Fish A-3 A.8 Direct Gamma Radiation (TLD)
A-4 A.9 Food Products A-4 A.10 Ground Water A-4 A.11 Annual Land Use Census A-5 V. ProgramImprovements A-5 Appendix B: Radiological Environmental Monitoring Program - Results Summary Air Particulate B-1 Air Radiciodine B-2 BroadLeafVegetation B-3 Food Products B-4 j
Drinking Water B-5 Fish B-7 Ground Water B-8 l
Milk B-9 l
l Shoreline Sediment B-10 Surface Water B-11 Direct Gamma Radiation (TLD)
B-12 Shoreline Sediment (Sites 208-1S,208-2S,208-3S)
B-13 Fish (Site 208 - Predator, Forager, and Bottom Feeder)
B-14 Appendix C: Sampling Deviations and Unavailable Analyses C.1 Sampling Deviations C-1 C.2 Unavailable Analyses C-3 C.3 Sample Deviation and Unavailable Reduction Plan C-3 Appendix D: Analytical Deviations - Lower Limits of Detection D-1 Appendix E: Radiological Environmental Monitoring Program Results E-1 1
4 1
l
LIST OF FIGURES FIGURE TITLE PAGE l
2.1-1 Sampling Locations Map (TLDs) 2-9
)
2.1-2 Sampling Locations Map (ten mile radius) 2-10 2.1-3 Sampling Locations Map (Discharge Canal) 2-11 3.12 Catawba Nuclear Station 1995 Land Use Census Map.
3-22 l
\\
l l
iv
LIST OF TABLES TABLE TITLE PAGE 2.1-A Radiological Monitoring Program Sampling Locations (TLD) 2-7 2.1-B Radiological Monitoring Program Sampling Locations.
2-8 2.2-A Reporting Levels for Radioactivity Concentrations in Environmental Samples 2-12 2.2-B REMP Analysis Frequency 2-13 2.2-C Lower Limit of Detection Capabilities for Environmental Sample Analysis 2-14 3.4-A Surface Water Sample Tritium Results - Location 208.
3-5 3.7-A Shoreline Sediment Sample Results - Location 208-1S, j
208-2S, and 208-3S 3-8 j
3.8-A Fish Sample Results - Location 208.
3-11 3.9-A Direct Gamma Radiation (TLD) Results.
3-14 3.9-B Comparison ofInner Ring / Outer Ring TLD Results 3-15 3.11-A Bottom Sediment Smnple Results - Location 208-lM, 208-2M, and 208-3M 3-18 3.12-A Annual Land Use Census Results 3-21 4.1-A 1995 Environmental and Effluent Dose Comparison for Liquid and Gaseous Waste Release Pathways 4-5 4.1-B Maximum Individual Dose Summary for 1995 4-7 5.0-A.
Duke Power Company Interlaboratory Comparison Program 5-5 5.0-B U.S. Environmental Protection Agency Interlaboratory Comparison Program 5-7 5.0-C State of North Carolina DEHNR 1995 Environmental
' Dosimeter Cross-Check Results 5-9 C.3-A Deviation Reduction Plan Overview.
C-4 C.3-B Deviation Reduction Plan Equipment Purchases C-5 Y
C.3-C Deviation Reduction Plan Air Site Upgrade Equipment Purchases C-6
LIST OF ACRONYMS Acronyms and their interpretations used in this report (displayed alphabetically)
ACRONYM DEFINITION BW Biweekly C
Control CL Critical Level CNS Catawba Nuclear Station DEHNR Department of Emironmental Health and Natural Resources DHEC Department of Health and Emironmental Control EPA EmironmentalProtection Agency FSAR Final Safety Analysis Report LLD Lower Limit of Detection M
Monthly MDA Minimum Detectable Actisity mrem millirem NIST National Institute of Standards and Technology NRC Nuclear Regulatory Commission ODCM Offsite Dose Calculation Manual pCi/kg picocurie per kilogram pCi/l picoeurie per liter pCi/m3 picocurie per cubic meter Q
Quarterly REMP Radiological Emironmental Monitoring Program SA Semiannually SLCs Selected Licensee Commitments SM Semimonthly TECH SPECS Technical Specifications TLD Thermoluminescent Dosimeter uCi/mi microcurie per milliliter W
Weekly sii
E l
l 1.0 EXECUTIVE
SUMMARY
l This Annual Radiological Environmental Operating Report describes the Catawba Nuclear l
l Station Radiological Environmental Monitoring Program (REMP), and the program results for the calendar year 1995.
Included are the identification of sampling locations, descriptions of environmental I
sampling and analysis procedures, comparisons of present environmental radioactivity l
levels and pre-operational environmental data, comparisons of doses calculated from l
environmental measurements and effluent data, analysis of trends in environmental l
radiological data as potentially affected by station operations, and a summary of environmental radiological sampling results. Quality assurance practices, sampling deviations, unavailable samples, and program changes are also discussed.
Sampling activities were conducted as prescribed by Selected Licensee Commitments (SLC's). Required analyses were performed and detection capabilities were met for all samples as required by SLC's. Supplemental analyses were performed for some media for additionalinformation. Nine-hundred seven samples were analyzed comprising 6750 test l
results in order to compile data for the 1995 report. Based on the annualland use census, the current number of sampling sites for Catawba Nuclear Station is sufficient.
Concentrations observed in the environment in 1995 for station related radionuclides were generally within the ranges of concentrations observed in the past. Inspection of data showed that radioactivity concentrations in surface water, drinking water, shoreline sediment, and fish are higher than the activities reported for samples collected prior to the operation of the station. Measured concentrations were not higher than expected, and all positively identified measurements were within limits as specified in SLC's. Additionally, environmental radiological monitoring data is consistent with effluents introduced into the l
l environment by plant operations. The total body dose estimated to the maximum exposed member of the public as calculated by environmental sampling data, excluding TLD results, was 4.19E-01 mrem for 1995. It is therefore concluded that station operations has had no significant radiological impact on the health and safety of the public or the environment.
l l
l Section 1 - Page 1 I
4
2.0 INTRODUCTION
2.1 SITE DESCRIPTION AND SAMPLE LOCATIONS Duke Power Company's Catawba Nuclear Station is a two-unit facility located on the shore of Lake Wylie in York County, South Carolina. Each of the two essentially identical units employs a pressurized water reactor nuclear steam supply system furnished by Westinghouse Electric Corporation. Each generating unit is designed to produce a net electrical output of approximately 1145 MWe. Units 1 and 2 achieved initial criticality on January 7,1985, and May 8,1986, respectively.
l Condenser cooling is accomplished utilizing a closed system incorporating cooling towers, instead of using lake water directly. Liquid effluents are released into Lake Wylie via the station discharge canal and are not accompanied by the large additional dilution water flow associated with "once-through" condenser cooling. This design results in greater radionuclide concentrations in the discharge canal given comparable liquid effluent source terms.
The CNS Radiological Environmental Monitoring Program (REMP) sampling locations are summarized in Tables 2.1-A and 2.1-B. Table 2.1-A lists the environmental Thermoluminescent Dosimeter (TLD) locations. Table 2.1-B lists all other sampling locations. The REMP sampling and analysis procedures are summarized in Appendix A.
A map depicting the site and area within one mile of CNS can be found in Figure 2.1-1. An area map encompassing a ten mile radius from the station can be found in Figure 2.1-2.
Figures 2.1-1,2.1-2, and 2.1-3 are maps depicting the specific positions of all REMP sampling locations. The !ccation numbers shown on these maps correspond to those listed in Tables 2.1-A and 2.1-B. Figure 2.1-1 comprises all sample locations within one mile of CNS.
Figure 2-D comprises all remaining locations. Figure 2.1-3 identifies location 208 (discharge canal) shoreline sediment (IS,2S, and 3S) and bottom sediment (IM,2M, and 3M) sampling points. Of these six sediment samples, only shoreline sediment at location 208-lS is required by CNS Final Safety Analysis Report (FSAR); the remaining five are supplemental samples first collected during 1986.
2.2 SCOPE AND REOUIREMENTS OF ENVIRONMENTAL MONITORING PROGRAM An environmental monitoring program has been in effect at Catawba Nuclear Station since 1981, four years prior to operation of Unit 1 in 1985. The preoperational program provides data on the existing environmental radioactivity levels for the site and vicinity which may be used to determine whether increases in environmental levels are attributable to the station.
section 2 Page I
1 The operational program provides surveillance and backup support of detailed effluent monitoring which is necessary to evaluate the significance, if any, of the contributions to the existing environmental radioactivity levels that result from station operation.
This monitoring program is based on NRC guidance as reflected in Selected Licensee Commitments Manual, with regard to sample media, sampling locations, sampling frequency and analytical sensitivity requirements. Indicator and control locations were established for comparison purposes to distinguish radioactivity of station origin from natural or other " man-made" environmental radioactivity. The environmental monitoring program also verifies projected and anticipated radionuclide concentrations in the environment and related exposures from releases of radionuclides from Catawba Nuclear Station. This program satisfies the requirements of Section IV.B.2 of Appendix I to 10CFR50 and provides surveillance of all appropriate critical exposure pathways to man and protects vital interests of the company, public and state and federal agencies concerned with the environment.
Reporting levels for activity found in environmental samples are listed in Table 2.2-A.
Table 2.2-B lists the REMP analysis and frequency schedule.
The Annual Land Use Census, required by Selected Licensee Commitments, is performed to ensure that changes in the use of areas at or beyond the site boundary are identified and that modifications to the Radiological Environmental Monitoring Program are made if required by changes in land use. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10CFR50. Results are shown in Table 3.12-A.
Participation in an approved Interlaboratory Comparison Program as required by Selected Licensee Commitments provides for independent checks on the precision and accuracy of measureraents of radioactive material in REMP sample matrices. Such checks are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10CFR50. A summary of the results obtained as part of this comparison program are in Section 5 of this annual report.
2.3 STATISTICAL AND CALCULATIONAL METHODOLOGY 2.3.1 ESTIMATION OF THE MEAN VALUE There was one (1) basic statistical calculation performed on the raw data resulting from the environmental sample analysis program. The calculation involved the determination of the mean value for the indicator and the control samples for each sample medium. The mean is a widely used statistic. This value was used in the reduction of the data generated by the sampling and analysis of the various media in the Environmental Monitoring Program. The following equation was used to estimate the mean (reference 6.8):
Section 2 - Page 2
N EX x =
N Where:
x = estimate of the mean, i = individual sample, N = total number of samples with a net activity (or concentration) xi = net activity (or concentration) for sample i.
1 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, AND CRITICAL LEVEL The Lower Level of Detection (LLD), Minimum Detectable Activity (MDA), and Critical Level (CL) are used throughout the Environmental Monitoring Program.
LLD - The LLD, as defined in the Selected Licensee Commitments Manual is the smallest concentration of radioactive material in a sample that will yield a net count, above the system background, that will be detected with 95% probability with only 5%
probability of falsely concluding that a blank observation represents a "real" signal.
The LLD is an apriori lower limit of detection. The actual LLD is dependent upon the standard deviation of the background counting rate, the counting efficiency, the sample size (mass or volume), the radiochemical yield and the radioactive decay of the sample between sample collection and counting. The " required" LLD's for each sample medium and selected radionuclides are given in the Selected Licensee Commitments and are listed in Table 2.2-C.
MDA - The MDA may be thought of as an " actual" LLD for a particular sample measurement remembering that the MDA is calculated using a sample background instead of a system background.
CL - The CL is defined as the net count rate which must be exceeded before a sample is considered to contain any measurable activity above the background.
Section 2 + Page 3
2.3.3 TREND IDENTIFICATION One of the purposes of an environmental monitoring program is to determine if there is a buildup of radionuclides in the environment due to the operation of the nuclear station. This is traditionally done by looking at historical data (including preoperational data) and determining if a trend exists. Trends, if they exist, may be either positive or negative. Since nuclear reactor operations do not remove radioactivity from the surrounding environment, a negative trend in a particular radionuclide's concentration in an environmental medium does not indicate that reactor operations are removing radioactivity from the environment but that reactor operations are not adding that radionuclide to the environment in quantities exceeding the preoperational level and that the normal removal processes (radioactive decay, deposition, resuspension, etc.) are influencing the concentration.
j l
Identifying a trend 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.
Substantial increases or decreases in the amount of a particular radionuclide's release from the nuclear plant will greatly affect the resulting environmental levels; therefore, a 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 change in the method of calculating the mean (using only net positive results incorporated in 1987) will also affect the apparent trends.
Because of the above considerations, how trends are identified will include some judgment by plant personnel on the factors affecting environmental levels.
2.3.4 TEST STATISTIC In some cases, we would not expect to observe a buildup of radionuclides in the environment, but instead would expect to see a measurable increase in levels over a short duration. This is the case for direct radiation measurements, where the radiation level is measured over a finite period and may be dependent upon whether plant discharges were occurring at that time or not. In this case, the correlation coefficient is not a sufficient indicator of whether effluents are having an impact on the environment, since there is no bioaccumulation. Another test is needed to give us a meaningfulinterpretation of the data.
Section 2 Page 4
r i
The statistic that compares the means from two sets of measurements to determine if l-there is a statistically significant difference is called the test statistic, or t-statistic, and is calculated as follows (reference 6.7):
Xi - X2 S
1 1
+ -
n n
i 2
Where:
K the mean value of the first set of measurements
=
l K
the mean value of the second ' set ofmeasurements
=
l l
S, the common variance of the two sets of measurements
=
g s,
=
j Where:
1 l
(n, - 1)s,2 + (y, _ 3),,2 g'2
=
n, + n - 2 2
l ni the number of measurements in the first data set
=
n2 the number of measurements in the second data set
=
l si the sample variance of the first data set
=
l s2 the sample variance of the second data set
=
The calculated value of the test statistic is then compared to expected values of the i
test statistic tabulated based on the number of measurements taken and the degree of confidence required for the results. The calculated value of the test statistic will be compared to the expected value at the 95% confidence level. A positive value occurs (the two sets of data are significantly different) when the absolute value of the calculated test statistic exceeds the absolute value of the expected tabulated value, i.
Due to the existence of naturally occurring differences in background radiation levels over time (as a result of solar cycles and other meteorological phenomena) and l
systematic errors due to instrument variability, ratios of measurements can be used to j
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 i
Section 2 Page 5
measurements, the inner ring of TLD results is ratioed with the outer ring of TLD l
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 l
in part onjudgment of plant personnel familiar with the factors affecting environmental levels, as well as the statistical results.
i l
l l
i t
l Section 2 Page 6
TABLE 2.1-A CATAWBA RADIOLOGICAL' MONITORING PROGRAM SAMPLING LOCATIONS (TLD SITES)
Site location Distance Sector Site location Distance Sector 200 StrE BOUNDARY 0.6 mi NNE 233 4-5 NHLE RADIUS 3.9 mi ENE 201 STTE BOUNDARY 0.5 mi NE 234 4-5 MILE RADIUS 4.5 mi E
202' STTE BOUNDARY 0.6 mi E
235 4-5 MILE RADIUS 3.9 mi ESE 203 STTE BOUNDARY 0.4 mi ESE 236 4-5 h'JLE RADIUS 4.3 mi SE 204 SITE BOUNDARY 0.5 mi SSW 237 4-5 hELE RADIUS 4.8 mi SSE 205 STTE BOUNDARY 0.3 mi SW 238 4-5 MILE RADIUS 4.0 mi S
206 STTE BOUNDARY 0.7 mi WNW 239 4-5 hELE RADIUS 4.5 mi SSW 207 STTE BOUNDARY 0.9 mi NNW 240 4 5 MILE RADIUS 4.1 mi SW 212 SPECIAL INTEREST 3.3 mi E
241 4 5 hHl S RADIUS 4.6 mi WSW 217 CONTROL 10.3 mi SSE 242 4 5 MILE RADIUS 4.6 mi W
222 StrE BOUNDARY 0.7 mi N
243 4-5 MILE RADIUS 4.4 mi WNW 223 SITE BOUNDARY 0.6 mi E
244 4-5 MILE RADIUS 4.0 mi NW 224' SITE BOUNDARY 0.6 mi ESE 245 4-5 MILE RADIUS 4.1 mi NNW 225 StrE BOUNDARY 0.7 mi SE 246 SPECIAL INTEREST 7.8 mi ENE 226 SITE BOUNDARY 0.5 mi S
247 CONTROL 7.3 mi ESE 227 STTE BOUNDARY 0.5 mi WSW 248 SPECIAL INTEREST 6.6 mi S
228 StrE BOUNDARY 0.6 mi W
249 SPECIAL INIEREST 8.1 mi S
229 STIE BOUNDARY 0.8 mi NW 250 SPECIAL INTEREST 10.4 mi WSW 230 4-5 MILE RADIUS 4.4 mi N
251 CONTROL 9.7 mi
%WW 231 4 5 MILE RADIUS 4.2 mi NNE 255 "
SITE BOUNDARY 0.6 mi ENE 232 4-5 MILE RADIUS 4.1 mi NE 256 "
SFTE BOUNDARY 0.6 mi SSE
- Deleted 09/14/89
" Added 09/14/89 Section 2 - Page 7
TABLE 2.1-B CATAWBA RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS TABLE 2.1-B CODES W
Weekly SM Senumonddy BW Biweekly Q
Quarterly M
Monthly SA Semiannually C
Control Sit
- Locanon DeScriPnon "a
wr w.kr kne Produce Leaf Wakr Part Sed (a)
Veir (b) 200 Site Boundary (0.6 mi NHE)
W M
201 Site Boundary (0.5 mi NE)
W M
205 Site Ekundary (0.3 mi SW)
W 208 Dtscharge Canal (0.5 mi S)
BW SA
$A 209 Dairy (6.0 mi SSW)
SM 210 Ebenezer Acctss(2.3 mi SE)
SA 2II Wyhe Dam (4.0 mi ESE)
BW 212 Tega Cay (3.3 mi E)
W 214 Rock Hill Water Supply (7.3 nu SE)
BW 215 Rner Pointe - Hwy 49 (4.2 mi NNE) CONTROL BW SA 216 Hwy 49 Bridge (4.0 nu NNE) CONTROL SA 217 Rock Hill Substatwn (10.3 mi SSE) CONTROL W
218 Belmont Water Supply (13.4 mi NNE) CONTROL BW M
219 Dairv (5.7 mi SW)
SM 22i Dairy (l4.5 mi NW) CON'IROL SM 226 Site Boundary (0.5 mi S)
M 252 Residence (0.7 mi SW)
Q 253 Irngated Gardens (Downstream withm 5 mile radius)
M(a) 254 Residence (0 8 mi N)
Q (a) During HaneSt Sca$on (b)When Available Section 2 Page 8
i l
l i
l Figure 2.1-1 SAMPLING LOCATIONS MAP (ONE MILE RADIUS)
)
i
)
\\
l i
1 -
l ll
\\
.an c....,
u 5
.e 7
- e
. i u
.,s.,
.r 1
y
(
/
~.,..
,=
p,_c, 4.
- [
a*
s l
M' r~
.e.
\\
I
~-
'}'- -,
m f
0
%q 1
1y A. ".' *.
-~"
o
~~
) 'P E
(
~3 o
/
I i
4*
- s* *
'g.
9 s
.. m 6
390
. TLD LOCATIONS g
s ALL OTHER LOCATsONS ow so eeeaonensv e
I l
Section 2 - Page 9 l
l
~
mm
.3
- nm*
s" 1
A 218 (IN
%[Q '
i
/
'l Mj a
L r,, y w
-ell m
'"x*
"f. s o,
/_
- \\
- a
?,1_,%, I
^ 22 4
~.
'{
\\lA:}
<fa ' N
~
^
s
(
3 w
'. s, p{,,r' ) \\ 3 /g!
y'~
4 '
y
)
I Gf b
t a ~ s
')
C m
f f-(
M 7;"(77 i, y
\\,L y
u 3
~~.j j
I@
- j
..e i
r N
., \\g e
U 2
c
- j\\as9h>
aa 4
~
{
'v n
}
yr.
, Q s2- 0 s
., gf, y, '
~b y
),, M 7k N
243 N 6
\\
[
'(' 8,
?-
- I k. ~,%[
4 b
,g
e I f g 4 I ,g 209 l[, v 1 a {J / v4 'O ~f"l '?, ( (a a>> d /st ,a x . j 'g p i. / d (uly <N, J 'y ~ q 8 ~ Nw ,y e b/ ~~ Q .s ? ~% **"'s I ~. M Y. y t 1.EGEND
- p.,
w,,,,,.o,,. ===== o .w .w
=
.an. o a p.
.e am.c..o me.a ww
..r.,
4 Als e sv 4"g,u 2 on N
mum Apdur L w a..<a j
. 4). /,
e,
-,==
- m.
w
- m a-
&=_ m_o s m
,/ G,
=
j [
c/ ijyQ
.g a.',-
_w
- t.,
+
Q
',J J,.4,.ps _
j.
~ * ~
7;
" Q2% ',
_j.13
~'= ~~ ~
t Icg_;
, A, ~p
&g.. _-..
g I
s.,,
T '
,3'l,'./
~
b3
~
P-
'f5
'f
.o, s
's
,4 3
,g#q. p_yl
- ,mr.'
'.~. :::,,,.
j
.. ' =. -<
-., ' V, ; /q
,/p
~
r
- G2 ex,
- :::'= o
/
t --
.f t
u.o.,..=.'~.,.=4, g#t~-;
t oe.
s
/a
.~
.,y /.\\ _
e co.o
~'.
-P I
\\
~
--'*.J.
- -'h
- O
.'4
./)'
/
s
~F^
(
.]
o com o < - - -.. ~
s
',,4
+
7 1 ',f-. '
-y,h. t,7 ?
~<a
- a-*=
~'
"".*."+*.oo.
g
-A f
4
/
(
0 Z,,"",'"
4Q (f wg 4 m'
/J r'.~sr.a.'.~
Y r
\\
1" s.o I.>
~
- Q, l
W
/
soo g
C)'v
.oa
- o. usa t
A
"',- M,1 4 1
'K
.n.r T~
sw Q g,,", "
- '*"8 k
1.
v
- w==== o='a a
~,
g s -
oa.
( ~N
/ '
-4=4 c.
(
. = -. -. c..
"L f
= * = ~.se
'r_ ' -
=. * * = = x f
m
- :: -.aaan. **
,a
.a w
4'.
L_.
N-
\\
w' EN,.
c.unut.
, so A.fiQas I l
x
. co l.N g
~
o.
o
.o-
.wa.
s,
x
- j* ' g n.u
_j v.
g p/
x x
g =
.~
6 unooi
/,
\\ s g
. * ~~
o
- /.
a,
<.=.=e.=
in= <=.w s
,,o.
)
yv e TLD LOCATIONS
.ca m
)
P a.. o ca ===,.
l s
e"* 4 J
o
%.s p
I A ALL OTHER LOCATIONS e
sam p.=
c' s
4 i
II CATAWBA NUCLEAR STATION r
3
/
SCALE OF WILES I
w'E,L
,_ u.I,_
I FIGURE 2.12 w
SAMPLING IiX'ATIONS MAP 7
(TEN MILE RADIUS)
U Section 2 - Page 10 1
9604300075 7
l Figure 2.1-3 SAMPLING LOCATIONS MAP (DISCHARGE CANAL)
RL DISCHARGE g
1 l
~
t l
l l
l WC DISCHARGE l
208 (35) 2$8(IM) l l
6 l
208 (25) 208 (2M)
I FLOW I
208 (15)
-PIER 208 (3M)
ROAD 1132 BRIDGE t
CATAWBA NUCLEAR STATION DISCHARGE CANAL Section 2 - Page !I
l l
TABLE 2.2-A REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES l
l Air Food Analysis Water Particulates Fish Milk Products (pCi/ liter) or Gases (pCi/kg-wet)
(pCi/ liter)
(pCi/kg-wet)
(pCi/m')
H3 20,000(*)
Mn54 1,000 30,000 Fe59 400 10,000 l
CoS8 1,000 30,000 Co60 300 10,000 l
Zn65 300 20,000 l
Zr-Nb-95 400 l
1131 2
0.9 3
100 i
Cs134 30 10 1,000 60 1,000 l
Csl37 50 20 2,000 70 2,000 Ba-La-140 200 300 (a) NOTE: Ifno drinking waterpathway exists, a value of 30,000 pCi/ liter may be used l
l l
l
[
Section 2 - Page 12
TABLE 2.2-B REMP ANALYSIS FREQUENCY
' SAMPLE ANALYSIS GAMMA TRITIUM LOW GROSS TLD MEDIUM SCHEDULE ISOTOPIC LEVEL BETA I-131 Air Radioiodine and Particulates Weekly X
X Direct X
Radiation Quarterly Monthly
)
Surface Composite X
Water Quarterly i
Composite X
Biweekly X
i Monthly Drinkmg Composite X
X Water Quarterly Shoreline Sediment Semiannually X
Milk Senimonthly X
X Fish Semiannually X
Broadleaf Monthly Vegetation (when X
available)
Monthly Food Products (during X
harvest season)
Section 2 - Page 13
TABLE 2.2-C LOWER LIMIT OF DETECTION (LLD)
CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS Analysis Water Air Fish Milk Food Sediment (pCi/ liter)
Particulates (pCi/kg-wet)
(pCi/ liter)
Products (pCi/kg-dry) or Gases (pCi/kg-wet) 3 (pCi/m )
Gross Beta 4
0.01 H3 2000(*)
Mn54 15 130 Fe59 30 260 CoS8,60 15 130 Zn65 30 260 Zr-Nb-95 15 I131 1 *>
0.07 1
60 Csl34 15 0.05 130 15 60 150 Csl37 18 0.06 150 18 80 180 Ba-La-140 15 15 (a) Ifno drinking waterpathway exists, a value of 3000 pCi/ liter may be used.
(b) Ifno drinking waterpathway exists, the LLD ofgamma isotopic analysis may be used.
1 t
l Section 2 - Page 14
3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DISCUSSION, INTERPRETATION, AND TRENDING OF RESULTS In addition to the " required" sampling and analyses described in CNS Selected Licensee Commitments Table 16.11-7, the following " supplemental" measures were taken during 1995.
These supplemental measures were first adopted during 1986 to better assess the impact of CNS operations on the environment in a more timely and reliable manner:
1)
Shoreline sediment (requiring collection at only one point along the CNS discharge canal (Location 208-lS) was collected at three points (Locations 208-lS, 208-2S and 208-3S).
2)
Shoreline sediment (requiring collection semiannually) was collected quarterly.
The first and third quarter samples from Locations 208-IS, 210 and 215 were considered to be the required samples and all remaining samples were considered supplemental.
3)
Fish (requiring collection from Locations 208 and 216 semiannually) were collected quarterly.
This year the second and fourth quarter samples were considered to be the required samples and the first and third quarter samples were considered supplemental.
4)
Bottom sediment (not requiring collection) was collected quarterly at CNS Discharge Canal Locations 208-lM, 208-2M, and 208-3M.
These were considered to be supplemental samples.
Summary tables containing 1995 information required by Technical Specification Administrative Control 6.9.1.6 for each required REMP sample type, can be found in Appendix B.
These summary tables are based upon required sample results and supplemental sample results.
All deviations from the sampling and analytical requirements of Selected Licensee Commitments Table 16.11-7 which occurred during 1995, are addressed in Appendices C and D, respectively.
For all 1995 REMP samples collected, required as well as supplemental, the reporting level limitations of Selected Licensee Commitments Table 16.11-7 were not exceeded. For REMP analyses, the LLD requirements of Selected Licensee Commitments Table 16.11-8 were met for Section 3 Page 1
1 4
all required and supplemental samples. The required reporting levels and LLD capabilities for REMP samples are listed in Tables 2.2-A and 2.2-C.
l Selected Licensee Commitments Table 16.11-7 (included as Table 2.2-A) provides reporting j
levels, as a function of sample type and radionuclide. If sample radionuclide activity exceeds 100% of reporting level (when summed over all detected radionuclides having a reporting level for the applicable sample type, and when the sums are averaged by location over the applicable calendar quarter), a special report must be submitted to the Nuclear Regulatory Commission.
