ML20082P994
| ML20082P994 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 12/31/1994 |
| From: | Jerrica Johnson, Miller T, Schleiger T COLORADO STATE UNIV., FORT COLLINS, CO |
| To: | |
| Shared Package | |
| ML20082P992 | List: |
| References | |
| NUDOCS 9504280004 | |
| Download: ML20082P994 (129) | |
Text
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' FORT ST. VRAIN 's N
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PUBLIC SERVICE COMPANY O f-COLORADO ,
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PROGRAM
SUMMARY
REPORT 1994 COLORADO STATE UNIVERSITY 9so4280004 ,so42o PDR ADOCK 0500o267 7RT COLLINS, COLORADO 80523 R PDR
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- i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ;
For the Fort St. Vrain Station l Operated by the Public Service Co. of Co!orado 1
Semmary Report for the Period i January 1.1994 - December 31.1994 i
l l
I "
1 Prepared by: / !b N Jaines E. Johnsongofessor Date lorado State University Prepared by: /
Thomas Miller, Lab. Coordinator
(( k8 Date Colorado State University Reviewed by: # tI-Timothy'II. Schleiger 1/
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' Date' Senior Health Physicist Approved by: dbd(Mdf6p //20/1g Date J.forst Frederic(Protection Manager Radiation
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i Acknowledeements Many persons have contributed to this project during 1994, and it is important to acknowledge their effort. We first thank the citizens from whose farms, homes, and ranches !
i we collect the environmental samples. Without their cooperation the project would not be l possible.
We also wish to acknowledge and thank Mr. Robert Keiss and his associates as well ,
as the Colorado Division of Wildlife, Fort Collins regional office for assisting with the fish collection. Their cooperation, equipment and expertise made the collection possible. [
The persons in this laboratory working directly on the project have been:
- Charles Sampier Chief Electronic Technician i Vaughn Jones Research Associate >
Grant Johns Student Employee {
Roy DePriest Student Employee !
Gerald M. Ward Professor Emeritus ;
i DD ,
James E. on Pro essor and Project Director j s -
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Thomas S. Miller Laboratory Coordinator l
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- e o l L
l.
l TABLE OF CONTENTS Page No. ,
i Acknowledgments ii l- List of Tables iv List of Figures vii l
I. INTRODUCTION 1 1
)
II. SURVEILLANCE DATA FOR 1994 !
l AND INTERPRETATION OF RESULTS A. External Gamma Exposure Rates 6 ;
B. Ambient Air Concentrations 12 C. Radionuclide Concentration in Water 28 D. Milk 67 -
E. Food Products 76 F. Aquatic Pathways 81 G. Sample Crosscheck Program 87 t
)
H. Summary and Conclusions 97 '
.1 III. ENVIRONMENTAL RADIATION SURVEILLANCE )
l PROGRAM AND SCHEDULE 113 1
l
. _ . - . --- .~
.- . . . .. -- . ~. - . - .
l LIST OF TABLES Page No. !
I II. A.1 Gamma Exposure Rates 8 ;
II.B.1 Concentrations of long-lived Gross Beta Particulate Activity in Air l
- a. First Quarter, 14
- b. Second Quarter, 15
- c. Third Quarter, 16 1 i
- d. Fourth Quarter, 17 II.B.2 Tritium in Atmospheric Water Vapor 1
- a. First Quarter, 20-
- b. Second Quarter, 21
- c. Third Quarter, 22 ;
I
- d. Fourth Quarter, 23 l II.B.3 Tritium Released in Fort St. Vrain Effluents,1994 24 i II.B.4 Radiocesium Concentrations in Ambient Air 27 II.C.1 Gross Beta in Drinking Water
- a. First and Second Quarter '
30 ,
- b. Third and Fourth Quarter 31 l II.C.2 Tritium in Drinking Water i
- a. First and Second Quarter 32 ;
i
- b. Third and Founh Quarter 33 II.C.3 Radionuclide Concentrations in Bi-weekly Composites of Drinking Water. 34-42 iv j
,p, e 1
LIST OF TABLES (Continued) l Page No.
]
II.C.4 Tritium in Surface Water --
i
- a. First Quarter 45 -
- b. Second Quarter 46 l
- c. Third Quarter 47
, i
- d. Fourth Quarter 48
.r II.C.5 Radionuclide Concentrations in Surface 49-60 II.C.6 Radionuclide Concentrations in Ground Water 62 l I
II.C.7 Tritium in Ground Water 63 II.C.8 Maximum Permissible Concentrations in Drinking Water 64 l II.D.1 Radionuclide Concentrations in Milk 69-74 II.D.2 Tritium in Milk 75 !
'II.E.1 Radionuclide Concentrations in Food Products 78 ,
II.E.2 Radionuclide Concentrations in Beef Samples .
i
- a. Collected 5/2/94 79
- b. Collected 12/5/94 80 !
l II.F.1 Radionuclide Concentrations in Fish 83 ;
II.F.2 Radionuclide Concentrations in Sediment at Location F-1
- a. January through August 84 ;
- b. September through December 85 f
II.F.3 Radiocesium Concentrations in Sediment from location R-10 86 t
6 V
., e LIST OF TABLES (Continued)
II.G.1 EPA Cross-check Data Summary 90-91 II.G.2 Tritium Crosscheck Analyses on Split Water Samples Determined by Colorado State University and Public Service Company
- a. First and Second Quarter 92
- b. Third and Fourth Quarter 93 II.G.3 Gross Beta Crosscheck Analyses on Split Water Samples Determined by Colorado State University and Public Service Company
- a. First and Second Quarter 94 l
- b. Third and Fourth Quarter 95 I II.G.4 Intralaboratory Crosscheck Results %
II.II.1 Data Summary 103-107 II.II.2 Summary Table of Arithmetic Means and Standard Deviations for Selected Sample Types 108-110 II.J.1 Tritium Concentrations in F-16 Well Water
- a. First IIalf 111
- b. Second Half 112 III. A.1 Detection Capabilities for Environmental Sample Analysis 115 III.C.1 Land-use Census,1994 118 F
Vi
,o e LIST OF FIGURES Page No.
l Figure II. A.1 Gamma Exposure Rates, 1978-1994 (Facility Area Only) 11 Figure II.B.1 Gross Beta Concentrations in Air 18 Figure II.C.1 Tritium Concentrations in F-16 Well Water, 1984-1994
( 65 Figure II.C.2 Tritium Concentrations in F-16 Well Water 66 Figure III.B.1 Close-in Sampling Locations 116 Figure III.B.2 Adjacent and Reference Sampling Locations 117 Figure Ill.C.1 Land Use Census,1994 119 l
$ii
__-- - - - - - - - - - - ---- - ---- - - --- - -- - - - - - - - _ - - - - - A
-l
.l I. Introduction to Radiological Environmental Monitoring Program (REMP) Data for the Period January 1,1994 - December 31,1994.- !
During 1994 the Fort St. Vrain Nuclear Station did not operate and is presently in a decommissioning phase. The operational phase of the reactor ended on August 18, 1989. Fuel removal operations were completed by June 10, 1992. The spent fuel is ,
stored nearby in an Independent Spent Fuel Storage Installation (ISFSI). !
A complete and detailed listing of radioactivity released by all effluent routes may .
be found in the Public Service Company of Colorado Annual Effluent Release Report for 1994 to the U.S. Nuclear Regulatory Commission. When possible in this report, any.
F correlation of radioactivity in environmental samples with the effluent release data is -
discussed. These discussions are presented in the appropriate sample type section and !
in the summary section, II.II. l Table III. A.2 lists the LLD values achievable by the counting systems used during 1994 on project sampics. These values are given for typical sample sizes, counting times y
and decay times. The LLD is, therefore, an a priori parameter to indicate the capability of the detection system used. The LLD values in Table III.A.2 were calculated as - -
suggested in NUREG-0472. -
Throughout the report, however, when a sample result is li:ted as less than a specified value, that value is the calculated minimum detectable concentration (MDC). i This approach is analogous to that of Currie (NUREG/CR-4007): the MDC is the same f
as S, , the critical signal, and the LLD is equal to So, the detectable signal. The MDC j i
1
l c ;
. . , - e*
l value applies to the actual sample size, counting time and decay time applicable to that individual sample. It is calculated for each radionuclide as:
imc- ., 1 i
Where: on = Standard deviation of background count rate ,
l E = Counting efficiency, c s' pCi-Y = Chemical yield (if any)
V = Sample volume (or mass) l X = 0.693/ Half-life ;
t = Decay time between sample collection and analysis This calculation method assumes that E and Y are constants and makes no allowance for l l
systematic error.
It should be noted that we have not used the notation " < MDC" for values less than MDC. Rather, we report the result as less than the actual MDC value. Because l
the MDC is dependent upon variables such as the background count time and sample i
size, the value will be different for each radionuclide for each sample type and even within sample type.
Essentially all radioactivity values measured on this project are near background levels and, more importantly, near the MDC values for each radionuclide and sample g type. It has been well-documented that environmental radioactivity values exhibit great inherent variability. This is partly due to sampling and analytical variability, but most 2
importantly due to true environmental or biological variability. As a result, the overall -
variability of the surveillance data is quite large, and it is necessary to use mean values from a rather large sample population size to draw any conclusions about the absolute radioactivity concentrations in any enviromnental pathway. -
The arithmetic mean for each sample set is listed in Table II.H.2. All measured i values, both positive and negative, are used in the calculations of the arithmetic mean.
This is the suggested practice by Gilbert (Health Physics 40:377,1984) and the NRC (NUREG/CR-4007).
Many sets of data were compared in this report. The statistical test used was either a "t"-test or a paired "t"-test. If data sets are noted to be significantly different or not significantly different, the confidence for the statement is at the 95% level ((a =
0.05), (1.96o)).
The Total Effective Dose Equivalent (TEDE) goal for decommissioning as set by the NRC (NUREG/CR-5512,1993) is 10 mrem / year for any member of the general public. This is the TEDE rate limit excluding background and medical radiation dose rate.
The maximum permissible dose commitment rate set by the EPA (40CFR190) for any specified member of the general public from any part of the nuclear' fuel cycle is 25 mrem / year.
Dose commitments can be calculated for hypothetical individuals for any mean concentrations noted in unrestricted areas that are significantly above control mean values.
The Offsite Dose Calculation Manual was changed from Issue 4 to Issue 5 3
effective September 15,1994. The revisions were made to reflect previous discrepancies between the REMP program and the ODCM.
4 -
The following is the footnote system used in this report.
- a. Sample lost prior to analysis,
- b. Sample missing :a site,
- c. Instrument malfunction.
- d. Sample lost during analysis.
- e. Insufficient weight or volume for analysis.
- f. Sample unavailable.
- g. Analysis in progress.
- h. Sample not collected (actual reason given).
- i. Analytical error (actual reason given).
N.A. Not applicable.
5
II. Surveillance Data for January Through December 1994 and Interpretation of Results t
A. External Gamma-ray Exposure Rates The average measured gamma-ray exposure rates expressed in mR/ day are given in Table II. A.1. The values were determined by CaF2 :Dy (TLD-200) dosimeters at each of 41 locations (see Table F-4 in ODCM). Two TLD chips per package are installed at each site and the mean value is repoitad for that site. The mean calculated total exposure is then divided by the number of days that elapsed between pre-exposure and post-exposure annealing to oixain the average daily exposure rate. The TLD devices are ;
changed quarterly at each location. Fading during field exposure is minimized by the post-annealing readout procedure. All TLD's are facing north to ensure consistent solar heating.
The TLD data indicate that the arithmetic mean measured exposure rate (plus 1.96 standard deviations) in the facility area for all of 1994 was 0.42 (0.12) mR/ day. The mean exposure rate was 0.41 (0.13) mR/ day for the adjacent area and 0.39 (0.12) mR/ day for the reference area. These mean values are not significantly different from each other and not different from the mean values measured during 1993.
The exposure rate measured at all sites is due to a combination of exposure from cosmic rays, from natural gamma-ray emitters in the earth's crust and from ground ,
l surface deposition of fission products due to previous world-wide fallout. The variation in measured values is due to true variation of the above sources plus the variability due i l
l 6
i
f to the measurement method. The purpose of having two TLD rings around the site is not to measure gamma-rays generated from the facility itself, but to document the presence or absence of gamma-ray emitters deposited upon the ground from the reactor effluent. Since the inception of power production by the reactor, there has been no detectr.ble increase in the external exposure rate due to reactor releases. Fallout deposition, from world-wide fallout, from the Chinese nuclear weapon tests, and from the Chernobyl accident, has been detected in the past.
The TLD system is calibrated by exposing chips to a scattered gamma-ray flux l
produced in a cavity surrounded by uranium mill tailings. This produces a gamma-ray l spectrum nearly identical to that from the natural background measured in the site environs. The quality control program includes calibration before readout of each quarterly batch of TLD devices.
For comparison purposes, EPA 402/R (Formerly 520/5) Environmental Radiation Data, lists very similar background external exposure rate values measured in Denver.
There has always been excellent agreement with the results from this program.
Figure II.A.1 shows the measured mean exposure rate in the Facility Area from 1978 to 1994. The steady decrease in exposure rate over the period is due to the decay and weathering of fission product deposition from previous atmospheric weapon tests.
f I
7 =
l i
Table II.A.1 Gamma Exposure Rates (mR/ day) 1994 Facility Area 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter l l
F-1 0.41 0.49 0.42 0.47 .
l F-2 0.47 0.35 0.44 0.38 ;
F-3 0.38 0.41 0.42 0.39 F-4 0.47 0.52 0.35 0.36 F-5 0.41 0.35 0.40 0.45 F-6 0.46 0.35 0.34 0.45 !
F-7 0.42 0.56 0.38 0.41 !
F-8 0.47 0.42 0.33 0.40 F-9 0.46 0.38 0.37 0.44 F-10 0.49 0.38 0.43 0.44 F-11 0.40 0.41 0.53 0.43 F-12 0.34 0.36 0.37 0.36 F-13 0.46 0.31 0.42 0.58 F-14 0.39 0.52 0.33 0.45 F-15 0.48 0.38 0.36 0.37 F-16 0.42 0.35 0.53 0.50 F-17 0.48 0.43 0.37 0.45 F-18 0.49 0.45 0.51 0.47 X(l .96o) 0.44(0.08) 0.41(O.13) 0.41(O.12) 0.44(0.10) l l
\
l l
8
Table II.A.1 (cont'd)
Adjacent Area 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter A-1 0.39 0.38 0.38 0.49 A-2 0.40 0.39 0.33 0.48 A-3 0.37 0.54 0.59 0.46 A-4 0.35 0.35 0.38 0.39 A-5 0.40 0.37 0.41 0.37 A-6 0.33 0.35 0.41 0.35 A-7 0.45 0.41 0.41 0.37 A-8 0.56 0.56 0.45 0.41 _
A-9 0.39 0.31 0.35 0.41 A-10 0.40 0.46 0.38 0.47 A-11 0.46 0.38 0.45 0.36 A-12 0.39 0.42 0.37 0.44 A-13 0.35 0.37 0.36 0.32 A-14 0.35 0.44 0.46 0.46 A-15 0.36 0.32 0.35 0.42 A-16 0.34 0.51 0.27 0.47 A-17 0.46 0.36 0.45 0.38 A-20 0.57 0.45 0.38 0.50 X(1.96o) 0.41(0.13) 0.40(0.13) 0.41(0.12) 0.42(0.11) 9
1 l
Table II.A.1 (cont'd) l Reference 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Area i
R-1 0.43 0.37 0.37 0.43 R-2 0.36 0.32 0.39 0.42 R-3 0.42 0.35 0.36 0.29 R-4 0.40 0.42 0.34 0.35 R-7 0.42 0.60 0.39 0.40 X(1.96o) 0.40(0.04) 0.41(0.20) 0.37(0.04) 0.38(0.10)
A i
l 10
Gamma Exposure Rates (mR/ day) 1978-1994 (Facility 1rea Only) f E
Exposure Rate (mR/ day) 0.6
~"
, n bn f*%%w
- 0.4 ev e n _sy v
e 0.3 0.2 0.1 0 '''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''
78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 Year
I II.B. Ambient Air Concentrations
- 1. Gross Beta Activity The air concentrations of long lived particulate gross beta activity measured at the '
facility and reference sampling sites are listed in Tables II.B.1(a-d) for each quarter of ,
1994. A-19, while technically in the adjacent zone, is only a few meters from the facility boundary and logically should be considered a facility site. It has been termed a facility site since the inception of the monitoring program. The reference sites R-3, R-4, and R-11 were established on January 1,1984 and are sufficiently distant to be considered reference (control) locations. (See Table F-4 in ODCM). Note that site F-7 is in the predominant wind direction of Platteville. Platteville is the nearest community with the highest D/Q as specified in the ODCM.
The reported concentrations are listed in units of femtocuries per cubic meter of ambient air (fCi/m3 ), although the measured activity is due to a combination of !
l radionuclides almost all of which are naturally occurring. All air filters are saved for i future analysis if warranted due to any possible accident scenario during decommissioning.
The mean gross beta concentration in air for all facility stations for all of 1994 was 28 fCi/m'. For 1993 the mean value was 24 fCi/m 3. The mean concentration for all reference stations for 1994 was 24 fCi/m 3. These measured mean values were not statistically significantly different at the 95% confidence level.
The gross beta concentrations in air for 1994 have been added to the plot of air 12
concentrations observed since 1973 (Figure II.B.1). In this figure the half-yearly mean values for the facility sites are plotted with the values from the reference sites. The contribution from the Chernobyl accident is clearly evident in 1986. It can be observed that overall mean values of the facility samplers are not significantly different from the reference samplers. World-wide fallout, principally due to past Chinese atmospheric nuclear weapon tests, is the predominant contributor above background to the measured values over the period shown.