All 1995 maxunum percent of reporting level values were well below the 100% action level. The highest value reached during 1995 was 53.2%, for surface water tritium collected during fourth quarter at CNS discharge canal Location 208.
Selected Licensee Commitments Section 16.11-13 addresses the actions to be taken when radionuclides other than the thirteen radionuclides listed are detected in REMP samples. The occurrences of these radionuclides are the result of CNS liquid effluents which contained the radionuclides.
The Nuclear Data ND6620 gamma spectroscopy system (which was used to analyze REMP samples collected during 1984,1985,1986, and most of 1987) was replaced by the Nuclear Data ND9900 gamma spectroscopy system on September 1,1987. When the ND6620 system was used to analyze samples prior to September 1,1987, a small but steady percentage (approximately five percent) of measurements for most of the thirteen radionuclides listed in technical specifications, yielded detectable low-level activity, even when the presence of such activity was highly unlikely as for control location samples and preoperational samples collected during 1984.
This phenomenon has not occurred using the ND9900 system, thus ending this trend and suggesting that the ND6620 system may have been vulnerable to false-positive results, possibly due to the method by which it estimated net activity even when its peak search routine failed to detect a peak.
This attribute must be considered when trending and comparing recent REMP results to those generated during the preoperational period and the operational period through August,1987.
All 1995 REMP analysis results were reviewed in order to detect and identify any significant trends. Many source ofinformation were examined to accomplish this and the resultant trending observations are included in Parts 3.1 through 3.11. Quarterly REMP verification reports were generated in order to track commitment requirements, and these reports were also used to evaluate potential trends.
l Section 3 - Page 2
l 3.1 AIRBORNE RADIOIODINES AND PARTICULATES 3.1.1 RADIOIODINES During 1995,258 radiciodine samples were analyzed,206 from the four indicator locations and 52 from the controllocation.
The term " airborne radiciodines" is used throughout this report to generically categorize sample results for the air charcoal cartridge filter. Radioactive iodines and other halogens are the only radionuclides (other than some which occur naturally) normally expected to be detected in these REMP samples. For the i
purpose of this report, the term " airborne radiciodines" refers to any and all
)
radionuclides reported in REMP air charcoal cartridge sample results, not just radiciodines.
K-40 and Be-7 which occur naturally, were routinely detected in REMP charcoal j
cartridge samples collected during 1995. Cs-137 activity was present on one cartridge, but not on the particulate filter. This was determined to be inherent in j
the charcoa.1 and was not included for trending purposes.
3.1.2 PARTICULATES During 1995,258 particulate filter samples were analyzed,206 from the indicator locations and 52 from the control location.
1 Be-7 which occurs naturally, was routinely detected in REMP airborne particulate filter samples collected during 1994. K-40 was occasionally detected in these samples. No other radionuclides were detected in any 1995 airborne particulate filter samples. These results were consistent with 1994 sample results.
3.2 GROUND WATER K-40 was the only radionuclide reported in the eight ground water samples collected during 1995. The K-40 results were relatively consistent with results from previous years.
There are no control ground water sample locations.
3.3 DRINKING WATER Tritium was detected in two of eight samples collected during 1995. This detection frequency was less than the frequency in 1984 when tritium was detected in eleven of the twelve samples (92% frequency). Also, K-40 which occurs naturally, was detected in drinking water samples.
Secdon 3 - Page 3
During 1984 (preoperation) and 1985, tritium was detected in drinking water samples with 71% frequency, at average detectable concentrations ranging from approximately 300 to 400 pCi/ liter. During the period from 1986 through 1989, tritium was detected in drinking water samples with 41% frequency, at average detectable concentrations ranging from approximately 500 to 800 pCi/ liter. This concurrent decrease in detection frequency and increase in average detectable concentration is probably attributable to the change in tritium analysis laboratories occurring during 1986 from a contractor laboratory to Duke Power's Radioanalysis Laboratory.
The tritium detection frequencies and low average concentrations which have been reported in previous years for all drinking water locations are consistent with ambient background levels and were probably not affected by CNS effluents.
3.4 SURFACE WATER K-40, Be-7 and tritium, all of which occur naturally, were detected in surface water samples collected during 1995. Tritium was detected in all of the four composite samples collected from discharge canal Location 208.
Table 3.4-A lists the annual average Location 208 surface water sample tritium concentrations,1984 through 1995. The table also lists the total tritium activity released into the CNS discharge canal via liquid effluents during each year. Ratios of the tritium sample concentration divided by the tritium effluent activity are also included.
Tritium concentrations in surface water collected from Location 208 exceed ambient background levels. CNS liquid effluents appear to be affecting discharge canal surface L
water tritium concentrations. The concentration / activity ratios are relatively consistent, considering the uncertainties inherent in such an evaluation.
l t
l 4
Section 3 - Page 4 l
l l
TABLE 3.4-A SURFACE WATER SAhiPLE TRITIUM RESULTS - LOCATION 208 Year Surface Water TotalH-3 Activity Concentration /
Average H-3 Conc.
Released in Liquid Activity Ratio (pCi/ liter)
Effluents (Curies) 1984 313 0
N/A l
1985 1190 175 6.8 1986 2340 236 9.9 1987 4170 728 5.7 l
1988 6030 706 8.5 I
l 1989 5270 890 5.9 1990 3980 594 6.7 1991 4868 646 7.5 1992 6583 774 8.5 1993 5980 826 7.2 1994 2106 585 3.6 1995 5130 490 10.5 l
1985 - 1995 4350 605 7.2 Average l
l Section 3 Page 5
3.5 MILK During 1995, 78 milk samples were analyzed, 52 at the two indicator Locations and 26 at the control Locations.
{
Cs-137 was detected in one milk sample collected during 1995 in which the concentration was 8.6 pCi/ liter.
This concentration is comparable to results obtained since 1987.
During 1984, Cs-137 was detected with 15.0% frequency (12/80), at concentrations ranging from 5.00 to 10.0 pCi/ liter.
4 The single detection of Cs-137 in 1995 indicator location milk sample i
4 occurred during second quarter. Cs-137 was not detected in any airborne emuents from CNS during 1994 or 1995. Cs-137 attributable to past nuclear weapons testing is known to exist in many environmental media at low, highly variable levels.
Based upon the overall consistency between indicator location, control location, and preoperational milk sample results, low-level Cs-137 activity in the single milk sample collected during 1995 cannot reasonably be attributed to CNS emuents.
3.6 BROADLEAF VEGETATION i
In 1995, 36 broadleaf vegetation samples were analyzed, 27 at three indicator Locations and nine at the control Location. Low levels of Cs-137 were detected in broadleaf vegetation samples collected throughout 1995 in four of the 27 indicator Location samples analyzed.
The average detectable Cs-137 concentration was 36 pCi/ wet-kilogram.
During 1984, Cs-137 was detected with 25.0% frequency (9/36), at concentrations ranging from 20.1 to 130 pCi/kg-wet.
i Cs-137 was not detected in CNS airborne emuents during 1994 or 1995.
Also, Cs-137 attributable to past nuclear weapons testing is known to exist in many environmental media at low, highly variable levels.
Based upon consistency between indicator location, control location, and preoperational broadleaf vegetation sample results, low-level Cs-137 e
activity in broadleaf vegetation samples collected during 1995 is not likely attributable to CNS emuents.
Section 3 - Page 6
3.7 SHORELINE SEDIMENT During 1995, a total of 20 shoreline sediment samples were analyzed, four from indicator Location 210 and 12 from indicator Location 208. Four contrci samples were analyzed from control Location 215.
In 1984, Fe-59 was reported in one of the six shoreline sediment samples at a concentration of 67.3 pCi/kg-dry. Cs-134 was reported in four of these samples at concentrations ranging from 24.4 to 39.2 pCi/kg-dry. Cs-137 was reported in two of these samples at concentrations of 41.7 and 173 pCi/kg-dry.
With exception of Cs-137, it was unlikely that these radionuclides were present in these preoperational samples; their detection was probably attributable to the ND6620 sensitivity phenomenon discussed previously.
No other Technical Specification radionuclides were detected in 1984 shoreline sediment samples.
l During 1995, Mn-54, Co-58, Co-60 and Cs-137 were detected in the majority of the twelve shoreline sediment samples collected from CNS discharge canal Locations 208-1S, 208-2S and 208-3S. These radionuclides have been predominant in shoreline sediment samples each year since 1986. The same radionuclides have been predominant in fish and bottom sediment samples collected from the discharge canal. Other radionuclides reported (besides K-40 and Be-7) were Co-57, Nb-95, Sn-113 and Sb-125. All detected radionuclides other than K-40 and Be-7 were attributable to liquid effluents.
Table 3.7-A summarizes shoreline sediment sample results for discharge canal Location 208 during the five year period from 1990 to 1995.
From 1990 through 1995, average detectable radionuclide concentrations have generally shown an increasing trend. For 1995, most concentrations were lower than previous year's. Parameter D which is the ratio of concentration to annual activity released displays a general increasing trend for Co-58, Co-60 and Cs-137. Correlations observed between Parameter D and Parameter F (ratio of sample concentration to cumulative decay corrected activity released) exhibit a generally increasing trend. Therefore, these observations seem to show that environmental removal processes j
have not overcome the accumulation of annual activity released via liquid effluents in shoreline sediment samples.
From the observations, annual activity released in liquid effluents may contribute to previously deposited activity in Location 208 shoreline sediment samples. Also, no samples analyzed from indicator Location 210 or control Location 215 resulted in detectable radionuclides other than those naturally occurring.
I Section 3 - Page 7
TABLE 3.7-A SHORELINE SEDIMENT SAMPLE RESULTS - LOCATION 208-1S,2S, AND 3S Radio-Parameter 1990 1991 1992 1993 1994 1995 nuclide(s) mummmmmmm ummmmanummmmmmmu Mn-54
[A]
58.8 137 155 160 65.8 122
[B]
11/12 4/12 9/12 10/12 9/12 10/12
[C]
34.4 30.2 23.2 13.5 10.3 16.8
[D]
1.7 4.5 6.7 11.9 6.4 7.3
[E]
54.6 54.5 47.5 34.6 25.7 28.2
[F]
1.I 2.5 3.3 4.6 2.6 4.3 Radio-Parameter 1990 1991 1992 1993 1994 1995 nuclide(s) mummmmmmmmmmmmmmmm-mmmmmmmm-Co-58
[A]
227 404 1227 1070 798 1326
[B]
11/12 6/12 11/12 12/12 12/12 12/12
[C]
244 196 364 398 272 308
[D]
0.9 2.1 3.4 2.7 2.9 4.3
[E]
248 203 370 408 283 316
[F]
0.9 2.0 3.32 2.6 2.8 4.2 Radio-Parameter 1990 1991 1992 1993 1994 1995 nuclide(s) l mammmmmmmmmmum mummmmmmmmemummmmumu-Co-60
[A]
193 488 633 1040 573 944
[B]
11/12 5/12 11/12 12/12 12/12 11/12
[C]
127 156 116 67.0 68.1 105
[D]
1.5 3.1 5.5 16 8.4 9.0
[E]
412 517 569 566 564 600
[F]
0.5 0.9 1.1 1.8 1.0 1.6
[A]
Average Detectable Concentration (pCi/kg-dry)
[B]
Fraction of Total Measurements Yielding Detectable Actisity
[C]
Annual Activity Released in Liquid Efiluents (mci)
[D]
Concentration / Annual Actisity Ratio (pCi/kg-dry per mci)
[E]
Decayed Cumulative Activity Released in Liquid Efiluents (mci)
[Fj Concentration / Cumulative Activity Ratio (pCi/kg-dry per mci)
Section 3 - Page 8
1 TABLE 3.7-A (Continued)
SHORELINE SEDIMENT SAMPLE RESULTS - LOCATION 208-IS,2S, AND 3S l
1 Radio-Parameter 1990 1991 1992 1993 1994 1995 nuclide(s) mush mmmmmmmmm ummmmmmm mum m mmmu Cs-134
[A]
33.2 16 3 50.8 84.0 34 0
[B]
6/12 2/12 4/12 4/12 2/12 0/12
[C]
10.2 5.6 4.3 3.20 1.17 0.54
[D]
3.3 2.9 11.8 26.3 29.1 0.0
[E]
27.3 25 23.P '
2C.2 15.6 11.7
[F]
1.2
.65 2.1 4.2 2.2 0.0 Radio-Parameter 1990 1991 1992 1993 1994 1995 nuclide(s) usammmmmmmmmmm
-mummmmmmemummmmmummmmmemummmmmmmmummmm Cs-137
[A]
81.8 64.9 107 126 107 85
[B]
12/1?
6/12 12/12 12/12 12/12 12/12
[C]
17 '
9.5 8.9 7.84 3.88 2.68
[D]
4.6 6.9 12.0 16.1 27.6 31.7
[E]
98.2 105 104 109 110 110
[F]
0.8 0.6 1.0 1.2 1.0 0.8
[A]
Average Detectable Concentration (pCi/kg-dry)
[B]
Fraction of Total Measurements Yielding Detectable Activity
[C]
Annual Activity Released in Liquid Efiluents (mci)
[D]
Concentration / Annual Activity Ratio (p C1/kg-dry per mci)
[E]
Decayed Cumulative Activity Released in Liquid Effluents (mci)
[F]
Concentration / Cumulative Activity Ratio (pCi/kg-dry per mci)
Section 3 Par.9
3.8 FISH A total of 24 fish samples were collected during 1995 with 12 callected from indicator Location 208 and 12 from control Location 216.
During 1984,2n 65 was reported in one of the twelve fish samples, at a concentration of 148 pCi/kg-wet. Nb-95 was reported in one of these samples at a concentration of 189 pCi/kg-wet. Cs-137 was reported in two of these samples at concentrations of 25.7 and 64.6 pCi/kg-wet. With exception of Cs-137, it was unlikely that these radionuclides were present in these preoperational samples; their detection was probably attributable to the ND6620 sensitivity phenomenon discussed previously. No other Technical Specification radionuclides were detected in 1984 fish samples.
1 During 1995, Mn-54, Co-58, Co-60, and Cs-137 were frequently detected in the twelve fish samples collected from CNS discharge canal Location 208. The four radionuclides have been predominant each year since 1986 and have also been predominant in shoreline and bottom sediment samples collected from the discharge canal. Detected radionuclides other than K-40 and Be-7 were attributable to liquid effluents from CNS. Cs-134 was not identified in fish samples in 1995.
1 Sample results for fish collected at indicator Location 208 were reviewed by type of fish.
Results showed that all radionuclide detection frequencies and concentrations were higher for forager fish than for predatory and bottom feeding fish.
These results have been observed from 1990 through 1995.
Table 3.8-A summarizes fish sample results for discharge canal Location 208 during the six year period 1990 through 1995.
From 1990 through 1995, average detectable. concentrations correlated acceptably with annual activities released in liquid effluents [ Parameter D] which is an important aspect of this report and of the data contained in Table 3.8-A. In addition, ratios for Co-58 and Cs-137 were higher in 1995 than previous years, and ratios for detectable concentrations and cumulative activity released [ Parameter F] were higher. There were no detectable occurrences of Cs-134 in twelve samples analyzed. Observation suggests that annual average detectable radionuclide concentrations from Location 208 fish samples were primarily dependent on the annual and the cumulative activities released via liquid effluents.
i se.n w i
TABLE 3.8-A FISH SAMP.LE RESULTS - LOCATION 208 Radio-Parameter 1990 1991 1992 1993 1994 1995 nuclide(s) muummmmmmmmm ummmmmmmm Mn-54
[A]
100 94.4 121.
60.1 22.9 56.5
[B]
3/12 4/12 1/9 5/14 1/12 3/12
[C]
34.4 30.2 23.2 13.5 10.3 16.8
[D]
2.9 3.1 5.2 4.4 2.2 3.4
[E]
54.6 54.5 47.4 34.6 25.7 28.2
[F]
1.8 1.7 2.5 1.7 0.9 2.0 Radio-Parameter 1990 1991 1992 1993 1994 1995 nuclide(s) mmmmmmmmm-m-
Co-58
[A]
301 292 270.7 557 114 890
[B]
7/12 6/12 3/9 9/14 5/12 5/12
[C]
244 196 364 398 272 308
[D]
1.2 1.5 0.7 1.4 0.4 2.9
[E]
248 203 436 410 283 316
[F]
1.2 1.4 0.6 1.4 0.4 2.8 i
Radio-Parameter 1990 1991 1992 1993 1994 1995 nuclide(s)
-mummmmmmmmmunummanummm ummmmmmmesummuummmemuumummum-Co-60
[A]
311 387 557 212 43.5 265
[B]
3/12 4/12 1/9 8/14 5/12 3/12
[C]
127 156 116 67.0 68.1 105
[D]
2.4 2.5 4.8 3.2 0.6 2.5
[E]
412 517 569 566 564 600
[F]
0.8 0.7 0.9 0.4 0.1 0.4
[A]
Average Detectable Concentration (pCi/k, wet) t
[B]
Fraction of Total Measurements Yielding Detectable Activity
[C]
Annual Activity Released in Liquid EfIluents (mci)
[D]
Concentration / Annual Activity Ratio (pCi/kg-wet per mci)
[E]
Decayed Cumulative Activity Released in Liquid Effluents (mci)
[F]
Concentration / Cumulative Activity Ratio (pCl/kg-wet per mci)
Sec6on 3 Page 11
1 TABLE 3.8-A l
(CONTINUED)
FISH SAMPLE RESULTS - LOCATION 208 Radio-Parameter 1990 1991 1992 1993 1994 1995 nuclide(s) m u mmemumsmummmmmm Cs-134
[A]
31.7 25.7 38 38.2 0
0
[B]
5/i2 6/12 3/9 1/14 0/12 0/12
[C]
10.2 5.6 4.3 3.20 1.17 0.54
[D]
3.1 4.6 8.8 11.9 0.0 0.0
[E]
27.3 25.1 22.3 19.1 14.8 11.1
[F]
1.2 1.0 1.7 2.0 0.0 0.0 l
i l
Radio-Parameter 1990 1991 1992 1993 1994 1995
{
nuclide(s) im muuuuuuuuu unummusiumum J
[A]
55.9 45.9 51.8 29.8 26.2 67.7
[B]
10/12 12/12 8/9 12/14 8/12 7/12
[C]
17.7 9.5 8.9 7.84 3.88 2.68
[D]
3.2 4.9 5.8 3.8 6.8 25.3 l
[E]
98.2 105 111 116 117 117
[F]
0.6 0.4 0.5 0.3 0.2 0.6
[A]
Average Detectable Concentration (pCi/kg-wet)
[B]
Fraction of Total Measurements Yielding Detectable Actisity
[C]
Annual Actisity Released in Liquid Efnuent;(mci)
(D]
Concentration / Annual Activity Ratio (pCi/kg-wet per mci)
[E]
Decayed Cumulative Activity Released in Liquid Effluents (mci)
[F]
Concentration / Cumulative Activity Ratio (pCi/kg-wet per mci) a Section 3 - Page 12 i
1 3.9 DI~ RECT GAMMA RADIATION (TLD)
Forty thermoluminescent dosimeters (TLD's) are located in the vicinity of CNS in order to monitor direct gamma radiation. The TLD locations are divided into four subgroups: three control locations, sixteen site boundary ring locations, sixteen 4-5 mile ring locations and five special interest locations. This data is shown in Table 3.9-A along with the respective values for previous years. The highest annual mean doserate for an indicator location was 4
28 mrad per quarter. That TLD was located at indicator location 206 (0.7 miles %WW from the site). The annual mean for the control locations was 20 mrad per quarter.
The t-statistic or t-test was used to compare 1995 TLD results to TLD measurements taken during preoperation. The ratio of site boundary and 4-5 nule ring results for 1995 was compared to the ratio of results for preoperation.
The value of the t-statistic calculated by comparing preoperational results to 1995 TLD results was -0.292. As shown in Table 3.9-B, this is within the boundary values of
- 2.042, based on 32 measurements and a 9.5% confidence interval.
In addition, the calculated total body dose (from gaseous effluents) for 1995 was 0.0664 mrem (0.06% of the measured TLD values) and it can be concluded that discharges from Catawba had very little impact upon the measured TLD values.
I I
i l
I section 3 Page 13
TABLE 3.9-A DIRECT GAMMA RADIATION (TLD) RESULTS All Locations Site Boundary Ring 4-5 Mile Ring Special Interest Control Locations Year (40 Locations)
(16 Locations)
(16 Locations)
(5 Locations)
(3 Locations)
Avg. Dose Avg. Dose Avg. Dose Avg. Dose Avg. Dose (mrad)
(mrad)
(mrad)
(mrad)
(mrad) 1984 82.9 87.5 82.6 71.2 79.3 1985 110.7 116.9 108.7 98.6 108.9 1986 98.9 104.3 98.5 85.7 94.4 1987 90.0 97.0 87.4 78.6 84.7 1988 70.9 74.6 70.3 63.I 67.1 1989 62.6 67.I 60.8 54.3 60.0 1990 46.4 52.0 44.5 39.1 39.I 1991 56.7 62.0 54.I 48.0 46.7 1992 74.3 80.4 72.5 66.2 64.5 1993 63.6 70.3 60.8 56.2 53.6 1994 69.0 76.3 69.3 66.5 63.9 1995 92.8 99.6 89.7 86.6 80.8 Section 3 - Page 14
TABLE 3,9-B l
,i i
Comparison ofInner Ring / Outer Ring TLD Results i
muummmmmmmmmmmmmuumme umummmmmmmummmmmmmum 1995 (mrad /yr)
Preop. (mrad /yr)
I Inner Ring 100.25 87.48 Outer Ring 91.82 82.60 Ratio 1.12 1.10 1
Variance 0.05 0.07 t-value
-0.292 t-table (95%)
- 2.042 Section 3 -Page 15
3.10 FOOD PRODUCTS Collection of food product samples from an irrigated garden at a residence located on Lake Wylie downstrean from CNS (Location 253) began in July,1989. During 1995, nine samples were collected from this location.
During 1995, K-40 was detected in all nine samples. These results were consistent with all sample results since 1989.
3.11 BOTTOM SEDIMENT During 1984, REMP bottom sediment samples were not a required collection media.
Samples were first collected during 1986 from three points in the discharge canal, i
following review of shoreline sediment and fish samples collected there. Bottom sediment control samples have never been collected.
During 1995, Mn-54, Co-58, Co-60 and Cs-137 were detected in most of the twelve bottom sediment samples collected from CNS discharge canal Locations 208-lM, 208-2M, and 208-3M. The four radionuclides have been predominant each year since 1986 along with Cs-134. These radionuclides have been predominant in shoreline sediment
)
samples collected from the discharge canal, samples for which average detectable concentrations are considerably lower. In addition, Co-57 and Sb-125 were identified in samples. All detected radionuclides were attributable to liquid effluents from CNS during 1995. Location 208-2M displayed the highest overall concentrations for the major radionuclides. Co-60 concentration was significantly higher with an average detectable concentration of 9446 pCi/kg-dry.
Table 3.11-A summarizes the bottom sediment sample results for discharge Location 208 during the period 1990 through 1995. Detection frequencies remained high and relatively stable throughout the period. Shoreline sediment frequencies paralleled this trend.
From 1990 through 1995, average detectable concentrations for bottom sediment correlated extremely well with cumulative, corrected activities released in liquid efDuents since preoperation [ Parameter E) as indicated by the consistent ratios of these values
[ Parameter F]. The one exception is Co-60 which has exhibited an increasing trend. Over the period of trending, indications show no significant environmental " removal" processes have decreased Co-60 accumulation to levels below that expected based on cumulative, decay corrected activities released in liquid etlluents since preoperation.
In all cases, the liquid effluent concentrations in 1995 followed the same changes as the average detectable concentrations. Therefore, the impact of plant operation on bottom sediment from Location 208 was at an expected level when considering the liquid effluent data for 1995.
section 3 - Page 16
The annual average detectable radionuclide concentrations for Location 208 bottom sediment samples tend to be largely dependent on the cumulative concentration and to a moderate degree for Co-60 and Cs-137 on annual activities released via liquid effluents. It appears that discharge canal activities deposited annually in bottom sediment are not removed by environmental processes at the same rate shown by activity measured in shoreline sediment and fish.
l i
1 Section 3 - Page 17
TABLE 3.11-A BOTTOM SEDIMENT SAMPLE RESULTS - LOCATION 208-1M,2M, AND 3M Radio-Parameter 1990 1991 1992 1993 1994 1995 nuclide(s) mummmmmmmmmum-mummmmmmmmmmmmumammmmmmmummummmmunemummmmmam Mn-54
[A]
381 453 525 372 277 338
[B]
12/12 11/12 12/12 12/12 12/12 11/12
[C]
34.4 30.2 23.2 13.5 10.3 16.8
[D]
11.1 15.0 22.6 27.6 26.9 20.1
[E]
54.6 54.5 47.4 34.6 25.7 28.2
[F]
7.0 8.3 11.1 10.8 10.8 12.0 Radio-Parameter 1990 1991 1992 1993 1994 1995 nuclide(s)
-mmmmmmmmmmmmu
-mmmmmmmmm-Co-58
[A]
783 691 1603 1597 1498 2067
[B]
8/12 10/12 7/12 10/12 10/12 9/12 (C]
244 196 364 398 272 308
[D]
3.2 3.5 4.4 4.0 5.5 6.7
[E]
248 203 423 410 284 316
[F]
3.2 3.4 3.8 3.9 5.3 6.5 Radio-Parameter 1990 1991 1992 1993 1994 1995 nuclide(s) mummmuummus um Co-60
[A]
4120 5100 7095 5792 5322 9446
[B]
12/12 12/12 12/12 12/12 12/12 12/12
[C]
108 156 116 67.0 68.1 105
[D]
29.4 32.7 61.2 86.4 78.1 90.0
[E]
318 517 569 566 564 600
[F]
10.0 9.9 12.5 10.2 9.4 15.8
[A]
Average Detectable Concentration (pCi/kg-dry)
[B]
Fraction of Total Measurements Yielding Detectable Activity l
[C]
Annual Actmty Released in Liquid EfIluents (mci)
[D]
Concentration / Annual Actidty Ratio (pCi/kg-dry per mci)
[E]
Decayed Cumulative Activity Released in Liquid EfIluents (mci)
[F]
Concentration / Cumulative Activity Ratio (pCi/kg-dry per mci)
Section 3. Pap: 1?
1 TABLE 3.11-A (Continued)
BOTTOM SEDIMENT SAMPLE RESULTS - LOCATION 208-1M,2M, AND 3M Radio-Parameter 1990 1991 1992 1993 1994 1995 nuclide(s) mammmmmmmmme mammmmmmmmmmmmmmummmmmmmmmmmmmmmmummmmmmmu Cs-134
[A]
127 122 78 184 0
72
[B]
9/12 8/12 7/12 5/12 0/12 1/12
[C]
10.2 5.6 4.3 3.20 1.2 0.54
[D]
12.5 21.7 18.1 57.5 0.0 133
[E]
27.3 25.1 22.3 19.1 14.8 11.1
[F) 4.7 4.9 3.5 9.6 0.0 6.5 Radio-Parameter 1990 1991 1992 1993 1994 1995 nuclide(s) muummusummummummum ummmmmmemummmmmu Cs-137
[A]
506 548 494 538 427 491
[B]
12/12 12/12 11/12 12/12 12/12 12/12
[C]
17.7 9.5 8.9 7.84 3.9 2.7
[D]
28.6 57.9 55.6 68.6 110 183
[E]
98.2 105 111 116 117 117
[F) 5.2 5.2 4.5 4.6 3.6 4.2
[A]
Average Detectable Concentration (pCi/kg-dry)
[B]
Fraction of Total Measurements Yielding Detectable Actidty
[C]
Annual Activity Released in Liquid Effluents (mci)
[D]
Concentration / Annual Activity Ratio (pCi/kgdry per mci)
[E]
Decayed Cumulative Activity Released in Liquid Elliuents (mci)
[FJ Concentration / Cumulative Activity Ratio (pCi/kg-dry per mci)
Section 3 - Page 19
- ~.
~ _ -...
l 1
3.12 LAND USE CENSUS The 1995 Annual Land Use Census was conducted as required by Selected Licensee I
Commitment 16.11-14. Table 3.12 summarizes the census results. Figure 3.12 contains 2
the map showing identified locations. Sectors shown in Table 3.12 which have no values listed had no corresponding location identified in that sector.
Based upon 1995 Annual Land Use Census results for the nearest residences and gardens, dose evaluations were performed to ensure that the current air and broadleaf vegetation sampling locations complied with the requirements of Selected Licensee Commitment and that no changes or additions to these locations were required. The evaluations showed that all existing air and broadleaf vegetation sampling locations complied with the 2
requirements. No changes or additions to these locations were required or made as a result of the 1995 Census.
The 1995 Annual Land Use Census included a search for all locations within a distance of five miles (eight kilometers) from CNS where any cattle or goats were kept (not just the nearest location in each sector). Numerous locations were identified within the five mile radius. Each location was investigated to determine whether the animals were being used for meat production, milk production, reproduction or a combination of these purposes.
Investigation of all locations revealed that none of the animals were " milking animals" (milk was not being consumed by humans). The three current CNS REMP milk sampling locations (dairies located at distances greater than five miles from CNS), have been sampled routinely since preoperation. No changes or additions to CNS REMP milk sampling locations were made as a result of the Census.
Section 3 Page 20
TABLE 3.12-A 1995 CATAWBA NUCLEAR STATION ANNUAL LAND USE CENSUS RESULTS Date(s) Performed 07/20/95 -08/16/95 Sector Distance Sector Distance (Miles)
(Miles)
N Nearest Residence 0.64 S
Nearest Residence 0.83 Nearest Garden 1.54 Nearest Garden 0.98 Nearest Milk Cow Nearest Milk Cow Nearest Beef Cow 4.87 Nearest Beef Cow 4.05 Nearest Goat Nearest Goat NNE Nearest Pesidence 0.63 SSW Nearest Residence 0.89 Nearest Garden 2.07 Nearest Garden 1.69 Nearest Milk Cow Nearest Milk Cow Nearest Beef Cow Nearest Beef Cow 3.04 Nearest Goat Nearest Goat NE Nearest Residence 0.60 SW Nearest Residence 0.65 Nearest Garden 2.39 Nearest Garden 0.66 Nearest Milk Cow Nearest Milk Cow
)
Nearest Beef Cow Nearest Beef Cow 2.59 Nearest Goat 2.95 Nearest Goat ENE Nearest Residence 0.62 WSW Nearest Residence 0.79 i
Nearest Garden 0.60 Nearest Garden 2.04 Nearest Milk Cow Nearest Milk Cow Nearest Beef Cow 4.17 Nearest Beef Cow 2.87 Nearest Goat 1.27 Nearest Goat E
Nearest Residence 0.65 W
Nearest Residence 0.96 Nearest Garden 0.84 Nearest Garden 1.15 Nearest Milk Cow Nearest Milk Cow Nearest BeefCow Nearest BeefCow 3.81 Nearest Goat Nearest Goat ESE Nearest Residence 0.84 WNW Necrest Residence 1.10 Nearest Garden 3.63 Nearest Garden 1.11 Nearest Milk Cow Nearest Milk Cow Nearest Beef Cow Nearest Beef Cow 4.34 Nearest Goat Nearest Goat 3.63 i
SE Nearest Residence 0.99 NW Nearest Residence 1.31 Nearest Garden 1.52 Nearest Garden 1.52 l
Nearest Milk Cow Nearest Milk Cow Nearest Beef Cow 4.05 Nearest Beef Cow 2.30 I
Nearest Goat 3.87 Nearest Goat 1.44 i
SSE Nearest Residence 0.62 NNW Nearest Residence 1.06 Nearest Garden 1.70 Nearest Garden 2.19 Nearest Milk Cow Nearest Milk Cow Nearest Beef Cow Nearest Beef Cow 3.49 Nearest Goat 3.54 Nearest Goat 2.62 Section 3. Page 21
Fig re 3.12
/
Q
/
) ' $F. }'s
' /)
\\
L H
Cat:.wb3 Nuclear
-h-
'y '
/
^
Station 1995 Land
/
\\
g j
s
/
/ ('s, N
Use Census Map -
)
1 7
o y<
.,s
[x
,k[' h
/'
+
[
/
hp Milk cow
(
l
(
UJ l
+
Goat
/
- yf' 'op ' p
/4>/
(,- ('
e r
j
/
. (i/
)
l gi A
N o n-Irrig a te d L
(
p' Y
G a rd en J
f li
\\
fg S(
j N
/
A n
x g
g
/f -
,-b
\\
\\
R e sid en c e 1
fxw // p
=
~c E
I A7%
i G
Beef cow l
( O
'f h
/s i
/,, X4 4
M
\\
", W^-
C
)
1-Stream s and L
g p
m h%
Shorelines
)
/i
~'
r
/
h
. >c 7 x/
Roads g
/
m g
'gX
[
/
g',
}
\\,
c ounty lin es s
'h Q$
R ailro ad s I
~
g
/h V^
3 h
'/
/0 g
1
\\
mg
' g^
- Q
}
(
y
,y -
I y) \\ _ %e /
J '
'\\k
/'t
[
z s
' r$
i f-3 q '? l}
['<)[ '~ Y >
/)
4 sd
~~
/
t 7 9,
W{
\\
_./
z< \\
Y W.=
m'
~( h, l
k$3xy L'
/\\.
/
SC A LE: 1:9 5040
=
r
,/'
/
~
f( '.
'[/
7 h/
s
[
/
- <7 rj/ 5 rnile's M
/'
Projection N.C. State Plans
\\
QlD dD
[',k)
(/
M sSE
- 4 w %,
l)
Y 4
/
jg Nh 1 A % cjrK J-tm J F xh @_ mtyfs August 1995 A
il ns/
m ca'2a,ss Seaion 3 - Page 22
l 4.0 EVALUATION OF DOSE FROM ENVIRONMENTAL l
MEASUREMENTS VERSUS l
ESTIMATED DOSE FROM l
RELEASES l
l 4.1 DOSE FROM ENVIRONMENTAL MEASUREMENTS l
l Annual doses to maximum exposed individuals were estimated based on measured l
concentrations of radionuclides in 1995 CNS REMP samples. The primary purpose of l
estimating doses based on sample results was to allow comparison to emuent program dose estimates. Doses based on sample results were conservatively calculated in a manner as equivalent as possible to emuent-based dose estimates.
l Doses based on sample results were calculated using the methodology and data presented I
in NRC Regulatory Guide 1.109. Measured radionuclide concentrations, averaged over the entire year for a specific radionuclide, indicator location, and sample type, were used to calculate REMP-based doses, after subtracting applicable average background concentration (as measured at the corresponding control location). Regulatory Guide l
1.109 consumption rates for the maximum exposed individual were used in the l
calculations.
When the guide listed "NO DATA" as the dose factor for a given radionuclide and organ, a dose factor of zero was assumed.
i i
Three radionuclides detected in 1995 REMP samples, Co-57, Sn-133 and Sb-125 had no dose factors listed in Regulatory Guide 1.109. Dose factors for these radionuclides were taken from Appendix C of NUREG/CR-1276.
l l
Maximum dose estimates (Highest Annual Mean Concentration) based on drinking water, t
milk, broadleaf vegetation, fish and shoreline sediment sample results are reported in Table l
4.1 - A.
REMP-based dose estimates were not reported for airborne radiciodine, airbome particulate, or ground water sample types because no radionuclides other than naturally-occurring K-40 and Be-7 were detected in these samples. Dose estimates were not reported for surface water or bottom sediment sample types because sampled surface water is not considered to be a potable drinking water source and because sampled bottom Section 4. Page 1
sediment is permanently submerged. Dose estimates based upon REMP TLD results are discussed in Section 3.9.
The maximum dose to each organ from any single sample type (the " limiting" sample type) other than direct radiation from gaseous emuents, was determined and reported in Table 4.1-A. For bone, liver, kidney, total body and lung, the limiting sample type was milk collected at Location 209. The maximum organ dose estimate for any single sample type,
(other than direct radiation from gaseous effluents) collected during 1995 was 1.73 mrem to the maximum exposed infant's liver from consuming milk collected at Location 209.
In order to generate REMP-based dose estimates which could be compared to reported emuent-based dose estimates, two additional evaluations were performed:
Maximum 1995 REMP-based dose estimates for drinking water, shoreline sediment and fish sample results were summed to determine the maximum total doses for all sampled liquid emuent release pathways. The dose contribution from shoreline sediment to each organ other than the skin was assumed to equal the total body contribution from shoreline sediment. The maximum total organ dose estimates for the critical age groups have been reported in Table 4.1-A.
The maximum total organ dose estimate for all liquid emuent release pathways sampled during 1995 was 0.558 mrem to the maximum exposed adult's GI-LLL The critical pathway was forager fish which accounted for 95% of the total GI-LLI dose of 0.568 mrem.
Maximum 1995 REMP-based dose estimates for airborne radiciodine, airborne particulate and broadleaf vegetation sample results were summed to determine the maximum total REMP-based doses for all sampled gaseous emuent release pathways. The resulting maximum total organ dose estimates for the critical age groups have been reported in Table 4.1-A.
The maximum total organ dose estimate for all gaseous emuent release pathways sampled
' during 1995 was 1.73 mrem to the maximum exposed infant's liver. The critical pathway was milk which accounted for 100% of the total liver dose.
4.2 ESTIMATED DOSE FROM RELEASES Throughout the year, dose estimates were calculated based on actual 1995 liquid and gaseous emuent release data. EGuent-based dose estimates were calculated using the LADTAP and GASPAR computer _ programs which employ methodology and' data presented in NRC Regulatory Guide 1.109. The 1995 CNS Annual Radioactive Emuent Release Report included calendar year dose estimates for the maximum exposed individual from liquid and gaseous emuent releases. These reported doses are shown in Table 4.1-A along with the corresponding REMP-based dose estimates.
Section4 Page 2
l Effluent-based liquid release doses are summations of dose contributions from drinking water, fish and shoreline sediment (estimated for the discharge canal) pathways.
1 The emuent-based gaseous release doses of Table 4.1-A report noble gas exposure and iodine, particulate and tritium exposure. For noble gas exposure there is no critical age group, as the maximum exposed individuals are assumed to receive the same doses, regardless of their age group. For iodine, particulate and tritium exposure, maximum total l
organ dose was 0.502 mrem for skin and critical age was child. The critical pathway for l
the exposure was broadleaf vegetation.
4.3 COMPARISON OF DOSES Tables 4.1-A shows comparisons of REh1P-based versus efFuent-based maximum dose l
estimates, critical ages, and critical pathways for liquid and gaseous release pathways. As discussed in Part 4.1, REMP-based estimates have been calculated to be as analogous as possible to corresponding emuent-based estimates. The estimates can then be compared directly.
One difference between environmental and efIluent-based dose estimates is all emuent-based dose estimates include pathway contributions from tritium contained in liquid and gaseous effluents. Drinking water pathways include dose contributions from tritium. Air, milk and broadleaf vegetation pathways do not include tritium's contribution. Similar differences exist for other radionuclides detected in emuent samples. However, as a result of dilution, transport, and radioactive decay, the concentrations are too low to be detected i
in REMP samples (and their associated dose contributions are therefore not accounted for in REMP-based dose estimates). These differences result in REMP-based dose estimates that are biased low in comparison to effluent-based estimates.
Significant levels of tritium and Cs-137 are present throughout the environment and are not attributable to CNS emuents. REMP samples often contain these radionuclides, sometimes at detectable levels much greater than levels anticipated to result from station effluents. In addition, high variability in the frequency and level that tritium and Cs-137 are detected in REMP indicator and control location samples, introduces large uncertainties when estimating REMP-based dose contributions from net detectable concentrations of these radionuclides. All 1995 REMP-based dose estimates, other than those for samples collected at the discharge canal, are entirely attributable to detection of tritium or Cs-137 in the corresponding REMP samples. It is probable that the doses typically overestimate the true contributions from tritium and Cs-137 released in CNS emuents.
Finally, airborne noble gas samples are not collected as part of the REMP, preventing an analogous comparison of emuent-based noble gas exposure estimates.
The REMP-based dose estimates were less than the corresponding effluent-based j
estimates for the liquid and gaseous release pathways, with the exception of the total body Section 4 - Page 3
estimates for the liquid pathway. The REMP-based dose estimate was 0.189 mrem for total body. The analogous effluent dose estimate was 0.164 mrem.. This indicates that effluent program dose estimates are both valid, and in the majority of cases, reasonably conservative. Doses to members of the public attributable to the operation of CNS are being maintained well within regulatory guidelines.
l l
i I
l t
i
.i-i Section 4 - Page 4 l
l
TABLE 4.1-A Page 1 of 2 1995 ENVIRONMENTAL AND EFFL'?ENT DOSE COMPARISON FOR LIQUID AND GASEOUS WASTE RELEASE PATHWAYS LIOUID RELEASE PATHWAY Environmental or L Critical Critical :
. Maximum' Dose *
~
Ehient Data Age '
- Pathway
- (mrem) :
Skin Environmental Teen Shoreline Sediment 1.74E-02 Skin Emuent Teen Shoreline Sediment 5.84E-02 Bone Environmental Child Fish 1.53E-01 Bone Emuent Teen Fish 1.73E-01 Liver Environmental Adult Fish 2.12E-01 Liver Emuent Teen Fish 2.60E-01 T. Body Environmental Adult Fish
' l.89E-01 T. Body Emuent Adult Fish 1.64E-01 Thyroid Environmental Child Drinking Water 2.75E-02 ThyToid Emuent Teen Shoreline Sediment 1.02E-01 Kidney Environmental Teen Fish 7.5 IE-02 Kidney Emuent Teen Fish 1.29E-01 Lung Environmental Teen Fish 3.99E-02 Lung Emuent Teen Shoreline Sediment 8.92E-02 GI-LLI Emironmental Adult Fish 5.58E-01 GI-LLI Emuent Adult Fish 1.73E+00 i
- Maximum dose is a summation of the fish, drinking water and shoreline sediment pathways.
l l
Section 4 Page $
l
TABLE 4.1-A Page 2 of 2 1995 ENVIRONMENTAL AND EFFLUENT DOSE COMPARISON FOR LIQUID AND GASEOUS WASTE RELEASE PATHWAYS GASEOUS RELEASE PATHWAY Environmental or --
Critical Critical Maximum Dose.
LOrgani Emuent Data -
- Age L Pathway
'imrem) '
NOBLE GAS EXPOSURE
)
Skin Environmental Not Sampled Skin Efiluent N/A Noble Gas 1.58E-01
)
T. Body Environmental Not Sampled T.. Body Effluent N/A Noble Gas 6.64E-02 i
l Environmental or Critical -
Critical Maximum Dose * -
Effluent Data' Age Pathway.
(mren0 IODINE, PARTICULATE, and TRITII.Si Bone Environmental Infant hiilk 1.48E+00 Liver Environmental Infant hiilk 1.73E+00 T. Body Environmental Adult h! ilk 3.55E-01
- Thyroid, Environmental 0.00E+00 Kidney Environmental Infant hiilk 4.65E-01 Lung Emironmental Infant h! ilk 1.88E-01 GI-LLI Environmental Teen hiilk 1.05E-02 Skin Environmental Teen Shoreline Sediment 1.74E-02 Skin Efiluent Child Vegetation 5.02E-01
- Maximum dose is a summation of the inhalation, milk and vegetation pathways.
Suuon 4 - Page 6
TARLE 4.1-B Maximum Individual Dosefor I995 based on Environmental Measurements (mrem)for Catmeba Nuclear Station Age Sample Medium Bone Liver T. Body Thyroid Kidney Lung GI-LLI Skin Infant Airborne 0.00E+00 0.00E+00 0.00E400 0.00E+ 00 0.00E+ 00 0.00E400 0.00E+00 0.00E400 Drinking Water 0.00E+ 00 2.10E-02 2.10E-02 2.10E-02 2.10E-02 2.10E-02 2.10E-02 0.00E+ 00 Milk 1.48E+00 1.73 E+00 1.23E-01 0.00E+ 00 4.65E-01 1.88E-01 5.42E-03 0.00E+ 00 TOTAL 1.48E+00 1.75E+00 1.44E-01 2.10E-02 4.86E-01 2.09E-01 2.64E-02 0.00E+00 Child Airborne 0.00E+ 00 0.00E+ 00 0 00E+00 0.00E+00 0.00E4 00 0.00E+00 0.00E+00 0.00E+00 Drinking Water 0.00E+00 2.14 E-02 2.14E-02 2.14E-02 2.14E-02 2.14E-02 2.14E-02 0.00E400 Milk 9.28E-01 8.88E-01 1.31 E-01 0.00E+ 00 2.89E-01 1.04E-01 5.56E-03 0.00E+ 00 BroadleafVegetation 3.06E-01 2.93E-01 4.32E-02 0.00E+ 00 9.55E-02 3.44E-02 1.83E-03 0.00E+00 Fish 1.53E-01 1.77E-01 9.12E-02 6.10E-03 5.49E-02 2.32E-02 1.30E-01 0.00E400 Shoreline Sediment 0.00E400 0.00E400 3.09E-03 0.00E+00 0.00E400 0.00E400 0.00E + 00 3.63E-03
. TOTAL 1.39E+00 1.38Et00 2.90E-01 2.75 E-02 4.61 E-01 1.83E-01 1.59E-01 3.63 E-03 Teen Airborne 0.00E+00 0.00E+00 0.00E+00 0.00E+ 00 0.00E+ 00 0.00E+00 0.00E+ 00 0.00E+ 00 Drinking Water 0.00Ei OO 1.12E-02 1.12E-02 1.12E-02 1.12E-02 1.12E-02 1.12E-02 0.00E400 Milk 3.85E-01 5.13E-01 1.79E-01 0.00E400 1.74E-01 6.78E-02 7.29E-03 0.00E+00 BroadleafVegetation 1.69E-01 2.25E-01 7.85E-02 0.00E+00 7.67E-02 2.98E-02 3.21E-03 0.00E4 00 Fish 1.21 E-01 2.00E-01 1.23E-01 7.39E-03 6.39E-02 2.87E-02 3.71E-01 0.00E+00 Shoreline Sediment 0.00E+00 0.00E+ 00 1.48E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.74E-02 TOTAL 6.75E-01 9.49E-01 4.07E-01 1.86E-02 3.26E-01 1.38E-01 3.93 E-01 1.74E-02 Adult Airborne 0.00E+ 00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Drinking Water 0.00E+00 1.59E-02 1.59E-02 1.59E-02 1.59E-02 1.59E-02 1.59E-02 0.00E+00 Milk 2.12E-01 2.91 E-01 1.90E-01 0.00E+ 00 9.86E-02 3.28E-02 5.63E-03 0.00E+00 BroadicafVegetation 1.84E-01 2.51E-01 1.65E-01 0.00E+ 00 8.52E-02 2.83 E-02 4.86E-03 0.00E+00 Fish 1.13 E-0 ?
1.96E-01 1.70E-01 9.61E-03 6.38E-02 2.71 E-02 5.42E-01 0.00E+ 00 Shoreline Sediment 0.00E+00 0.00E400 2.65E-03 0.00E400 0.00E+00 0.00E t00 0.00E400 3.IIE-03 TOTAL
__ 5.09E-01 7.54E-01 5.44E-01 2.55E-02 2.64E-01 1.04E-01 5.68E-01 3.1IE-03 NOTE: Dose tables are provid:d for sampic inedia displaying positive nuclide occurrence.
Section 4 Page 7
- I 8 8 I I 8 8 I I 8 8 s s
w I e w e m c w
w c c e e
.I 8 8 8 8 8 2 U 8 8 8 8 8
.. s 6
s 6
a a
y I $
I I I I I I I I I ?
?
w w
w w
w w
w w
w w
w w
w 8 8 8 8 3 8 8 8 8 8 8 2 2
s s
s.. s a n
-f I I I I I I I I I I I E 5
w w
w w
w w
w g
w 8 8 8 8 8 8 8 I 8 8 8 -
a w
w w
2 x
s s e
s t
5
] I I I I I I I I I I I 8 4
x w
w w
w w
w w
w w
g 8 8 8 8 8 8 I 8
.E - 8 8 mg w
m
~
8 8 8 8 { 8 8 8 { g g a g
^
3 r 2 2 2 m
m s c w
w w
2 2
I.
8 8 8 8 8 8 8 8 8 2 2
8 g
5 I I I I 8 8 8 I 8 8 I s a
w w
w w
c
.I* 8 8
.I 8 8 1
w e
s w
2 e
ag 8 8 8 8 8 2
2 s.
a m
I 8 I I I 8 I 8 I I I I 8
A t 3
w a
w w
w I
w I
w w
w I
% %=
M
= 8 8 8 8 8 8 8 8 8 8 8 8
g t
j j { g,
.8 gR s
8 8 8 8 8 8 8 8 8 8 3 3g j
g y a
%m g
c
<2 6
. at a A'
l C-tie j =g
-i -i -i -i i -i -:
'4 d'4
- E
=
C4l E E E E E E N E
< W
~
ik a 1-
~
n I
5 h E
4 8 4 4 $ E E E * *
- 4 4 i
14 2
5, W W W W = W 5 5 5 W
- 8 8
e m
.C g
a. ~ a.
a a a a
m g
a 8
k 8
y N N 3 $ $ N N N k k k
, c c w
c c c c c w
w w
w L
E w
E 0
C E
C C
C C
C E
E.
g a z
- 8 I
=
E z z z a o
m c
~
w N
d" a
4 4
{8 $ $ N E 8 8 4 4 8 8 ?
W 8
5 c c c w
w 5 w 5 W "8
8 s
b, 6
u w
C C
C 8
~
n w
e z z e e
a. < e a
m
^
c C
=
9 k
b eu 7
8 3
e a c = c c = = c y c c c g 5
g C
C C
C C
C C
m C
C C
c a,
a z z z z z z z = z z z m
e, I I I 3 8 I E E I 3
- k E
m 5 W W W 5 W
W W W 5 W I
g m.
m m -
m 8 m
n..
i p
w M
m a
e
=
o m
a k
5 8 8 E B 8 8 E 8 8 E E 6
I I
E sssssN d M. s$
I.
8 e
=
m
. m e a
=
t 3
m
. =
e
==
v e
+
=
m N
I N N 4 ', 4 4 4 4 4 8 8 0<
- E t
)
=
u.
i
- t >
a
- 5 =
8 e
C
=
C
. ~
. n n
C g
a z e
z e
a m
m w
=
z I
w I
l d
1 I E R R % E E E - 3 I j m
l U
h $ $ b c $ b I b $
'il N
1 m
s
.E 8
.. ~ _.
.n.-
d e
8 y
g 8
8 g
8 8
e.
w w
w w
w w
w w
w W
w W
E 8
8 8
8 8 8
8 3
5 9
8 9
m m
E.
8 8
8 8
g 8
8 g
3 g
+
+
+
w w
w w
w w
w w
w w
w w
+
8 :
2 8
3 3
E.
E E
8 e,
8 8
8 8
8 8 8
g 8
s 4
+
+
1 3
w w
w w
w w
w w
w w
w w
W 3
8 8
8 8 8 8 8
8 8
3 y
a 6
6 6
6 s
s w
t T
8 8
8 ?
8 8 I 8
8 8
T E
w w
w w
w w
w w
w w
w w
=
g 8
E 2 3 3 3 8 8
8 8
8 6
3 8 8 8
8-8 8 8
t 2
8 g
N e
=
w w
w w
=
=
w w
w w
w
-p a =
=
=
s
.a 3
a
=
4 s a
E 8
8
=.
8 8
8 8
8-8 t
i w
w w
w w
w w
w w
w w
w 3
8 s
E.
a a
3e 4
3 7
?
?
7 2
?
?
?
?
w w
w w
w w
w w
w w
w w
3 2
a 8
.s.s 8 8 8
q
=
q
%m W t 1
$E
.I I.
I
.E E
8 I
I I
8 g%
gg.
4 a
g
< a ;e o
x.v v
c.
-e a
E D ji U k
4 M
.E
.u z
,E. % :{
4 4 4 4 4 4 4 4 4
4 w
x w
v.
n g
g
=
}
W li 1
U E
8 e
e m
e e
e e
w m
1 e
e e
e e
e e
e a
e e
y i
4 y
w w
w w
w w
w w
w w
w E
5 9 E E
4 9 4
E E
E.
E A
1 w
g r-es n
n m
n v
?
g A
m E
-e e
s
=
=
n y
L e
e s
= <
0 C
W O
O C
O Q
W W
W U
e c
C C
E C
C C
C C
9 3
3 C
g C
6.
E E
E E
E E
E 6
e e
,g r
3 D
C a
w w
p s
m m
w I
4 g
e e
E o
m 2
C "w
".e e
2 w
C C
C n
w y
g w
4 E
E n
4 m
n 4
w N
N N
"s 5
}
c = = =
=
=
c
,R M
l*.
C C
C C
C C
C C
C C
J E
E E
E E
E E
E E
E M
^
j l
3 e
w w
c a e s
w s
e s
5 E
E, E
4 4
4 4
4
~
3 a
n n
n m
n v
^
h.
e
=
w w
w w
w w
w w
w w
w w
N D
w n
A E
S
$$E h5
? E 5
4 n
s e
g e d w
=
w e
w w
w w
w E
E C
C
,E C
k N
4 k
N E
E E
E w
n e
E a
5 d
d.
j E
8 8 E
E E
~ 3 b
b s
e e
e 2
4 9
M 2
L b
6 N,
E N
L 6
3 I
- b..
=
a.
a s.
g a.
g 3 ?
a.
a a
w w
w w
a w
w w
w w
w w
w 8
a 8
6 s
s s
s ea n
E ?
g
?
?
?
?
?
?
?
?
e a
a w
w w
w w
w w
w w
a w
w I
3 3
8 8
8 8
8 E
s s
6 s
a s
a ee n
b g
g 8
8 8
8 8
8 8 8 8,
g y
3 w
w w
w w
w w
w w
w w
w w
W I
E.
.E I.
I E
I.
I E E 2
n m
g E
s a
s.
8
?
?
g
=.
s.
a.
=.
=.
A w
w w
w w
w w
w w
w w
w w
5 4
4 8 E.
8 8
8 8
3 3 E.
A a
e
~
g
?
?
?
?
?
?
g
?
1 e
9
+
=
w w
w w
w w
w w
w w
w w
w w 2 3
2 8
8 3
3 3
8 8
c.
c.
t
?
?
?
?
g
?
?
?
?
I e
e
+
a w
w w
w w
w w
w w
w w
w w
a 8 8 8
8 8
8 8
8 3
y 6
s s
6 6
n
~
Q
? ?
?
?
?
I
?
?
?
I
?
?
?
m*%
E j
w w
w w
w w
w w
i w
w w
w
.s c
3 8
3 3
8 8
8 2
8 8
8 2
s s
A 4
c.
%q D E
5 m
g.,.sl t &
gl e,i g 8
8 8
8 8 8
3 8
3 3
=
5 u g
e.
w
,,.6 N
4
- g
- 6 E
5$
E Ei 5
- s. z.N sf
- -; a
.; -; 4 -;
- 4
-a c;; 44
.o 3
2 wa y
y "(
- C e.
O w
k g
M %
st 3
'E a
g.E
^!