There has never been a significant difference observed in gross beta air concentrations between facility and reference sites. Thus, it can be concluded that reactor air effluents of particulate fission products or activation products during operation or decommissioning were not a source of dose commitment for the Fort St. Vrain environs population.
1 13
s Table II.B.1(a) Concentrations of Long-lived Gross Beta Particulate Activity in Air (fCi/m 3) 1" Quarter 1994 Collection Facility Reference F-7 F-9 F-16 A-19 R-3 R-4 R-11 01/07 20(1.5)* 19(1.5) 19(1.5) 20(1.6) 19(1.4) 18(1.5) 18(1.4) 01/14 26(1.3) 23(1.1) 26(1.2) 30(1.4) 19(1.0) 24(1.3) 24(1.1) 01/22 23(2.9) 22(1.1) 25(1.1) 29(1.3) 24(1.0) 23(1.0) 21(1.0) 01/29 23(1.2) 23(1.2) 26(1.3) 30(1.5) 24(1.1) 24(1.2) 25(1.2) 02/05 32(1.4) 32(1.3) 32(1.5) 30(1.4) 20(1.0) 21(1.0) 25(1.3) 02/12 29(1.2) 29(1.2) 30(1.2) 33(1.3) 25(1.1) 29(1.2) 25(1.1)
E 02/19 33(1.3) 48(2.6) 29(1.3) 48(9.7) 18(1.0) 19(1.2) 25(1.1) 02/26 35(1.3) 42(1.5) 32(1.2) 28(1.1) 27(1.2) 27(1.1) 23(1.0) 03/05 64(1.8) 57(1.6) 51(1.6) 50(1.6) 24(1.0) 23(1.1) 30(1.3) 03/12 61(1.7) 51(1.5) 50(1.4) 42(1.4) 28(1.1) 27(1.2) 30(1.2) '
03/19 45(1.7) 51(1.8) 64(1.8) 64(2.0) 32(1.3) 31(1.3) 32(1.3) 03/26 18(1.1) 18(1.0) 19(1.1) 19(1.1) 17(0.96) 18(1.0) 19(1.0)
X 34 35 34 35 23 24 25 1.96o 29 27 26 25 8.6 8.0 8.1 hIax:64 5(1.96o): 35(27) Atax:32 5(1.%):24(8.3) 51in:18 n:48 hiin:17 n:36
- - 1.96o (Due to counting statistics)
________.--___--__-a -- - - - - _ - _ _ _ _ _ _ _ _ _ - - _ . - _ - _ _ - _ . . _ - -
Table II.B.1(b) Concentrations of Long-lived Gross Beta Particulate Activity in Air (fCi/m 3) 2"d Quarter 1994 Collection Facility Reference F-7 F-9 F-16 A-19 R-3 R-4 R-11 04/02 18(1.0)* 19(1.1) 20(1.1) 20(1.2) 18(0.97) 18(0.98) 18(1.0) 04/09 21(1.1) 19(1.1) 19(1.1) 22(1.2) 23(1.1) 19(1.0) 18(1.1) 04/16 24(1.1) 24(1.1) 24(1.1) 22(1.1) 22(1.0) 21(1.1) 22(1.1) 04/23 25(1.2) 25(1.2) 27(1.2) 29(1.4) 26(1.1) 25(1.1) 24(1.2) 04/30 14(0.90) 13(0.87) 14(0.88) 13(0.91) 13(0.82) 16(1.0) 12(0.78) 05/07 24(1.1) 24(1.0) 24(1.0) 24(1.1) 23(1.0) 24(1.1) 23(1.0)
G 05/14 22(1.1) 11(1.0) 23(1.1) 25(1.2) 23(1.1) 23(1.1) 22(1.0) 05/21 25(1.2) 28(l.2) 28(1.2) 29(1.3) 27(1.2) 26(1.2) 26(1.2) 05/28 23(1.1) 23(1.1) 26(1.2) 22(1.2) 23(1.1) 23(1.1) 23(1.1) 06/04 23(1.1) 22(1.0) 23(1.1) 23(1.2) 24(1.1) 23(1.1) 21(1.0) 06/11 21(1.0) 20(0.98) 23(1.1) 22(1.2) 22(1.1) 20(1.1) 19(0.99) 06/18 20(1.1) 19(1.1) 21(1.2) 20(1.2) 19(1.1) 19(1.1) 20(1.1) 06/25 26(1.2) 28(1.2) 30(1.4) 21(1.1) 27(1.1) 25(1.2) 21(1.0)
X 22 21 23 22 22 22 21 1.96o 6.2 9.6 7.9 7.7 7.3 5.8 6.6 Alax:30 X(1.%): 22(8.1) Atax:27 X(1.96a):22(6.7) hiin:11 n:52 Alin:12 n:39
- .1.% (Due to counting statistics)
1 Table II.B.1(c) Concentrations of Long-lived Gross Beta Particulate Activity in Air (fCi/m3) d 3 Quarter 1994 Collection Facility Reference F-7 F-9 F-16 A-19 R-3 R-4 R-11 07/02 24(1.2)* 23(1.1) 24(1.2) 24(1.3) 12(0.81) 22(1.2) 21(1.1) 07/D'; 22(1.1) 21(1.1) 23(1.2) 23(1.2) 29(1.6) 22(1.1) 21(1.1) 07/16 24(1.2) 23(1.2) 26(1.3) 26(1.4) 22(0.95) 30(1.6) 22(1.2) 07/23 29(1.2) 27(1.1) 29(1.3) 27(1.4) 29(1.3) 26(1.2) e 07/30 31(1.2) 31(1.2) 31(1.3) 30(1.5) 31(1.3) 31(1.2) 34(2.9) 08/05 32(1.3) 30(1.3) 32(1.4) 34(1.5) 35(1.4) 31(1.2) 28(1.3)
E 08/12 29(1.2) 27(1.2) 30(1.3) 30(1.4) 26(1.2) 25(1.1) 28(1.3) 08/20 30(1.1) 29(1.1) 31(1.2) 31(1.3) 28(1.1) 30(1.1) 29(1.1) 08/27 31(1.3) 31(1.2) 33(1.3) 32(1.4) 33(1.4) 31(1.3) 30(1.3) 09/03 27(1.2) 26(1.1) 27(1.2) 27(1.3) 29(1.2) 26(1.1) 27(1.2) 09/10 27(1.3) 25(1.2) 29(1.3) 31(1.4) 22(1.1) 27(1.2) 27(1.2) 09/17 21(1.1) 20(1.1) 22(1.2) 23(1.3) 20(1.2) 19(1.1) 19(1.1) 09/24 29(1.2) 28(1.2) 29(1.3) 24(1.2) 29(1.2) 25(1.1) 24(1.1)
X 27 26 28 28 28 27 26 1.96o 6.8 6.9 6.6 7.0 8.5 7.4 8.3 Max:34 X(1.%): 27(7.0) Max:35 X(1.96a):27(S.2)
Min:20 n:52 Min:12 n:37
- - 1.96o (Due to counting statistics) e - Insufficient volume for analysis
Table II.B.1(d) Concentrations of Long-lived Gross Beta Particulate Activity in Air (fCi/m3 )
1 4"' Quarter 1994 Collection Facility Reference F-7 F-9 F-16 A-19 R-3 R-4 R-11 10/01 32(1.3)* 30(1.3) 33(1.4) 32(1.4) 24(1.2) 27(1.2) 27(1.2) 10/08 23(1.0) 21(0.94) 21(1.0) 18(0.90) 20(0.99) 22(1.0) 22(0.99) 10/15 39(3.4) 35(1.4) 39(1.5) 31(1.6) 35(1.4) 31(1.3) 33(1.3) 10/22 34(1.7) 26(1.0) 24(1.1) 24(1.1) 23(1.1) 23(1.1) 22(1.0) 10/29 33(1.4) 33(1.3) 35(1.4) 36(1.5) 30(1.3) 29(1.3) 28(1.3) 11/05 21(1.1) 21(1.0) 20(1.1) 21(1.1) 23(1.1) 21(1,1) 21(1.0) 11/12 39(1.4) 39(1.3) 37(1.4) 36(1.4) 39(l'.3) 35(1.4) 37(1.3) 11/19 24(1.2) 25(1.1) 21(1.0) 25(1.3) 24(1.1) 21(1.0) 25(1.1) 11/26 31(1.3) a 30(1.3) 31(1.4) 23(1.2) 23(1.1) 26(1.2) l 12/03 14(1.0) 13(0.92) 14(1.4) 15(1.1) 11(0.99) 10(0.91) 10(0.96) 12/10 32(1.3) 31(1.2) 34(1.4) 28(1.3) 27(1.2) 25(1.2) 32(1.3) 12/17 38(1.4) 36(1.3) 38(1.3) 39(1.5) 31(1.3) 33(1.4) 33(1.3) 12/24 32(1.4) 28(1.3) 30(1.3) 37(1.6) 24(1.3)g 23(1.2) 26(1.3) 12/31 39(1.5) 38(1.4) 41(1.5) 43(1.6) 33(1.4) 30(1.3) 31(1.3)
X 31 29 30 30 26 25 27 1.96o 15 14 16 16 13 12 13 Max:43 X(1.%): 30(15) Max:39 X(1.%):26(13)
Min:13 n:55 Min:10 n:42
- - 1.96o (Due to counting statistics) a - Sample lost prior to analysis
i j
.. 4' Figure II.B.1 ;
Gross Beta Concentrations in Air )
1000 )
l l
w se E < -
100
$ t a #i 8 % I li lI y- ..
I \\ \\ ..
1 k \\ \\ , \
. 1 - \\ l\ f f ll i l e <
{i T) \
l lt _
.i
)
Nh b4 t L
l i
10 ,,,,,,,,,,,,,,,,,,, ,,,,,,,,,,,,,,,,,,,,,,,
73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 Facility Cumulative Year nererence cumulative Average Y=47 Average T=48
-+- Facility Sampling Stations -*-Reference Sampling Stations I
18 l l
- 2. Tritium Activity Atmospheric water vapor samples are collected continuously by passive absorption on silica gel at all seven air sampling stations (four in the facility area and three in the reference area). The specific activky of tritium in water extracted from these weekly samples in 1994 is listed in Tables II.B.2(a-d).
The release mode of tritium from the facility was either batch liquid releases from holding tanks (system 62) or gaseous release. The tank water is first analyzed and then released with sufficient additional dilution, if necessary, to meet 10CFR20 concentration limits. The summary of tritium release by all modes is shown in Table II.B.3. The I summary indicates that the total tritium released in 1994 was 2.3 times less than that released in 1993 by all routes. The continuous gaseous stack release was 1.6 times greater than in 1993. But this effluent release was not detected at any air sampling sites.
Inspection of Table II.B.2 shows essentially no detectable tritium activity concentrations in any periods during 1994. There was no correlation with the effluent release of tritium (see Table II.B.3). Inhalation in any case is not a significant pathway for dose to humans. The milk and food pathway are the only significant source of radiation dose to humans from environmental tritium. See results in sections II.D and II.E for these pathways.
F l
19
~.
Table II.B.2(a) Tritium in Atmospheric Water Vapor (pCi/L) 1" Quarter 1994 Collection Facility Reference F-7 F-9 F-16 A-19 R-3 R-4 R-11 01/07 < 400 < 400 < 400 < 400 < 400 < 400 < 400 01/14 < 390 < 390 < 390 < 390 < 390 < 390 < 390 01/22 < 390 < 390 < 390 < 390 < 390 < 390 < 390 01/29 < 390 < 390 < 390 < 390 < 390 < 390 < 390 02/05 < 390 < 390 < 390 < 390 < 390 < 390 < 390 02/12 < 390 < 390 < 390 < 390 < 390 < 390 < 390 S 02/19 < 390 < 390 < 390 < 390 < 390 < 390 < 390 02/26 < 390 < 390 < 390 < 390 < 390 < 390 < 390 03/05 < 410 < 410 < 410 < 410 < 410 < 410 < 410 03/12 < 390 < 390 < 390 < 390 < 390 < 390 < 390 03/19 < 380 < 380 < 380 < 380 < 380 < 380 < 380 03/26 < 380 < 380 < 380 < 380 < 380 < 380 < 380
_ _ _ _ _ ._.m _ . - . _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ . _ . . _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ . - _ _ _ _ _ _ _ _ _ _ . _ _ - - _ _ _ _ _ - _ _ _ _ _ _ _ _ . - _ _ _ _ _ _ _ _ _ _ - _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ . - _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . . - - _ _ . - . . _
l
- 3 1
j Table II.B.2(b) Tritium in Atmospheric Water Vapor (pCi/L) 2"d Quarter 1994 Collection Facility Reference t F-7 F-9 F-16 A-19 R-3 R-4 R-11 l
I 04/02 < 380 < 380 < 380 < 380 < 380 < 380 < 380 04/09 < 380 < 380 < 380 < 380 < 380 < 380 < 380 04/16 < 390 < 390 < 390 < 390 < 390 < 390 < 390 04/23 < 390 < 390 < 390 < 390 < 390 < 390 < 390 04/30 < 390 < 390 < 390 < 390 < 390 < 390 < 390 05/07 < 380 < 380 < 380 < 380 < 380 < 380 < 380 0 05/14 < 380 < 380 < 380 < 380 < 380 < 380 < 380 05/21 < 380 < 380 < 380 < 380 < 380 < 380 < 380 05/28 < 380 < 380 < 380 < 380 < 380 < 380 < 380 M/04 < 380 < 380 < 380 < 380 < 380 < 380 < 380 06/11 450(520)* 530(520) 550(520) < 380 < 380 < 380 < 380 06/18 < 400 < 400 < 400 < 400 < 400 < 400 < 400 06/25 < 380 < 380 < 380 < 380 < 380 < 380 < 380
- 1.96o (Due to counting statistics)
Table II.B.2(c) Tritium in Atmospheric Water Vapor (pCi/L)
]
3"' Quarter 1994 Collection Facility Reference F-7 F-9 F-16 A-19 R-3 R-4 R-11 07/02 < 380 < 380 < 380 < 380 < 380 < 380 < 380 07/09 < 380 < 380 < 380 < 380 < 380 < 380 < 380 07/16 < 380 < 380 < 380 < 380 < 380 < 380 < 380 07/23 < 380 < 380 < 380 < 380 < 380 < 380 < 380 07/30 < 380 < 380 < 380 < 380 < 380 < 380 900(1070)*
08/05 < 380 < 380 < 380 < 380 < 380 < 380 < 380 l U 08/12 < 380 < 380 < 380 < 380 < 380 < 380 < 380 08/20 < 410 < 410 < 410 < 410 < 410 < 410 < 410 08/27 < 380 < 380 < 380 < 380 < 380 < 380 < 380 09/03 < 390 < 390 < 390 < 390 < 390 < 390 < 390 09/10 < 380 < 380 < 380 < 380 < 380 < 380 < 380 09/17 < 380 < 380 < 380 < 380 < 380 < 380 < 380 09/24 < 380 < 380 < 380 < 380 < 380 < 380 < 380 l l
- - 1.96o (Due to counting statistics)
~.
Table II.B.2(d) Tritium in Atmospheric Water Vapor (pCi/L) 4* Quarter 1994 Collection Facility Reference F-7 F-9 F-16 A-19 R-3 R-4 R-11 10/01 < 380 < 380 < 380 < 380 < 380 < 380 < 380 10/08 < 380 < 380 < 380 < 380 < 380 < 380 < 380 10/15 < 380 < 380 < 380 < 380 < 380 < 380 520(630) 10/22 < 380 < 380 < 380 500(680) < 380 430(680) 680(680) 10/29 470(680)* < 380 < 380 < 380 < 380 < 380 < 380 11/05 < 390 < 390 < 390 < 390 < 390 < 390 < 390 U 11/12 < 410 < 410 < 410 < 410 < 410 < 410 < 410 11/19 < 380 < 380 < 380 < 380 < 380 < 380 < 380 11/26 < 380 < 380 < 380 < 380 < 380 < 380 < 380 12/03 < 390 < 390 < 390 < 390 < 390 < 390 < 390 12/10 < 400 < 400 590(680) < 400 < 400 < 400 < 400 12/17 < 390 < 390 < 390 < 390 < 390 < 390 < 390 12/24 < 410 < 410 < 410 < 410 < 410 < 410 < 410 12/31 < 410 < 410 < 410 < 410 < 410 < 410 < 410
- - 1.96o (Due to counting statistics)
. j' Table H.B.3
, Tritium Released (Ci) In Fort St. Vrain Effluents,1994 MODE JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC TOTAL i Continous 0.0786 0.0381 0.0761 0.0492 0.0268 0.0641 0.0862 0.16 0.261 0.211 0.48 0.354 1.88 Gaseous Stack l Batch Liquid 0.224 0.0278 0.0773 0.0056 0.0136 0.016 0.0147 0.0298 0.332 0.491 0.00398 0.096 1.33 TOTAL 0.303 0.0659 0.153 0.0548 0.0404 0.0801 0.101 0.19 0.593 0.702 0.484- 0.45 3.21 S
i i
6 i
L
___ _ ...-----.- .- _._-- ,---- _ -,-.<...._.~ ..-.-_ . - , . _ - . . . - - - - - - - . - _ _ , ~ - . . , . . . . - . , - _ , , . - - , _ . - . . . - ~ , = - . __ , . _ . , . _ _ _ . -
l
,, a= 1
- 3. Concentrations of Gamma-ray Emittine Radionuclides in Ambient Air Table II.B.4 lists measured ambient air concentrations of Cs-134 and Cs-137.