~
W u
e e
e 9
=
.tgM U
.E y
a g
g g
g a
g g
g g
g g
3 E E
~ E 4 4 4
~ 2 1
q
- ~
~ -
y
.=g 1
1 H
t E < <
4 4
4 4
e e
9 E
Q E
R C
C e
"E 0
0 C
0 C
6 O
o 0
0 e
4 G A 2 0
0 t
u u
a z s z z z a z m
n J
S 2
E v
b I
e 4
e O
e e e O
m
. e s<
a Q
=
o 3
a.
c.
c
=
w w
w w
w w
w w
C m
e
.M m.
e 4
e W
9 N
m w
w w
9 Q
g m
z z z n
m n
N N
c C
C 4
w "J
m H
k e-4 e
< e 4
o i
O O
2<
O O
O C
w C
C 2
a M
E W
0 0
0 0
0 C
O P
O C
O E.
=
J z z z z z z z
vi z z z
H m
1 E
i a a a 6
a w
6 u e a a
w E
y A
4 4 4 2 3
3, 2
~.
~
~
E o
n
=.
t e
e e
e e
e e
.n w
g g
g g
g g
g g
g g
g e.
m m
m r.
se M
g p
p p
o U
O M
e e
8 e
e k
e
.E 5
m.
O.
I w
c w
w w
w w
w w
U U
e w
w o
m e
z 9.e N.
w 9
D N
m Z
Z e
ao no m
M 4
I E
A 2
o N
9
=
4
[
s 3
e a
a 9
g y
a u w
a w
z w
a v
3 4
.?
~
l v
s I
a.
a.
3 g
- 8..
9 W
W w
w W
W w
w w
M w
ra; k
k k
k k
o m
m I
T
?
?
I T
e
?
e e
g o
y q
w w
w w
w w
w w
w w
w w
o o
o o
w a
w I
.e o
o o
o e 3 3
8 8
2 8
8 8
8, g
9 a
+
+
+
+
+
+
+
+
+
g a
w w
w w
a w
w w
w w
w o
.k e
e x
e o
-g o
n
~
t E
'1 s.
g
=
?
?
?
?
?
=
q k
- w w
w w
r.s:
rs; M
w w
x W
g g
E 3
k 3
8 8
.k
.k 3
8 o
e o
g o
o 1
?
?
?
?
?
e
?
=
a:
w w
w w
w w
w w
W w
w w
o o
e e
H o.
'1 I
al=
e o
e o
e a
=
o e
e 8
o o
e e
o e
o o
g g
o
+
+
+
+
+
+
+
+
+
,A,.
w w
w w
w w
ist w
sa:
w w
w o
o o
e o
o o
en m.
o
.e
.o o
e o
e m
e g
O o
e o
so so 4
e*
e o
?
?
?
?
?
?
?
?
9 9
w w
x w
- s; w
x w
w w
w w
e o
o o
e o
se ao
.o
- * =
o o
o e
o e
o.
.e o
N N
=4:
o o
o e
e e
A Q A.6w
.x =,-
0 s.
.o o
I k
o g %
o e
o a m eg C
5 g a 3
=
c o
U
< 3h 4:
c, A
c, w
e a
2 u$E $.
4 4
.i 4
4 J
.2 E
S..$
.i
-?.
.i a
a 3
.;g 3
=
Q
==
N
. E,,
E a
m.
e a
M W
E
%q'
.e e
e e
e e
m m
e w
w E
m a
9 9
9 9
9 9
o
=
9 9
m N
Q w
w w
sa W
w w
w ra; w
-a
=
e en m
m u
o n
e w
o.
e
.g w
m
~
='
~
n n
4
=
n
~
n
=
w 0
2 s
g C
C H
H H
H H
e m
a E,
m u
y <
9 e
o N
c q
O O
W O
O O
2 0
=
w W
g 0
0 E
O O
O O
O Z
N, E
E,
=
=
v 6
x x
8 x
x x
x z
J m
B N
e m
e e
m w
w e
g 4
F 9
9 9
9 9
=
9 E
o
=.-
2 0,
"es "w
w w
w o
m m
e n
n ec M
O
1 g
g 6
Z Z
4 N
M N
=
m M
i w
l a
Ese
-7 "1
J H
H H
H H
H M
N H
k o
p A
C C
C 0
C 2
O w
c O
O O
O O
O O
O O
E O
O O
E E
E E
Z Z
Z E
e E
E E
m A
m m
m W
W W,
e g
3 9
9 o
e e
o e
e o
~
w i.;
x a
w w
a w
w
=
x m
~
m 4
6 4
m o
n m
O g
9 m
n
~
~
~
9
=
n m
o
=
n e
n e
w n
I C=
e e
e e
e e
e m
ce 9
e t,
9
=
=
=
9 9
9 m
- n; w
w s
a r;
z w
sa:
E m
e o
e e
m m
m
=
=
w m
4 n
e t-m r~
a n
A M
=
N F5 M
N E
N N
N a
.=
5 g
g m.
H e
e o.
m w
w m
o s
s s
e e
o M.-
S
.h.
N d
N d
N N
N N
N N
N a
m n
m
.a n.
w n
8's W
O O
g C
as')
N P
M M
M A
O E
E e
z M
M E
N M
M E.
a 5-i 6
I.
t
=.
m.
=
=
s e
e m
4 9
j y
jl j
e s
e e
o 2
L h
6 g
4 a
j 6
4 C
6 I
. ~..,.. - - -..
.-. -.........- - - ~- -.~ ~.. -. -..... - -.... -... -. -.. -. _.
i
= 0 8 8
8 8
8 8
8 8
3 8
3 G
s i
1 s s s
s 5 8 8
8 8
8 8 8
8 8
2 8
E s
8 8
8 8
8' 8
8 8
8 g
8 g
( s s s
s s
s s
a s
s i
s 8
8 8 - 8 8 8 8
8 8
8 o
j
^ 8 8
8 8
8 8
8 8
8 g
8 g
j s & &
s 1 &
1 G s i
e t
a 8 8 8
8 8
8 8
8 8
8 E
E 2
l
.E 3 8 8
8 8
8 8
8 8
8 8
8 8
i E s s 1 2 s
s & s s
s s
s k
g 8 8
8 8
8 8
8 8
8 8
8 8
g 8
8 8 8 8
8 8
8 8
g 8
g
^]
I s
s & & &
s i
e 8
8 4
8 8
8 8
8 8 4 8 4
s 3=Q 8 8 8
8 8
8 8
8 8
g 8
g s &
a s a s a s e i
s g
J.
8 8.8 8
8 8 8
8 8
9 8
a m
s
~
~
8 8
8 8
8 8 8 8
8 g
8 g
i s
a s s s s & s u
s 8 8 5 8 8
8 8 8
8 8
8 8
u%.3 m
m i
=4 at V
'N %
.)
s.j l 8
8 8
8 8
8 8
8 8
8 l
~
8 g S w
g (
.2 h s
c E
n 't e
k1.s-4
.4
.a 1
a
.J
.4
.1
.a 7*
3 1
.a
.a a
a
.a
.a a
g a
i y
=
w](
~
g 4 %
M a
3"%
- 4 4 :
- 's I
8 e
I n
w w
w w
w E
d 8 E R 3
~
w w
w w
w w
a g
8 8
f
~
4 5
~
4 4
s e H
a 4
E r-8 1
O b 8 0 b -O c b E 8
I s
E q d d y d d d d d
0 E
a' C
C n.
C C
C 0
0 n
e x
z 4
x.
e 3
g 4
e g
u
=
g 4
i
$" 8 4 4 4 8
8 4 8
4 8
w 2 m o a W
W W W W W W a
W 8,
e w
=
e e n
~. -
m q
g z
e z
~
~
=
e 3
S g g 5 5
- g 2 g g e
E
,t
=
- : : ~
e g
E E x E E E E E
- E E
8 7
3*
- s 4
8 8
8 s
s 8
W W W W W W W W W
W W
i g
s. *
~
.n
~.
y
-. - - ~
~.
.s e
t e 4 8 5 8 4
8 8
?
8 a
1 4 W
=
W W W
W W W W W W 8
. ~
~
,,. n
- - ~.
~ - -
- ~
E5 3
i g
n i y y 5 y $
8 5 $
8 ;
e =
w e
w w
w w
w w
w c
c 5
C 4
n R 5
% ~
5.
a i
. x - ~ - - ~ -.
y g
.I.
=
k 3 E 8 8 3 5
E E E 3 3 E h
$ 0 1 0 4 $ & G d d
1
I 3
2 0
2 0
3 0
0 0
4 0
3 1
L 0
L 0
0 0
0 0
0 0
0 4
0 0
0 E
E F
E E
E E
E E
E E
E E
+
+
+
+
+
I 0
5 0
7 0
4 0
0 0
6 0
G 0
G 5
4 0
3 0
5 0
0 0
1 0
I.
3 3
6 0
5 0
1 0
0 0
9 0
6 1
0 0
0 0
0 0
0 0
0 2
0 3
2 g
0 0
0 0
0 0
0 0
0 0
a
+
+
+
+
+
+
+
+
+
0 0
0
+
m E
E E
E E
E E
E E
E E
E E
0 0
0 0
0 0
0 0
0 I
0 0
0 0
0 0
0 0
0 7t 0
0 2
0 1
3 0
0 0
0 0
0 0
0 0
1 0
6 2
y 3
0 0
0 0
7 0
0 0
2 0
3 2
e 4
0 0
0 0
4 0
0 0
4 0
0 0
+
+
+
+
n
+
+
+
E E
E E
E E
E E
E E
E E
E
+
d i
7 0
0 0
0 4
0 0
0 6
0 0
9
)
K 1
0 0
0 0
8 0
0 0
7 0
1 4
1 m
0 0
0 0
7 0
0 0
4 0
6 5
er m
d 0
0 0
0 0
0 0
0 0
0 0
3 3
0 0
0 0
0 0
0 0
0 0
0 0
0
(
io
+
+
+
+
+
+
+
+
+
+
+
E r
e y
E E
E E
E E
E E
E E
E E
s h
3 0
0 0
0 0
0 0
0 0
0 0
0 o
T 0
0 0
0 0
0 0
0 0
0 0
1 1
D 0
0 0
0 0
0 0
0 0
0 0
6 6
y 3
2 0
2 0
7 0
0 0
2 0
3 2
d 0
4 0
0 0
0 0
0 0
0 0
0 0
o
+
+
E E
E E
E E
E
+
+
+
E E
E E
E E
B.
l 8
0 6
0 6
0 0
0 6
0 0
2 T
l.
3 0
8 0
9 0
0 0
1 6
9 0
1 1
1 3
0 2
0 5
0 0
0 2
0 3
2 0
3 0
7 0
0 0
1 0
3 1
e 0
0 0
0 0
0 0
0 r
0
+
+
+
+
+
4 0
0 0
v E
E E
E E
E E
E E
E E
E E
+
J 7
I 1
l 0
9 0
4 0
0 0
6 0
0 7
0 0
0 4
0 1
7 I.
0 6
0 3
4 1
0 9
0 8
0 0
0 1
0 6
E a
t a
0 0
0 0
0 0
0 0
1 0
0 1
M D
e 0
0 0
0 0
0 0
0 0
0 0
4 n
+
+
+
+
+
+
+
4
+
+
o E
E E
E E
E E
E E
E E
E E
5 d D
0 0
0 0
0 4
0 0
0 3
0 e
3 g
0 0
0 0
0 1
0 0
0 5
0 0
5 9 M 0
0 0
0 0
2 0
0 0
1 k
0 0
1 91 C G'
)g
)g p
l r
k a
n h k 0
0 0
0 I
i i 5
1 0
5 0
0 od
/
7 u
o s /
0 0
0 0
0 0
fe C
5 mni F C 6
0 0
5 0
8 0
0 0
7 0
7 t
9 0
6 0
3 7
5 0
P 0
5 1
a a p
8 2
6 6
3 r
3 s
p 4 A
y o
(
e r
(
4 v p n =
Mt a
t n
s o
t e
r n n x i 9 e e c tai L
L L
L L
L o
t' h
o E
igN n t
8 8
8 8
t i
s o
0 0
t r
x ic a
0 0
L 0
L 0
L L
L 8
t l
C d
0 l
a m
2 2
A 2
A 2
A A
A 2
A 2
P m e /
I n
I I l
n G
u c
h n
p
=
m o
0 0
0 0
0 0
0 M
E E
E m
)
s 1
1 6
5 5
5 6
5 5
6 6
5 7
m ii C
4 1
0 0
r F x x
8 l
E E
E E
E E
E E
E 0
0 e
a 4
I 9
M.
7 9
4 6
6 5
0 9
2 0
(
8 8
3 1
2 6
4 7
6 1
3 t
)
mM d
=
C n
8 2
2 6
1 2
1 2
1 4
2 e
o e
l t
l s
i tm r
e C A
t.
A A
A A
A i
f g
p T
m 6
T T
T T
T 5
5 8
7 n
g e
i 9 n
0 A
A A
A A
4 0
0 0
m A
o E
D D
D D
D E
E E
E C
o C
0 m
D s
i 4
7 7
4 3
O O
7 O
O O
O O
2 6
3 0
e I
p r r
D N
N 7
N N
N N
N 4
3 4
2 es
/ o o
m t
D t
c c
e a
a A
A A
r F
m F
y 6
T T
T 5
9 8
5 4
4 8
7 e
4 A
A A
0 0
0 4
0 0
0 0
(
n n
E D
D D
E E
E E
E E
E E
r o
e i
0 0
3 5
4 9
2 7
3 d
s o i o
K 0
O O
O 3
2 6
8 1
0 3
0 t
t a
c l
D 3
N N
N 2
8 3
2 1
1 2
2 a
u F
m no A
A A
A A
A A
A A
A e
u i
d T
T T
T T
T T
3 T
T T
7 c
t c
s oo A
A A
A A
A A
0 h
r A
A A
0-a e
D D
D D
D D
D E
D D
D E
y o
g h
O O
O O
O O
O 7
O O
O 0
t 2
3 x i n
T i
N N
N N
N N
N 5
N N
N 2
l I
)g x
k l
(
/
y 6
6 5
5 5
9 8
6 5
5 6
7 e
Ci d
0 0
0 0
0 0
0 0
4 0
0 0
g o
E E
E E
E E
E E
E E
E E
p B.
a 5
t 3
6 7
6 7
3 0
2 5
3 s
r U
e g
T 8
S.
3 5
2 2
2 8
1 6
8 0
L 6
2 9
8 4
4 2
2 5
1 1
t k
=
a W
)
m 9
5 6
5 6
5 9
8 5
4 4
8 7
e c
e E
E E
E E
E E
E E
E E
e 6 r
0 0
0 a
v E
0 0
0 0
0 0
0 0
0 r
m f
J 7
O 7
9 5
6 5
3 4
1 2
0 3
8 3
(
r I
0 N.
6 2
6 7
5 7
0 u
I 1
2 5
3 8
2 1
3 3
7 2
y S mw =
h h
t W
a A
I 0
=
T
'A A
A l'
5 T
5 8
7 5
4 4
5 0
0 T
e A
A A
p 0
0 0
0
)
h in r
n A
a o
D D
E D
E E
E E
E E
E D
s e
B O
O 6
O 3
2 1
7 3
2 3
O 5
7 5
6 2
4 7
1 i m y
F s
ne N
N 1
N 1
2 1
1 2
3 8
N m i o
t o
ar n
r f
t i
e n
k e
e e
t l
4 8
9 0
5 5
5 1
a d
h cn ic i
0 4
x 4
7 1
t o
(
i 5
5 5
6 6
9 9
31 1
1 3
3 3
n n
e e
0 n
b r
a o
l C e i M C
F 0
Z N
Z 1
C C
a I
t i
3 a
d s
s l
I i
g t
a B
s O
U R
1 1
i i
f 1
Dosefrom Shoreline Sediment Pathwayfor 1995 Data Maximum Exposed Child Shoreline Recreation =
14 hr(in one year)
Shore Width Factor =
0.2 Sediment Surface Mass =
40 kg/m2 Child Dose from Shorline Sedhnent Pathway (mrem) = Sherline Recreation (hr) x External l
Dose Factor (mrent'hr per pCL'm2) x Shore Width Factor x Sediment Surface Mass (kg/m2) x Sediment Concentration (pC1/kg)
External Dose Factor Standing Highest AnnualNet Dose on Contaminated Ground Mean Concentration I
(mrentiir per pC1/m2)
Indicator Sediment (mrem) i Radionuclide T. Body Skin Location (pCitg)
T. Body Skin Ma-54 5,80LO9 6.80E-09 208-2S 122.27 7.94E-05 9.31 E-05 Co-58 7.00E-09 8.20 E-09 208-2S 1326.43 1.04E-03 1.22 E-03 i
Fe-59 8.00E-09 9.40E-09 ALL 0.00 0.00E+00 0.00E+00 Co-60 1.70E-08 2.00E-08 208-2S 944.33 1.80E-03 2.12 E-03 Zn~65 4.00E-09 4.60E-09 ALL 0.00 0.00E+00 0.00E+00 Nb-95 5.10E-09 6.00LO9 208-2S 113.00 6.45E-05 7.59E-05 Zr-95 5.00E-09 5.80LO9 ALL 0.00 0.00E+00 0.00E+00 i
l I-131 2.80E-09 3.40E-09 ALL 0.00 0.00E+00 0.00E+00 I
Cs-134 1.20E-08 1st0E-08 ALL 0.00 0.00E+00 0.00E+00 Cs-137 4.20E-09 4.90E-09 208-1S 85.00 4.00E-05 4.66E-05 BaLa-140 2.10E-09 2.40E-09 ALL 0.00 0.00E+00 0.00E+00
- Sb-125 3.10E 09 3.50E-09 208-3S 148.45 5.15E-05 5.82 E-05
- Co-57 9.10L10 1.00E-09 208-2S 36.90 3.76E-06 4.13 E-06
- Sn-113 1.90 E-09 2.20E-09 208-2S 71.10 1.51 E-05 1.75E-05 i
i Dose Commitment (mrem) =
3.09E-03 3.63 E-03 i
- Dose Factors from Reference 6.11 i
I I I 8 I I
.I. I I I I ?
8 w
w w
w w
w x
x w
w w
w U 8 8 8 8 8 8 $
8 8 8 8
.I 8 8 I 8 8 8 y 8 $ 8 g g
w
& a i
1 i s w
5*
w
& w w
8 8 8 8 8 8 8 8 8
=
a a
I I I I I I I I I I I ?
?
3f5 5 i i i i 1 5 i i i E E
E
- * * * * * * * * * * ~
~
t 8
'1 1 g 8 g g g 8 g 8 8 g a s
=
x w
w w
a w
I &
w s
e g 8 8 8 8 8 8 8 8 8 8 8 :
{ $ $ $ 8 8 8 8 8 $ 8 8 3 I
w w
w I & 1 1 &
w 1 i e s
p 8 4 8 8 8 8 8 8 8 8 8
f 8 8 8 8 8 8 8 8 g 8 a
s m
2 1 c s s c c w
c e
E 8 8 8 8 I.* 8 0 8 8 8 8 8 :
=
4 R
8 8 { $ $ $ 8 8 8 $ 8 $
8 I
e =
I & a w
w w
w
& 1 I w
I w
I l
- 8 8 8 8 8 8 8 8 8 8 8 8 8
\\
i
.. e s uAO 1
_g 3 1 s.,
g*
I i
i lE 2 8 8 8 8 8 8 8 8 8 8 $
g 3st.
<:.2 )
a w
1
- EA m
g f
k$l 3j 4 4 4
-4 4 a 4
! 4 4 4
=
u jg E 7 E E 7 4 a 1 1 7 q =
A4,
w 3E 7
ne w$
4 4 E 4 4 4 % 5 8 8 4 3 5 l
5*
.5 5 : 4 8 8 E 8 0 4 8,
8 L
- w w
w w
g w
w w
w w
w w 1
g
- - - ~ ~
'l y 4 4 4 4 4 4 4 4 E E 3 S l
w
. = m w
= m e
w y
w w
v E
a e e 4 e e e o e A 8 8 E
r
=
x z, z z z z z a a w a J
r 0
A 5
I I D @ N 4 8 8 I 4 6 8 5 b
u t
a 5 d = c W M,
5 5,
W
'A t =
- o a
e e - e ~
~. - 8 q
_3-6
- z z z a
a a
1 i
< r < <
5 1 % 9 % % % % % 4 % %
%< 4 L
A e a = = m a a w
m
w y
g 1 a e e e e e 8i e c e 8 ag z z z z z z ~ z z z.
i B
2" 4 8 4 4 4 5 $ 4 :
8 5 s
2
- W W
,h 4 5 W W -
e-W W W 8
a p m ~ m
=
m.
- ~..
~
m n
1 2
8 : E 8 E 8 8 8 8 8 8 E l
I
'
- k 5 8
,% i t i # $
a 8 g e
a a
+ -
y a e a a a, -
1 Su 4 4 4 8 8 8 8 4 8 5 0-j i
}4 2 W = 5 N n d W
-W W =
=x
.. n ~ - =,
. e
=
~.
.e z. z..... - ~ z I
E*
^
5 3
i.
'i 8 F 8 8 :
.F E :: 5 5 4 e
j 9
5 c
w v
s z
s
- c c 5 -
=
=
g
-3 e
a s
8 8 8 { 8 { 8 8 8 8 {
8 I i i w
I w
1 1 I w
w w
G 8 8 8 8 8 8 8 8 8 4 8 4
s e
y I I I I I I I I I ? I
?
w w
w w
w w
w w
w w
w w
a 8 8 8 8 8 8 8 8 8 R 8 R
s...
4 s
F I I I I I I I I I ? I 8
.I-w w
w w
w w
w w
w w
w 3
8 8 8 8 8 8 8 8 E 8 E
a
.. s e
s -
y t
E
] 8 { 8 { 8 8 3 2 % 8 $
8 x 1 w
I w
i i i i i i w
I c 8 8 E. - 8 8 8 8 8 8 8 8 8
e s s
s s s a
y { { 8 8 8 8 { 8 { s 8 a
w w
I i 1 I w
I w
e I w
g 8 8 8 8 8 8 8 8 8 6 8 8
i 1
t I I I I I ! I I I ? I
?
w w
w w
w w
w w
w w
w w
8 8 8 8 8 8 8 8 8 8.i s
s 3*
I 8 I I I I I I I ? I
?
A i
w w
w w
w w
w w
w w
w w
= 8 8 8 8 8 8 8 8 8 8 8 8,
m =
- s. s s
- . s a
% g 6
)
Ei*2g
.8 8 8 8 8 8 8 8 8 3 s% g, q
gge i
<25
+
%p e m I
- t
- t
-E
$ z j.3 g l
gt 4 d 4 d d d 4 d d s d" 1
q a < a < < < a < < ~
e=,, E 3
a.
g 1
0
- i 4 44 4 8 8 8 8 4 8 4 l
m
.n.
- * * = W
=
w
- W W W 8
8 8 e
n n ~
5
-1 m,
g m
-. ~
m
- ~
n n
g h
I' h!4 $$$$h4 4 8 l
=
y r
. = c y = = = = c y y y u
c-t e e e
e e e e e n.
e a
m z z, x z z z z a
W e
m
~g u
=
t E
5 4 4 % % 4 8 8 8 8 4 5 g
r s 5 : = = W W 5
,5 W W W y
a e
e e a
l g
y J
z z z a w
e 4
- i a
E 5
1 % % % 4 % %
4 % % %
e 1
x o a a a = c 2 y = m e
~
w g e e o e e e e n o e e
=
z e z z z z z
a z
z z N
E i 8 8 8 4 8 3 5 4 4 4 4
= W W W W W 5 W W W W W x
g
- ~ ~
e n
- ~... ~
m E
8 4 8 8 8 4 8 8 4 4 4 4
S
- W E W W W W W W W E,
8 F n * * =, n.- e *
- n
~
M S
l k
Y d
- 5 W D E
.s, d 4 8,
5 I.
- a e
e r
z z
. x M
T s
M M
i i
=
e.
a e
e g
4 E
6 a
4 9
g og
- 2 6
w 4
N, z
N
=
g y
- i e
3 3
=
+
w
t
.t' 4o I
}
y 7
. i ;*
l tI t
C J
0 0
0 0
0 0
0 0
0 3
0 3
0 0
0 0
0 0
0 0
0 4
0 I.
+
+
+
+
+
+
+
+
+
+
4 l
E E
E E
E E
E E
E E
E E
i 0
0 0
0 0
0 0
0 0
1 0
2 0
3 G
0 0
0 0
0 0
0 0
0 2
0 0
0 0
0 0
0 0
0 3
0 3
0 0
0 0
0 0
0 0
0 2
0 2
g 0
0 0
0 0
0 0
0 0
0 0
0 n
+
+
+
+
+
+
+
+
+
+
m E
E E
E E
E E
E E
E E
E 0
0 0
0 0
0 0
0 0
0 0
8 I
0 0
0 0
0 0
0 0
0 9
0 9
0 0
0 0
0 0
0 0
0 2
0 2
0 0
0 0
0 0
0 0
0 2
0 2
ye 0
0 0
0 0
0 0
0 0
0 0
0 n
+
+
+
+
+
+
+
+
+
+
i E
E E
E E
E E
E E
E E
E d
0 0
0 0
0 0
0 0
0 7
0 7
K 0
0 0
0 0
0 0
0 0
6 0
6
)
m 0
0 0
0 0
0 0
0 0
7 0
7 e
r m
d 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0
(
io
+
+
+
+
+
+
+
+
+
+
+
+
r E
E E
E E
E E
E E
E E
E e
y s
h 0
0 0
0 0
0 0
0 0
0 0
0 o
T 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 D
y 0
0 0
0 0
0 0
0 0
2 0
2 d
0 0
0 0
0 0
0 0
0 0
0 0
e
+
+
+
+
+
+
+
+
+
+
E E
E E
E E
E E
E E
E E
B.
0 0
0 0
0 0
0 0
0 5
0 5
T 0
0 0
0 0
0 0
0 0
8 0
8 0
0 0
0 0
0 0
0 0
7 0
7 a
ta 0
0 0
0 0
0 0
0 0
1 0
1 D
r 0
0 1
9 0
0 0
0 0
0 0
0 e
+
4
+
E E
E E
E E
E E
+
+
+
+
+
+
v E
E E
F S
J 0
0 0
d 0
0 0
0 0
5 0
5 I
9 0
0 0
u 0
0 0
0 0
2 0
2 9
0 0
0 0
0 0
0 0
0 2
0 2
1 r
0 0
0 0
0 0
0 0
0 1
0 l
o e
0 0
0 0
0 0
0 0
0 0
0 e
fn l
E E
E F
E E
E E
E E
E E
n
+
+
+
+
+
+
4
+
+
+
e e
)
0 0
0 0
0 0
0 0
0 9
0 9
y e g
0 0
0 0
0 0
0 0
0 6,
0 6
I a T k
0 0
0 0
0 0
0 0
0 1
0 1
w i/
h d C
t e
p l
)
(
a n
d r a s n
u o
ely 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 P o o
n ni e g n x a
Ai r
(
0 0
0 0
0 0
0 0
0 6
t Fk p
n a a 3
0 i
t c
t r
t h n oE tn e e c o
s t
e r n L
L.
L L.
I L.
L.
L L
it e
h o
a m e u o
ig N n ta i l
L c
t l
n o
i c 1
g m C
l C d o A
A I
L I
L I
IA A
2 A
c a L
0 L
t A
A A
A A
I InL e
i x
=
V x
)
)
d e
I 5
5 5
5 6
5 5
6 6
6 5
n fa e
L.
0 0
0 0
4 4
4 0
0 0
0 e
M t
r a
s l
E E
E E
E E
E E
E E
E m
e 1
4 4
6 7
5 0
2 5
2 8
(
e g
i 2
3 2
6 4
9 0
6 4
1 3
t G
l n
1 1
3 3
8 1
3 I
2 2
4 en d
i a
tm i
o C
A A
A A
A A
A i
m p
T T
6 T
T T
T T
5 5
8 r
/
g A
A A
A A
A A
4 0
0 m
0 o
B m
n e
m D
D E
D D
D D
D E
E E
C 2
9 7
4 m
m r
I O
O 3
O O
O O
O 3
9 3
e r
N N
4 N
N N
N N
2 1
2 e
s o
(
o D
t r
r c
f o
a A
A A
e c
F y
6 T
T T
5 9
8 5
5 5
8 t
e 4
A A
A 0
0 4
0 0
0 4
a n
E D
D D
E E
E E
E E
E e
d s
F s
i 7
O O
O 2
4 9
4 2
0 1
6 8
2 1
3 6
7 8
o e
o K
D D
1 N
N N
1 4
1 1
6 5
1 so D
n o
A A
A A
A A
A A
A A
x i
i A
A A
A A
A A
A A
A
)
t d
T T
T T
T T
T 3
T T
T s
o 0
g e
y D
D D
D D
D D
E D
D D
r k
c h
O O
O O
O O
O 3
O O
O 9
(
n T
N N
N N
N N
N 2
N N
N e
I g
asU y
e0" 6
6 6
6 9
9 6
5 5
6 d
0 0
0 0
0 0
=
l E
E E
E E
E 0
0 0
0 o
)
I.
7 4
9 3
3 3
E E
E E
F 4
0 4
9 3
m T
1 2
2 3
3 5
9 4
1 1
8 g
1 2
5 6
9 2
8 4
9 5
8 e
k r
m
(
2 6
7 5
6 5
9 8
6 4
4 8
4 y
r 0
0 0
0 6
a e
E 0
0 0
4 0
0 v
E E
E w
i 0
2 7
1 E
E E
E E
E E
0 6
0 9
7 9
8 L
h 9
7 3
8 0
5 3
1 9
4 4
t 5
9 1
2 2
4 1
8 1
1 3
aP no A
A A
i
=
T T
6 T
6 9
8 6
5 4
5 ta A
A 0
0 e
A 0
0 0
0 0
0 t
)
n e
ra o
D D
E D
E E
E E
E E
E g
i 7
6 2
2 2
4 e
y l
O o
8 O
7 2
3 5
7 l
8 e
8 3
V e
N h
5 N
5 8
4 5
8 l
2 n
m e
r in o
f e
k e
e a
d e
o n
i 4
7 d
s t
l 4
8 9
0 5
5 5
1 3
3 l
cu 5
5 D
i(
5 6
6 9
9 3
n a
e e
o a
h r
1 1
1 a.
s s
e e
n g
i M C
F C
Z N
I l
C C
t e
a d
s a
i e
s l
R T
U
J 2
1 0
1 0
3 0
0 0
3 0
3 1
L E
0 0
I E
0 0
0 0
0 0
4 0
0 0
0
+
+
+
+
+
+
l 9
t E
E E
E E
E E
E E
E Et 0
5 0
1 0
0 0
3 0
J 7
0 0
0 0
0 9
C 0
9 0
5 0
3 1
1 0
1 0
4 0
0 0
2 0
7 3
0 0
0 0
0 0
0 0
0 2
0 3
2 g
0 0
0 0
0 0
0 0
4 0
0 4
4
+
+
+
+
+
+
+
+
+
m0E E
E E
E E
E E
E E
E E
E 0
0 0
0 0
0 0
0 3
0 9
7 I
0 0
0 0
0 0
0 0
0 1
0 3
s.
0 0
0 0
0 0
0 0
0 2
0 7
2 y
3 0
0 e
0 7
0 0
e 2
0 3
2 4
0 0
e 0
0 0
0 e
0 e
e.
0 e
+
+
+
+
+
+
+
+
n d
E E
E E
E E
E E
E E
E E
E i
9 0
0 0
0 6
0 0
0 9
0 9
9 E
5 0
0 0
0 7
0 0
0 4
0 3
3
)
m 0
0 0
0 9
0 0
0 5
0 7
6 1
er
(
ld 9
0 0
0 0
0 0
e 0
0 0
3 3
m e
0 0
0 0
0 0
e 0
0 0
4 4
e
+
+
+
+
+
+
+
+
+
r E
E E
E E
E E
E E
E E
E E
e y
s h
0 0
0 0
0 0
0 0
0 0
0 9
9 o
T 0
0 0
0 0
0 0
0 0
0 0
3 3
D 0
0 0
0 0
0 0
0 0
0 0
7 7
y 3
2 0
2 0
7 0
0 0
2 0
3 1
d 0
0 0
0 0
4 0
0 0
0 0
0 8
E
+
+
+
+
+
+
o E
E E
E E
E E
E E
E E
E B.
6 9
0 9
0 4
0 0
0 2
0 9
3 0
1 0
6 0
5 0
0 0
6 0
3 2
T 1
3 0
2 0
5 0
0 0
5 0
7 1
3 2
9 2
O 6
0 0
0 1
0 3
1 r
4 0
4 4
G 0
0 0
0 0
0 0
0 e
+
+
+
+
+
+
v E
E E
E E
E J
3 0
0 9
0 1
E E
E E
E E
E 0
0 0
t 0
9 0
I 3
3 0
I.
0 0
0 0
0 6
0 3
0 5
1 0
3 0
1 0
0 0
1 0
7 2
a t
a 0
0 0
0 0
6 0
0 0
1 0
0 4
0 0
1 D
e 0
0 0
0 0
0 n
+
+
+
+
+
0 0
6 0
+
+
+
+
+
e E
E E
E E
E E
E E
E 5
B 0
0 0
0 0
t 0
0 0
t E
E E
0 0
t 9 n 0
0 0
0 0
S.
0 0
0 2
0 0
2 9 e 0
0 0
0 0
1 0
0 0
1 0
0 1
e g
1 T
h r
L l
)g 0
0 0
od a
nh k 0
C u
o i /
5 1
0 5
0 0
0 0
0 0
0 0
g p
n ni FCi 6
0 0
5 0
3 0
0 0
1 0
7
)
s fe 3
t 9
0 6
6 0
0 0
7 7
n a a p
8 2
6 0
5 5
1 3
s yo e r
(
4 L
5 A
a C
3 Mt n
wp t
p 4 s
e r n t
x
=
h
(
e e c t
i 8
8 e o n
N n h E o 9 ig a
L L.
8 L
L L
L, c
t 0
0 L
0 0
L L
I 0
l 0
8 0
8 t
o i o a
C d
2 2
A 2
I 2
A 4
A 2
A 2
i a
c A
t 0
f P m a
I InL r
x
=
u n
L
)
t 1
h e
m s m c C i
4 0
ii n
p J
5 5
5 5
6 5
5 M M 0
0 r
6 5
7 e
F x o
J 4
0 0
0 0
m 1
I E
E E
E E
E E
E E
E E
E
(
a C
4 l
1 3
2 6
4 9
0 6
4 1
3 9
t 4
4 6
7 5
0 2
5 2
S 6
8 mM x
C 2
n 4
1 1
3 3
S i
3 t
2 2
4 1
ie
)
o d
=
ita r
e l
A A
A A
A A
A n
f O
t a
T T
6 T
T T
T T
S 5
8 7
i se g
A A
0 A
A A
A A
C 0
8 0
m e
g P
n o
n o
D D
E D
D D
D D
E E
E E
C s
i 9 L
O O
3 O
O O
O O
3 9
3 0
s 2
9 7
4 6
o
)
e D
u0 N
N 4
N N
N N
N 2
1 2
1 e
ro D
r p
t
/ o ca A
A A
m tc e
a F
y 6
T T
T 5
9 8
5 5
5 S
7 e
0 A
A A
4 0
0 0
0 0
O 0
r F
n E
D D
D E
E E
t 6
7 8
6 e
d m n s
6 7
O O
O 2
4 9t E
E E
E E
6 9
2 o
o K
4 2
0 1
0
(
o i D
r t
N N
N 1
4 1
1 6
5 1
1 ta t
l n
c u
a o
A A
A A
A A
A A
A A
F m
i di T
T T
T T
T T
3 T
T T
7 t
0 A
A A
0 u
s o
A A
A A
A A
A D
D D
E e
r D
D D
D D
D D
E c
e y
s o
c e
h O
O O
O O
O O
3 O
O O
9 9
6 ao n
T D i i
N N
N N
N N
N 2
N N
N 1
l I
)g x
y 6
6 M
M 4
4 0
0 0
0 0
6 9
9 6
5 5
6 7
k I
d 0
0 0
W
(
o E
E E
E E
E E
E E
E E
E e
B.
7 4
9 3
3 1
4 0
4 9
3 6
g p
a T
1 2
2 3
3 5
9 4
I.
1 8
0 s
r g
1 2
5 6
9 2
8 4
9 5
1 1
U e
k ta
=
W 6 6
7 5
6 5
9 8
4 4
8 7
e c
v E
E E
E 4
0 N
0 0
0
)
1 m e e
0 4
0 0
0 E
r 0
r a
J 0
2 7
t E
E E
E E
E'9 E
0 6
0 9
7 A
6 9
7 3
8 0
5 3
1 9
4 4
0 f
I m
r 5
9 t
2 2
4 1
9 1
1 3
1
(
u y S aw =
h h
A A
A A
t
)
e A
A a
=
T T
M M
0 0
M 9
9 5
4 5
T 0
0 T
A P
I s
A r
n n
a o
D D
E D
E E
E E
E E
E D
h i y
7 6
2 2
5 7
2 4
e B
O O
8 O
7 2
I.
9 3
1 8
O s
n N
N 5
N 5
E 4
5 8
1 2
N iF i o
e o
n m
t a
a o
r r
t l
e f
n k
e d
e e
ta t
4 9
9 0
5 5
5 1
s c
0
~
o n n
i 4
7 4
cu 5
3 3
1
)
o 6(
m 5
4 4
9 9
3 5
r 1
1 3
e e
m b
1 e.
I 1
n g
i in C
e e
C C
t l
s s
e 3 a
d h
C F
C 7
N Z
1 a
a B
e s
T
- U R
I I
,iliIllll l(,
l Dosefrom Shoreline Sediment Pathwayfor 1995 Data Maximum Exposed Teen i
i 1
Shoreline Recreation =
67 hr(in one year)
Shore Width Factor =
0.2 Sediment Surface Mass =
40 kg/m2 Teen Dose from Shorline Sediment Pathway (mrem) = Shortine Recreation (hr) x External Dose Factor (mrem /hr per PCkm2) x Shore Width Factor Sediment Surface Mass (kg/m2) x Sediment Concentration (pCLkg)
External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration (nmm/hr per pCFm2)
Indicator Sediment (mrem)
Radionuclide T. Body Skin Location (pCVkg)
T. Body Skin Mn-54 5.80E-09 6.80E-09 208-2S 122.27 3.80E-04 4.46E44 Co-58 7.00E-09 8.20E-09 208-2S 1326.43 4.98E-03 5.83 E-03 Fe-59 8.00E-09 9.40E-09 ALL 0.00 0.00E+00 0.00E+00 Co.60 1.70E 08 2.00E-08 208-2S 944.33 8.60E-03 1.01E-02 Zn 65 4.00E-09 4.60E-09 ALL 0.00
').00E+00 0.00E+00 N b-79 5.10E-09 6.00E-09 208-2S 113.00 3.09E-04 3.63 E-04 Zr-95 5.00E-09 5.80E-09 ALL 0.00 0.00E+00 0.00E+00 1 131 2.80E-09 3.40E-09 ALL 0.00 0.00E+00 0.00E+00 l
Cs-134 1.20E-08 1.40E-08 ALL 0.00 0.00E+00 0.00E+00 Cs-137 4.20E-09 4.90E-09 208-1S 85.00 1.91E-04 2.23 E-04 BaLa-140 2.10E-09 2.40E-09 ALL 0.00 0.00E+00 0.00E+00
- S b-125 3.10E-09 3.50E-09 208-3S 148.45 2.47E-04 2.78E-04
- Co.57 9.1 E-10 1E-09 208-2S 36.90 1.80E-05 1.98E-05
- Sn.113 1.9E-09 2.2 E-09 208-2S 71.10 7.24 E-05 8.38E-05 Dose Commitment (mrem) =
1.48 E-02 1.74 E-02
' Dose Factors from Reference 611 1
a 0
0 0
0 0
0 0
0 0
0 0
2 2
J 0
0 0
0 0
0 0
0 0
0 0
0 0
J
+
+
+
+
+
+
+
+
+
E l
E E
E E
E E
E E
E E
E E
l 0
0 0
0 0
0 0
0 0
0 0
9 9
C 0
0 0
0 0
0 0
0 0
0 0
5 5
0 0
0 0
0 0
0 0
0 0
0 1
1 0
0 0
0 0
0 0
0 0
0 0
2 2
g 0
0 0
0 0
0 0
0 0
0 0
4 0
a
+
+
+
+
+
+
+
+
+
+
m.
E E
E E
E E
E E
E E
E E
E 0
0 0
0 0
0 0
0 0
0 0
9 9
1 0
0 0
0 0
0 0
0 0
0 0
5 5
0 0
0 0
0 0
0 0
0 0
0 1
1 0
0 0
0 0
0 0
0 0
0 0
2 2
y 0
0 0
0 0
0 0
0 0
0 0
0 0
en
+
+
+
+
+
+
+
+
+
+
di E
E E
E E
E E
E E
E E
E E
0 0
0 0
0 0
0 0
0 0
0 9
9 i
K 0
0 0
0 0
0 0
0 0
0 0
5 5
)
0 0
0 0
0 0
0 0
0 0
0 1
1 ner m
d
(
i 0
0 0
0 0
0 0
0 0
0 0
2 2
0 0
0 0
0 0
0 0
0 0
0 0
0 o
+
+
+
+
+
4
+
+
r E
E E
F F
E E
E E
E E
E E
e y
s h
0 0
0 0
c 0
0 0
0 0
0 9
9 0
0 0
0 0
0 0
0 0
0 0
5 5
o T
D 0
0 0
0 0
0 0
0 0
0 0
1 1
y 0
0 0
0 0
0 0
0 0
0 0
2 2
d 0
0 0
0 0
0 0
0 0
0 0
0 0
o
+
+
+
+
+
+
4
+
+
E E
E E
E E
E E
E E
E E
E B.
0 0
0 0
0 0
0 0
0 0
0 9
9 T
0 0
0 0
0 0
0 0
0 0
0 5
5 0
0 0
0 0
0 0
0 0
0 0
1 1
0 0
0 0
0 0
0 0
0 0
0 2
2 r
0 0
0 0
0 0
0 0
0 0
0 0
e
+
+
+
+
+
+
+
+
+
+
+
4 a
i E
E E
E E
E F
E E
E E
E E
v t
L 0
0 0
0 0
0 0
0 0
0 0
9 9
0 0
0 0
0 0
0 0
0 0
0 5
5 a
0 0
0 0
0 0
0 0
0 0
1 1
0 D
5 0
0 0
0 0
0 0
0 0
0 0
0 0
e 0
0 0
0 0
0 0
0 0
0 0
0 0
9 t
n
+
+
+
+
+
+
+
+
+
+
+
+
l 9
o E
E E
E E
E E
E E
E E
E E
u d
I)
B 0
0 0
0 0
0 0
0 0
0 0
0 0
1 0
0 0
0 0
0 0
0 0
0 0
0 0
r T
0 0
0 0
0 0
0 0
0 0
0 0
0 oA
(
p fd l
n
(
r 1)
/
0 n
a ye i
a n i Wlp 0
0 0
0 0
0 0
0 0
0 0
e l
0 0
0 0
0 0
0 0
0 0
0 0
o u
o tac 0
0 0
0 0
0 0
0 0
0 0
7 ws t
n a a 2
o t
n a
p e r r
A h x n
t Mtn t
taE e
s e
r s t
c e e c ta i L.
L.
L t
J L
L I.
1 o e l
I.
4 P
n h
o ig N n ta L
L l
J m
o i
L L
l c
C l
Cd m lA IA A
IA A
A A
A A
IA A
2 l
re u I
u s
l I ta m
=
)d
)
Wi n
e a
x t
I 5
5 5
5 M
4 M
4 0
0 0
r 5
5 6
6 5
7 e
s L
0 4
0 0
0 m
a e
o g
g L
E E
E E
E E
E E
E E
E E
(
nM n
0 2
0 0
9 7
9 l
B 5
t i
i I
0 1
4 0
7 1
0 5
5 l.
t 0
n G
4 5
e l
1 I
3 4
9 2
3 1
2 2
4 1
m k
C i
s n
p t
i A
A A
A A
A A
a
/
e r
m T
T M
T T
T T
T 5
5 8
7 sm g
A A
A A
A A
A 0
0 0
0 o
D i
L O
O 8
O O
O O
O 5
2 4
0 s
e n
r o
D D
E D
D D
D D
E E
E E
C 5
9 3
6 5
n e
m
(
r N
N 2
N N
N N
N 1
1 1
1 e
r o
D o
o t
r t
c c
a A
A A
f a
F y
6 T
T T
5 9
0 5
5 5
9 7
e 0
A A
A E
E E
E E
E E
0 0
n 0
0 0
0 4
0 e
F E
D D
D E
s e
e d
o s
s i
3 O
O O
0 4
5 0
7 7
6 0
6 3
2 3
2 9
0 7
o o
K 3
1 1
4 3
0 1
D D
D 1
N N
N 1
x m
(
a A
A A
A A
A A
A A
A
)
1 i
d T
T T
T T
T T
3 T
T T
7 e
s i
A A
A A
A A
A 0
A A
A 0
t e
r D
D D
D D
D D
E D
D D
E g
e 3
5 5
a c
h o
O O
O O
O O
9 O
O O
0 s
n T
U N
N N
N N
N N
N N
N 1
1 i
=
)
m d
0 m M E
E E
E E
E E
E y
7 6
6 9
9 6
4 5
6 7
0 4
0 E
E E
E 0
0 0
0 0
0 r
o e
B.
2 7
t 2
6 6
0 t
4 3
5 i
T 7
6 9
7 9
S 6
t 2
1 3
9 n
4
(
0 1
3 4
6 I
6 3
1 7
1 1
y t
a w
0 6
7 5
6 5
9 9
6 4
4 0
7 h
3 r
0 4
0 0
0 0
0 0
0 0
4 0
t 7
e E
E E
E E
E E
E E
E E
E a
h P
I 5
4 0
1 1
3 9
5 1
1 2
1 7
5 2
4 4
6 5
5 8
9 5
5 r
5 4
7 9
4 9
5 0
e 4
7 i
2 ta W
g A
A A
A n
=
T T
M T
6 9
8 6
5 5
5 T
d e
A A
a e
D D
E D
0 0
0 0
0 s
0 0
A i
)
n r
m E
E t
K E
E E
D 4
4 2
4 6
2 7
3 i
e B
O O
3 O
8 2
0 1
2 9
0 O
r y
)
1 e
N N
4 N
4 6
3 4
6 7
2 N
n i
o no n
f i
r e
k e
e d
s en l
4 7
4 i
0 o
6 c
4 8
9 0
5 5
5 1
3 3
D
(
u 5
5 5
6 6
9 9
1 1
1 1
3 n
o 3
n t
e i
te o
e e
n b
r s.
1 i
g C
C t
5 s
s i
a d
S C
F C
I N
Z 1
a d
s te B
A U
I a+
m 8
8
?
8 8
8 8
8 8
8, I
9 "4
,=
=
w
=
=
x w
w a
=
w w
5 8 3
8
.E 8
4 8
8 8-Q 3
8 y I
?
?
I I.
?
e i
2 w
w w
w w
w w
w w
w
=
=
3 8
8 8
8 8 -.
8 8
8 4
8 E
w m
n
- e. { 8 8 8
g 8
?
8 8
8 8
9 W
w w
w w
w
=
x w
w w
w 3
8 8 8 8
8 8
8 8
8 8
8 a
3 6
e 8
8 8
8 8
8
?
E
'l w.
8 8
8 I
?
w w
w w
w w
w w
=
=
w 8
s 8 8 8
8 8
8
.?
8 8
3 5
8 1
]
g 8 8
8 8 8
8 8
8
~
?
\\
+
+
w w
w w
=
w w
=
w w
a
=
g w 8 4
4 8
8 8
4 8
8 8
8 a
s t
?
I T I
T
?
e
?
s
?
w w
w w
w w
a w
w w
w j
2 8
8 8 8 8 8
8 8
8 E
.E 0
1 n
tk q
A g
?
?
?
?
9
?
s' y
w w
w w
w w
w w
w a
w n
=
~
m ~-
8 8
8 8
8 8
8 8
8 8
s
~
1 A
2 n
a
- 1! -
e e
.I eg
=
2 -?
Kg g g *g 2g e.
1 e
.m l
t C E
J~ E.
1 i
+
IE e
4 E
,u a $. li. -i
.i. 4 4 -i -i -i i -i 4
.I
.=
Ly3 3
g n
- u 5
1 CE 8
m e
e e
9 9
e a
e c
I 4
y x
w w
w w
w w
w w
w 5
8 E
,8 8,
E.
E 8
4 8
~ wE 5
w E
i
~
~
~
e e
=
E b
y E E I E E E
E E I
I E
,i g
=
w
c c =
w w
w c
R C
C 8
C C
C C
C 8
4 I
v w
a z n
a z
z z
a a
C.
.C.
C 3
w e
m e
e e
e e
e e
e w
6 g
=
9 e
e a
e a
E w
= c w
w w
w w
w w
o 3g 4
C C
C Q
2 8
8
.G i
t 3
x z a e
a a
w n
pa
=
w r
e 5
1 g
9 A
C C
2 C
C C
O
8 w
2 O
C A
M f
C C
C C
C C
C 8
C C
C
.C, E
4 4
E 4
E 4
a Y.
E E
M A
b Y
Y T
m I
e e
w w
w w
w w
a w
w w
w d
6, I
=
n 5
n m
e e
w w
e 6
m t
9 9
e 9
e e
e e
b s
W W
w w
w w
w w
w w
w 6
9 e
m g
g e
e e
a e
m
.N m
n m
w n.
e w
we 1
i x
w e
N m
e M
a j
.$c L
I 8
8 8
g e
i d d s d,
w s
s x
e s
w a
n w
n L
C C
m a
n
.e n
n m
n e
o f.
4 7
w 4
w 4
m n
e e6 a
4-s e
s y
e s
E I 8 8 8 8
8 8
8 N
8 3
,t 5,
,.I $d d d
d d 2 3h$
3 x
x
-~
t 4
s e
0 0
0 0
0 0
0 0
0 3
0 3
J 0
0 0
0 0
0 0
0 0
0 0
0 I
+
+
+
+
+
+
+
+
L E
E E
E E
E E
E E
E E
F.
I 0
0 0
0 0
0 0
0 0
6 0
6 C
0 0
0 0
0 0
0 0
0 8
0 8
0 0
0 0
0 0
0 0
0 4
0 4
0 0
0 0
0 0
0 0
0 2
0 2
g 0
0 0
0 0
4 0
0 0
0 0
0 n
+
+
+
+
+
+
+
+
+
E E
+
E E
E E
E E
E E
E E
a 0
0 0
0 0
0 0
0 0
3 0
3 l
0 0
0 0
0 0
0 0
0 8
0 8
0 0
0 0
0 0
0 0
0 2
0 2
0 0
0 0
0 0
0 0
0 2
0 2
y 0
0 0
0 0
0 0
0 0
e 0
0 0
n
+
+
+
+
+
+
+
+
+
+
d E
E E
E E
r.
E E
E E
E E
i 0
0 0
0 0
0 0
0 0
2 0
2 K
0 0
0 0
0 0
0 0
0 5
0 5
)
0 0
0 0
0 0
0 0
0 8
0 8
m er m
i 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 k
(
o
+
+
+
+
+
+
+
+
+
+
r e
y E
E E
E E
E E
E E
E E
E s
h 0
0 0
0 0
0 0
0 0
0 c
0 o
T 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 D
y 0
0 0
0 0
0 0
0 0
1 0
1 d
0 0
0 0
0 0
0 0
0 0
0 0
e
+
+
+
+
+
+
+
+
+
+
l E
E E
E E
E E
E E
E E
E l.
0 0
0 0
0 0
0 0
0 5
0 5
T 0
0 0
0 0
0 0
0 0
6 0
6 0
0 0
0 0
0 0
0 0
1 0
1 a
ta 0
0 0
0 0
0 0
0 0
t 0
D 1
r 0
0 0
0 0
0 0
0 0
t 0
0 e
+
+
+
+
+
+
+
+
+
5 h
E E
E E
E E
E E
E E
E 1
E 0
0 0
0 0
0 0
0 0
t 0
t 9
0 0
0 0
0 0
0 0
0 5
0 5
0 0
0 0
0 0
0 0
0 2
0 2
9 i
r t
0 0
0 0
0 0
0 0
0 1
0 1
l e
0 0
0 0
0 0
0 0
0 o u n
+
+
+
+
+
+
+
+
4 0
0 fd t
E E
E E
5 E
E E
E E
E E
+
+
e 0
0 0
0 0
0 0
0 0
4 0
4 yA I
0 0
0 0
0 0
0 0
0 8
0 8
a 0
0 0
0 0
0 0
0 0
1 0
I wd h e
)
l g
t s
a nd k 0
0 0
0 0
0 0
0 0
0 0
a o u
o ei 0
0 0
0 0
6 0
0 0
0 0
/
eC P p I) n n i 4
0 4
6 0
0 0
0 0
6 t
F
/
n a a 3
0 n Fz i
Al r (p
e r
t h n o
p t
(
s t
e r n m
i e e c o
n h
e ta u i
igN n t
6 L
L L.
L L.
l I
a 6
c A
A I
L I
L.
L.
L L
t L
L o
a t
L L
L IA 2
A o
c a t
0 t
l C
d A
A A
A A
A e m r
n 4 I
gi I 1 t
e x n
=
V a c
)
e 5
5 5
m n
I.
5 5
5 5
o L
0 0
M 4
0 M M M m
fM a
C E
E 0
0 0
e I
r l
x I
0 t
E E
E E
E E
E El t.
(
E 0
2 0
0 9
7 9
B e
G 4
5 4
0 7
1 0
5 5
l.
tn 1
t 3
4 9
2 3
1 2
2 4
d
)
e d
tm a
e A
A A
A A
A A
i o
t m
s T
T M
T T
T T
1 5
5 5
r e
g A
A A
A A
A A
0 0
0 m
B i
L O
O 8
O O
O O
O 5
2 4
e g
s 5
9 3
6 n
o n
e D
D E
D D
D D
D E
E E
C m
G r
N N
2 N
N N
N N
1 1
t nh o
o p
t I
r
/
c f
m a
A A
A M
T T
T 5
9 8
5 5
5 9
e F
y A
A A
4 0
0 0
0 0
0 e
e r
n E
D D
D E
E E
E E
E E
s m
e i
6 3
2 3
2 9
0 7
d s
o
(
o K
3 O
O O
0 4
5 0
7 7
6 D
r D
t N
N N
1 3
1 1
4 3
8 o
tc n
a o
A A
A A
A A
A A
A A
F i
d T
T T
T T
T T
3 T
T T
t i
A A
A A
A A
A 0
s o
A A
A e
e D
D D
D D
D D
E D
D D
r s
y o
g 5
h O
O O
O O
O O
9 O
O O
D n
N N
N N
N N
N N
N N
1 I
x
)g k
ly 7
M M 4 6
9 9
6 4
5 6
0 0
0 0
0 0
0 0
m
(
l 2
7 t
7 9
8 6
4 2
1 3
E E
E E
E E
E E
t E
E E
e I.