These values are from gamma-ray spectrum analyses of weekly air filters composited quanerly from each of the seven air sampling stations. Occasional positive values can be noted (see first quarter Cs-137 values). IIowever, in every case these are very close to the lower limit of detection. Cs-l',7 activity was released via the liquid effluent pathway during 1994 (see sediment results in Table II.F.2(a-b)). The occational positive values are either measurement system false positives or Cs-137 concentrations possibly due to resuspension of surface soil. The Cs-137 activity in surface soil is due to Chernobyl or previous world-wide fallout which is bound by clay minerals on the surface of undisturbed soil. For the entire year, the mean of the facility stations was not different from the mean of the reference stations.
Although only Cs-134 and Cs-137 are reported, each gamma-ray spectrum is scanned for evidence of peaks from other fission products and activation products. Only gamma-ray activity due to the naturally occurring background radionuclides was observed. During the second quarter of 1986, however, many other fission product and activation product radionuclides were observed due to the Chernobyl accident. Of these only Cs-137 can still be detected, but at steadily decreasing concentrations.
1-131 was not measured at the air sampling stations during any period of 1994.
Due to the time period since the end of operation, there is no logic in I-131 monitoring and it was discontinued in January 1993. It is worthy to note that I-131, due to facility 25 g
effluent, was never measured in any environmental sample during the operational phase n
i- or since the reactor was permanently shut down in August 1989.
26 1
~
3 Table II.B.4 Radiocesium Concentrations in Ambient Air. (fCi/m )
i 1994 Radio- Facility Reference Collection nuclide Periods F-7 F-9 F-16 A-19 R-3 R-4 R-11 1" Cs-134 < 1.0 < 0.48 < 0.34 0.39(0.33) < 0.92 < 0.19 < 0.36 9"^ "*' Cs-137 < 1.1 < 0.47 < 0.%
0.51(0.46) 1.2(0.36) 0.79(0.24) 0.62(0.45) 2'"' Cs-134 < 1.6 < 0.62 < 1.7 < 1.5 < 1.4 < 0.37 < 1.2 j
t Cs-137 < 1.6 < 0.74 < 1.5 < 1.5 < 1.4 0.46(0.45) < 1.4 3"' Cs-134 2.1(2.2)* < 0.71 < 0.69 < 1.9 < 0.73 < 1.4 < 0.%
9"* "*' Cs-137 < 1.8 < 0.80 < 2.0 < 1.5 1.2(0.85) 0.81(0.99) 1.9(1.5) 4* Cs-134 < 0.68 < 0.52 < 0.69 < 0.55 < 1.5 < 0.49 < 1.0 Cs-137 < 0.78 < 0.56 0.66(0.76) < 0.88 < 1.5 < 0.56 1.3(1.4)
- - 1.W (Due to counting statistics) .
I 1
w L_ . . . . . . . .
- _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - -_d
II.C. Radionuclide Concentrations in Water
- 1. Drinking Water Drinking water is sampled weekly and composited biweekly at two locations.
IAcation R-6 is the well used for drinking water by the town of Gilcrest, Colorado, and R-3 is a water hydrant located on the old CSU dairy farm. The Gilcrest well is the nearest public water supply that could be affected by the facility effluents. R-3 samples are from the Fort Collins drinking water supply and serve as a reference location since its source is run-off surface water from the Rocky Mountains to the west. Water treatment systems for the two water supplies are very different.
Tables II.C.1(a-b) show gross beta concentrations measured in 1994 from each water supply. As in every past year, the mean for the Gilcrest site was higher than the Reference site in Fort Collins. This is due to the different water treatment practices and the different supply sources. The city of Gilcrest does not completely filter the well supply water and natural radionuclide concentrations due to the suspended solids are responsible for the higher measured concentrations. As can be observed in Table II.H.2, however, the mean for the entire year for the Gilcrest site was again lower than that observed prior to 1994. This decrease was due to a recent change in treatment practice by the town of Gilcrest.
Tables II.C.2(a-b) list measured tritium concentrations in these same two drinking water sources. There is no significant difference in the yearly mean tritium concentrations in the two drinking water supplies. The EPA limit for community i
drinking water systems is currently 20,000 pCi/L for tritium.
The two drinking water supplies were also analyzed biweekly for fission product 28 1
o 0 e 1
1 and activation product concentrations. !
Inspection of Table II.C.3 reveals occasional positive values of radionuclide i
concentration, but with the exception of Cs-137, these are interpreted to be random j variations about the detection limit. The Cs-137 is the residue from the 1986 Chernobyl ,
l I
accident fallout as well as from past world-wide fallout from nuclear weapons testing.
.i I
29
Table II.C.1(a) Gross Beta in Drinking Water (pCi/L) 1" and 2"d Quarter 1994 _
Collection Gilcrest Ft. Collins Dates R-6 R-3 12/31 01/07 2.3(2.3)* 1.2(0.60) 01/14 01/22 2.3(2.2) 0.99(0.59) 01/29 02/05 3.0(2.3) 0.90(0.59) 02/12 02/19 2.0(2.2) 1.5(0.71) 02/26 0.$/05 1.8(2.2) 1.4(0.60) 03/12 03/19 4.0(2.3) 0.89(0.57) g 03/26 04/02 5.1(2.4) 1.4(0.60) 04/09 04/16 3.8(2.3) 1.3(0.59) 04/23 04/30 4.3(2.4) 1.2(0.59) 05/07 05/14 3.1(2.3) 1.5(0.61) 05/21 05/28 2.6(2.2) 1.3(0.59) 06/04 06/11 2.1(2.2) 1.0(0.58) 06/18 06/25 1.8(2.2) 0.85(0.57)
- - 1.96o (Due to Counting Statistics)
e.
Table II.C.1(b) Gross Beta in Drinking Water (pCi/L) 3"' and 4"' Quarter 1994 Collection Gilcrest Ft. Collins Dates R-6 ' R-3 07/02 07/09 2.3(2.2)* 1.3(0.59) 07/16 07/23 3.0(2.2) 1.3(0.60) 07/30 08/05 2.6(2.2) 1.3(0.60) 08/12 08/20 2.4(2.3) 1.3(0.60) 08/27 09/03 2.4(2.2) 1.4(0.60) 09/10 09/17 2.0(2.2) 1.3(0.59) 3 09/24 10/01 1.9(2.2) 1.6(0.61) 10/08 10/15 2.5(2.2) 1.5(0.60) 10/22 10/29 1.7(2.2) 1.5(0.60) 11/05 11/12 2.4(2.2) 1.3(0.60) 11/19 11/26 2.8(2.2) 0.65(0.56) 12/03 12/10 1.6(2.1) 1.1(0.59) 12/17 12/24 1.2(2.3) 0.81(0.59)
- - 1.% (Due to Counting Statistics)
Table II.C.2(a) Tritium in Drinking Water (pCi/L) 1" and 2"d Quarter 1994 Collection Gilcrest Ft. Collins Dates R-6 R-3 12/31 01/07 < 400 < 400 01/14 01/22 < 390 < 390 01/29 02/05 < 390 < 390 02/12 02/19 < 390 < 390 02/26 03/05 < 390 < 390 03/12 03/19 < 380 < 380 g ; 03/26 04/02 < 380 < 380 01/09 04/16 < 380 < 380 04/23 04/30 < 380 < 380 05/07 05/14 < 380 < 380 05/21 05/28 < 390 < 390 06/04 06/11 < 390 < 390 06/18 06/25 < 380 < 380
s Table II.C.2(b) Tritium in Drinking Water (pCi/L) 3"' and 4"' Quarter 1994 Collection Gilcrest Ft. Collins Dates R-6 R-3 07/02 07/09 < 390 < 390 07/16 07/23 < 380 < 380 07/30 08/05 < 380 < 380 08/12 08/20 < 380 < 380 08/27 09/03 < 390 < 390 09/10 09/17 < 380 < 380 3 09/24 10/01 < 380 < 380 10/08 10/15 410(680)* < 380 10/22 10/29 < 380 < 380 11/05 11/12 < 380 < 380 >
11/19 11/26 < 390 < 390 12/03 12/10 < 380 < 380 12/17 12/24 < 380 < 380
- 1.96o (Due to Counting Statistics)
_ _ _ . _ _ . _ _ _ _ ____ ____.__________ _ ..._, - _ _ _ . - . . _ _ __ _ . . , , _ _ . . _ . . _ .-. ._ _ _ _ ~ _ . _ _ _ _ _ _
Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L)
Collection for two weeks ending for two weeks ending for two weeks ending Date 1/8 1/22 2/5
, Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 Cs-134 < 0.63 < 1.2 < 1.1 < 1.2 < 1.0 < 1.1 Cs-137 4.1(0.94)* < 1.4 4.9(1.6) 4.8(1.9) 3.1(1.6) 4.5(1.6)
Zr-95 < 1.4 < 4.1 < 2.3 < 3.6 < 2.7 < 2.7 Nb-95 < 0.85 < 1.0 1.9(1.6) < 1.2 < 1.0 1.8(1.4)
Co-58 < 0.57 < 1.1 < 1.0 < 1.1 < 1.1 < 1.0 g Mn-54 _
< 0.61 1.4(1.5) 1.1(1.3) < 1.3 < 1.0 < 1.1 l 1
Zn-65 < 1.6 < 3.3 < 3.1 < 3.6 < 2.9 < 2.9 l
Fe-59 < 2.7 < 2.7 4.5(4.7) < 3.0 < 3.2 < 3.2 .
l Co-60 < 0.58 2.0(1.5) < 1.1 < 1.2 < 1.0 < 1.0 l I
Ba-140 < 0.99 < 1.9 < 1.8 10(11) < 3.9 3.9(4.5)
La-140 < 1.1 < 2.2 < 2.1 11(12) < 4.5 4.5(5.2)
- 1. (Due to counting statistics)
_ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 1
~.
Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L)
Collection for two weeks ending for two weeks ending for two weeks ending Date 2/19 3/5 3/19 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 Cs-134 < 2.0 < 1.1 < 2.0 < 2.0 < 1.5 < 1.5 Cs-137 3.0(2.9)* 4.7(1.7) < 2.5 2.7(3.0) 2.3(2.2) 3.1(2.2)
Zr-95 < 4.6 < 2.6 < 4.7 < 4.7 < 5.0 < 4.4 Nb-95 < 1.8 < 1.1 < 1.8 < 1.8 < 1.4 < 1.3 Co-58 < 2.1 < 1.0 < 1.9 < 1.8 < 1.4 < 1.3 Mn-54 < 2.0 < 1.1 < 2.0 < 2.1 < 1.6 2.2(1.8)
Zn-65 < 5.4 < 3.3 < 5.6 < 5.4 < 4.4 < 3.9 Fe-59 < 5.8 < 3.1 < 5.9 < 4.7 6.9(6.8) < 5.0 Co-60 < 2.2 < 1.0 < 2.2 < 2.1 < 1.7 < 1.6 Ba-140 < 7.2 < 1.7 < 7.2 < 15 < 2.5 < 2.4 La-140 < 8.2 < 2.0 < 8.3 < 18 < 2.9 < 2.7
- 1.W (Due to counting statistics) n -
s Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L) i Collection for two weeks ending for two weeks ending for two weeks ending Date 4/2 4/16 4/30 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 Cs-134 < 1.2 < 2.2 s 6.64 < 1.1 < 1.3 < 2.3 Cs-137 6.1(1.8)* 4.0(3.1) 5.5(0.97) 2.0(1.7) 5.6(1.9) 5.0(3.3)
Zr-95 < 2.6 < 6.4 < 1.4 < 3.2 < 2.9 < 5.2 Nb-95 1.7(1.9) < 2.0 1.8(0.89) < 1.0 < 1.4 < 2.1 Co-58 1.8(1.7) < 1.9 < 0.68 < 1.0 < 1.2 < 2.1 Mn-54 < 1.2 < 2.2 0.86(0.79) 1.6(1.4) < 1.3 < 2.2 Zn-65 < 4.3 < 6.7 < 2.0 < 3.2 < 4.3 < 6.5 Fe-59 < 4.2 < 5.0 < 1.9 < 2.7 < 3.1 < 5.3 Co-60 < 1.2 < 2.3 < 0.61 < 1.2 < 1.2 < 2.4 Ba-140 < 8.0 < 14 < 1.0 < 1.9 3.8(3.4) < 5.0 La-140 < 9.3 < 16 < 1.2 < 2.2 4.4(4.0) < 5.7
- 1.96a (Due to counting statistics)
1 Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L)
Collection for two weeks ending for two weeks ending for two weeks ending Date 05/14 05/28 06/11 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 Cs-134 < 1.2 < 2.1 < 2.0 < 2.0 < 1.9 < 1.6 Cs-137 4.9(1.7)* < 2.6 < 2.5 < 2.5 < 2.4 < 1.9 Zr-95 < 2.7 < 4.9 < 5.5 < 4.7 < 4.6 < 3.6 l Nb-95 < 1.1 < 1.9 < 1.8 < 1.h < 1.8 < 1.4 Co-58 1.2(1.4) < 2.1 < 1.9 <2i < 2.2 < 1.4 3 Mn-54 2.0(1.4) < 2.1 < 2.0 < 2.1 < 2.0 < 1.6 Zn-65 < 3.6 < 5.9 < 5.6 < 5.3 < 5.6 < 4.3 Fe-59 4.4(3.7) < 5.7 < 4.6 < 4.7 < 6.2 < 3.6 Co-60 < 1.1 < 2.3 < 2.2 < 2.1 < 2.1 < 1.6 Ba-140 < 2.0 < 3.4 < 3.3 < 7.2 < 9.1 < 2.5 La-140 < 2.3 < 3.9 < 3.8 < 8.2 < 10 < 2.9
- 1.96a (Due to counting statistics)
~.
i Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L)
Collection for two weeks ending for two weeks ending for two weeks ending i Date 06/25 07/09 07/23 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 Cs-134 < 2.1 < 1.2 < 2.4 < 1.3 1.7(1.4)* < 2.0 Cs-137 < 2.5 6.0(1.8) < 2.9 2.6(2.0) 2.7(1.7) < 2.5 Zr-95 < 5.5 < 2.6 < 5.5 < 2.8 < 2.7 < 4.6 Nb-95 < 1.8 < 1.1 < 2.2 < 1.2 < 1.1 < 1.8 Co-58 < 1.9 < 1.1 < 2.5 < 1.2 < 1.3 < 1.8 w
Mn-54 < 2.0 < 1.2 < 2.4 < 1.3 < 1.2 < 2.0 Zn-65 < 5.8 < 3.0 < 6.5 < 3.6 < 3.2 < 5.3 Fe-59 < 5.9 < 3.2 < 7.0 < 3.6 < 2.7 < 4.6 Co-60 < 2.2 2.4(1.4) < 2.5 < 1.2 < 1.3 < 2.1 Ba-140 < 7.1 < 1.9 8.2(9.8) < 4.0 < 1.9 8.7(8.9)
La-140 < 8.2 < 2.1 9.5(11) < 4.6 < 2.2 10(10)
- 1.96o (Due to counting statistics)
s l Table H.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L)
Collection for two weeks ending for two weeks ending for two weeks ending Date 08/06 08/20 09/03 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 Cs-134 < 0.53 < 2.0 < 2.0 < 1.2 < 2.0 < 2.1 Cs-137 3.9(0.81)* < 2.5 < 2.5 5.9(1.8) < 2.4 2.6(3.1)
Zr-95 < 1.1 < 5.0 < 4.7 < 2.7 < 4.7 < 4.9 Nb-95 < 0.50 < 1.9 < 1.8 < 1.1 < 1.9 < 1.9 Co-58 < 0.48 < 1.8 < 2.0 < 1.2 < 1.8 < 1.9 Mn-54 0.85(0.62) < 2.0 < 2.0 < 1.2 < 2.0 2.8(2.6)
Zn-65 < 1.3 < 5.7 < 5.3 < 3.4 < 5.4 < 6.2 Fe-59 3.0(1.6) < 4.8 < 4.7 4.2(3.8) < 5.8 < 4.9 Co-60 < 0.49 < 2.2 < 2.1 1.1(1.3) < 2.2 < 2.2 Ba-140 < 0.84 < 3.3 < 3.3 < 1.9 8.4(8.5) < 3.4 La-140 < 0.97 < 3.8 < 3.8 < 2.2 9.7(9.8) < 3.9
- 1.96o (Due to counting statistics)
1 Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L)
Collection for two weeks ending for two weeks ending for two weeks ending Date 09/17 10/01 10/15 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 Cs-134 < 2.5 < 1.8 < 2.0 < 1.7 < 1.9 < 2.1 Cs-137 4.3(3.6)* < 2.3 < 2.5 2.9(2.4) < 2.4 2.5(3.0)
Zr-95 < 6.5 < 4.4 < 5.4 < 4.4 < 4.5 < 4.7 Nb-95 < 2.3 < 1.6 < 1.9 < 1.5 < 1.8 < 1.8 Co-58 < 2.3 < 1.9 < 1.9 < i.7 < 2.0 < 1.9 g Mn-54 4.2(3.0) < 1.9 < 2.1 < 1.7 < 2.0 < 2.1 Zn-65 < 7.4 < 5.1 < 5.5 < 4.4 < 5.2 < 5.6 '
Fe-59 < 5.9 < 4.5 < 5.9 < 4.0 < 5.8 < 4.7 Co-60 < 2.7 - 3.4(2.4) < 2.2 < 1.8 < 2.1 < 2.2 Ba-140 < 7.8 < 3.1 < 7.2 < 5.1 < 7.8 < 7.7 La-140 < 8.9 < 3.6 < 8.3 < 5.9 < 8.9 < 8.8
- - 1.96a (Due to counting statistics)
Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L)
Collection for two weeks ending for two weeks ending for two weeks ending Date 10/29 11/12 11/26 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3
~
Cs-134 < 1.9 < 2.1 < 2.0 < 1.9 < 2.1 < 2.1 l Cs-137 < 2.4 2.5(3.0)* < 2.4 2.8(2.7) < 2.5 4.1(3.1)
! Zr-95 < 4.5 < 4.7 < 5.1 < 4.4 < 5.4 < 4.8 l Nb-95 < 1.8 < 1.8 < 1.8 < 1.7 < 1.8 < 1.9 l
Co-58 < 2.0 < 1.9 < 1.8 2.3(2.3) < 1.9 < 1.9 g Mn-54 < 2.0 < 2.1 < 2.1 2.5(2.5) < 2.0 < 2.1 Zn-65 < 5.2 < 5.6 < 5.4 < 5.1 < 5.5 < 5.7 Fe-59 < 5.8 < 4.7 < 4.5 < 5.1 < 4.7 < 5.9 Co-60 < 2.1 < 2.2 < 2.1 < 2.1 < 2.1 < 2.2 Ba-140 < 7.8 < 7.7 < 3.2 < 5.3 < 3.3 < 3.4 La-140 < 8.9 < 8.8 < 3.7 < 6.0 < 3.7 < 3.9
- - 1.96o (Due to counting statistics)
~ __ __ _. . _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _.
~
Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L)
Collection for two weeks ending for two weeks ending Date : 12/10 12/24 4
Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 Cs-134 < 2.0 < 2.2 < 2.1 < 2.3 Cs-137 < 2.5 4.3(3.2)* < 2.6 < 2.6 Zr-95 < 4.7 < 5.1 < 4.9 < 6.1 Nb-95 < 1.9 < 2.0 < 1.9 < 2.0 Co-58 < 2.0 < 2.0 < 2.3 < 1.9 Mn-54 3.3(2.4) 3.2(2.6) < 2.1 < 2.2 Zn-65 < 5.5 < 5.9 < 6.0 < 5.9 Fe-59 < 5.3 < 5.1 < 5.0 < 6.6 Co-60 < 2.1 < 2.4 < 2.2 < 2.2 Ba-140 < 3.3 < 3.5 13(12) < 3.5 La-140 < 3.8 < 4.1 15(14) < 4.0
- - 1.W (Due to counting statistics)
- 2. Surface Water Surface water is collected from five sites. Since the facility liquid effluent can be directed to either the St. Vrain Creek or the South Platte River, there are upstream l and downstream sampling locations on both river courses.
Tables II.C.4(a-d) show tritium concentrations measured during 1994 at the four surface water sites and the effluent route site. The aritlunetic mean value for the two downstream locations in 1994 was not significantly different from the two (.pstream ;
) locations (Table II.II.2). There were detectable tritium concentrations at A-25, which is the principal effluent route. This can be noted from September through October and on December 10.
Table II.C.5 shows measurements of fission product and activation product concentrations in surface water samples collected monthly. There were occasional positive values, but the mean of the downstream sites was not significantly different from the mean of the upstream sites during 1994 for any of the gamma-ray emitting radionuclides measured. This has been the case since the inception of reactor operations at the Fort St. Vrain site. The occasional positive values are either fallout Cs-137, which can be expected, or values close to the uncertainty limits and assumed to be false positives.
In addition to the monthly sampling of the South Platte River and St. Vrain Creek, a continuous water sampler collects an aliquot of the effluent stream from the Farm Pond (A-25), at a preset frequency. The sample is dumped after each aliquot in l
to a 5 gallon collection jug. To prevent overflow of the jug in the one-week sampling ,
i period, the aliquot value and/or the sampling frequency is adjusted. The weekly 1
1 43
l composites are then combined and analyzed monthly. The results of these samples are also shown in Tables II.C.4 and II.C.5. During the third and fourth quarters of 1994, there was detectable tritium in the farm pond overflow (A-25) due to decommissioning activities. These concentrations correspond to the effluent release report. These concentrations were much lower than the EPA drinking water limit (20,000 pCi/L). No elevated tritium concentrations were detected, however, at the downstream location (R-
- 10) during the entire year.
Mean values of the other radionuclides were less than MDC with the exception of Cs-137. The Cs-137 mean in downstream water was not statistically higher than upstream and therefore the activity is concluded to be due to worldwide fallout. The correlation of the tritium concentrations at A-25 with the effluent release information is good.
44
Table II.C.4(a) Tritium in Surface Water (pCi/L) 1" Quarter 1994 Collected Downstreams Upstream Effluent F-20 R-10 A-21 F-19 A-25 6 0.1/07 < 400 < 400 < 400 < 400 < 400 01/14 < 410 < 410 < 410 < 410 < 410 01/22 < 410 < 410 < 410 < 410 < 410 01/29 < 410 < 410 < 410 < 410 < 410 02/05 < 390 < 390 < 390 < 390 < 390 02/12 < 390 < 390 < 390 < 390 < 390 N 02/19 < 380 < 380 < 380 < 380 < 380 02/26 < 390 < 390 < 390 < 390 < 390 03/05 < 390 < 390 < 390 < 390 < 390 03/12 < 380 < 380 < 380 < 380 < 380 03/19 < 390 < 390 < 390 < 390 < 390 03/26 < 390 < 390 < 390 < 390 < 390 b
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l 4 4 4 4 4 5 5 5 5 6 6 6 6 a l o 0 0 0 0 0 0 0 0 0 0 0 0 0 u C Q
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x Table II.C.4(c) Tritium in Surface Water (pCi/L) 3"' Quarter 1994 Collected Downstreams Upstream Efiluent F-20 R-10 A-21 F-19 A-25 07/02 390(550)* < 380 < 380 < 3E0 < 390 07/09 < 380 < 380 < 380 < 380 -< 390 07/16 < 380 < 380 < 380 < 380 < 380 07/23 < 380 < 380 < 380 < 380 < 380 07/30 < 380 < 380 570(770) < 380 < 380 08/05 < 380 < 380 < 380 < 380 < 380 D 08/12 < 380 < 380 < 380 < 380 < 380 08/20 < 380 < 380 < 380 < 380 < 380 08/27 < 380 < 380 < 380 < 380 < 380 09/03 < 450 < 450 < 450 < 450 < 370 09/10 < 390 < 390 < 390 < 390 1600(1080) 09/17 < 380 < 380 < 380 < 380 1500(490) 09/24 < 380 < 380 < 380 < 380 520(1100)
- 1.96a (Due to counting statistics)
, Table II.C.4(d) Tritium in Surface Water (pCi/L) 4* Quarter 1994 Collected Downstreams Upstream Effluent F-20 R-10 A-21 F-19 A-25 10/01 < 380 < 380 < 380 < 380 < 380 10/08 < 450 < 380 < 470 < 450 < 380 10/15 < 380 < 380 < 380 < 380 2700(480)*
10/22 < 380 < 380 < 380 < 380 2100(480) 10/29 < 380 < 380 < 380 < 380 1300(480) ,
11/05 < 390 < 380 < 390 < 390 < 400 N 11/12 < 390 < 380 < 390 < 390 < 380 11/19 < 380 < 380 < 380 < 380 < 380 11/26 < 410 < 380 < 410 < 410 < 390 12/03 < 380 < 390 < 380 < 380 < 380 12/10 < 380 < 380 < 380 < 380 710(480) 12/17 < 380 < 390 < 380 < 380 < 390 12/24 < 380 < 380 < 380 < 380 < 380 12/31 < 390 < 390 < 390 < 390 < 420
- 1.% (Due to counting statistics)
Table ILC.5 Radionuclide Concentrations In Surface Water (pCi/L)
Collection Date: January 14, 1994" Downstream Sites Upstream Sites Effluent Radionuclide St. Vrain S. Platte St. Vrain S. Platte Goosequill F-20 R-10 A-21 F-19 A-25 Cs-134 < 1.0 < 1.0 < 2.2 < 1.8 < 2.0 Cs-137 5.8(1.5)* 3.9(1.5) < 2.7 < 2.2 < 2.4 Zr-95 < 2.5 < 2.5 < 5.2 < 4.3 < 6.3 Nb-95 < 0.92 < 1.1 < 2.0 < l .7 < 1.9 Co-58 < 0.92 < 0.92 < 2.0 < l .7 < 1.8 Mn-54 < 0.99 < l .0 < 2.2 2.6(2.2) < 2.0 Zn-65 < 2.5 < 2.8 < 6.0 < 5.0 < 5.3 Fe-59 < 2.4 3.4(3.4) < 5.2 < 4.3 < 4.6 Co-60 < 0.91 < 1.0 < 2.3 < 1.9 < 2.2 Ba-140 < 1.6 < l .7 21(23) < 3.0 < 17 La-140 < 1.8 < 1.9 24(26) < 3.4 < 20 4
- - 1.W (Due to counting statistics)
- - A-25 collected January 15,1994
J
-t Table II.C.5 Radionuclide Concentrations In Surface Water (pCi/L)
Collection Date: February 12, 1994**
Downstream Sites Upstream Sites Effluent Radionuclide St. Vrain S. Platte St. Vrain S. Platte Goosequill F-20 R-10 A-21 F-19 A-25 Cs-134 2.7(2.3)* < 1.9 < 1.5 < 1.2 < 1.0 Cs-137 < 2.5 3.4(2.7) 2.4(2.2) 5.0(1.8) 5.4(1.5)
Zr-95 < 4.7 < 4.4 < 3.5 < 2.8 < 2.2 Nb-95 < 1.8 < 1.8 < 1.3 < 1.2 < 1.0 Co-58 3.2(2.4) < 2.0 < 1.6 < 1.2 < 0.91 Mn-54 < 2.1 < 1.9 < 1.5 < 1.1 1.2(1.2)
Zn-65 < 5.3 < 5.3 < 4.1 < 3.8 < 3.0 Fe-59 < 4.7 < 5.4 < 4.2 < 2.7 < 2.3 Co-60 < 2.2 < 2.0 < 1.6 < 1.1 < 0.%
Ba-140 < 3.2 < 3.1 < 2.4 < 3.1 < 1.6 La-149 < 3.7 < 3.6 < 2.8 < 3.6 < 1.9
- - 1.96a (Due to counting statistics)
" - A-25 collected February 14, 1994
e
~.
Table II.C.5 Radionuclide Concentrations In Surface Water (pCi/L)
Collection Date: March 12, 1994**
Downstream Sites Upstream Sites Effluent Radionuclide St. Vrain S. Platte St. Vrain S. Platte Goosequill F-20 R-10 A-21 F-19 A-25 Cs-134 < 2.0 < 2.1 < 2.1 1.4(1.4)* < 2.0 Cs-137 < '2.5 < 2.5 < 2.5 2.7(1.7) 3.1(2.8)
Zr-95 < 4.7 , < 5.8 < 6.2 < 2.7 < 4.5 Nb-95 < 2.3 < 1.9 < 1.8 < 1.1 < 1.7 Co-58 < 2.3 < 1.9 < 2.3 < 1.3 < 1.8 v.
~
Mn-54 < 2.0 2.6(2.5) < 2.1 < 1.2 < 2.0 Zn-65 < 5.3 < 5.6 < 5.5 < 3.1 < 5.0 Fe-59 < 4.7 < 6.2 < 6.9 < 3.6 < 6.4 Co-60 < 2.2 < 2.2 < 2.2 < 1.3 < 2.1 Ba-140 < 3.3 < 3.4 < 3.4 < 1.9 < 11 La-140 < 3.8 < 3.9 < 3.9 < 2.2 < 13
- - 1.% (Due to counting statistics)
- - A-25 collected March 15, 1994 l
i Table II.C.5 Radionuclide Concentrations In Surface Water (pCi/L)
Collection Date: April 9,1994" Downstream Sites Upstream Sites Effluent Radionuclide St. Vrain S. Platte St. Vrain S. Platte Goosequill F-20 R-10 A-21 F-19 A-25 I
Cs-134 < 1.1 < 1.2 < 2.1 < 1.9 < 0.69 Cs-137 7.3(1.7)* 3.5(1.8) < 2.6 < 2.3 5.3(1.0)
Zr-95 < 3.0 < 2.5 < 4.9 < 4.5 2.3(2.2)
Nb-95 1.8(1.7) 3.0(1.6) < 1.9 < 1.7 < 0.85 Co-58 < 1.0 < 1.1 < 2.0 < 2.1 < 0.76 Mn-54 < 1.2 < 1.2 < 2.2 < 2.0 < 0.71 Zn-65 < 4.2 < 4.0 < 5.9 < 5.3 < 2.5 Fe-59 < 3.5 < 3.6 < 6.6 < 4.5 < 1.6 Co-60 < 1.1 < 1.1 < 2.2 < 2.1 < 0.64 Ba-140 < 4.9 < 4.7 < 3.5 < 8.1 < 1.1 La-140 < 5.6 < 5.4 < 4.0 < 9.3 < 1.3
- 1.% (Due to counting statistics)
" A-25 collected April 15. 1994
___ _- - ._ -_ _-- _ ______. ______ _ _ -_ ____.- - _ _ _ _ _ . __ . .. . - . - - . _~
Table II.C.5 Radionuclide Concentrations In Surface Water (pCi/L)
Collection Date: May 14, 1994" Downstream Sites Upstream Sites Effluent Radionuclide St. Vrain S. Platte St. Vrain S. Platte Goosequill F-20 R-10 A-21 F-19 A-25 Cs-134 < 2.0 < 1.0 < 1.1 < 2.1 < 1.2 Cs-137 < 2.5 1.8(1.5)* 4.4(1.7) < 2.5 5.4(1.7)
Zr-95 < 4.7 < 2.3 < 2.5 < 5.3 < 2.5 Nb-95 < 1.8 < 0.95 < 1.2 < 1.9 < 1.1 Co-58 < 2.0 < 0.92 < 1.0 < 2.0 < 1.1 u,
Mn-54 < 2.0 < 1.0 < 1.1 < 2.1 < 1.2 Zn-65 < 5.7 < 2.9 < 3.3 < 6.0 < 3.2 Fe-59 < 4.6 < 2.3 < 2.6 < 4.8 4.9(4.5)
Co- 60 < 2.2 < l .1 < 1.1 < 2.2 < 1.1 Ba-140 < 3.3 < 1.6 < 3.3 < 5.4 < 1.8 La-140 < 3.8 < 1.9 < 3.8 < 6.2 < 2.1
- - 1.96o (Due to counting statistics)
- A-25 collected May 15. 1994 I
, s . - , - . . , . - ,, . . . + , . . . . . , , , .w -- -- , , ~ , ,
-t i
Table II.C.5 Radionuclide Concentrations In Surface Water (pCi/L)
Collection Date: June 11, 1994" Downstream Sites Upstream Sites Effluent Radionuclide St. Vrain S. Platte St. Vrain S. Platte Goosequill F-20 R-10 A-21 F-19 A-25 Cs-134 < 1.2 < 1.1 < 2.4 < 1.2 < 1.2 Cs-137 3.5(1.8)* 5.5(1.6) < 2.9 5.9(1.8) 2.0(1.8)
Zr-95 < 2.6 < 2.4 < 6.8 < 2.5 < 2.8 Nb-95 < 1.2 < 1.2 < 2.2 1.8(1.6) < 1.1 Co-58 < 1.1 < 1.0 2.9(3.1) < 1.3 < 1.1 u
Mn-54 < 1.2 < 1.1 < 2.5 < 1.1 < 1.2 Zn-65 < 3.5 < 3.2 < 6.7 < 2.9 < 3.4 Fe-59 < 2.9 < 3.2 < 7.3 < 3.6 < 2.8 Co-60 < 1.1 < 1.0 < 2.5 1.3(1.3) < 1.3 Ba-140 < 4.8 < 4.3 < 10 < 4.7 < 2.0 La-140 < 5.5 < 4.9 < 12 < 5.4 < 2.2
- 1.W (Due to counting statistics)
" A-25 collected June 15, 1994 l
l
, _ . - - .- - .. .-m. ~m. . - - , - - - -- . . - . - .-c , _ , - , _ , ., . , . - . - . _.w r
12 Table II.C.5 Radionuclide Concentrations In Surface Water (pCi/L)
Collection Date: July 9,1994" Downstream Sites Upstream Sites Effluent Radionuclide St. Vrain S. Platte St. Vrain S. Platte Goosequill F-20 R-10 A-21 F-19 A-25 Cs-134 < 1.2 < 1.3 < 2.1 < 2.2 < 0.62 Cs-137 4.9(1.9)* 4.7(2.0) < 2.6 < 2.7 4.5(0.94)
Zr-95 < 3.1 < 2.8 < 4.9 < 5.1 < 1.7 Nb-95 < 1.3 3.5(1.5) < 1.9 < 2.0 < 0.57 Co-58 2.0(1.6) < 1.2 < 2.1 < 2.0 < 0.55 Mn-54 < 1.3 < 1.2 < 2.1 < 2.2 0.81(0.76)
I Zn-65 < 3.3 < 3.3 < 6.0 < 6.1 < 1.6 Fe-59 < 3.5 < 3.5 < 4.9 < 5.0 < 1.5 Co-60 < 1.2 < 1.3 < 2.3 < 2.4 < 0.58 Ba-140 < 2.1 < 2.1 < 6.5 < 6.4 < 3.0 La-140 < 2.4 < 2.4 < 7.5 < 7.4 < 3.4
- 1.W (Due to counting statistics)
" - A-25 collected July 15,1994
t Table II.C.5 Radionuclide Concentrations In Surface Water (pCi/L)
Collection Date: August 12, 1994" Downstream Sites Upstream Sites Effluent Radionuclide St. Vrai.n S. Platte St. Vrain S. Platte Goosequill F-20 R-10 A-21 F-19 A-25 Cs-134 < 1.2 < 2.0 < 2.1 < 1.2 < 1.2 Cs-137 < 1.4 3.9(2.9)* < 2.6 3.5(1.8) 4.7(1.8) 7r-95 < 2.7 < 4.7 < 4.9 < 2.7 < 2.6 Nb-95 < 1.0 < 1.9 < 1.9 < 1.1 1.5(1.7) u, Co-58 < 1.1 < 1.9 < 2.1 < 1.1 1.5(1.6)
Mn-54 < 1.2 < 2.0 < 2.1 < 1.2 < 1.2 Zn-65 < 3.1 < 5.4 < 6.0 < 3.4 < 3.1 Fe-59 < 2.7 < 5.1 < 4.9 5.3(3.6) 4.3(4.8)
Co-60 < 1.3 < 2.2 < 2.3 < 1.1 < 1.1 Ba-140 < 1.9 < 4.5 < 6.5 < 1.9 < 1.9 La-140 < 2.2 < 5.2 < 7.5 < 2.2 < 2.2
- 1.h (Due to counting statistics)
Ji
" A-25 collected August 15,1994
t Table II.C.5 Radionuclide Concentrations In Surface Water (pCi/L)
Collection Date: September 12, 1994**
Downstream Sites Upstream Sites Effluent St. Vrain S. Platte St. Vrain S. Platte Goosequ r F-20 R-10 A-21 F-19 A-25 Cs-134 < 2.3 < 2.1 < 2.0 < 1.8 < 2.1 Cs-137 < 2.9 < 2.6 < 2.4 2.3(2.6)* < 2.5 Zr-95 < 5.6 < 4.9 < 4.6 < 4.2 < 4.7 Nb-95 < 2.1 < 1.9 < 1.8 < 1.6 < 1.9 Co-58 < 2.5 < 1.9 < 1.8 < 1.7 < 1.9 Mn-54 < 2.4 < 2.1 < 2.1 < 1.8 2.2(2.5)
Zn-65 < 6.4 < 5.9 < 5.5 < 4.8 < 5.3 Fe-59 < 6.9 < 4.9 < 4.6 < 5.0 < 4.8 Co-60 < 2.5 < 2.2 < 2.1 < 1.9 < 2.1 Ba-140 < 3.9 < 3.4 < 3.2 < 2.9 < 8.6 I2-140 < 4.5 < 3.9 < 3.7 < 3.3 < 9.8
- - 1.W (Due to counting statistics)