2 6
6 0
t 4
3 g
a g
T 7
6 9
8 1
3 4
6 1
6 3
1 7
I s
k U
=
4 6
7 5
4 0
0 0
0 0
0 0
5 9
9 6
4 4
8 6
r 0
0 0
)
e m
A E
E E
E E
E E
E E
E E
e 7
5 2
4 4
6 5
5 0
9 5
I r
5 4
0 1
5 4
7 9
4 9
5 m
4 7
1 2
1 3
9 5
1 f
2
(
no i
A A
A ta
=
T T
M T
6 9
8 6
5 5
5 t
A 0
0 0
0 0
0 0
e
)
e A
A r
n g
a i
D D
E l
E E
E E
E E
E e
e e
t O
O 3
O 8
2 0
1 2
9, 0
4 4
2 4
6 2
7 3
V y
e N
N 4
N 4
6 3
4 6
7 2
n m
o o
n r
f i
m e
e l
d s
a i
4 7
40 o
e d
4 8
9 0
5 5
5 1
3 n
D i(
u 5
5 5
6 6
9 9
3 I
3 1
n a
e e
e n
h 1
s s
t a
t e
e 1
l g
s M
C F
C Z
N 7
1 C
C I
u a
d la a
t d
s A
U M
J ll ll
, i
I 2
1 0
1 0
3 0
0 0
3 0
3 1
L 0
4 0
0 0
4 0
0 0
4 0
4 4
+
+
+
+
+
L.
E E
E E
E E
E E
E E
E E
E
+
l 6
2 0
4 0
9 0
0 0
0 0
1 2
C 6
0 0
2 0
0 0
0 0
0 0
6 4
1 2
0 2
0 6
0 0
0 3
0 9
5 0
0 0
0 0
0 0
0 0
2 0
3 2
g 0
0 0
0 0
0 0
0 0
0 0
4 0
n
+
+
+
+
+
+
+
+
+
m E
E E
E E
E E
E E
E E
E E
0 0
0 0
0 0
0 0
0 5
0 0,
0 0
0 0
0 0
0 0
7 0
6t 7t I
0 0
0 0
0 0
0 0
0 1
0 9
2 y
3 0
0 0
0 7
0 0
0 2
0 3
2 e
0 0
0 0
0 0
0 0
0 4
0 0
4 u
+
+
+
+
+
+
+
+
n E
t 0
0 0
2 0
6 3
E 6t E
E E
E E
E E
E E
E E
E d
0 0
0 0
0 0
0 6
0 1
8 0
0 0
0 9
)
m 0
0 0
0 9
0 0
0 5
0 9
6 1
er l
0 0
0 0
0 0
0 0
0 0
0 3
3 m
h 0
0 0
0 0
0 0
0 0
0 0
4 0
(
e
+
+
+
+
+
+
+
+
+
+
+
r e
y E
E E
E E
E E
E E
E E
E E
s h
0 0
0 0
0 0
0 0
0 0
0 t
t o
T 0
0 0
0 0
0 0
0 0
0 0
6 6
0 0
0 0
0 0
0 0
0 0
0 9
9 D
y 3
2 0
2 0
7 0
0 0
1 0
3 1
d 0
0 0
0 0
4 0
0 0
0 0
4 4
E
+
+
o E
E E
E E
E E
E E
E E
E
+
+
+
+
B.
3 2
0 3
0 9
0 0
0 2
0 t
0 T
0 1
0 6
0 3
0 0
0 0
0 6
7 1
3 0
2 0
5 0
0 0
1 0
9 1
3 2
0 2
0 6
0 0
0 1
0 3
1 r
4 0
0 0
0 0
0 0
0 0
0 4
0
+
+
+
+
+
+
e E
E E
E E
E E
E E
E E
E E
A 2
9 0
9 0
0 0
0 0
5 0
1 6
I 4
3 0
1 0
0 0
0 0
5 0
6 9
5 1
0 1
0 l
0 0
0 1
0 9
1 a
t a
0 0
0 0
0 0
0 0
1 0
0 1
M e
0 0
0 0
0 0
0 0
D 4
0 0
0 n
+
+
+
+
+
+
+
+
+
+
e E
E E
E E
E E
E E
E E
E E
5 B
0 0
0 0
0 0
0 0
0 3
0 0
3 0
0 0
0 0
8 0
0 0
1 0
0 1
9 0
0 0
0 0
1 t
g 0
0 0
1 0
0 1
9 l k
1 u i
l g
0 0
0
/
)
C r d g
a n h /1 5,
1 0
5 0
0
)
k 0
0 0
0 0
0 0
oA k
p u
o i C 6
0 0
5 0
8 0
0 0
7 0
7 s
7 n ni F
3 7
5 f
/
d C
5 n n a p
5 9
0 6
6 0
0 0
6 0
t 1
1 0
2 3
ye p 3 Ai r 4
e
(
(
4 h n t
a s t
wo n =
s t
e r n o
e e c t
io o
h p i 9 h
t x
a 0
igN m i c L
L a
8 8
8 8
L, L
L L
t c ta 0
0 L
0 L
0 l
L L
0 L
0 8
8 O
2 2
A 2
A 2
A A
A 2
A 2
PaE d o r
x l
I nL tn t
I
/
e i h m c C
=
n p
)
s u o
I 5
5 5
5 m
5 5
6 1
L 0
0 0
M 0
0 0
M M 0
e 5
7 i
4 L
E 0
F m C
E E
E E
E E
E E
E E
E m
0 r
(
i x
8 I
0 t
0 2
0 0
9 7
9 l
8 5
t mx 4
G 4
5 4
0 7
1 0
5 5
l.
0 1
)
n 1
1 3
4 9
2 3
1 2
2 4
1 e
a d
=
oM e
t l
tm r
s m
/
e O A
A A
A A
A A
d f
a T
T 6
T T
T T
T 5
5 8
7 g
A A
A A
A 0
0 0
m p
g A
A 0
0 o
e n
n s
i 9 u.
D D
E D
D D
D D
E E
E E
C 5
9 3
6 5
o 0
0 O
O 8
O O
O O
O 5
2 4
0 e
I D
p r
N N
2 N
N N
N N
1 1
1 1
on
/ o D
m tc A
A A
er a
y 6
T T
T 5
9 8
5 5
5 9
7 m F e
4 A
A A
E E
E E
E E
E 0
0 4
0 E
D D
D E
0 4
0 0
n
(
n d
i 6
3 2
3 2
9 0
7 5
r o
K 3
O O
O 0
4 5
0 7
7 6
0 o i r
t 1
N N
N 1
3 1
1 4
3 5
1 t
a o
c l
t a
u c
F m
a A
A A
A A
A A
A A
A d
e u
F i
T T
T T
T T
T 3
T T
T 7
o A
A A
A A
A A
0 A
A A
0 s
c e
ry D
D D
D D
D D
E D
D D
E o
c s
5 5
D a
h O
O O
O O
O O
9 O
O O
0 o
T o
x i D
N N
N N
N N
N 1
N N
N 1
B
)
n g
x o
k i
d 0
M 4
0 0
0 0
l y
7 6
6 6
9 9
s o
M 4
5 6
7
(
/
t E
E E
E E
E 0
0 4
0 O
e e
E E
Et 2
6 6
0 1
1 4
3 5
E E
E a
p c
B.
g 2
7 s
r g n
T 7
6 9
7 9
8 6
4 2
1 3
0 8
1 3
4 6
1 6
3 1
7 1
1 U
e k I
t
=
aW1
)
6 7
5 6
S 9
9 6
4 4
8 7
2 m
r 0
e e
e 0
0 0
0 0
0 0
0 0
4 0
r c
b E
E E
E E
E E
E E
E E
E a
7 5
2 4
4 6
5 5
8 9
5 5
m f
I 5
4 0
1 5
4 7
9 4
0 5
0
(
r 4
7 1
2 1
3 9
5 1
1 2
1 u
y S
aw =
h h
A A
A A
t s
a i e
P F =
T T
6 T
6 9
8 6
5 5
5 0
T A
A 0
A 0
0 0
0 0
0 A
)
n n
r o
D D
E D
E E
E E
E E
E D
h i ea 4
4 2
4 6
2 7
3 i
B O
O 3
O 8
2 0
s 1
2 9
0 O
F n
y N
N 4
N 4
6 3
4 6
7 2
N o
en m i e t
o a
r r
n f
t i
e n
k e
e e
tn l
4 8
9 0
5 5
5 1
J 3
1 d
s a
i 4
7 4
c 0
o n
c D o i(
5 5
6 6
9 9
3 I
1 3
u 5
n n
o e
e n
b r
1 s
l 1
s a
C e i M C
F C
Z N
Z 1
1 t
o g
C C
a lu 3 a da B
d s
R I
A U
I
- Ill, i
l
a Dosefrom Shoreline Sediment Pathwayfor 1995 Data Maximum ExposedAdult Shoreline Recreatios =
12 hr(in one year)
Shore Width Factor =
0.2 Sediment Surface Mass =
40 kg/m2 Adult Dose from Shorline Sediment Pathway (mrem) = Shorline Recreation (hr) x External Dose Factor (mrem!hr per pCFm2) x Shore width Factor x Sediment surface Mass (kg/m2) x Sediment Concentration (pl%g)
External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration (mrem /hr per pCi/m2)
Indicator Sediment (mrem)
Radionuclide T. Body Skin Location (pCLig)
T. Body Skin Mn.54 5.80E-09 6.80E-09 208 2S 122.27 6.81E-05 7.98E-05 Co-58 7.00E-09 8.20E-09 208-2S 1326.43 8.91 E-04 1.04E-03 Fe-59 8.00E-09 9.40E-09 ALL 0.00 0.00E+00 0.00E+00 Co-60 1.70E-08 2.00E-08 208 2S 944.33 1.54E-03 1.81E-03 Zn.65 4.00E-09 4.60E-09 ALL 0.00 0.00E+00 0.00E+00 N b-95 5.10E-09 6.00E-09 208-2S 113.00 5.53E-05 6.51 E-05 Zr.95 5.00E-09 5.80E-09 ALL 0.00 0.00E+00 0.00E+00 1131 2.80E-09 3.40E-09 ALL 0.00 0.00E+00 0.00E+00 Cs-134 1.20E-08 1.40E-08 ALL 0.00 0.00E+00 0.00E+00 Cs-137 4.20E-09 4.90E-09 208-1S 85.00 3.43E-05 4.00E-05 Bata.140 2.10E-09 2.40E-09 ALL 0.00 0.00E+00 0.00E+00
- Sb-125 3.10E-09 3.50E-09 208-3S 148.45 4.42E-05 4.99FA5
- Co-57 9.10E-10 1.00E-09 208.2S 36.90 3.22 E-06 3.54E-06
- Sn.113 1.90E-09 2.20E-09 208-2S 71.10 1.30E-05 1.50E-05 Dose Commitment (mrem) =
2.65 E-03 3.11 E-03
- Dose Factors from Reference 6.11
5.0 QUALITY ASSURANCE 5.1 DUKE POWER COMPANY ENVIRONMENTAL LABORATORIES 5.1.1 SAMPLE COLLECTION Radiological and Environmental Services, Fisheries, and Aquatic Ecology performed the environmental sample collections as specified by approved sample collection procedures.
5.1.2 SAMPLE ANALYSIS The Radiological and Environmental Services Group performed the environmental sample analyses as specified by approved analysis procedures.
5.1.3 DOSIMETRY ANALYSIS The Radiation and Dosimetry Records group performed environmental dosimetry measurements as specified by approved dosimetry analysis procedures.
5.1.4 INTRALABORATORY OUALITY ASSURANCE Radiological and Environmental Services has an internal quality assurance program which monitors each type ofinstrumentation for reliability and accuracy. Daily quality control checks ensure that instruments are in proper working order and these checks are used to monitor instrument performance.
Additionally, National Institute of Standards and Technology (NIST) standards that represent counting geometries are analyzed as unknowns at various frequencies ranging from weekly to annually to verify that efficiency calibrations are valid. The frequency is dependent upon instrument use and performance.
Investigations are performed and documented should calibration verification data rai: out oflimits.
section 5 Page 1
5.1.5 INTERLABORATORY OUALITY ASSURANCE 5.1.5.1 DUKE POWER'S AUDIT DIVISION The Catawba Nuclear Station Radiation Protection Section participated in a Quality Assurance audit during the period of February 27 through March 16,1995. This audit was conducted by the Nuclear Assessment and Issues Division, Regulatory Audit Group. No recommendations l
pertaining to the Catawba Radiological Environmental Monitoring Program were identified in the audit.
I l
5.1.5.2 DUKE POWER'S NUCLEAR PRODUCTION INTERCOMPARISON PROGRAM i
I The Radiological and Environmental Services group participated in the l
Duke Power Nuclear Generation Department Intercomparison Program l
during 1995. Interlaboratory cross-check standards, including marinelli j
beakers, air filters, air cartridges, gross alpha / beta on smears, and tritium in water samples were analyzed at various times of the year by the four counting laboratories in Duke Power Company for this program. A j
summary of these Intercomparison Reports for 1995 is documented in Table 5.0-A.
l 5.1.5.3 U.S. NUCLEAR REGULATORY COMMISSION INSPECTIONS i
The Radiological Environmental Monitoring Program was not audited by the NRC in 1995.
5.1.5.4 UNITED STATES ENVIRONMENTAL PROTECTION AGENCY INTERCOMPARISON PROGRAM i
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, mixed gamma in milk, gamma in air filters, iodinc in milk, tritium in water, iodine in water, gross beta in air filters and gross beta in water.
Radiological and Environmental Services prepared and analyzed each sample as quickly as possible. Data obtained greater than EPA limits is documented by follow-up investigations. The Radiological and l
l Section 5 - Page 2
l l-Environmental Services EPA Intercomparison Report code is "CP". A l-summary of the EPA Intercomparison Reports for 1995 is documented I
in Table 5.0-B.
An investigation was made into failed Beta in Water and Gamma in Water dated 4/18/95. Both tests conducted by Radiological and Environmental Services failed high due to cross-contamination of the samples. The investigation reviewed preparation of samples, training of personnel, materials used for sample preparation, laboratory area used for preparation, and review ofdata.
One sample was analyzed but results were not reported by the required date. (See corrective action #1 below)
After careful review of preparation of samples, it was determined that all procedure steps were accurately followed. No deviation in preparation procedures were found. Laboratory personnel that performed the analysis were sufficiently trained and had conducted similar analyses l
with acceptable results. The contamination of the cross-check samples is l
believed to have resulted &om analysis of primary reactor coolant samples by Radiological ana Environmental Services. The potential existed for glassware and work surfaces to be contaminated with.
primary coolant in the preparation area. This is considered to be the root cause of the contamination.
Corrective actions are as follows-I
- 1) The receipt and tracking of EPA samples was refined in order to t
meet all future deadlines.
- 2) An entire process improvement initiative was implemented that i
i distinctly isolates all lab work by potential activity.
- 3) Specific glassware ha:, been physically identified for all analyses i
types, e.g. environmental, efl1uent, primary reactor coolant, EPA, l
etc..
- 4) Cleaning procedures have been reviewed and improved for glassware and counter surfaces, minimizing the potential for 1
contamination.
- 5) Data reviewers have been reminded to use historicalinformation as
" benchmark" data to find potential anomalies.
- 6) Procedures will be modified for 1996 samples to include a blank to be prepared with each set of samples. This will verify the presence of any interfering contaminants in sample matrices.
l t
Section 5 Page 3
5.1.5.5 NRC/ STATE OF S.C. INTERCOMPARISON PROGRAM Radiological and Environmental Services routinely participates with the Bureau of Radiological Health of the State's Department of Health and Environmental Control (DHEC) in an intercomparison program.
Radiological and Environmental Services sends air, water, milk, vegetation, sediment, and fish samples which have been collected to the State of South Carolina DHEC Laboratory for intercomparison analysis.
5.1.5.6 STATE OF N.C. TLD INTERCOMPARISON PROGRAM Radiation Dosimetry and Records routinely participates in a TLD i
intercomparison program. Every six to eight months, the State ofNorth Carolina Radiation Protection Section irradiates environmental dosimeters and sends them to the Radiation Dosimetry and Records group for analysis of the unknown estimated delivered exposure. A summary of the State of North Carolina Environmental Dosimetry Intercomparison Report for 1995 is documented in Table 5.0-C.
5.2 CONTRACTOR LABORATORIES No contractor laboratories were used during 1995.
4 Section 5 - Page 4
1 i
TABLE 5.0-A 1
DUKE POWER COMPANY INTERLABORATORY COMPARISON P.ROGRAM 1995 CROSS-CHECK RESULTS FOR THE RADIOLOGICAL & ENVIRONMENTAL SERVICES LABORATORY Gamma:
....a,
'C611sEAioris$.~.Ge6mettfi
!Nuclides
. _s.
(RsfefenceNaldslll fRiportedp
~~
j{A csp 6uicEj[a,iigej
. ~. - ~.
.. - =
iDstef
~ {(fi/l)
}(pCi/l)lJj(
jgalusj
,.g g'
e V(pCi/lji 6/23/95 3.5 Liter Cr-51 1.93E4 - 3.42E4 2.57E4 2.60E4 Mn-54 1.30E4 - 2.30E4 1.73E4 1.77E4 Co-58 5.82E3 - 1.03E4 7.76E3 8.01E3 Fe-59 5.46E3 - 9.68E3 7.28E3 7.51E3 Co-60 1.31E4 - 2.33E4 1.75E4 1.78E4 Zn-65 1.31E4 - 2.33E4 1.75E4 1.84E4 Cs-134 7.95E3 - 1.41E4 1.06E4 9.8E3 Cs-137 7.36E3 - 1.31E4 9.81E3 9.97E3 Ce-141 5.62E3 - 9.96E3 7.49E3 7.70E3
",m
~
C511ehtIoni[Ge6hiyj fl5EElIIldl.$Ihceptance. Range # $Rsfdenes@aise7!
Rep 6rieb 3%. e:
'~
apM.Ci/t6.tal$-
,1.,(pCi/to(dif.f.
EVslusi %
~ ~,
~
6/23/95 1.0 Liter Cr-51 4.45E4 - 7.89E4 5.93E4 6.02E4 Mn-54 3.02E4 - 5.35E4 4.02E4 4.16E4 Co-58 1.36E4 - 2.41E4 1.81E4 1.88E4 Fe-59 1.27E4 - 2.25E4 1.69E4 1.34E4 Co-60 3.04E4 - 5.39E4 4.05E4 4.20E4 Zn-65 3.03E4 - 5.37E4 4.04E4 4.34E4 Cs-134 1.83E4 - 3.25E4 2.44E4 2.26E4 Cs-137 1.70E4 - 3.02E4 2.27E4 2.28E4 Ce-141 1.31E4 - 2.31E4 1.74E4 1.85E4 Section 5 - Page 5 1
1 Gamma:
C611Astion)ll Geometry
%blidei ?AEcepisace Range?
$Refdrencs VslSes
[?ReportAd3
- fDa(si
~ ?(pC..i../ tots!.). ?
l(pCi/inisi))
jValdsb 8/18/95 Cartridge I-131 4.43E 7.86E-1 5.91E-1 6.07E-1 Tritium:
Cdbedddn $dedmet$ fNudidE; IAscepianedRarigej [R5ferencs Vdide6 [REhrishi tDate i.
f(pCi/ml)j
[(pQilml)l; (Value)
?h1Ci/ml)l 8/18/95 20ml vial H-3 1.22E 3.39E-3 2.04E-3 1,74E-3 1
\\
l Section 5 - Page 6
TABLE 5.0-B U.S. ENVIRONMENTAL PROTECTION AGENCY INTERLABORATORY COMPARISON PROGRAM 1995 CROSS-CHECK RESULTS FOR THE RADIOLOGICAL & ENVIRONMENTAL SERVICES LABORATORY Gammain Water:
...C,.
.. ! L. <...
...c.. ;.
~...._;
RL f Cb11ection Dafb);
1Nd$lide(s))
- 1. Control Linsitsjj' TKn6wn Valse;
' JReported!
.m
.-_..m
._m gL> S.i A p g ngulyF nyak ~
p o~.
g gg 2/3/95 I-131 82.7 - 117.3 100 98.7 m
w 4/18/95 Co-60 20.3 -37.7 29 30.7 Cs-134 11.3 - 28.7 20 213.7("
Cs-137 2.3 - 19.7 11 276.3(4 ni 4
y
~
6/9/95 Ba-133 65.1 - 92.9 79 81.0 Co-60 31.3 -48.7 40 41.7 Zn-65 62.1 - 89.9 76 81.0 Cs-134 41.3 -58.9 50 46.7 Cs-137 26.3 - 43.7 35 34.7 y
10/6/95 I-131 122.0 - 174.0
?48 158.7
~
N 10/17/95 Co-60 40.3 - 57.7 4) 50.0 Cs-134 31.3 - 48.7 40 37.7 Cs-137 21.3 -38.7 30 30.0 I1/3/95 Ba-133 81.7 - 116.3 99 100 l
Co-60 51.3 - 68.7 60 55.7 l
Zn-65 102.5 - 147.5 125 132.7 Cs-134 31.3 -48.7 40 35.3 Cs-137 40.3 - 57.7 49 51.3 j
Section 5 - Page 7
\\
Gamma in Milk:
w.
idollestion;Datef iNUhlid$s)) jC6htrolLimijs h:
[K_nopnjaSej:
Rep 6r$d)
- g@
[(3LSignia[N$3)]
((pCi/l)]
SValue::
ggg g;j;p -
9/29/95 I-131 81.7 - 116.3 99 106.3 Cs-137 41.3 - 58.7 50 49.3 Betain Water:
SCdllestionDite4 (Nuclide($)l IContr61 Limitsi dKnow(V50et
{fRehorted!
f(3 Sigma;Nf3)j f..(s..ci/l)]
BVahie]
1/27/95 Gross Beta 0.0 - 13.7 5.0 8.3 (2) 4/18/95 Gross Beta 69.3 - 103.9 86.6 405.0 m 7/21/95 Gross Beta 10.7 - 28.1 19.4 27.3 10/27/95 Gross Beta 16.1 - 33.5 24.8 29.0 Tritium in Water:
@olisction DatsA
?Nuclide(s)) [C8ntrol Limitsi l Knop (yalue?
FReported i
~'
[(3; Sigma (N=3)j j(pCi/l)]
(Valusi i il(pCi/1)1
'~
f(pCi/l)i 3/10/95 H-3 6144.2 - 8725.8 7435 7132.3 8/4/95 H-3 4028.5 - 5715.5 4872 4626.7 i
Air Filter:
[Collsction DafeL L;Nuhlids(s).:.
- Control Limits;;.
IKn6wn VAlue) l Reported ll
(.(3 Sigma!N=3);[
ll(pCi/1)}
gValuel
. (pCi/lO f(pCi/lf 8/25/95 Cs-137 16.3 - 33.7 25.0 26.7 Gross Beta 69.3 - 103.9 86.6 86.7 (1) See Explanation in Section 5.1.5.4.
(2) This value was not reported before the due date and was not included in the reports.
Section 5 Page 8
TABLE 5.0-C STATE OF NORTH CAROLINA DEPARTMENT OF ENVIRONMENTAL HEALTH AND NATURAL RESOURCES 1995 ENVIRONMENTAL DOSIMETER CROSS-CIIECK RESULTS 2
s
~$h.E
,j{I f) l Q Qjfgpf b [g':
$Cidss2 h$hk.$4
.[StAti6f3C)I
$$$AcAddli;
- 7h$beptanbe?
~
C s
^
SbiE81 IDslissr$dVAldey
[IRep60$dNalds:3 i[Criteriai m
g
_ g.
g c,.
- s.....
.':.~.
?? }
May-95 100 92.5 Pass 1
Nov-95 60
' 6.9 Pass i
)
l Section 5 - Page 9
6.0 REFERENCES
6.1 Catawba Selected License Commitments j
6.2 Catawba Technical Specifications 6.3 Catawba Final Safety Analysis Review 6.4 Catawba Offsite Dose Calculation Manual 6.5 Catawba Annual Environmental Operating Report 1985 - 1994 6.6 Catawba Annual Effluent Report 1985 - 1994 6.7 Probability and Statistics in Engineering and Management Science, Hines and Montgomery,1969, pages 287-293.
6.8 Practical Statistics for the Physical Sciences, Havilcek and Crain,1988, pages 83-93.
6.9 Nuclear Regulatory Commission Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluatics Compliance with 10CFR50, Appendix I.
6.10 Radiological and Environmental Services Operating Procedures 6.11 NUREG/CR-1276, Users Manual for LADTAP II - A Computer Program for Calculating Radiation Exposure to Man from Routine Release of Nuclear Reactor Liquid Effluents.
Section 6 Page 1
n.-a s
w,r,a oa
+
A
.m e
a 4
a s
n i
APPENDIX A
{
ENVIRONMENTAL SAMPLING AND ANALYSIS PROCEDURES l
1 l
l APPENDIX A ENVIRONMENTAL SAMPLING AND ANALYSIS PROCEDURES Adherence to established procedures for sampling and analysis of all environmental media at Catawba Nuclear Station was required to ensure compliance with Station Selected Licensee Commitments.
Analytical procedures were employed to ensure that Selected Licensee Comnutments detection capabilities were achieved.
Environmental sampling and analyses were performed by Radiological and Emironmental Sersices, Dosimetry and Records, Fisheries and Aquatic Ecology.
This appendix describes the environmental sampling frequencies and analysis procedures by media type.
I.
CHANGE OF SAMPLING PROCEDURES No sampling changes were made to the sampling procedure during 1995.
II. DESCRIPTION OF ANALYSIS PROCEDURES Gamma spectroscopy analyses are performed using high purity germanium gamma detectors and Canberra analytical sofhvare. Designated sample volumes are transferred to appropriate counting geometries and analyzed by gamma spectroscopy. Perishable samples such as fish and broadleafvegetation are ground to achieve a homogeneous mixture. Soils and sediments are dried, sifted to remove foreign objects (rocks, clams, glass, etc.) then transferred to appropriate counting geometry.
Low-level iodine analyses are performed by passing a designated sample aliquot through an ion exchange resin to remove and concentrate any iodine in the aqueous sample (milk or water).
The resin is then dried and transferred to appropriate counting geometry and analyzed by gamma spectroscopy.
Tritium analyses are performed quarterly b, using low-level environmental liquid scintillation l
analysis technique on a Packard 2550 liquid scintillation system.
l l
Gross beta analysis is performed by concentrating a designated aliquot of sample precipitate l
and analyzing by gas-flow proportional counters.
Appendix A Page 1
III.
CIIANGE OF ANALYSIS PROCEDURES Low Level Iodine 131 (LLI-131) analysis was discontinued for all surface water sites on January 28,1995. This analysis was not required for surface water samples by Selected License Commitments.
IV.
SAMPLING AND ANALYSIS PROCEDURES A.1 AIRBORNE PARTICULATE AND RADIOIODINE Airbome particulate and radiciodine samples at each of five locations were composited by means of continuous air samplers. Air particulates were collected on a particulate filter and radiciodines were collected in a charcoal cartridge situated behind the filter in the sampler. The samplers are designed to operate at a constant flow rate (in order to compensate for any filter loading) and are set to sample approximately 2 cubic feet per minute. Filters and cartridges were collected weekly. A weekly gamma analysis and gross beta analysis were performed on each filter and a weekly gamma analysis was performed on each charcoal cartridge. The filter and charcoal cartridge were analyzed independently. The continuous composite samples were collected from the locations listed below.
Location 200 Site Boundary (0.6 mi. NNE)
=
Location 201 Site Boundary (0.5 mi. NE)
=
Location 205 Site Boundary (0.3 mi. SW)
=
Location 212 Tega Cay, SC (3.3 mi. E)
=
Location 217 Rock Hill Substation (10.3 mi. SSE)
=
A.2 DRINKING WATER Biweekly composite dnnkmg water samples were collected at each of two locations.
A low-level Iodine-131 analysis was perfonned on each biweekly composite c.mple. A gross beta and gamma analysis was performed on monthly composites. Tridum analysis was performed on the quarterly composites. The composites were collected biweekly from the locations listed below.
Location 214 Rock Hill Water Supply (7.3 mi. SE)
=
Location 218 Belmont Water Supply (13 4 mi. NNE)
=
A.3 SURFACE WATER Biweekly composite samples were collected at each of three locations. A low-level Iodine-131 analysis was performed on each biweekly composite sample until Jar.uary 28,1995. A gamma analysis was performed on the monthly composites. Tritium Appendix A-Page 2
analysis was performed on the quarterly composites. The composites were collected biweekly from the locations listed below.