- - A-25 collected September 15, 1994
________ _ _ ____ _ _. ~ , , _ . . -. __ _ ._. .-. ___ _ - . - _ . . _ _ .
7q Table II.C.5 Radionuclide Concentrations In Surface Water (pCi/L)
Collection Date: October 8,1994" l
Downstream Sites Upstream Sites Ef0uent Radionuclide St. Vrain S. Platte St. Vrain S. Platte Goosequill F-20 R-10 A-21 F-19 A-25 Cs-134 < 1.8 < 1.1 < 2.1 < 2.1 < 2.2 Cs-137 < 2.2 4.8(1.7)* 3.4(3.1) < 2.5 3.6(3.2)
Zr-95 < 4.8 < 2.5 < 5.6 < 5.5 < 5.1 Nb-95 < 1.7 1.3(1.3) < 2.0 < 1.9 < 2.0 Co-58 < 1.8 < 1.0 < 1.9 < 1.9 < 2.0 u
Mn-54 < 1.9 < 1.1 < 2.1 < 2.1 < 2.5 Zn-65 < 4.8 < 3.1 < 5.9 < 5.6 < 5.9 Fe-59 < 5.0 < 2.6 < 5.0 < 4.8 < 7.2 Co-60 < 1.9 < 1.1 < 2.2 < 2.2 < 2.3 Ba-140 < 2.9 < 1.8 < 7.9 < 6.4 < 11 La-140 < 3.4 < 2.0 < 9.1 < 7.3 < 13
- - 1.W (Due to counting statistics)
- - A-25 collected October 15,1994
Table II.C.5 Radionuclide Concentrations In Surface Water (pCi/L)
Collection Date: November 12, 1994**
Downstream Sites Upstream Sites Effluent
. Radionuclide St. Vrain S. Platte St. Vrain S. Platte Goosequill F-20 R-10 A-21 F-19 A-25 Cs-134 < 2.2 < 1.2 < 2.0 < 2.2 < 2.2 Cs-137 < 2.7 5.2(1.9)* < 2.5 < 2.7 < 2.7 Zr-95 < 6.1 < 2.7 < 4.7 < 5.9 < 5.1 Nb-95 < 2.0 1.9(1.4) < 1.8 < 2.0 .< 2.0 _
Co-58 < 2.0 < 1.1 < 1.8 < 2.0 < 2.0 Mn-54 < 2.2 < 1.3 < 2.1 < 2.2 < 2.2 Zn-65 < 6.0 < 3.2 < 5.3 < 5.6 < 6.2 Fe-59 < 5.1 < 2.9 < 4.7 < 5.1 < 6.8 Co-60 < 2.3 < 1.1 < 2.2 < 2.3 < 2.3 Ba-140 10(9.6) 2.8(2.4) < 8.4 < 3.6 < 3.5 La-140 12(11) 3.3(2.7) < 9.7 < 4.1 < 4.1
- - 1.96o (Due to counting statistics)
- - A-25 collected November 15, 1994
Table II.C.5 Radionuclide Concentrations In Surface Water (pCi/L)
Collection Date: December 10, 1994**
Downstream Sites Upstream Sites Effluent
- Radionuclide St. Vrain S. Platte St. Vrain S. Platte Goosequill F-20 R-10 A-21 F-19 A-25 Cs-134 < 2.3 < 1.1 < 1.0 < 2.8 2.1(2.5)*
Cs-137 < 2.8 5.0(1.6) 6.9(1.5) 4.3(4.2) < 2.5 Zr-95 < 5.5 < 2.3 < 2.2 < 6.9 < 4.6 Nb-95 < 2.1 < 1.1 < 1.2 f 2.7 < 1.8 Co-58 < 2.3 < 1.0 1.51.3) < 2.9 2.4r2.9) m . . . -
Mn-54 < 2.4 1.4(1.3) 1.3(i.2) < 2.9 < 2.2 Zn-65 < 6.7 < 3.5 < 3.3 < 8.1 < 5.5 Fe-59 < 5.5 3.1(3.1) < 2.9 < 7.0 < 4.7 Co-60 < 2.5 < 1.0 < 1.0 < 3.1 < 2.2 Ba-140 8.0(8.6) < 1.8 < 1.7 < 4.7 < 3.3 I2-140 9.2(9.9) < 2.1 < 1.9 < 5.4 < 3.8
- - 1.% (Due to counting statistics)
- - A-25 collected December 15. 1994
i
- 3. Ground Water -
Ground water is sampled quarterly at two locations. These are at F-16, a well on the farm immediately north and the closest to the facility down the hydrological gradient, and at R-5, a well at a personal residence in the town of Milliken. Table !
II.C.6 lists the measured concentrations of fission products and activation products in ground water. The Cs-137 results are not surprising due to residue of Chernobyl fallout. !
The other results above MDC are assumed to be statistically false positive values.
Table II.C.7 shows tritium concentrations in the same well water samples. No tritium concentrations above the MDC were observed. Figure II.C.1 shows measured tritium concentrations in the F-16 well from 1984 through 1994. We initiated a weekly sampling of this site beginning early in 1991 and have continued to date. The data for the weekly samples of the F-16 well for 1994 are shown in Table II.J.1 (see summary section). Figure II.C.2 is a plot of this data for 1993 and 1994. ;
For comparison purposes we include Table II.C.8 which lists the Maximum Permissible Concentrations in drinking water from the old 10CFR20.
61
1 Table II.C.6 Radionuclide Concentrations in Ground Water (pCi/L) 1" 2*8 3"' 4*
Radio- Quarter Quarter Quarter Quaner )
F-16 R-5 F-16 R-5 F-16 R-5 F-16 R-5 Cs-134 < 1.2 < 2.1 < 2.0 < 1.2 < 2.0 < 2.2 < 1.9 < 2.3 Cs-137 3.5(1.7)* 3.6(3.1) < 2.5 6.3(1.9) 4.9(2.9) 3.7(3.1) < 2.3 < 2.7 Zr-95 < 2.5 < 5.4 < 5.6 < 2.7 < 4.8 < 5.0 < 4.4 < 5.2 Nb-95 < 1.1 < 2.0 < 1.9 < 1.5 < 2.0 < 1.9 < 2.0 < 2.0 Co-58 < 1.0 < 2.1 < 2.2 < 1.1 < 2.0 < 2.0 < 1.7 < 2.4 Mn-54 < 1.1 < 2.1 < 2.0 < 1.2 < 2.0 < 2.1 < 1.9 2.9(2.7)
Zn-65 < 3.3 < 6.4 < 5.8 < 5.0 < 5.6 < 5.6 < 5.1 < 6.0 Fe-59 < 3.4 < 5.0 < 4.8 < 3.0 < 4.6 < 5.6 < 4.4 8.8(7.8)
Co-60 < 1.1 3.4(2.7) < 2.2 1.6(1.4) < 2.2 < 2.4 < 2.0 - < 2.4 Ba-140 < 4.4 6.2(6.3) < 3.3 < 2.1 < 3.3 < 3.5 < 3.1 < 3.6 La-140 < 5.0 7.2(7.2) < 3.8 < '2.4 < 3.8 < 4.0 < 3.5 < 4.2
- - 1.96o (Due to counting statistics)
I
l 0
4 5- 8 9 3 9 R 1 <
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r e/ 9 t
a ue1 c2 Qllo/ 1 1
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8 1
3 o F <
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5- 9 Cp 4 9 R 3
(
9 1 <
r rd 49 e
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t a a c2 ule1/
W Ql o80 d dCr 6 0
9 n i h
1 3
u T F <
o r
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u 4 9
5- 8 3
t 9 R i
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7 atc4 u e1 Ql /
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e c 1
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- . 111
- c. ..
i Table II.C.8 ,
Maximum Permissible Concentrations in Drinking Water.
(10CFR20, Appendix B, Table II)
Radionuclide Concentration (pCi/L) !
II-3 3 x 106 I-131 3 x 102 Cs-134 9 x 105 ,
Cs-137 2 x 104 Zr-95 6 x 104 ;
5 Nb-95 1 x 10 i Co-58 1 x 105 Mn-54 1 x 105 Zn-65 1 x 105 ;
Fe-59 6 x 104 Co-60 5 x 104 Ba-140 3 x 104 La-140 2 x 104 i
l l
I 64
m Tritium Concentration in F-16 Well Water i 1984-1994 g Concentration (pCi/L) 10000_. __ - - . . _ . . . . _ _ _
_ _ . _ . __ _- . __ _ _ _ __ .L ._ _ _ _ _ _ _ _ __.. _ ._.
{
1000_
_ _f I
_ ___..._ {
i- ~
... _ . o Z Z:z
- _ _ __ _____ _____ _ rz.=_:= = = x= d =_z:_:r = _ 4 : Tz:Zz =
_ _ . ._ .._ f. -. __ _ _ _ _ _ _ .
3
[]
100 iiiiiiiiiiiiiiiiiiiiiiiiiiiiiii,iiiiiiiiii 84 85 86 87 88 89 90 91 92 93 94 Year
~
m C
Tritium Concentrations at F-16 Well Water a 0:
O Concentration (pCi/L) b 1993 1994 10,000 .
. 1
. : 4
. i i
.i 8 i 1,000 .
9no ^
1
'g
> a v i
- o . a !
C2 C2 v@DN@ V v
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i I,,1,,f,,I,,f,,f,,f..I,,I,,I,,I,,!,,1,,I,,l.,l.,f,,i,,f,,I,,I,,I,,I,,!,,!,,f,,f,,f,,I,1 1,,I,,!,,1,,1,,l.,
~
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N O 7 A S 2 *T N S
- N O " R S e g N O 7 8 2 T M " "9 R 8 S g N O 9 M 2A"A4e eA"e&Sgses2A"A4"ee Aed-g30A Date CoIIceted
i II.D. Milk The dairy food chain is the critical pathway for potential radiation dose commitment around any nuclear facility. This is true for both chronin and acute releases.
The critical individual would be an infant consuming milk produced from cows grazing local pastures. Milk is the critical pathway for potential dose commitment to humans from environmental contamination of H-3 and Cs-137. For this reason milk is sampled extensively to document the presence or absence of radioactivity due to the decommissioning operation.
There are no dairies (or personal milk cows) in the facility area which is within a 1.6 km radius from the facility. The five dairies in the adjacent area,1.6-8 km radius, were selected as they are located in the highest X/Q areas. The description of these k> cations can be found in Table F-4 of the ODCM and Figure III.B.2. The single reference location dairy, R-8, is 22.5 km Northwest of the facility in the least predominant wind direction. Herd management practices are similar at all dairy locations. The cows in the milking herd are never on pasture but are managed under dry-lot management which is typical of the Western U.S.
Table II.D.1 lists the concentrations of all gamma-emitting radionuclides that are investigated in milk samples.
Natural-potassium, as measured by K-40, is extremely constant in milk. The mean literature value for cow milk is 1.5 g/L. K concentrations are homeostatically controlled and independent of K intake. K-natural is measured in all milk samples as a quality control measure for the other radionuclides determined in the same sample by gamma-ray spectrometry. ;
i 67
i l
Table II.D.2 lists measured tritium concentrations in milk. Elevated tritium concentrations in milk due to facility effluents were not observed during the operational or defueling phase, or the decommissioning phase to date. During 1994, only three l
detectable concentrations were observed. These could easily be false positive values since the mean of the 5 adjacent sites was not statistically greater than the reference site.
This implies that any tritium from facility effluent is not contributing radiation dose to humans via the milk pathway. Tritium concentrations in milk should respond rapidly to ;
changes in tritium concentrations of the forage water intake or drinking water intake to the cow. This is due to the short biological half-life for water in the cow (about three days for the lactating cow). As noted in previous reports, the reported tritium concentration in milk is the tritium in water extracted from the milk. Centamination of milk samples by any radionuclide due to facility effluents has never been observed during the operational, defueling or decommissioning phases of Fort St. Vrain.
E 68
Table II.D.1 Radionuclide Concentrations in Milk (pCi/L)
Location A-6 A-18 A-23 A-24 A-26 R-8 Collection 1/14/94 1/14/94 1/14/94 1/14/94 1/14/94 1/14/94 I Date Cs-134 < 1.3 < 2.2 < 1.4 < 2.1 < 1.3 < 1.2 Cs-137 8.1(2.5)* < 2.6 7.4(2.5) < 2.5 6.7(2.4) 6.3(2.2)
Ba-140 < 1.9 < 3.4 < 7.8 < 3.4 8.5(9.7) < 4.3 La-140 < 2.2 < 4.0 < 9.0 < 3.9 9.8(11) < 5.0 Collection 2/12/94 2/12/94 2/12/94 2/19/94 2/19/94 2/12/94 Date Cs-134 < 2.3 < 1.4 < 2.2 < 1.3 < 1.3 < 2.0 g Cs-137 6.5(3.3) 6.1(2.6) < 2.7 5.7(2.4) 6.1(2.4) < 2.4 Ba-140 < 3.7 < 3.3 6.3(7.0) < 1.9 < 2.0 < 3.2 La-140 < 4.2 < 3.8 7.2(8.1) < 2.2 < 2.3 < 3.6 Collection 3/12/94 3/12/94 3/12/94 3/12/94 3/12/94 3/12/94 Date Cs-134 < 2.0 < 2.2 < 2.2 < 1.5 < 2.2 < 2.2 Cs-137 < 2.5 3.9(3.1) 3.9(3.2) 3.9(2.2) < 2.7 < 2.6 Ba-140 < 3.2 < 6.6 < 5.7 < 2.4 < 8.6 < 3.4 La-140 < 3.6 < 7.5 < 6.5 < 2.8 < 9.9 < 3.9
- 1.96a (Due to counting statistics)
t Table II.D.1 Radionuclide Concentrations in M'1k (pCi/L)
Imcation A-6 A-18 A-23 A-24 A-26 R-8 Collection 04/09 04/09 04/09 M/09 04/09 04/09 Date Cs-134 < l .0 < 2.2 < l .3 < 1.2 < 0.77 < 2.1 Cs-137 6.3(1.8)* < 2.6 6.0(2.5) 2.9(1.8) 7.7(1.4) < 2.6 Ba-140 < 2.6 < 3.5 < 3.8 < 3.9 < 2.3 < 5.5 La-140 < 2.9 < 4.0 < 4.3 < 4.5 < 2.6 < 6.3 -
Collection 05/14 05/14 05/14 05/14 05/14 05/14 Date Cs-134 < 2.1 < l.2 < 2.1 < 1.5 < 2.2 < 1.4 g Cs-137 < 2.6 8.1(2.1) 2.6(3.0) 7.1(2.8) 4.5(3.1) 5.3(2.6)
Ba-140 < 3.8 < 1.7 < 3.3 < 2.8 < 4.5 < 2.3 I2-140 < 4.3 < 2.0 < 3.8 < 3.2 < 5.2 < 2.7 Collection 05/28 05/28 05/28 05/28 05/28 05/28 Date Cs-134 < 1.3 < l .4 < 1.2 < 0.74 < 2.2 < 2.1 Cs-137 6.8(2.4) 6.5(2.5) 2.2(1.7) 5.3(1.3) 6.3(3.1) 3.3(3.0)
Ba-140 < 1.9 3.3(3.1) < 2.6 < 1.4 < 3.4 < 3.3 La-140 < 2.2 3.8(3.6) < 3.0 < 1.7 < 3.9 < 3.8
- - 1.96o (Due to counting statistics) l
t ..
1 Table II.D.1 Radionuclide Concentrations in Milk (pCi/L) location A-6 A-18 A-23 A-24 A-26 R-8 Collection 06/11 06/11 06/11 06/11 06/11 06/11 Date Cs-134 < 1.5 < 1.4 < 2.0 < 1.3 < 2.1 < 2.3 Cs-137 7.3(2.6)* 6.2(2.5) < 2.4 5.7(2.5) < 2.7 < 2.7 Ba-140 < 2.2 < 2.0 9.0(7.1) < 3.7 < 3.4 < 3.6 La-140 < 2.5 < 2.3 10(8.2) < 4.3 < 3.9 < 4.1 -
Collection 06/25 06/25 06/25 06/25 06/25 06/25 Date Cs-134 < 2.3 < 1.2 < 1.6 < 0.95 < 2.3 < 2.0 3 Cs-137 2.9(3.3) 5.9(2.1) < 1.9 6.4(1.7) 3.9(3.3) 4.5(2.8)
Ba-140 < 3.6 < 2.3 < 2.5 < 2.0 < 3.7 < 3.1 La-140 < 4.1 < 2.7 < 2.9 < 2.3 < 4.3 < 3.6 Collection 07/09 07/09 07/09 07/09 07/09 07/09 Date Cs-134 < 2.1 < 1.4 < 1.3 < 1.4 < 2.3 < 2.1 Cs-137 < 2.6 7.4(2.6) 8.0(2.4) 6.4(2.6) < 2.9 3.1(3.1) i Ba-140 < 3.7 < 2.1 < 1.9 3.6(3.0) < 3.8 < 3.4 La-140 < 4.2 < 2.4 < 2.1 4.1(3.4) < 4.4 < 3.9
- - 1.96o (Due to counting statistics) 4
_ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = _ _ _ _ _ _ --- ___ m _ _ - __ __- _ _ _ _ . , - _m -
Table II.D.1 Radionuclide Concentrations in Milk (pCi/L) location A-6 A-18 A-23 A-24 A-26 R-8 Collection 07/23 07/23 07/23 07/23 07/23 07/23 Date Cs-134 < 1.6 < l .6 < 2.1 < 2.1 < 2.1 < 2.2 Cs-137 5.8(2.9)* 6.9(2.9) < 2.5 < 2.6 2.8(3.0) 3.1(3.1) ,
Ba-140 < 2.7 < 2.9 < 3.3 < 3.4 < 6.0 < 3.4 La-140 < 3.1 < 3.4 < 3.7 < 3.9 < 6.9 < 3.9 Collection 08/12 08/12 08/12 08/12 08/12 08/12 Date Cs-134 < 2.3 < 2.5 < 1.6 1.6(1.8) < 1.4 < 1.4 g Cs-137 < 2.8 < 3.1 8.5(2.8) 7.4(2.8) 6.1(2.6) 6.7(2.7)
Ba-140 < 4.3 < 5.0 < 2.8 < 2.2 < 2.8 < 2.5 La-140 < 5.0 < 5.8 < 3.2 < 2.6 < 3.2 < 2.9 Collection 08/27 08/27 08/27 08/27 08/27 08/27 Date Cs-134 2.3(2.6) 2.4(2.3) < 2.1 < 1.3 < 1.3 < 2.1 Cs-137 < 2.6 3.1(2.8) < 2.6 7.1(2.4) < 1.5 3.1(3.1)
Ba-140 3.9(4.6) < 3.1 < 3.4 < 1.9 < 2.0 < 3.4 La-140 4.5(5.3) < 3.6 < 3.9 < 2.2 < 2.3 < 4.0
- 1.96a (Due to counting statistics)
-- - - _ _ .- - _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ . . __ -, ._ -_ ._.~ . . . - . .
Table II.D.1 Radionuclide Concentrations in Milk (pCi/L)
Location A-6 A-18 A-23 A-24 A-26 R-8 Collection 09/10 09/10 09/10 09/10 09/10 09/10 Date Cs-134 < 2.1 < 2.1 < 2.2 < 2.3 < 2.1 < 2.0 Cs-137 < 2.6 < 2.6 5.4(3.1)* < 2.8 < 2.6 < 2.4 Ba-140 < 4.3 < 3.4 < 5.6 < 3.6 < 6.3 < 3.1 La-140 < 5.0 < 3.9 < 6.5 < 4.2 < 7.2 < 3.6 Collection 09/24 09/24 09/24 09/24 09/24 09/24 Date Cs-134 4.9(3.1) < 2.1 < 2.2 < 1.8 < 2.2 < 2.6 g Cs-137 < 3.1 < 2.5 3.1(3.1) < 2.1 < 2.6 5.7(3.7)
Ba-140 < 4.0 < 3.4 < 6.4 < 2.8 9.6(9.7) < 4.1 La-140 < 4.6 < 3.9 < 7.3 < 3.2 11(11) < 4.7 Collection 10/08 10/08 10/08 10/08 10/08 10/08 Date Cs-134 < 2.1 < 2.2 < 2.2 < 2.2 < 2.3 < 2.0 Cs-137 < 2.5 4.0(3.2) < 2.7 < 2.7 < 2.8 < 2.5 Ba-140 < 4.3 < 5.1 < 3.5 6.7(6.8) < 3.6 < 3.2 I2-140 < 5.0 < 5.9 < 4.0 7.8(7.8) < 4.2 < 3.7
- 1.W (Due to counting statistics) i
Table II.D.1 Radionuclide Concentrations in Milk (pCi/L)
Location A-6 A-18 A-23 A-24 A-26 R-8 Collection 11/12 11/12 11/12 11/12 11/12 11/12 Date Cs-134 < 2.2 < 2.1 3.0(2.9)* < 2.2 < 2.0 < 1.9 Cs-137 < 2.6 < 2.6 < 3.0 3.5(3.2) < 2.4 < 2.4 Ba-140 < 3.5 < 3.4 < 3.9 7.1(6.8) < 3.2 < 4.1 La-140 < 4.0 < 3.9 < 4.5 8.2(7.8) < 3.6 < 4.8 Collection 12/10 12/10 12/10 12/10 12/10 12/10 Date Cs-134 < 2.2 < 2.2 < 2.5 < 2.2 < 2.6 < 1.8 g Cs-137 < 2.6 < 2.6 < 3.0 < 2.6 < 3.2 2.5(2.7)
Ba-140 < 3.5 < 3.5 6.6(7.3) < 3.4 < 4.2 < 3.0 La-140 < 4.0 < 4.0 7.6(8.4) < 4.0 < 4.8 < 3.4
- - t.96a (Due to counting statistics)
Table II.D.2 Tritium in Milk (pCi/L) :
Collection Adjacent Reference j A-6 A-18 A-23 A-24 A-26 R-8 1/14/94 < 390 < 390 < 390 < 390 < 390 < 390 2/12/94 < 390 < 390 < 390 < 390 < 390 < 390 3/12/94 < 380 < 380 < 380 < 380 < 380 < 380 4/9/94 < 380 < 380 < 380 < 380 < 380 < 380 5/14/94 < 380 < 380 < 380 < 380 < 380 < 380 5/28/94 < 380 < 380 < 380 < 380 < 380 < 380 6/11/94 < 380 < 380 < 380 < 380 < 380 < 380 6/25/94 < 380 < 380 < 380 < 380 < 380 < 380 DI 7/9/94 < 380 < 380 < 380 < 380 < 380 < 380 7/23/94 < 380 < 380 < 380 < 380 < 380 < 380 8/12/94 < 380 < 380 < 380 < 380 < 380 < 380 8/27/94 < 390 < 390 < 390 < 390 < 390 < 390 9/10/94 < 380 < 380 < 380 < 380 < 380 < 380 9/24/94 < 380 < 380 < 380 1100(460)* < 380 < 380 10/8/94 < 380 < 380 < 380 < 380 < 380 550(450) 11/12/94 < 380 < 380 < 380 < 380 < 380 < 380 12/10/94 420(460) < 390 < 390 < 390 < 390 < 390
- - 1.96o Due to counting statistics I
4
.__ = _ _ __
m _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ . _ . _ _ _ _ _ _ _ _ _
_ _ _ _ _ _ _____m ._ _ _ _ . -___ ____ . _ .
II.E. Food Products
,' Food sampling locations wer; selected from areas possibly irrigated by surface
(-
water downstream of the FSV' discharge point or by well water from the aquifer most i likely to be contaminated by seepage from the farm pond. The locations of these food product collection sites are described in Table F-4 of the ODCM. One sample of each !
principal class of food products was collected from these locations. Locations and ;
available produce often change due to owner needs, harvest time, harvest size, etc.
Each sample is homogenized, without drying, immediately after collection. The j sample is then counted by gamma-ray spectrometry. Table II.E.1 lists the date of collection and the results for the 1994 harvest. One food sample showed low but-detectable Cs-137 from past Chernobyl world-wide fallout deposition. The gamma-ray spectra were scanned for other radionuclides, but only the naturally occurring radionuclides were observed, presumably due to surface soil deposits.
If Cs-137 was released due to decommissioning, the primary food chain to l
humans would be through pasture to dairy and beef cattle and to meat and milk. )
Therefore, in addition to extensive milk sampling, and since beef cattle graze near the effluent routes from the facility, these animals are routinely slaughtered and muscle tissue is analyzed for the radionuclides susprted in the effluent. During operation of the ,
reactor, for a significant period (1973-1983) animals were taken from the pasture'and counted in the CSU Whole-Body Counter. No I-131 or Cs-137 due to plant efiluent was ever detected in this herd.
In 1992, one animal that grazed the pastures north of the facility, and also had drinking access to the C-oosequili ditch, was slaughtered and the tissue analyzed. Tissues 1
76
i from this animal will serve as a control for others slaughtered after decommissioning was initiated. -
1 In 1994, two animals were collected for comparison purposes. One animal was i l
removed from the pasture on 5/2/94 and one animal was removed on 12/5/94. Tables -
II.E.2a and II.E.2b give the slaughter dates. Each carcass was aged, according to i
general practice for one week in a cooler. Ground meat samples representing the total carcass were mixed and ten random one-kilogram samples of ground beef were packed into one-Liter Marinelli beakers for gamma-ray spectrum analysis. Subsamples of each were taken for tritium analysis. The tritium activity was measured in the water vacuum
{
distilled from each sample.
There is evidence of Cs-137 activity in both beef animals but no detectable tritium activity. The mean of the Cs-137 activity concentration in the two animals was not statistically different than the control animal slaughtered in 1992.
t 77
Table II.E.1 Radionuclide Concentrations in Food Products (pCi/kg)
Collection Date: August 23,1994 l Location Food Type Cs-134 Cs-137 R-6 Large Peppers < 8.5 < 9.3 l R-6 Small Peppers < 6.7 < 7.1 A-27 Corn < 5.5 < 6.3 A-27 Rhubarb < 9.3 < 10 A-27 Squash < 7.7 < 8.6 A-27 Tomatoes < 6.9 4.3(9.2)*
- 1,960 (Due to Counting Statistics.)
78
Table II.E.2(a) Radionuclide Concentrations in Beef Samples Collected on 5/2/94 Radionuclide concentrations in Beef Beef Sample # K-nat Cs-137 H-3 g/kg pCi/kg pCi/L 1 1.5(0.077)* 9.1(8.9) < 380 2 1.3(0.018) 14(3.9) < 380 3 0.21(0.022) 10(4.6) < 380 4 0.21(0.024) 12(4.8) < 380 5 1.0(0.060) 8.2(6.9) < 380 6 0.19(0.021) 12(4.2) < 380 7 0.17(0.021) 15(4.3) ~ ',< 380 8 1.0(0.061) 6.3(5.1) < 380 9 1.1(0.052) 4.1(3.4) -
< 380 10 1.0(0.043) 9.2(6.4) < 380 l
X(1.96o) 0.77(0.96) 10(6.3) < 380 1 1
- - 1.96o (Due to Counting Statistics)
Cow slaughtered on 5/5/94 at Colorado State University meats processing laboratory.
Cow donated by Ben Ilouston. Animal grazed on pasture north of FSV, and had access to Goosequill Ditch.
i 79
Table II.E.2(b) Radionuclide Concentrations in Beef Samples Collected on 12/5/94 Radionuclide concentrations in Beef Beef Sample # K-nat Cs-137 II-3 g/kg pCi/kg pCi/L 1 1.1(0.056)* < 5.4 < 380 2 0.91(0.057) 6.8(6.5) < 380 3 1.1(0.054) < 5.1 < 380 4 1.1(0.046) < 4.4 < 380 5 0.24(0.016) 12(3.4) < 380 6 1.2(0.059) 6.8(6.8) < 380 7 0.94(0.057) 5.7(6.4) < 380 8 1.0(0.054) 7.3(6.1) < 380 9 1.1(0.059) < 5.6 < 380 10 0.23(0.021) 10(4.1) < 380 X(1.96o) 0.89(0.66) 8.1(4.3) < 380
- - 1.W (Due to Counting Statistics)
Note:
Cow slaughtered on 12/6/94 at nearby commercial meat processing plant. Cow donated by Ben Ilouston. Animal grazed on pasture north of FSV, and had access to Goosequill Ditch.
80
i
,, ** \
II.F. Aquatic Pathways j Table II.F.1 shows radionuclide concentrations measured in fish samples collected j l
at F-19, A-25 and R-10 on two dates in 1994. The fish were collected by shocking and 1 netting and the composite sample was homogenized without cleaning and analyzed on a 1 wet weight basis. Detectable Cs-137 and Co-60 activity concentrations were observed I in upstream and effluent fish during 1994 but was barely detectable in downstream fish l during the first half only. The Co-60 activity can only be traced to the decommissioning !
efforts. The Cs-137 activity concentrations were significantly greater than observed l during 1992 and 1993. The Cs-137 activity is also attributed to decommissioning effluent. )
Assuming ICRP-23 consumption of fish the Total Effective Dose Equivalent (TEDE) commitments for both Co-60 and Cs-137 to an adult would be: j Co-60: 5.6 x 10-3 mrem / year l
Cs-137: 2.2 x 10-2 mrem / year l T(,tal: 2.8 x 10 2 mrem / year .
l The above committed dose rate is negligible compared to the appropriate ,
l standards or to the naturally occurring background dose rate of approximately 350 !
l mrem / year in the local environs.
Table II.F.2(a-b) shows the measured concentrations of both Cs-137 and Cs-134 ,
l i
in surface sediment collected at F-1, located at the intersection of the Goosequill and Jay ;
I l
Thomas ditches. There was measurable activity of both Cs-134 and Cs-137 due to the :
1 decommissioning effluent. The concentrations observed in 1994 were significantly greater than observed in previous years but in no case did the Cs-137 concentration 81
1 exceed the NRC guideline of 15,000 pCi/kg (15 pCi/g). The cesium ions are bound ,
nearly irreversibly by the clay mineral matrix in the sediment and not available for food-chain transport.
Table II.F.3 shows the radiocesium concentration in sediment at location R-10, the downstream location. At this site, no Cs-134 was detected and the Cs-137 activity was similar to previous years. Therefore, it can be concluded that Cs-137 due to decommissioning work did not reach this downstream location.
i a
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82
4 Table II.F.1 Radionuclide Concentrations in Fish (pCi/kg)
Collection Date April 18,1994 October 27,1994 Radionuclide Upstream Effluent Downstream Upstream Effluent Downstream ,
F-19 A-25 R-10 F-19 A-25 R-10 Cs-134 < 2.0 < 3.9 < 2.9 < 4.3 < 6.3 < 4.4 Cs-137 17(2.9)* 17(4.8) < 6.1 < 4.9 24(8.4) < 5.0 i
< 3.1 < 2.6 < 5.9 < 5.4 < 5.9
~
Co-58 3.0(3.0)
Mn-54 < 2.1 < 4.4 < 2.8 < 4.6 < 6.4 < 4.7 Zn-65 < 7.3 < 9.7 < 8.9 < 12 < 17 < 13 !
Fe-59 < 5.4 < 5.6 < 4.6 < 7.0 < 20 < 14 5 Co-60 3.2(2.7) 4.8(4.5) < 3.1 < 4.8 15(8.0) < 4.8
' 1.h (Due to Counting Statistics.)
r
4 Table II.F.2a Radiocesium Concentrations in Sediment from Location F-1 Radionuclide Concentration (pCi/kg)
Collection Date: January 14, 1994 Cs-134 39(13)*
Cs-137 34(17)
Collection Date: February 12, 1994 Cs-134 40(43)
Cs-137 42(66)
Collection Date: March 12, 1994 Cs-134 63(48)
Cs-137 350(66)
Collection Date: April 9,1994 Cs-134 40(33)
Cs-137 440(48)
Collection Date: May 14,1994 Cs-134 < 25 Cs-137 190(38)
Collection Date: June 11,1994 Cs-134 12(7.3)
Cs-137 81(84)
Collection Date: July 9,1994 Cs-134 < 22 Cs-137 120(30)
Collection Date: August 12, 1994 Cs-134 < 22 Cs-137 70(32)
- - 1.960 Due to Counting Statistics 84 e
d Table II.F.2b Radiocesium Concentrations in Sediment from Location F-1 Radionuclide Concentration (pCi/kg)
Collection Date: September 10, 1994 Cs-134 29(24)* ,
Cs-137 77(29) j Collection Date: October 8,1994 l l
Cs-134 < 29 i l
Cs-137 100(33) .
Collection Date: November 12, 1994 Cs-134 < 28 Cs-137 , 200(38)
Collection Date: December 10,1994 Cs-134 37(28)
Cs-137 180(35) l
- - 1.96a Due to Counting Statistics j i
85
1 Table II.F.3 Radiocesium Concentrations in Sediment from location R-10 1 I
Radionuclide Concentration (pCi/kg) '
Collection Date: May 9,1994 Cs-134 < 6.0 Cs-137 58(7.4)*
Collection Date: September 10,1994 Cs-134 < 22 Cs-137 < 24
- - 1.96<r Due to Counting Statistics 86 1
II.G. Sample Crosscheck Program To assure both the accuracy and precision of the environmental data obtained from the radiation surveillance program provided for the Fort St. Vrain facility, Colorado State University participates in a number of interlaboratory and intralabt.atory quality assurance programs. The U.S. Environmental Protection Agency (EPA) sponsored laboratory intercomparison studies program is the principal crosscheck. This involves the analysis of a variety of environmental media containing various levels of radionuclides. The media, type of analys'.s and frequency of analysis for the EPA l
program are summarized below.