Location 208 Discharge Canal (0.5 mi. S)
=
Location 211 Wylie Dam (4.0 mi. ESE)
=
Location 215 River Pointe-Hwy 49 (4.2 mi. NNE)
=
A.4 MILK Biweekly grab samples were collected at each of three locations. A gamma and low-levelIodine-131 analysis was perfonned on each sample. The biweekly grab samples were collected from the locations listed below.
Location 209 Wood Dairy-(6.0 mi. SSW)
=
Location 219 Pursley Dairy-(5.7 mi. SW)
=
Location 221 Oates Dairy -(14.5 mi.- NW)
=
A.5 B.RO A DLE AF VEGETATION Monthly samples were collected as available at each offour locations. A gamma analysis was performed on each sample. The samples were collected from the locations listed below.
Location 200 Site Boundary (0.6 mi. NNE)
=
Location 201 Site Boundary (0.5 mi. NE)
=
Location 217 Rock Hill Substation (10.3 mi. SSE)
=
Location 226 Site Boundary (0.5 mi. S)
=
A.6 SHORELINE SEDIMENT Semiannual samples were collected at each of three locations. A gamma analysis was performed on each sample following the drying and removal ofrocks and clams. The samples were collected from the locations listed below.
Location 208 Discharge Canal (0.5 mi. S)
=
Location 210 Ebenezer Access (2.3 mi. SE)
=
Location 215 River Pointe-Hwy 49 (4.2 mi. hWE)
=
A.7 FISH Semiannual samples were collected at each of two locations. A gamma analysis was performed on the edible portions ofeach sample. Boney fish (i.e. Sunfish) were prepared whole minus the head and tail portions. The samples were collected from the locations listed below.
Appendix A-Page 3
Location 208 Discharge Canal (0.5 mi. S)
=
Location 216 Hwy 49 Bridge (4.0 mi. NNE)
=
A.8 DIRECT GAMMA RADIATION (TLD)
Thermoluminescent dosimeters (TLD) were collected quarterly at forty locations. A gamma dose rate was detemuned for each TLD. The TLDs were placed as indicated below.
An inner ring of 16 TLDs, one in each meteorological sector in the general area ofthe site boundary.
An outer ring of 16 TLDs, one in each meteorological sector in the 6 to 8 kilometer range.
The remauung TLDs were placed in specialinterest areas such as population centers, residential areas, schools, and at three control locations.
TLD locations are listed in Table 2.1-A.
A.9 FOOD PRODUCTS Monthly samples were collected when available during the harvest season at one location. A gamma analysis was performed on each sample. The samples were collected from the location listed below.
Location 253 hrigated Gardens (2.1 mi. SSE)
=
A.10 GROUND WATER Grab samples were collected quarterly from residential wells at each of two locations.
A gamma analysis, low-level I-131 analysis, and a tritium analysis were performed on each sample. The samples were collected from the locations listed below.
Location 252 Residence (0.7 mi. SW)
=
Location 254 Residence (0.8 mi. N)
=
Appendix #. Page 4
A.11 ANNUAL LAND USE CENSUS An Annual Land Use Census was conducted to identify within a distance of 8 kilometers (5.0 miles) from the station, the nearest location from the site boundary in each ofthe sixteen meteorological sectors, the following:
The Nearest Residence The Nearest Meat Animal The Nearest Garden greater than 50 square meters or 500 square feet The Nearest Milk-giving Ammal (cow, goat, etc.)
The census was conducted July 20 - August 16,1995 and the results are shown in Table 3.12-A.
Appendix A Page 5
V.
PROGRAM IMPROVEMENTS Trending of both air sampler and water sampler site locations is performed for continuous identification of any problems impacting the sample deviation rate of the Radiological Environmental Monitoring Program (REMP).
Each air site has been evaluated for correct grounding, proper voltage range and the equipment requirement to install surge and lightning suppressers. Modifications based upon the site evaluations will be made to the air sampler sites in 1996.
Various equipment upgrades and purchases were made in 1995 to enhance the Radiological Environmental Monitoring Program for Catawba Nuclear Station. A thorough description of the purchases and upgrades to the environmental program may be found in the " Sampling and Deviation Reduction Plan for 1995 and 1996"in Appendix C, Section C.3.
Appendix A Page 6
APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OF RESULTS 1995 Note: Locations, respective sectors and distances are included in Section 2.1, Site Descriptions
Environmental Radiological Monitoring Program Sunnary Name of Facility
. CATAW8A NUCLEAR STAT!0N Occket Nurter
- 50-413,414 Location of Facility : COUNTY, S.C.
Reporting Period : 1 JAN 1995 through 31-DEC-1995 Time Report Generated : 11.JAN 1996 13:50:42 Database Name
- $0lSK12 (USER.ASC)CATAW8A NUCLEAR STAT 10N95.SAFj3
................................................................................................~.~.~...........................
l l
l l Location with Highest Mean l l No. of Medlun or l Type & Total l Lower l
All Indicator l--"-*"--""-*""""-l l Non-Pathway l Nunter of l Limitofl Locations l Name, Olstance and Direction l Control Locations l Routine Serpled 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.
...............................................................................~...................................
IR PARTICULATE l l
l l
l l
PCl/M3) l l
l l
l217(10.0MiSSE) l l
l l
1 I
I LOCATIONS l MN 54 258l 0.00E+00l 0.00E+00(
0/ 206) l 0.00E+00(
0/ 50) l 0.00E+00(
0/ 52) l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00[ 0.00E+00 ~ 0.00E+00 l l
l l
i I
I lCo-58 258l 0.00E+00l 0.00E+00(
0/ 206) l 0.00E+00(
0/ 50) l 0.00E+00(
0/ 52) 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 lFE-59 258l 0.0CE+00l 0.00E+00(
0/ 206) l 0.00E+00(
0/ 50) 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 lCo-60 258l 0.00E+00l 0.00E+00(
0/206)l 0.00E+00(
0/ 50) l 0.00E+00(
0/ 52) l 0
l l
l 0.00E+00~ 0.00E+00 [
0.00E+00--0.00E+00l 0.00E+00~ 0.00E+00 l l
l l
l l
lZN-65 258l 0.00E+00l 0.00E+00(
0/ 206)-
0.00E+00(
0/ 50) 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 1
1 I
I l28-95 258l 0.00E+00l 0.00E+00(
0/ 206) l 0.00E+00(
0/ 50) 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+00l I
I I
I i
lZR-95 258l 0.00E+00l 0.00E+00(
0/ 206) l 0.00G+00(
0/ 50) 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 I
I I
I I
I lt131 258l 7.00E02} 0.00E+00(
0/ 206) l 0.00E+00(
0/ 50) 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 I
I I
I 1
lCS134 258l 5.00E02l 0.00E+00(
0/ 206) l 0.00E+00(
0/ 50) 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
1 I
I I
I lCS-137 258l 6.00E02l 0.00E+00(
0/ 206) l 0.00E+00(
0/ 50) l 0.00E+00(
0/ 52) [
0 l
l l
0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 l 0.00E+00-0.00E+00l l
l l
l l
l lBALA140 258l 0.00E+00l 0.00E+00(
0/ 206) l 0.00E+00(
0/ 50) 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
l212(3.3MiE) l l
l BETA 258l 1.00E02l 3.67E 02( 206/ 206) l 4.88E-02( 52/ 52) l 3.23E-02( 52/ 52) l 0
l l
l 3.63E-03~ 0.20 l
1.51E 02- 0.20 l 1.49E-02 8.31E-02l ean and range based upon detectable measurements only raction of detectable measurements at specified locations is indicated in parentheses, (Fraction) ero range indicates no detectable activity measuretrents f LLO is equal to 0, then LLO is not required by Technical Specifications Appendix 8. Page 1
Envirotwental Radiological Monitoring Program Swriary Nama of Facility
- CATAWBA NUCLEAR STAT 10N Cocket Nunter 50 413,414 Location of Facility : COUNTY, S.C.
Reporting Period 4 1 JAN 1995 through 31 DEC-1995 Time Report Generated i 11 JAN 1996 13:50:42 Database Name
- SCISK1:(USER.ASC)CATAW8A NUCLEAR STAT!0495.SAF;3 l
l l
l Location with Highest Mean l lko.of Medlun or l Type & Total l L owe.-
l All Indicator l-------**-----------------l l Non-Pathway l Nwber of l Limitofl Locations l Name,DistanceandDirectionl Control Locations l Routine Sampled l
Analyses l Detection l Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) l Report (Units) l Performed l (LLD) l Range l Code Range l
Range l Meas.
AIRRA010100!NESl l
l l
l l
(PCl/M3) l l
l l
l 217 (10.0 Mi SSE) l l
1 I
I I
I 5 LOCATIONS lMN54 258l 0.00E+00l 0.00E+00(
0/ 206) l 0.00E+00(
0/ 50) 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+00l l
l l
1 1
I lCO-58 258l 0.00E+00l 0.00E+00(
0/ 206) l 0.00E+00(
0/ 50) l 0.00E+00(
0/ 52) l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l
1 I
I I
I lFE59 258l 0.00E+00l 0.00E+00(
0/ 206) l 0.00E+00(
0/ 50) l 0.00E+00(
0/ 52) 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 lCO60 258l 0.00E+00l 0.00E+00(
0/ 206) l 0.00E+00(
0/ 50) 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+00l I
I I
I I
I lZN65 258l 0.00E+00l 0.00E+00(
0/ 206) l 0.00E+00(
0/ 50) l 0.00E+00(
0/ 52) l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 1
I I
I I
I lNS-95 258l 0.00E+00 l 0.00E+00(
0/ 206) l 0.00E+00(
0/ 50) l 0.00E+00(
0/ 52) l 0
l l
l 0.00E+00-0.00E+00l 0.00E+00--0.00E+00[ 0.00E+00--0.00E+00l l
1 I
i l
I l2R95 258l 0.00E+00l 0.00E+00(
0/ 206) l 0.00E+00(
0/ 50) l 0.00E+00(
0/ 52) l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00[ 0.00E+00--0.00E+00l I
I I
I I
I lI-131 258l 7.00E-02l 0.00E+00(
0/ 206) l 0.00E+00(
0/ 50) l 0.00E+00(
0/ $2) l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00- 0.00E+GO [ 0.00E+00--0.00E+00l I
l I
I I
I lCS134 258l 5.00E02l 0.00E+00(
0/ 206) l 0.00E+00(
0/ 50) l 0.00E+00(
0/ 52) 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
l200(0.6MiNNE) l l
lCS137 258l 6.00E02l 2.07E 02( 6/ 206) l 2.59E-02(
2/ 50) l 0.00E+00(
0/ $2) l 0
l l
l 4.75E-03--5.20E-02l 2.11E02--3.07E-02l 0.00E+00-- 0.00E+00 [
l l
I I
I I
lBALA140 258l 0.00E+00l 0.00E+00(
0/ 206) l 0.00E+00(
0/ 50) l 0.00E+00(
0/ 52) l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l
' Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)
Zero range indicates no detectable activity measurements If LLO is equal to 0, then LLD is not required by Technical Specifications Appendix 8 Page 2
Environmental Radiological Monitoring Program Stanary Name of Facility
- CATAW8A NUCLEAR STAT!ON Docket Ntznber
- 50 413,414 Location of Facility : COUNTY, S.C.
Reporting Period : 1 JAN 1995 through 31 DEC-1995 Time Report Generated : 11-JAN 1996 13:50:42 Database Name
$0lSK1 (USER. ASC)CATAW8A NUCLEAR STAT 10N95.SAF;3 l
l l
l Location with Highest Mean l l No. of Medlun or l Type & Total l Lower l
All Indicator l-- - --- -- - ----
*-l l Non-Pathway l Number of l Limitofl Locations l Name, Distance and Direction l Control Locations l Routine Serpled l
Analyses jDetectionl Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) l Report (Units) l Perfornied l (LLD) l Range l Code Range l
Range l Meas.
BROADLEAFVEGETl l
l l
l l
(PCl/ WET /KG) l l
l l
l 217 (10.0 Mi SSE) l l
l l
l l
1 4 LOCATIONS lMN54 36l 0.00E+00l 0.00E+00(
0/ 27) l 0.00E+00(
0/ 9) l 0.00E+00(
0/ 9) l 0
l l
l J.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l l
l 1
I I
I lCO-58 36l 0.00E+00l C.00E+00(
0/ 27) l 0.00E+00(
0/ 9) l 0.00E+00(
C/ 9) l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l
1 I
I I
I lFE59 36l 0.00E+00l 0.00E+00(
0/ 27) l 0.00E+00(
0/ 9) l 0.00E+00(
0/ 9) l 0
l l
l 0.00E+00-0.00E+00]
0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 1
I I
I I
I lCo-60 36 l 0.00E+00l 0.00E+00(
0/ 27) l 0.00E+00(
0/ 9) l 0.00E+00(
0/ 9) [
0 l
l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00-
.00E+00 l l
1 I
I I
I lZN-65 36[ 0.00E+00l 0.00E+00(
0/ 27) l 0.00E+00(
0/ 9) l 0.00E+00(
0/ 9) l 0
l l
l 0.00E+00--0.00E+00[
0.00E+00- 0.00E+00 l 0.00E+00--0.00E+00l l
1 1
I I
l lNS-95 36 l 0.00E+00l 0.00E+00(
0/ 27) l 0.00E+00(
0/ 9) l 0.00E+00(
0/ 9) [
0 l
l l 0.00E+00--0.00E+00l 0.00E+00--0.00E*00l 0.00E+00-0.00E+00l l
1' I
I I
I lZR-95 36l 0.00E+00l 0.00E+00(
0/ 27) l 0.00E+00(
0/ 9) l 0.00E+00(
0/ 9) l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l 1
1 I
I I
I lt-31
.6' 60.
l 0.00E+00(
0/ 27) l 0.00E+00(
0/ 9) l 0.00E+00(
0/ 9) l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 1
I I
I I
l lCS-134 36l 60.
l 0.00E+00(
0/ 27) l 0.00E+00(
0/ 9) l 0.00E+00(
0/ 9) 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
l201(0.5MiNE) l l
lCS137 36) 80.
l 36.
(
4/ 27) l 36.
(
4/ 9) l 0.00E+00(
0/ 9) l 0
l l
l 19.
-- 59.
l 19.
-- 59.
l 0.00E+00-0.00E+00l I
I I
l l
l lBALA140 36l 0.00E+00l 0.00E+00(
0/ 27) l 0.00E+00(
0/ 9) l 0.00E+00(
0/ 9) l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)
Zero range irrjicates no detectable activity measurements if LLD is equal to 0, then LLC is not required by Technical Specifications Appendix 8 Page 3 N
P
Environmental Radiological Monitoring Program Summary Name of Facility
- CATAWSA NUCLEAR STATION Docket Ntsnber 50 413,414 Location of Facility : COUNTY, S.C.
Reporting Period : 1 JAN 1995 through 31 0EC 1995 Time Report Generated : 11-JAN-1996 13:50:42 Database Name
- 50!SK13 (USER.ASC] CATAWBA NUCLEAR STATION 95.SAF;3 l
l l
l Location with Highest Mean l lNo.of Medlun or l Type & Total l Lower l
All Indicator
l l Non-Pathway l Ntaber of l Limitofl Locations Name, Distance and Direction l Control Locations l Routing Sagled l
Analyses l Detection l Mean (Fraction)
Location Mean (Fractic.1) l Mean (Fraction) l Report (Units) l Performed l (LLD) l Range l Code Ranoa l
Range l Meas.
CROPS l
l l
l l
l (FCI/ WET /r0) l l
l l
lNOCONTROLLOCATION l l
l l
l l
l 1 LOCATION l MN 54 9l 0.00E+00l 0.00E+00(
0/ 9) l 0.00E+00(
0/ 9) l 0.00E+00(
0/ 0) l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l
1 i
i l
I lCO-58 9l 0.00E+00l 0.00E+00(
0/ 9) [
0.00E+00(
0/ 9) 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 1
I I
I I
I lFE59 9l 0.00E+00l 0.00E+00(
0/ 9) l 0.00E+00(
0/ 9) l 0.00E+00(
0/ 0) l 0
l l
l 0.00E+00. 0.00E+00 l 0.00E+00. 0.00E+00 l 0.00E+00. 0.00E+00 l l
1 1
I I
I lCo-60 9l 0.00E+00l 0.00E+00(
0/ 9) l 0.00E+00(
0/ 9) l 0.00E+00(
0/ 0) l 0
l l
l 0.00E+00-.0.00e+00l 0.00E+00~ 0.00e+00 l 0.00E+00. 0.00E+00 l l
1 I
I I
i lZN65 9l 0.00E+00l 0.00E+00(
0/ 9) {
0.00E+00(
0/ 9) 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
l 1
I lNS-95 9l 0.00E+00 [ 0.00E+00(
0/ 9) l 0.00E+00(
0/ 9) l 0.00E+00(
0/ 0) l 0
l l
l 0.00E+00~ 0.00E+00 l 0.00e+00 ~ 0.00e+00 { 0.00E+00-.0.00E+00l l
I I
I I
I l2R95 9l 0.00E+00l 0.00E+00(
0/ 9) l 0.00E+00(
0/ 9) 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 I
I I
I I
I lI-131 9l 60.
l 0.00E+00(
0/ 9) l 0.00E+00(
0/ 9) 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
1 I
l l
lCS134 9l 60.
l 0.00E+00(
0/ 9) l 0.00E+00(
0/ 9) l 0.00E+00(
0/ 0) l 0
l l
l 0.00E+00.0.00E+00l 0.00E+00~ 0.00E+00 l 0.00E+00 ~ 0.00E+00 l 1
1 I
I I
I lCS137 9l 80.
l 0.00E+00(
0/ 9) l 0.00E+00(
0/ 9) l 0.00E+00(
0/ 0) l 0
l l
l 0.00E+00~ 0.00E+00 l 0.00E+00~ 0.00E+00 [ 0.00E+00--0.00E+00l 1
I i
l l
l lBALA-140 9l 0.00E+00l 0.00E+00(
0/ 9) l 0.00E+00(
0/ 9) 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 Mean and range based upon detectable mea %rements only Fraction of detectable measurements at specified tocations is indicated in parentheses, (Fraction)
Zero range indicates no detectable activity measurements If LLO is equal to 0, then LLD is not required by Technical Specificatiors Appendix 8 - Page 4
Envirorunratd R:ediologicat Monitoring Program Sumiary Name of FaclLity CATAWBA NUCLEAR OTMION Docket Nunber 50 413,414 Location of Facility : COUNTY, S.C.
Reporting Period : 1-JAN 1995 through 31 0EC 1995 Time Report Generated : 11 JAN 1996 13:50:42 Database Name S0!SK1:(USER.ASC] CATAWBA NUCLEAR STATION 95.SAF;3 l
l l
l Location with Highest Mean l lNo.of Mediun or l Type & Total l Lower l All Indicator l--'-"-""""""-"""---l l Non-Pathway l
Nurber of l Limitofl Locations l Name,DistanceandDirectionl Control Locations l Routine samled l
Analyses l Detection l Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction). l Report (Units) l Performed j (LLD) l Range l Code Range l
Range l Meas.
DRINKING WATER l
l l
l l
l (pct / LITER) l l
l l
l218(13.5 min) l l
1 1
I I
l 2 LOCAft0NS l ANAL 1-LL 26l 1.0 l 0.00E+00(
0/ 13) l 0.00E+00(
0/ 13) l 0.00E+00(
0/ 13) l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00 " 0.00E+00 l 0.00E+00-0.00E+00[
l i
I I
I I
l ANAL 2LL 26l 1.0 l 0.00E+00(
0/ 13) l 0.00E+00(
0/ 13) l 0.00E+00(
0/ 13) l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00 " 0.00E+00 l 0.00E+00 " 0.00E+00 l 1
I I
I I
I l MN 54 26l 15.
l 0.00E+00(
0/ 13) 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 I
I I
I I
I lCo-58 26l 15.
l 0.00E+00(
0/ 13) l 0.00E+00(
0/ 13) l 0.00E+00(
0/ 13) l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00 " 0.00E+00 l 0.00E+00 " 0.00E+00 l 1
1 I
I I
I lFE59 26l 30.
l 0.00E+00(
0/ 13) l 0.00E+00(
0/ 13) l 0.00E+00(
0/ 13) l 0
l l
l 0.00E+00 " 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l
l l
l l
1 lCO-60 26l 15.
l 0.00E+00(
0/ 13) 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[ 0.00E+00- 0.00E+00 l l
l l
l l
l l 2N 65 26l 30.
l 0.00E+00(
0/ 13) l 0.00E+00(
0/ 13) l 0.00E+00(
0/ 13) l 0
l l
l 0.00E+00 " 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00{
l l
I I
I i
lNS95 26l 15.
l 0.00E+00(
0/ 13) 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 i
I I
I I
lZR95 26l 15.
l 0.00E+00(
0/ 13) 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
1 I
I I
I l t 131 26 l 15.
l 0.00E+00(
0/ 13) l 0.00E+00(
0/ 13) l 0.00E+00(
0/ 13) l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00 " 0.00E+00 l 0.00E+00 " 0.00E+00 l l
l l
l l
l lCS-134 26l 15.
l 0.00E+00(
0/ 13) l 0.00E+00(
0/ 13) l 0.00E+00(
0/ 13) l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00" 0.00E+00 l l
l 1
I l
l l CS 137 26l 18.
l 0.00E+00(
0/ 13) l 0.00E+00(
0/ 13) l 0.00E+00(
0/ 13) l 0
l l
l 0.00E+00 " 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l l
l l
1 I
I lBALA140 26l 15.
l 0.00E+00(
0/ 13) l 0.00E+00(
0/ 13) l 0.00E+00(
0/ 13) l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l 0.00E+00--0.00E+00l Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)
Zero range indicates no detectable activity measurements If LLO is equal to 0, then LLO is not required by Technical Specifications Appendix p - Page 5
Environmental Radiological Monitoring Program Surmary Name of Facility
- CATAWSA NUCLEAR STAfl0N Oocket Ntater
- 50-413,414 Location of Facility : COUNTY, S.C.
Reporting Period ? 1-JAN-1995 through 31 DEC 1995 Time Deport Generated : 11 JAN-1996 13:50:42 Database Name
- $0lSK1:(USER. ASC)CATAWSA NUCLEAR STATION 95.SAF;3 l
l l
l Location with Highest Mean l lNo.of Medlun or l Type & Total l Lower l All trdicator l----
-l l Non-Pathway l Nunber of l Limitofl Locations l Name,DistanceandDirectionl 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 (LLO) l Range l Code Range l
Range l Meas.
CRINKING WATER l l
l l
l l
(PCl/ LITER) l l
l l
l218(13.5 min) l l
l l
l 214 (7.3 Mi NNE) l l
2 LOCAT10NS l BETA 26l 4.0 l
4.8
( 11/.. 13) l 4.8
( 11/ 13) l 4.5
( 11/ 13) l 0
l l
l 2.3 7.8 l
2.3
-- 7.8 l
1.7 13.
l Dw TRifium l
l l
l l
l (PCl/ LITER) l l
l l
l l
l l
l l214 l
l 2 LOCATIONS lH-3 8l 2.00E+03l 4.28E+02(
1/ 4) l 4.28E+02(
1/ 4) l 2.21E+02(
1/ 4) l 0
l l
l 4.28E+02-4.28E+02l 4.28E+02-4.28E+02 l 2.21E+02--2.21E+02l Dean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction) 2ero range indicates no detectable activity measurements If LLD is equal to 0, then LLD is not required by Technical Specifications Appendix B. Page 6
Envircranental Radiological Monitoring Program Sumary Name of FaclLity
- CATAWBA NUCLEAR STATION Occket Nuter
- 50 413,414 Location of Facility : CCUNTY, S.C.
Reporting Period. 1-JAN 1995 through 31-CEC 1995 Time Report Generated : 11-JAN 1996 13:50:42 Database Name
- $0!SK1:(USER. ASC] CATAWBA NUCLEAR STATION 95.SAF;3 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-Pathway l Nunber of l Limitofl Locations l Name,DistanceandOfrectionl 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
Corte Range l
Range l Meas.
ilSN l
l l
l l
l (PCl/ WET /KG) l l
l l
l216(4.0MiNNE) l l
l l
l208(0.5 mis) l l
2 LOCATIONS lMN-54 12l 1.30E+02l 20.
(
1/ 6) l 20.
(
1/ 6) l 0.00E+00(
0/ 6) [
0 l
l l
20.
-- 20.
l 20.
20.
l 0.00E+00-0.00E+00l l
l l
l208 l
l l CO 58 12l 1.30E+02l 1.10E+02<
3/ 6) l 1.10E+02(
3/ 6) l 0.00E+00(
0/ 6) [
0 l
l l
14.
--2.54E+02l 14
-2.54E+02l 0.00E+00--0.00E+00l l
l l
1 I
I lFE-59 12l 2.60E+02l 0.00E+00(
0/ 6) l 0.00E+00(
0/ 6) l 0.00E+00(
0/ 6) l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l f
I I
I I208 l
l lCO-60 12l 1.30E+02l 92.
(
1/ 6) l 92.
(
1/ 6) l 0.00E+00(
0/ 6) l 0
l l
l 92.
-- 92.
l 92.
-- 92.
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+00 l 0.00E+00. 0.00E+00 l 0.00E+00. 0.00E+00 t i
I I
i l
I lN895 12l 0.00E+00l 0.00E+00(
0/ 6) l 0.00E+00(
0/ 6) l 0.00E+00(
0/ 6) l 0
l l
l 0.00E+00- 0.00E+00 l 0.00E+00- 0.00E+00 l 0.00E+00--0.00E+00[
l i
I I
I i
lZR95 12 l 0.00E+00l 0.00E+00(
0/ 6) l 0.00E+00(
0/ 6) l 0.7)E+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
1 l
I I
1 lI131 12l 0.00E+00l 0.00E+00(
0/ 6) l 0.00E+00(
0/ 6) l 0.00E+00(
0/ 6) l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l l
l 1
1 I
I lCS-134 12l 1.30E+02l 0.00E+00(
0/ 6) l 0.00E+00(
0/ 6) l 0.00E+00(
0/ 6) l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00- 0.00E+00 l 0.00E+00-0.00E+00l l
1 1
I208 I
I lCS137 12l 1.50E+02l 30.
(
4/ 6) l 30.
(
4/ 6) l 15.
(
1/ 6) l 0
l l
l 25.
39 l
25.
-- 39.
l 15.
15.
l l
l 1
I I
I lBALA140 12l 0.00E+00l 0.00E+00(
0/ 6) l 0.00E+00(
0/ 6) l 0.00E * '30(
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 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)
Zero range indicates no detectable activity measurements If LLO is equal to 0, then LLO is not required by Technical Specifications Appendix B Page 7
environmental Radiological Monitoring Program Sunnary Name of Facility
. CATAW8A NUCLEAR STATION cocket Nuter 50 413,414 Location of Facility : COUNTY, S.C.
Reporting Perico bJAM 1995 through 31.oec.1995 Time Report Generated ? 11.JAN 1996 13:5o:42 catabase Name t So l ski t (USER. ASC) CATAWSA NUCLEAR STATION 95. SAF;2 l
l l
l Location with HigNst Mean l lNo.of Mediun or l Type & Total l Lower l
Att Indicator
[........-.....--..........-...l l Non-Pathway l Nuter of l Limit of l Locations l Name,oistanceandoirectionl Control Locations l Routine Sarrpled l
Analyses joetectionl Mean (Fraction) l Location Mean (Fraction) l Mean (Fraction) l Report (Units) l Perforced l (Llo) l Range l Code Range l
Range l Meas.