Medium Analysis (radionuclide) Freauency Water II-3 Semiannually Water Gross # Semiannually Water Co-60, Zn-65, Cs-134, Cs-137 Semiannually Water Gross #, Cs-134, Cs-137 Semiannually Air particulate Cs-137, Gross # Semiannually Milk Cs-137 Annually ,
For each radionuclide analysis of a particular medium, three independent measurements are performed and all results are reported to the EPA. It should be noted that during 1989, the CSU laboratory became certified by the EPA for drinking water analysis.
Table II.G.1 gives the EPA crosscheck data for 1994. The EPA uses the parameter, Estimated Laboratory Precision (ELP), calculated as one standard deviation for one determination. The normalized deviation of our mean from the known is l 1
l calculated as:
87
CSU mean value - EPA known value oW Where: o = standard deviation of the mean of all participating laboratory results n = number of analyses by our laboratory, normally n=3 The control limit is determined by the mean range of all results and three standard deviations of the range. If any result exceeds three standard deviations from the mean (warning level), the result is unacceptable. Whenever our mean value falls outside this limit, the calculations are rechecked and the sample reanalyzed if possible. During 1994 all results except seven were within the warning level. The results exceeding the warning level have the superscript notation n-1,2,3... in Table II.G.I. The explanation for the incorrect result is given in Table II.G.I.
Table II.G.; lists independent results for II-3 in water samples split between the l CSU !aboratory and the laboratory at Fort St. Vrain. The comparison between laboratories in general was acceptable.
Table II.G.3 lists the results of gross beta analyses of the split water samples.
The procedural differences between the laboratories were previously investigated and minimized. It is concluded that the differences can be attributed only to total analytical uncertainty.
Table II.G.4 shows results of an intralaboratory crosscheck program. Replicate samples are independently analyzed. The replicate results are not statistically different and imply that the precision of the methods is acceptable.
During 1994 approximately 20% of all '; oratory calculations that partly involve technician input were recalculated by a differe.1 technician. Only an occasional input 88
or calculation error was detected. This result gives further credence to the laboratory i- results which are not solely computer calculated and listed.
Computer calculations are often recalculated by hand and those done during 1994 l were all verified to be correct.
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Table II.G.1 EPA Cross-Check Data Summary,1994.
Date Radionuclide CSU Value EPA Value 1 E.L.P.
- Normalized Deviation from known*
- WATER, Tritium (pCi/L)
Mar 4 311 3500 4900 490 -5.08 Aug 5 3H 9010 9950 995 -1.63 WATER, Beta (pCi/L)
Jul 22 Beta 6 10 5 -1.39 Oct 28 Beta 25 23 5 0.81 !
WATER, Gamma (pCi/L)
Jun 10 Co-60 44 50 5 -1.96 Zn-65 86 134 13 -6.442 Cs-134 40 40 5 -0.12 Cs-137 54 49 5 1.85 Nov 04 Co-60 55 59 5 -1.39 Zn-65 77 100 10 -4.04 Cs-134 23 24 5 -0.23 !
Cs-137 54 49 5 1.85 ,
I WATER, Performance (pCi/L)
Apr 19 Beta 58 120 18 -5.713 I Cs-134 18 34 5 -5.77' Cs-137 20 29 5 -3.12 Oct 18 Beta 155 142 21 1.10 Cs-134 35 20 5 5.4 35 Cs-137 69 39 5 10.236 MILK (pCi/L) l Sep 30 Cs-137 62 59 5 1.15 l
90
_ . .. - . ._ - - . -_ . . - _ . = _ - - . __
I Table H.G.1 EPA Cross-Check Data Summary,1993. I Date Radionuclide CSU Value EPA Value 1 E.L.P.
- Normalized (
Deviation from l known**
AIR FILTERS (pCi/ Filter) ;
Aug 26 Beta 66 56 10- 1.67 l Cs-137 30 15 5 5.31 7 1
- E.LP. - Expected Laboratory Precision.
" Normalized Deviation - (CSU mean - EPA known)/(cVii);if this value falls between upper & lower warning levels, the accuracy is acceptable. ,
- 1. Analytical Error f
- 2. Under Estimation of Zinc 't 34 Complications with new processing technique i 7. Possible false positive .
k
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Tchle II.G.',
Tritium Crosscheck Analyses on Split Water Samples Determined by Colorado State University and Public Service Company.
l a) 1" and 2"d Quarters l Collection Sample Tritium Concetrations (pCi/L) f Date Location CSU PSC l
Jan 14 A-25 < 390 < 869 f Jan 14 A-21 < 410 ..< 869 Jan 05 E-41 a < 869 i
i Feb 12 A-25 560(460) < 895 Feb 12 A-21 < 390 < 895 l Feb 02 E-41 < 390 < 895 Mar 12 A-25 < 380 < 862 ;
Mar 12 A-21 < 380 1130(1080)* !
Mar 02 E-41 < 390 1150(1090)
Apr 09 A-25 < 380 < 794 :
Apr 09 A-21 < 380 < 853 Apr 06 E-41 < 390 < 883 l l
May 14 A-25 < 380 < 849 ,
May 14 A-21 < 380 < 849 ;
May 11 E-41 < 390 < 849 ;
f Jun 11 A-25 < 390 < 835 [
Jun 11 A-21 < 380 < 835 l Jun 13 E-41 < 390 < 835
- - 1.96o (Due to Counting Statistics) l a - Sample lost prior to analysis 92
Tcbic II.G.2 Tritium Crosscheck Analyses on Split Water Samples Determined by Colorado State University and Public Service Company. r b) yd and 4th gggg73 Collection Sample Tritium Concetrations (pCi/L)
Date Location CSU PSC Jul 09 A-25 < 390 < 868 Jul 09 A-21 < 380 < 868 Jul 06 E-41 < 390 < 868 $
l Aug 12 A-25 < 380 < 918 Aug 12 A-21 < 380 < 918 :
1 Aug 03 E-41 470(460)* < 918 !
Sep 10 A-25 1500(480) < 838 Sep 10 A-21 < 390 < 838 Sep 07 E-41 < 380 2030(1120)
Oct 08 A-25 < 380 1260(1080)
Oct 08 A-21 < 470 < 857 1
Oct 12 E-41 440(460) < 857 Nov 12 A-25 < 380 < 899 Nov 12 A-21 < 390 < 899 Nov 02 E-41 < 380 < 899 l
Dec 10 A-25 < 390 < 819 Dec 10 A-21 < 380 < 819 Dec 07 E-41 < 380 < 819
- - 1,% (Due to Counting Statistics)
I 93 y-
Tchle H.G.3 Gross Beta Crosscheck Analyses on Split Water Samples Determined by Colorado State University and Public Service Company, a) 1" and 2"d Quarters Collection Sample Gross Beta (pCi/L)
Date Location CSU PSC Jan 14 A-25 12(6.0)* 26.3(10.4)
Jan 14 A-21 5.8(5.8) 16.1(9.6)
Jan 05 E-41 11(5.9) 185(19.3)
Feb 12 A-25 14(6.2) < 6.67 Feb 12 A-21 14(6.1) 40.9(11.1)
Feb 02 E-41 12(6.0) < 6.99 Mar 12 A-25 9.6(5.8) < 6.04 Mar 12 A-21 16(6.2) 13.4(8.92)
Mar 02 E-41 12(5.9) 12.1(8.78)
Apr 09 A-25 15(6.2) < 6.87 Apr 09 A-21 16(6.4) < 28.8 Apr M E-41 18(6.4) < 7.32 May 14 A-25 10(6.0) 10.3(7.82)
May 14 A-21 6.8(5.7) < 5.59 May 11 E-41 7.7(5.9) < 5.59 Jun 11 A-25 13(5.9) < 10.1 Jun 11 A-21 6.2(5.7) < 10.1 l Jun 13 E-41 9.7(5.8) < 10.1
- - 1.96cr (Due to Counting Statistics) 94 y
Ttble II.G.3 Gross Beta Crosscheck Analyses on Split Water Samples Determined by Colorado State University and Public Service Company. j 8
L b)3'd and 4 ' Quarters )
Collection Sample Gross Beta (pCi/L)
Date Location CSU PSC ,
Jul 09 A-25 12(6.0)* 15.4(13.6)
Jul 09 A-21 13(6.0) 19(15.5) I Jul 06 E-41 7.3(5.8) < 10.9 l
Aug 12 A-25 11(5.9) 12.4(8.29)
Aug 12 A-21 10(6.0) 21.8(9.54) =
Aug 03 E-41 8.3(5.9) < 5.59 Sep 10 A-25 12(6.0) < 6.82 Sep 10 A-21 7.7(5.8) < 7.35 Sep 07 E-41 14(6.1) 9.72(8.73)
Oct 08 A-25 6.7(5.8) 15.2(7.85)
Oct 08 A-21 15(6.2) 8.91(3.71)
Oct 12 E-41 10(6.0) 10.6(8.08)
Nov 12 A-25 13(6.1) 19.4(S.83)
Nov 12 A-21 9.5(5.9) 12.1(8.23)
Nov 03 E-41 13(6.1) 20(9.11)
Dec 10 A-25 19(6.4) 16.7(8.54)
Dec 10 A-21 11(6.0) 16.3(8.5)
Dec 07 E-41 8.0(5.9) 10.9(7.51)
- - 1.96o (Due to Counting Statistics) 95
Table II.G.4 Intralaboratory Cross-Check Results (pCi/L). (Replicate Analysis of Same Sample)
Ratumuctede Drinking Water l' Quarter 2" Quarter 3d Quarter 4* Quaner A B A B A B A B Col 34 < 2.0 < 2.0 < l .2 < 2.0 <20 <20 < 1.9 < 2.1 Cs 137 3 0(2.9f < 2.5 4.9 (1.7) < 2.5 < 2.5 < 2.4 2.7 (2.8) < 2.5 Zr.05 <46 < 4.7 < 2.7 < 5.5 < 4.7 < 4.7 < 5.4 < 5.4
-1 Nt9 6 5
<18 <18 < l .1 < l.8 < j .8 < l.9 < l .7 < I.8 Co-38 < 2.1 < l .9 1.2 (1.4) < l .9 < 2.0 < l .8 < I .7 < l .9 Ma.54 <20 < 2.0 2.0 (1.4) <20 <20 < 2.0 < 2.0 < 2.0 Zn-65 < 5.4 < 5.6 <36 < 5.6 < 5.3 < 5.4 < 5.2 < 5.5 Ft-59 <58 < 5.9 4.4 (3.7) <46 <47 < 5.8 < 5.6 < 4.7 CW < 2.2 < 2.2 < I .1 < 2.2 < 2.1 < 2.2 < 2.1 < 2.1 h Da-140 < 7.2 < 7.2 < 2.0 < 3.3 < 3.2 8.4(85) < 3. I < 3.3 La.140 < 8_2 < 8.3 < 2.3 < 3.8 <38 9.7(98) < 3.6 < 3.7 Gross Beta 2.0 (2.2) 1.5 (2.2) 3.2 (2.3) 5.5 (2.4) < I .7 2.4(2.3) 2.4 (2.2) 2.5(22)
H-3 < 390 < 410 < 380 < 300 < 380 < 390 < 380 < 390 Radionuciale %Bik I" Quaner 2" Quarter 3* Quarter 4* Quarter A B A B A B A B l
i Cs-134 < 2.0 < 2.2 < l .2 < l .4 1.6 (1.8) < l.3 < 2.0 < 2.6 Cs-137 < 2.4 < 2.6 8.1 (2.1) 6.5 (2.5) 7.4 (2.8) 7.1 (2.4) < 2.4 < 3.2 Ba-140 < 3.2 < 3.4 < l .7 3.3 (3.1) < 2.2 < l .9 < 3.2 < 4.2 12-140 <36 < 3.9 < 2.0 3.8 (3.6) < 2.6 < 2.2 < 3.6 < 4.8 H.3 < 390 < 380 < 380 < 380 < 380 < 380 < 380 < 390 l - e w. (D m cemens sw ms>
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., . . _ . .. , .-- - .- _ _ . _ . _ _ _ _ _ _ _ . . s- _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ . _ _
I l
II.II. Summary and Conclusions Table 1I.11.1 summarizes the radiation and environmental raeioactivity I measurements conducted during 1994 in the environs of the Fort St. Vrain facility, owned and operated by Public Service Company of Colorado. The values for each I
sample type may be compared to pre-operational and operational periods for this facility, as well as to the values from other U.S. environmental monitoring programs (e.g., EPA 520). It must be emphasized, however, that the mean values in Table II.H.1 are only the means of the values greater than MDC, the statistically minimum detectable concentration. The range also is given only for detectable measurements. The mean and range values, therefore, are not the true means or ranges if any of the values in the sample population were less than MDC. The format of Table II.H.1 is a requirement of the NRC.
Inspection of Table II.II.1 reveals that there were no individual measurements that exceeded the Reporting Level (RL) (see Table F-3 in ODCM). The Chernobyl world-wide fallout was still observable as Cs-137 in several sample types. Decommissioning activity was observed in Goosequill sediment samples and occasional fish samples.
For the category of gross beta concentrations in drinking water, the mean for the Gilcrest well was again significantly greater than for the reference supply located in Fort Collins. The reason for this observation is solely due to the fact that the town of Gilcrest still does not completely filter its drinking water supply. The procedure was improved in the last two years but it is still not complete and the activity concentration is still elevated due to naturally occurring radioactive materials from soil and fertilizer contamination. The following conclusions seem valid:
97
- a. None of the individual fission product or activation product radionuclides measured were significantly higher in the Gilcrest drinking water;
- b. Tritium concentrations measured at Gilcrest were not statistically greater than those in Fort Collins; and
- c. The city of Gilcrest does not filter and treat its well water to the same degree as Fort Collins. This has been verified and evidenced by the fact that the gamma-ray spectra of the suspended solids from Gilcrest water samples show only elevated concentrations of the natural radionuclides.
It has been concluded in previous reports that the elevated gross beta concentrations in Gilcrest water are due to elevated concentrations of the naturally occurring U-238, and Th-232 decay products.
For the category of tritium in surface water elevated concentrations were noted at station A-25, the outlet of the Farm pond dur' m g the last quarter of 1994. A-25 is directly in the principal effluent route and elevated concentrations should be expected when release is significant. Downstream surface water concentrations of tritium have occasionally been elevated, but there is significant dilution before ary human use of this water. During 1994 elevated tritium concentrations were not obs rved downstream and the mean values for the first and second half of 1994 were not significantly different.
Cs-137 was also observed in many environmental samples but is due to the Chernobyl world-wide fallout. The only exception was the elevated Cs-13*/ in sediment in the liquid effluent pathway. These values, however, are well below NRC guideline values.
Tritium concentrations from well water site F-16 do appear to be less than in 98
o 1
I 1993 and imply only short term contamination of the aquifer. Typically lateral water i movement in western soils is approximately 30 m/ year. Weekly sampling was initiated in 1991 to observe the movement more closely, but in any case the well at F-16 is not used for drinking water purposes and elevated tritium concentrations have not been observed in any food chain sample. Residents at the F-16 residence purchase bottled water for their primary consumption.
Table 11.11.2 presents an additional summary of mean values for selected sample types. The sample types and radionuclides were chosen on the basis of their importance l
in documenting possible radiation dose to humans. Air and surface water would be the j predominant environmental transport routes and drinking water and milk would be the l
predominant sources of radiation dose if significant radioactivity release from FSV occurred. Table II.H.2 also allows comparison to the four most recent years of operation.
The arithmetic means and standard deviations in Table II.II.2 were calculated for all sample results. It should be repeated that the tabular data presented in the body of this report contain only positive calculated values above the minimum detectable concentration (MDC) levels. Any calculated values less than zero or less than the minimum detectable concentration are lisyd as less than the actual MDC for that sample analysis. The actual result in all cases was used in the calculation for the arithmetic mean values for the periods in Table II.II.2. Therefore, all values, negative as well as l
positive, were included. This procedure is now generally accepted and gives a proper )
estimate of the true mean value. Because of this procedure, however, the values listed in Table 11.11.2 cannot be calculated directly from the tabular values in the report. It 99
must be emphasized that while it is true that no sample can contain less than zero radioactivity, due to the random nature of radioactive decay, it is statistically possible to obtain sample count rates less than background and hence a negative result. It is equally true that many sample types do in fact have zero concentrations of certain radionuclides.
Therefore, to obtain the correct mean value from the distribution of analytical results, all positive results must be averaged with all negative results. If the negative results were omitted, the resulting arithmetic mean would be falsely biased high.
From the values presented in Tables II.H.1 and II.H.2 and the tabular data of the report, the following observations and conclusions may be drawn:
- 1. As in every previous report, it was again apparent that for most sample types the variability observed around the mean values was great. This variability is partly due to counting statistics and methodological variation, but principally due to true environmental variation (often termed sampling error). It must be recognized and accounted for in analyses of any set of environmental data before meaningful conclusions can be drawn;
- 2. Tritium was detected in the effluent pathway only during the last quarter of 1994. The release of tritium was indeed much less than in operational years. Since the tritium is released as tritiated water, the dilution by the i
surrounding hydrosphere is great and consequently the mean values of l i
downstream surface water were not statistically greater than upstream concentrations. No tritium was detected in ground water or any food samples:
100
- 3. The Chernobyl world-wide fallout has totally obscured what fission product debris has remained in the FSV environs from the October 1980 Chinese atmospheric nuclear weapon test. The biosphere will contain the Chernobyl fallout, particularly Cs-137, for an equally long period.