GROUND wafer l
l l
l l
l (pct / LITER) l l
l l
lNoCoNTRolLoCAT!oN l I
I I
i l
I 2 LoCAtloNS lH3 8l 2.0ce+o3l 0.00e+o0(
o/
8)'l 0.coe+o0( 0/ 4) l 0.0ce+0c(
0/ 0) l o
[
l l o.coe+00..o.coe+0cl 0.0oe+00.o.0ce+ool 0.0oe+00--0.00e+0cl 1
1 1
1 I
I l MN 54 8l 15.
l o.coe+o0( o/ 8) l 0.0ce+0o(
0/ 4) l o.o0e+00(
o/ 0) l o
l l
l 0.0oe+oo-.o.0ce+0al 0.coE+oo--o.ooe+0cj o.0ce+00-o.coe+0al I
I I
I I
I lCo.58 8l 15.
I o.00s+oo( 0/ 8) I o.0oe+ow o/ 4) i o.oce+oo( of o) l o
l l
l o.0ce+oo..o.0oe+ool o.coe.co.. o.00s co I o.00e+ao.. o.coe+oo 1 i
l l
I I
I lFe-s9 8l 30.
l o.00e+oo( o/ 8) j o.coe+00(
o/ 4) l o.0oe+00(
0/ 0) l o
l l
l o.0a+oo..o.0ce+ool o.0ce+00..o.coe+ool 0.coe+00. 0.0ce+oo l 1
I I
I I
I lCo.60 8l 15.
I o.ow+co( of 8) I c.coe.co( o/ 4) 1 0.0ce+0o(
o/ o) 1 0
l l
l o.0oe+co..o.ca+ool 0.coe+00..o.coe+ool c.0ce+co..o.oos+col l
l I
I l
l lzN.65 8l so.
l 0.00e+0c(
0/ 83l o.coe+co( Of c) l o.coe+0a( o/ o) I o
l I
l o.coe+co-.c.c0e+col c.0ce co.. o.coe+oo 1 0.0x +00.
0.coe+oO !
I I
I l
lNs-95 8l 15.
l 0.ox.c0(
0/ 831 0.coe+0c(
o/ 43l o.coe+0a( of o) l o
l I
i o.0*+oo..o.0ce+ooI o.coe+oo..o.coe.col o.00s+00..o.coe+ool l
1 1
I I
I l2R95 8l 15.
l 0.0ce+00(
0/ 8) l o.00e+00(
0/ 4) l o.0ce+00(
0/ o) l 0
l l
l o.0oe+oo..o.coe+ooI a.0oe+o0. 0.coe+oo I o.coe+00. 0.coe+oo l l
l i
I I
l l I-131 8l 15.
l 0.0oe+0o(
of 8) l o.coe+00( 0/ 4) l 0.coe+00( o/ 0) l 0
l l
l o.00e+00 0.00e+oo l o 00e+00 0.0oe+0cl 0.coe+oo..o.0oe+00l l
1 I
I i
l lCS-134 8l 15.
l 0.oce+00(
of 83l o.00e+oo(
of 4> l o.ox+0a(
of c) l o
l l
l 0.0cc+00. 0.ooe+0o l o.oce+00..o.coe+0cl 0.0:e+oo..o.0ce+00l l
1 I
i i
I lCS137 8l 18.
l o.0oe+00(
o/ 8) l 0.00e+0o(
o/ 4) l 0.oCe+00(
o/ 0) l 0
l l
l o.coe+00..o.o0s.col o.oce+00..o.coe+ool 0.ooe+oo..o.0ce+00l l
l l
l 1
l l84tA.140 8l 15.
I o.coe+oo( 0/ 83 l 0.coe+oo( of 4) l o.ooe+oo( Of 0) l o
l l
l 0.ooe+00-.o.coe+ool 0.00e+00.o.00e+0cl 0.00s+oo..o.ooe+oOl Mean ard range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)
Zero range Indicates no detectable activity measurements if LLo is equal to 0, then LLo is not required by Technical Specifications Appendix 8 - Page 8 l
Environmental Radiological Monitoring Prograta Suianary Name of Facility
- CATAWBA NUCLEAR STAf!ON Docket Nunber s 50 413,414 Location of FaclLity : COUNTY, S.C.
Reporting Period. 1-JAN-1995 through 31 DEC 1995 Tisa Report Generated : 11-JAN 1996 13:50:42 Database Name 50!SK1:(USER.ASC]CATAW8A NUCLEAR STATION 95.SAF;3 l
l l
l Location with Mighest Mean l l No. of Medlun or l Type 8 Total l Lower l
All Indicator l-- ---- - - ----- --
*.l l Non-Pathway l
Nunber of l Limitofl Locations l Name,DistanceandDirectionl
.% trol L x ations l Routine Styled 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 j
Range l Meas.
iLr l
l l
l l
l
.PCl/ LITER) l l
l l
l221(12.3MiNV) l 1
I I
I I
I LOCAr:0NS l +54 78l 0.00e+00l 0.00e+00(
0/ 52) l 0.00E+00(
0/ 263l 0.00e+00(
0/ 26) l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00-0.00E+00l 0.00E+00- 0.00E+00 [
l l
I I
I I
lCo-58 78l 0.00E+00l 0.00E+00(
0/ $2) 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.t0E+00l 0.00E+00--0.00E+00l l
l l
l 1
l lFE59 78l 0.00E+00l 0.00E+00(
0/ 52) 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 l
l 1
I I
I lCo-60 78l u.00E+00l 0.00E+00(
0/ $2) 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 [ 0.00E+00--0.00E+00[
l l
I i
l l
lZN-65 78l 0.00E+00l 0.00E+00(
0/ 52) l 0.00E+00(
0/ 26) l a.00E+00(
0/ 26) l 0
l l
l 0.00E+00-0.00E+00l 0.00E+00--0.00E+00l L).00E+00 - 0.00E+00 l I
I I
I I
I lNS95 7Ll 0.0G?+00l 0.00E+00(
0/ 52) 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 l
l l
l 1
I lZR95 78j 0.00E+00l 0.00E+00(
0/ 52) 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 l
l 1
I i
lI131 78l 15.
l 0.00E+00(
0/ 52) l 0.00E+00(
0/ 26) l 0.00E+00(
0/ 26) l 0
l l
l 0.00E+00.-0.00E+00l 0.00E+00. 0.00e+00 l 0.00E+00--0.00E+00l 1
I I
I l
l lLLI-131 78l 1.0 l 0.00E+00(
0/ 52) 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 1
1 I
I i
1 lCS-134 78l 15.
l 0.00E+00(
0/ $2) l 0.00E+00(
0/ 26) l 0.00E+00(
0/ 26) l 0
l l
l 0.00E+00 0.00E+00 l 0.00E+00. 0.00E+00 l 0.00E+00-.0.00E+00l l
l l
l209(7.0Mi$$W) l
[
lCS-137 78l 18.
l 8.6
(
1/ 52) !
8.6
(
1/ 26) l 0.00E+00(
0/ 26) l 0
l l
l 8.6
-- 8.6 l
8.6
-- 8.6 l 0.00E+00-0.00E+00l l
l l
1 1
I l8ALA-140 78l 15.
l 0.00E+00(
0/ f2) l 0.00E+00(
0/ 26) l 0.00E+00(
O! 26) l 0
l l
l 0.00E+00-0.00E+00l 0.00E+00--0.00E+00l 0.00E+00- 0.00t*00l ean and range based upon detectable measurements only raction of detectable measurements at specified locations is indicated in arentheses, (Fraction) ero range indicates no detectable activity measurements f LLO is equal to 0, then LLD is not required by Technical Sp M ficat N s Appendix 8 - Page 9
Environmental Radiological Monitoring Prograra Stmnary Name of Facility
- CATAW8A NUCLEAR STATION Docket N mber
- 50-413,414 Location of Facility : COUNTY, S.C.
Reporting Period : 1-JAN 1995 through 31 DEC-1995 Tia2 Report Generated + 11-JAN-1996 13:50:42 Database Name
- $0!SK1:CUSER.ASC] CATAWBA NUCLEAR STATION 95.SAF;3 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-Pathway l
Nurber of l Limitofl Locations l Name,DistanceandDirectionl Control Locations l Routine Sampled l
Analyses l Detection l Mean (Frar' 1 l Location Mean (Fraction) l Mean (Fraction) l Report (Units) l Performed l (LLD) l Range l
Code Range l
Range l Meas.
SEDIMENT l
l l
l l
l (PCI/0RY/KO) l l
l l
l215(4.1MiNNE) l l
l l
l208(0.5 mis) l l
3 LOCATIONS lMN54 6l 0.00E+00l 41.
(
1/ 4) l 41.
(
1/ 2) l 0.00E+00(
0/ 2) l 0
l l
l 41.
-- 41.
l 41.
41.
l 0.00E+00--0.00E+00l 1
I I
I208 l
l lCO-58 6l 0.00E+00l 2.54E+02(
2/ 4) l 2.54E+02(
2/ 2) l 0.00E+00(
0/ 2) l 0
l l
l 1.38E+02-3.70E+02l 1.38E+02--3.70E+02l 0.00E+00--0.00E+40l l
l l
I I
I lFE-59 6l 0.00E+00l 0.00E+00(
0/ 4) l 0.00E+00(
0/ 2) l 0.00E+00(
0/ 2) l 0
l l
l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 1
I I
I208 I
i lCo-60 6l 0.00E+00l 3.41E+02(
2/ 4) l 3.41E+02(
2/ 2) l 0.00E+00(
0/ 2) l 0
l l
l 1.05E+02-5.76E+02l 1.05E+02--5.76E+02l 0.00E+00--0.00E+00l l
l 1
I I
I l2N65 6l 0.00E+00l 0.00E+00(
0/ 4) l 0.00E+00(
0/ 2) l 0.0M +00(
0/ 2) l 0
l l
l 0.00E+00-0.00E+00l 0.00E+00-0.00E+00l 0.00E+00--0.00E+00l l
l l
l l
I lNS95 6l 0.00E+00l 0.00E+00(
0/ 4) l 0.00E+00(
0/ 23l 0.00E+00(
0/ 2) l 0
l l
l 0.00E+00-0.00E+00l 0.00E+00.0.00E+00l 0.00E+00--0.00E+00l 1
1 I
I I
I l2R-95 6l 0.00E+00l 0.00E+00(
0/ 4) l 0.00E+00(
0/ 2)l 0.00E+00(
0/ 2) l 0
l l
l 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 ll131 6l 0.00E+00l 0.00E+00(
0/ 4) l 0.00E+00(
0/ 2) l 0.00E+00(
0/ 2) l 0
l l
l 0.00E+00--0.00E+00l 0.00E.00. 0.00E+00 l 0.One+00. 0.00E+00 l 1
I I
I i
I lCS134 6l 1.50E+02l 0.00E+00(
0/ 4) l 0.00E+00(
0/ 2) l 0.00E+00(
0/ 2) l 0
l l
l 0.00E+00-0.00E+00l 0.00E+00. 0.00E+00 l 0.00E+00-.0.00e+00l 1
I I
I208 l
l lCS137 6l 1.80E+02l 85.
(
2/ 4) l 85.
(
2/ 2) l 0.00E+00(
0/ 2) l 0
l l
l 37.
-- 1.33E+02l 37.
- 1.33E+02 l 0.00E+00--0.00E+00l l
l l
l l
1 lBALA140 6l 0.00E+00l 0.00E+00(
0/ 4) l 0.00E+00(
0/ 2) l 0.00E+00(
0/ 2) l 0
l l
l 0.00E+00-0.00E+00l 0.00E+00--0.00E+00l 0.00E+00 0.00E+00 l 03ean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)
Zero range indicates no detectable activity measurements If LLO is equal to 0, then LLO is not required by technical Specifications Appendix 8 - Page 10
Environmental Radiological Monitoring Program Surmary Nama of Facility CATAWSA NUCLEAR STAfl0N Occket Nunber
- $0-413,414 Location of Facility COUNTY, S.C.
Reporting Period : 1 JAN 1995 through 31 DEC-1995 Tima Report Oenerated : 11-JAN-1996 13:50:42 Database Name
- $0lSK1:(USER.ASC) CATAWBA NUCLEAR STATICN95.SAF;!
l l
l l
Location with Highest Mean l lNo.of Medium or l Type & Total l Lower l
Att Indicator l------------------------l l Non-Pathway l NLsrber of l Limitofl Locations l Name,DistanceandDirectionl Control Locations l Routine Sarnpled 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.
SURFACE WATER l
l l
l l
l (PCl/ LITER) l l
l l
l215(4.1MiNNE) l 1
I I
I I
3 LOCATIONS lMN-54 39 15.
l 0.00E+00(
0/ 26) l 0.00E+00(
0/ 13) l 0.00E+00(
0/ 13) l 0
l l 0.00E+00--0.00E+00l 0.00E+00- 0.00E+00 l 0.00E+00 0.00E+00 l l
1 I
I I
I lCO-58 39l 15.
l 0.00E+00(
0/ 26) l 0.00E+00(
0/ 13) l 0.00E+00(
0/ 13) [
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 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+00l 0.00E+00- 0.00E+00 [ 0.00E+00--0.00E+00l l
I I
I I
i lCo-60 39l 15.
l 0.00E+00(
0/ 26) l 0.00E+00(
0/ 13) l 0.00E+00(
0/ 13) {
0 l
l l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l
1 I
I I
I lZN-65 39 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+00l 0.00E+00- 0.00E+00 l 0.00E+00-0.00E+00l l
l I
1 l
lNS-95 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+00l 0.00E+00--0.00E+00l 0.00E+00--0.00E+00l l
1 I
I I
l lZR95 39 l 15.
l 0.00E+00(
0/ 26) l 0.00E+00(
0/ 13) l 0.00E+00(
0/ 13) {
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 l-131 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+00l 0.00E+00-0.00E+00l 0.00E+00 0.00E+00 l l
l l
I i
l lCS134 39l 15.
l 0.00E+00(
0/ 26) l 0.00E+00(
0/ 13) l 0.00E+00(
0/ 13) l 0
l l
l 0.00E+00- 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00- 0.00E+00 l I
I I
I I
l l CS-137 39 l 18.
l 0.00E+00(
0/ 26) l 0.00E+00(
0/ 13) l 0.00E+00(
0/ 13) [
0 l
l l 0.00E+00- 0.00E+00 l 0.00E+00--0.00E+00l 0.00E+00 0.00E+00 l l
l 1
l i
I lBALA140 39l 15.
l 0.00E+00(
0/ 26) l 0.00E+00(
0/ 13) l 0.00E+00(
0/ 13) l 0
l l
l 0.00E+00- 0.00E+00 l 0.00E+00-.0.00e+00l 0.00E+00. 0.00E+00 l SW TRITIUM l
l l
l l
l (PC1/ LITER) l l
l l
}215(4.1MiNNE) l l
l l
l208(0.5 mis) l l
3 LOCAfl0NS lH3 12l 2.00E+03l 4.17E+03(
5/ 8) l 5.13E+03(
4/
- 4) l 2.89E+02(
1/ 4) l 0
l l
l 3.48E+02--1.06E+04l 9.02E+02--1.06E+04l 2.89E+02--2.89E+02l Mean and range based upon detectable measurements only Fraction of detectable measurements at specified Locations is indicated in parentheses, (Fraction)
Zero range indicates no detectable activity measurements if LLD is equal to 0, then LLD is not required by Technical Specifications Appendix 8 - Page 11
Environmental Radiological Monitoring Program Surrnary Name of Facility
- CATAWBA NUCLEAR STATION Docket Nunber 50 413,414 Location of Facility : YORK COUNTY, S.C.
Reporting Period : 1 JAN 199> through 31 0EC-1995 Time Report Generated : 17 JAN-199615:58:04 Database Name
- 50!SK1:(USER.ASC)CNS95.SAF:3 l
l l
l Location with Highest Mean l l No of Medlun or l Type & Total l Lower l
All Irdicator l------------------------l l Won-Pathway Nurber of l Limitofl Locations l Name, Distance and Direction l Control Locations l Routine Sanpled 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.
0! RECT RAD-TLD l
l l
l l
l (mR/ QUARTER) l l
l l
l l
l l
l l 206 (0.7 Mi WW) l l
40 LOCATIONS l Wt/QTR 159l 0.00E+00l 24
( 147/ 147) l 28.
(
4/ 4) l 20.
( 12/ 12) l 0
l l
l 14 37.
l 27.
-- 31.
l 15.
24.
l Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)
Zero range indicates no detectable activity measurements if LLD is equal to 0, then LLO is not required by Selected Licensee Connitments
- Control Locations: 217 (10.0 Mi SSE) 247 (7.5 Mi ESE) 251 (9.8 Mi WW)
Appendix 8 - Page 12
Catawba Nuclear Station Sites 208-IS,208-2S,208-3S Shoreline Sediment Results for 1995 Sample Year 208-IS The activities for 208-IS were taken from the APPENDIX B, Page 10 Indicates Highest Mean ALL 1995 MEAN VALUE for Sample Medimn (H)
Mn54 41.00 41.00 CoS8 254 00 254.00 Nb95 Sbl25 Co60 341.00 341.00 Csl37 85.00 85.00 H
Snll3 CoS7 208-2S IQ95 2Q95 3Q95 4Q95 Mn54 42.70 43.10 281.00 122.27 H
Cc58 77.70 561.00 357.00 4310.00 1326.43 H
Nb95 113.00 113.00 H
Sb125 73.70 58.60 200.00 110.77 Co60 332.00 311.00 2190.00 944.33 H
Csl37 27.10 41.70 74.30 78.10 55.30 Snll3 71.10 71.10 H
CoS7 36.90 36.90 H
208-3S IQ95 2Q95 3Q95 4Q95 Mn54 37.10 41.20 151.00 76.43 Co58 345.00 776.00 232.00 1724.00 769.25 Nb95 61.20 61.20 Sbl25 115.00 177.00 67.80 234.00 148.45 H
Co60 297.00 417.00 235.00 935.00 471.00 Csl37 103.00 91.60 43.50 58.80 74.23 Snll3 CoS7 Appendix B - Page 13 l
l l.
Catawba Nuclear Station Site 208 Fish (Predator, Forager, Bottom Feeder) Results for 1995 Sample Year
=.
208 - Predator (Bass)
Indicates Highest Mean 3/29 6/14 9/20 12/6 MEAN VALUE for Sample Medium (H)
Mn54 CoS8 Co60 Nb95 Csl37 30.8 20.8 25.1 23.9 67.7 H
208 - Forager (Sunfish)
Mn54 19.70 26.00 32.40 56.50 H
CoS8 254.00 385.00 62.60 754.00 890.10 H
Co60 92.50 114.00 169.00 265.50 H
Nb95 13.80 13.80 H
Csl37 25.10 25.10 208 - Bottom Feeder (Catfish)
Mn54 CoS8 19.90 14.10 151.00 84.30 Co60 Nb95 Csl37 39.00 12.10 45.10 Appendix B - Page 14
/
r.---_---.,-----
APPENDIX C SAMPLING DEVIATIONS UNAVAILABLE ANALYSES
APPENDIX C CATAWBA NUCLEAR STATION SAMPLING DEVIATIONS & UNAVAILABL;E ANALYSES DEVIATION & UNAVAllABil RFASON CODES HF Blovm Fuse PO Power Outage FZ Sample Frozen PS Pump out of service / Underrotng Repair IW Inclement Weather St.
Sarnple less1mst due to laboratory Accident tr Line Clog to Sarnpler sat hiotor / Rotor Seaed OT Other TF Torn Filter PI Power Interrupt VN Vandahsm PNt Preventive Ntatntenance C.1 SAMPLING DEVIATIONS The following deviations from sampling requirements occurre i during 1995:
Air Particulate and Air Radiciodines Location Scheduled Actual Collection Reason Corrective Action Collection Datee Dates 200 5/31-6/7/95 5/31-6/1/95 PI Reset breaker and tried to restart sampler. Breaker tripped again.
Contacted CNS staff for repairs.
8/23-8/30/95 8/23-8/27/95 PO Power was lost to sample station.
Notified CNS staff to contact 1&E technician.
I1/1-11/8/95 11/1 11/2/95 PO Reset breaker. Breaker trip probably due to inclement weather.
I 11/8-11/15/95 11/8-11/11/95 PO Reset breaker. Breaker trip probably due to severe thunderstorms on 11/11.
205 4/5-4/12/95 4/5/95 BF Reason unknown. Replaced f"se and noted incident on sampler tag.
5/24-5/31/95 5/24-5/28/95 BF Reason unknown Replaced fuse and noted incident on sampler tag for sampler #8.
217 2/8-2/15/95 2/8-2/11/95 BF Pam unx.,own Replaced air sampler
- LVAS 17.
5/24-5/31/95 5/24-5/30/95 BF Reason unkncwn. Replaced fuse and noted incident on sampler tag for t
sampler #1191.
Appendix C Page 1
Drinking Water Location Scheduled Actual Collection Reason Corrective Action Collection Dates Dates 214 2/15-3/1/95 3/1/95 PS No water flowing to sampler. Collected grab sample.
3/1-3/15/95 3/8-3/15/95 OT Valve to water supply was closed.
Reopened valve. Collected an abbreviated sample.
218 8/16-8/30/95 8/30/95 VN Drain valve was open and there was no water in tank. Closed drain. Collected grab sample.
Surface Water Location Scheduled Actual Collection Reason Corrective Action Collection Dates Dates 208 3/1-3/15/95 3/15/95 PS Collected grab sample. (a) 3/15-3/29/95 3/29/95 PS Collected grab sample.
3/29-4/12/95 4/12/95 PS Collected grab sunple.
4/12-4/26/95 4/26/95 PS Collected grab sample.
4/26-5/10/95 5/10/95 PS Collected grab sample.
5/10-5/24/95 5/24/95 PS Collected grab sample.
5/24-6/7/95 6n/95 PS Collected grab sample.
6n-6/21/95 6/21/95 PS Collected grab sample.
6/21-7/5/95 7/5/95 PS Collected grab sample.
7/5 7/19/95 7/19/95 PS Collected grab sample.
7/19 8/2/95 8/2/95 PS Collected grab sample.
215 7/19-8/2/95 8/2/95 PS Collected grab sample. Pump was not working. Notified CNS staff to initiate work request.
8/2-8/16/95 8/l1-8/16/95 PS Collected abbreviated sample. Pump wiring was defective. Work request was completed on 8/l1/95 and equipment l was returned to senice.
(a) Following repeated problems with Site 208 sampler operation, a work plan was created and initiated 3/15/95. Maintenance scheduling team reviewed location week of 4/1/95. Following discussions between Engineering Staff and Radiation Protection Staff, the decision was made to completely renovate the sampler / pier location. Work on the plans and materials began 4/20/95. Additional work control steps were taken to assure proper parts, drawings and scheduling. Completion of all construction was accomplished 7/15/95 and following testing and reordering electrical components Site 208 was returned to senice on 8/2/95.
Appenix C - Page 2
C.2 UNAVAILABLE ANALYSES The following unavailable analyses occurred during 1995:
Air Particulate and Air Radiciodines Lo:ation Scheduled Reason Corrective Action Collection Dates 200 6n4/14/95 IW Water collected in receptacle causing breaker to continuously trip. Outlet will be waterproot: d.
8/30-9/16/95 PO The breaker had tripped. Reset breaker.
TLD Iecation Scheduled Reason Corrective Action Collection Dates 233 3/30-6/29/95 VN Branch of tree had been trimmed and TLD was missing.
Replaced with 3rd Quaner TLD.
C.3 SAMPLE DEVIATION AND UNAVAILABLE REDUCTION PLAN Re sampling deviation and reduction plan was initiated by the REMP working group on 9/25/95.
Items were identified to be addressed and/or implemented to reduce the number of sample deviations and unavailable samples. Table C.3 A identifies the plan's schedule and activities.
TABLE C.3-A Deviation Reduction Plan Overview Actisity Date Target Date STATUS Description Initiated Completion CODE Purchase additional air samplers for dual air monitoring 10/5/95 10/5/95 C
Purchase "ISCO" portable composite water samplers 10/5/95 10/5/95 C
Consistent Deviation / Unavailable codes implemented 10/5/95 10/5/95 C
Air site electrical modifications 10/9/95 6/1/%
I Air site grounding 10/10/95 6/1/96 I
Deviation section of AEOR to include more detail 10/17/95 11/15/95 C
i Modify air sampler housing to accommodate dual samplers 1/1/96 3/31/96 P
P = Pending, I ~ In Process, C = Comp /eted l
Appenhx C - Page 3
PURCHASE ITEMS Table C.3-B lists items for the emironmental monitoring program that were purchased to improve and enhance the environmental sample collection program. Included are sampling equipment and supplemental sampling items.
TABLE C.3-B Deviation Reduction Plan Equipment Purchases Sample Stream ITEM DESCRIPTION ITEM QUANTITY AIR 1/3 HP low volume air sample pump 8
AIR Elapsed time meter,0.0 - 999.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> (may be reset) 8 AIR NEMA conduit box for elapsed time meter 8
WATER "lSCO" model 3710 portable composite sampler 2
WATER Model 913 power converter & battery charger.120/60 2
WATER 100' of 3/8" bulk vinyl suction tube 2
WATER 3/8" vinyl suction line accessorv kit 2
WATER Weighted 3/8" stainless steel strainer 2
WATER Silicone rubber pump tube. 50' roll I
WATER Model 934 nickel-cadmium rechargeable batterv pack 1
SITE MODIFICATIONS AIR SITES - Air sampler modifications willinclude the following:
1 - Purchase additional air samplers for dual air monitoring to be implemented at each environmental air monitoring site. The additional samplers will be housed in existing sample houses.
2 - Upgrade electrical equipment at each air sample site. This will include the installation oflightning arrestors, waterproof outlets, GFCI breakers, and surge protectors.
3 - Grounding of air sample houses and air sample cages to < 0.025 ohms.
4 - Modify air sample houses to allow for sufficient heat removal during summer months.
Currently, each air sample house is cooled by a continuously operating electrical cooling fan. After electrical modifications and grounding are completed, the sample houses will be physically altered to allow for natural cross-ventilation to occur to supplement the electrical fan. Sample house door hinges on both sides of the house will be moved and reversed to allow for a small, free, open air space to be created. This modification will create additional heat removal capability during the summer months while still protecting the air samplers inside the house from the emironment (i.e. wind, rain, snow).
Appendix C - Page 4
Sample site visits and evaluations for all of Catawba's air sampling sites was perfomied on 12/11/95. The purpose was to identify the exact electrical equipment upgrade needs for each site.
Results of the site visits are displayed in Table C.3-C.
TABLE C.3-C Deviation Reduction Plan Air Site Upgrade Equipment Purchases SPECIFIC UPGRADE ITEM 200 201 205 212 217 Ground Rod w/ clamps 5/8 x 8 1
2/0 Bare Copper ft 10' 5'
WP Male Plug Woodhead 4
4 4
4 4
Multioutlet Box (4) WP receptacles 1
1 1
1 1
Vertical Fence Grd clamp
- 1. 4"
- 1. 3" Horizontal Fence Grd. Clamp Equip. Grd. Clamp 2/0 1
1 1
Single phase panel arrestor SDSAl 175 1
1 Surge suppresser 1
1 1
1 Ground Clamp 1
1 WATER SITES - Water sampler modifications will include the following:
1 - Purchase portable water compositors (ISCO) for utilization when water sites are undergoing preventive maintenance or repair.
2 - Upgrade electrical supply at each surface water site (if necessary) to accommodate the ISCO portable water composite samplers.
Amwlix C - Page 5
s a
APPENDIX D ANALYTICAL DEVIATIONS No analytical deviations were incurred for the 1995 Radiological Environmental 31onitoring Program.
Appendix D - Page 1
APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS 1995 This appendix includes all of the sample analysis reports generated from each sample medium for 1995. Appendix E is located separately from this report and is permanently archived at Duke Power Company's Environmental Center radiological environmental master file, located at the McGuire Nuclear Station Site in lluntersville, North Carolina.
Appendix E. Page I
-