Nuclear weapon test fallout has, since the inception of the project, been noted to be the predominant source term above natural background. The Chernobyl reactor fire debris was superimposed on the we- oons test fallout from 1986 to present. It is the variation in fallout deposition, in addition to the variation in naturally occurring radionuclides, that mandates the large numbar of environmental samples to detect any possible radioactivity due to fa:ility effluents. A simple comparison of pre-operational and operational values is of little value, for most sample types, because the fallout deposition was considerably greater during the pre-operational period due to world-wide fallout;
- 4. The prompt and sensitive detection of the Chinese weapon test fallout and the Chernobyl fallout in the past assures that the environmental monitoring program is of adequate scope and sensitivity to detect any accidental releases from the FSV decommissioning; and
- 5. Release of decommissioning radioactive waste was evident in the Goosequill sediment. Since this is primarily Cs-137 in sediment, its transfer to plant and animal food chains will be minimal.
It can be concluded from the data collected by the environmental monitoring program that the radiation dose commitments calculated for the closest human inhabitants 101
f ',
j ..
a t,
or other parts of the nearby ecosystems due to current facility effluents are negligible.
Natural background radiation and the dose commitment from atmospheric fallout are the only known significant sources of radiation dose to the residents of the area.
During the current decommissioning phase of the facility it is concluded that this Radiological Environmental Monitoring Program is more than adequate to detect and quantify any possible routine or accidental release of radioactivity.
j s
1 102
Table 11.11.1 Radiological Environmental Monitoring Program Annual Summary Fort St. Vrain Station, Plattesille, Colorado Medium or Type and Total Facihty locations Adjacent Locations with flighest Annual Mean Reference Number of Pathway Samples Number of Mean (f)' Range Locations Mean Name Mean Locations Mean Nonroutine (Unit of Analyses (f)' Range Distance & Range (f)' Range Reported measurement) Performed Direction Measurements Direct Radiation TLD(164) 0.42(72/72) 0.41(72/72) A-8 CO 66 0.50(4/4) 0.39(20!20) 0 (mR/ day) 0.27-0.59 (0.27-0.59) 4.7 km Sec 8 (0.41-0.56) (0.294).60)
Air, Particulates Gross Beta (362) 28.4(208/208) -
F-16 3-Bar Ranch 29(52/52) 24(155/156) 0 (fCi/m') (11-64) 1.2 km Sec I (14-64) (10-39) .
1 Gamma Spectrometry F-7 CR 21 & 34 0 !
Cs-134(28) 1.2(2/16) -
2.l(1/4) -
(0.39-2.1) 1.5 km Sec 7 Cs-137(28) 0.89(4/16) -
R-11 Johnstown 1.3(3/4) 1.0(6/12) 0 (0.51-1.2) Services Bldg (0.62-1.9) (0.46-1.9) 8 w
10.5 km Air, 11-3(364) 515(6/208) -
R-il Johnstown 700(3/52) 630(4/150) 0 Atmospheric (450-590) Services Bldg (520-900) (430-900)
Water Vapor 10.5 km (pCi/m')
Drinking Water Gross Beta (52) 2.6(26/26) -
R-6 Gilcrest City 2.6(26/26) 1.2(26/26) 0 (pCi/L) (l.2-5.1) Water (1.2-5.1) (0.65-1.6) 9.3 km 11-3(52) 410(1/26) -
R-6 Gilcrest City 410(1/26) -
0 Water 9.3 km Gamma Spectrometry Cs-134(52) 1.7(1/26) -
R-6 Gilcrest City 1.7(1/26) -
0
- Water 9.3 km Cs-137(52) 4.2(12/26) -
R-6 Gilcrest City 4.2(12/26) 3.2(18/26) 0 (2.0-6.1) Water (2.0-6.1) (2.04.0) <
9.3 km f
i Table II.H.1 Radiological Environmental Monitoring Prop m Annual Summary Fort St. Vrain Station, Platteville, Colorado i
hiedium or Type and Total Facility Locations Adjacent Iecations with liighest Annual Mean Reference Number of Pathway Samples Number of Mean (f)' Range locations Mean Name Mean Locations Mean Nonroutine (Unit of Analyses (f)' Range Distance & Range (f)' Range Reported measurement) Performed Direction Measurements Drinking Water Zr-95(52) - - - - -
0 (pCi/L)
, Nb-95(52) 1.8(3/26) -
R-6 Gilcrest City 1.8(3/26) 1.8(1/26) 0 (1.7-1.9) Water (1.7-1.9) 9.3 km Co-58(52) 1.5(2/26) -
R-3 Fort Collms 1.8(1/26) 2.3(1/26) 0 (1.2-1.8) City Water 45.1 km Mn-54(52) 2.l(6/26) -
R-3 Fort Collins 2.3(6/26) 2.3(6/26) 0 (0.85-4.2) City Water (1.6-3.2) (1.6-3.2)
_ 45.1 km O Zn-65(52) - - - - -
0 Fe-59(52) 4.6(5/26) -
R-6 Gilcrest City 4.6(5/26) 4.2(1/26) 0 (3.0-6.9) Water (3.04.9) 9.3 km Co-60(52) - -
R-3 Fort Collins 2.2(4/26', 2.2(4/26) O City Water (1.1-3.4) (1.1-3.4) ,
45.1 km Ba-140(52) 8.4(4/26) -
R-6 Gilcrest City 8.4(4/26) 7.5(3/26) 0 (3.8-13) Water (3.8-13) (3.9-10) 9.3 km La-140(52) 9.7(4/26) -
R-6 Gilcrest City 8.4(4/26) 8.5(3/26) 0 (4.4-15) Water (4.4-15) (4.5-11) 9.3 km ,
Surface Water 11-3(60) < 390 1155(2/24) A-25 Farm Pond i155(2/24) < 380 0 (pCi/L) G10-1600) 2.2 km Sec 1 G10-1600)
____._.-_.m__._ . _ . _ . . _ _ _ _ _ . _ _ . . - _ . _ . - _ . _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ - _ _ _ . , _ _ _ - _ - . . . . . ,
- _e--- . ~v - . + - - - ~ .
Table 11.11.1 Radiological Environmental Monitoring Program Annual Summary Fort St. Vrain Station, Platieville, Colorado Medium or Type and Total Facility locations Adjacent Iecations with Ilighest Annual Mean Reference Number of Pathway Samples Number of Mean (f)' Range locations Mean Name Mean locations Mean Nonroutine (Unit of Analyses (f)' Range Distance & Range (f)' Range Reported measurement) Performed Direction Measurements Gamma Spectrometry Surface Water Cs-134(60) 2.l(2/24) 2.l(1/24) F-20 St. Vrain 2.7(1/20) < l .4 0 (pCi/L) (1.4-2.7) Creek 1.5 km Sec 16 Cs-137(60) 4.5(10/24) 4.3(12/24) F-20 St. Vrain 5.3(4/12) 4.2(10!!2) 0 (2.3-7.3) (2.0-6.9) Creek (3.5-7.3) (1.8-5.5) 1.5 km Sec 16 Zr-95(60) -
2.3(1/24) A-25 Farm Pond 2.3(1/24) -
0 2.2 km Sec 1 Nb-95(60) 1.8(2/24) 1.5(1/24) R-10 S. Platte @ 2.4(4/12) 2.4(4/12) 0
~
o (1.8-1.8) CO 60 (1.3-3.5)
" 10.1 km Co-58(60) 2.6(2/24) 2.3(3/24) A-21 St. Vrain 2.9(1/17) < l .3 0 (2.0-3.2) (1.5-2.9) Creek 2.4 km Sec 11 Mn-54(60) 2.6(1/24) 1.6(5/24) F-19 S. Platte 2.6(1/12) 2.0(2/12) 0 (0.81-2.4) 1.2 km Sec 4 (1.4-2.6)
Zn-65(60) - - - - -
0 Fe-59(60) 5.3(1/24) 4.6(2/24) F-19 S. Platte 5.3(1/12) 3.3(2/12) 0 (4.3-4.9) 1.2 km Sec 4 Co-60(60) 1.3(1/24) -
F-19 S. Platte 1.3(1/12) -
0 1.2 km Sec 4 Ba-140(60) 9.0(2/24) 21(1/24) A-21 St. Vrain 21(1/12) 2.8(1/12) 0 (8.0-10) Creek 2.4 km Sec 11 La-140(60) 11(2/24) 24(1/12) A-21 St. Vrain 24(1/12) 3.3(1/12) 0 (9.2-12) Creek 2.4 km Sec 11
Table 11.11.1 Radiological Environmental Monitoring Program Annual Summary Fort St. Vrain Station, Platteville, Colorado Medium or Type and Total Facihty locations Adjacent L.ocations with liighest Annual Mean Reference Number of Pathway Samples Number of Mean (O' Range locations Mean Name Mean Locations Mean Nonroutine (Umt of Analyses (O' Range Distance & Range (O' Range Reported measurement) Performed Direction Measurements Ground Water 11-3(8) < 390 - - -
< 3% 0 (pCi/L)
Gamma Spectrometry Ground Water Cs-134(8) - - - - -
0 (pCi/L)
Cs-137(8) 4.2(2/4) -
R-5 Milliken 4.5(3/4) 4.5(3/4) 0 (3.5-4.9) 9.5 km (3.3-3.6) (3.6-6.3)
Zr-95(8) - - - - -
0 Nb-95(8) - - - - -
0
@ Co-58(8) - - - - -
0 Mn-54(8) - -
R-5 Milliken 2.9(1/4) 2.9(1/4) 0 9.5 km Zn45(8) - - - - -
0 Fe-59(8) - -
R-5 Milliken 8.8(1/4) 8.8(1/4) 0 9.5 km Co-60(8) - -
R-5 Milliken 2.5(2/4) 2.5(2/4) 0 9.5 km Ba-140(8) - -
R-5 Milliken 6.2(1/4) 6.2(1/4) 0 9.5 km Sediment (pCi/kg, dry)
Gamma Spectrometry Cs-134 Cs-137
.q Table II.II.1 Radiological Environmental Monitoring Pavgri-ii Annual Summary Fort St. Vrain Station, Platteville, Colorado Medium or Type and Total Facility Locations Adjacent Locatiocs with flighest Annual Mean Refeience Number of Pathway Samples Number of Mean (O' Range Locations Mean Name Mean Locations Mean Nontoutine (Unit of Analyses (f)' Range Distance & Range (f)' Range Reported measurement) Performed Direction Measurements Milk (pCi/L) 11-3(102) -
760(2/85) R-8 Borba Dairy 550(1/17) 550(1/17) 0 (420-1100) 23 km Gamma Spectrometry Milk (pCi/L) Cs-134(102) -
2.8(5/85) A-6 IIenrikson 3.6(2/17) -
0 (1.6-4.9) Dairy (2.3-4.9) 7.1 km Sec 6 Cs-137(102) -
5.6(45/85) A-6 IIenrikson 6.2(7/17) 4.3(10/17) 0 (2.9-8.5) Dairy (2.9-8.1) (2.5-6.7) 7.1 km Sec 6 Ba-140 -
7.0(10/85) A-26 Docheff 9.0(2/17) -
0
~
o (3.3-9.6) Dairy (8.5-9.6)
" 7.8 km Sec 11 La-140 -
7.4(10/85) A-26 Docheff 10(2/17) - 0 (3.8-11) Dairy (9.8-11) 7.8 km Sec 11 Gamma Spectrometry Food Products Cs-134 - - - - -
0 (pCL%g, wet)
Cs-137 -
4.3(1/4) A-27 WCR 36 4.3(1/4) -
0 4.3 km Sec 4
- 1. Mean and Range based upon detectable measurements only..
Fraction (f) of detectable measurements at specified locations is mdicated in parentheses.
. _ _ _ ._. . . _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ . .-- _ _ _ _ _ _ . - . _ _ _ _ _ _ _ _ . . - _ _ - _ - _ ~ _ - . _ . - _ _ _
Table II.H.2 Summary Table of Arithmetic Means and Standard Deviations for Selected Sample Types 1990 1991 1992 1993 1994 X 1.96o X 1.96o X 1.96o X 1.960 X 1.96o 11-3 Atmospheric Water Vapor (DCi/L)
Facility < 260 290 < 9.4 400 980 830 430 130 520 90 Reference < 300 290 < 80 400 780 530 420 50 630 350 Gross Beta Air (fCi/m')
Facility 23 12 29 31 25 15 24 14 28 9.2 Reference 23 12 25 23 25 12 22 14 24 5.3 I-131 Facility 1.5 3 1.6 13 25 9.0 -' - - -
Reference 1.4 9 0.52 14 23 6.9 - - - -
Cs-137 Facility 0.55 0.92 0.12 0.69 1.0 0.22 1.6 2.9 0.89 0.61 Reference 0.22 0.66 0.98 1.3 1.1 0.40 1.3 2.3 0.98 0.95 II-3 Drinkine Water (DCi/L)
Gilcrest < 240 320 30 410 550 90 < 430 50 410 680 No longer analyze for I-131.
Table II.H.2 Summary Table of Arithmetic Means and Standard Deviations for Selected Sample Types 1990 1991 1992 1993 1994 X 1.96o X 1.96o X 1.96o X 1.96o X 1.96o Ft. Collins < 220 290 < 50 350 500 50 < 420 40 < 380 10 Gross Beta Drinkine Water (DCi/L)
Gilcrest 4.5 1.8 5.8 2.4 4.5 2.3 3.2 2.9 2.6 1.7 Ft. Collins 0.86 0.39 0.95 0.35 0.90 0.31 0.92 0.72 1.2 0.48 I-131 Gilcrest 0.017 0.19 < 0.0028 0.16 0.29 0.14 -2 - - -
Ft. Collins 0.046 0.24 < 0.022 0.20 0.35 0.15 - - - -
5
- Cs-137 Gilcrest 1.3 1.4 2.2 1.6 3.4 1.1 3.8 3.1 4.2 2.3 Ft. Collins 2.4 1.8 1.7 1.2 3.4 0.88 3.4 2.3 3.7 2.4 II-3 Surface Water (DCi/L)
Effluent 300 620 1500 2500 770 590 < 420 20 1500 640 Downstream < 370 400 6.2 430 990 860 < 420 50 390 550 Upstream < 420 350 20 420 640 0 < 450 200 570 770 Cs-137 Effluent 1.4 1.9 1.7 2.0 3.6 1.4 3.6 2.8 4.3 2.3 2
No longer analyze for I-131
_ , - - - - . - . _ ~ _ _- - - _ _ _ _ _ _ _ _ _ _ _ ___ _ ____ _ _ -
i Table II.H.2 Summary Table of Arithmetic Means and Standard Deviations for Selected Sample Types i I
1990 1991 1992 1993 1994 5 1.96o X 1. % 5 1.96o X 1.96o 5 1. W Downstream 2.1 1.9 2.3 1.7 3.5 1.2 3.8 2.2 4.5 2.5 i Upstream 2.2 1.9 2.0 1.9 3.8 0.89 3.6 2.3 4.1 2.8 I H-3 Milk (oCi/L)
Adjacent < 280 330 < 130 360 760 590 <430 140 760 660 Reference < 290 340 < 110 400 590 90 < 420 20 550 450 1-131 Adjacent 0.53 2.0 0.070 0.39 < 0.32 0.13 -i - - -
o Reference 0.0060 0.33 < 0.0028 0.24 < 0.37 0.13 - - - -
Cs-137 Adjacent 1.5 2.0 1.9 1.8 5.0 1.5 4.9 4.5 5.6 3.4 I I
Reference 16 2.3 2.4 1.9 4.6 0.68 5.4 3.6 4.3 2.9 l l
I 1
No longer analyze for I-131
Table II.J.la Tritium Concentrations in F-16 Well Water Date Collected Concentration (pCi/L) 1/7 < 390 1/14 < 390 1/22 < 390 1/29 < 390 2/5 490(350)*
2/12 < 390 2/19 < 390 2/26 < 390 3/5 < 410 __
3/12 < 380 3/19 < 380 d,
~
3/26 < 380 4/2 < 380 4/9 < 380 4/16 < 380 4/23 < 380 4/30 < 380 5/7 < 380 5/14 < 380 5/21 < 390 5/28 < 430 6/4 < 390 6/11 < 390 6/18 < 380 6/25 < 380 7/2 < 370
- 1.h . Due to counting statistics
} 111 L
I Table II.J.lb Tritium Concentrations in F-16 Well Water (continued)
Date Collected Concentration (pCi/L) 7/9 < 390 7/16 < 380 7/23 < 380 i 7/30 < 380 8/5 < 380 8/12 < 380 8/20 < 380 8/27 < 380 ,
I 9/3 < 370
~
9/10 < 380 9/17 < 380 9/24 < 380
, 10/1 < 380 10/8 < 380 10/15 < 380 10/22 < 380 10/29 < 3PO 11/5 < 400 11/12 < 380 11/19 < 380 11/26 < 390 12/3 < 380 12/10 < 380 12/17 < 390 12/24 < 380 12/31 < 420 112
e III. Radiological Environmental Monitoring Program
]
I A. Sample Collection and Analysis Schedule
.l Table F-1 in the Offsite Dose Calculation Manual (ODCM) outlines the sampling design, the collection frequency and the type of analysis for all environmental samples. :
It should be repeated that this schedule was adopted January 1,1984, and while different I
in certain aspects from the previous schedule, has as its intent the same objective. That objective is to document the radiation and radioactivity levels in the critical pathways of possible dose to humans. Such data is necessary to demonstrate Fort St. Vrain radioactive effluents produce environmental concentrations that are within appropriate environmental protection limits and at the same time are as low as reasonably achievable. .
During 1994, there were no changes in the sampling program. Iodine-131 analysis was -
dropped at the beginning of 1993 for milk and air samples. The operational phase of the i facility ended permanently in August of 1989 and due to the short half-life ofI-131 (8.05 days), there is no longer any inventory of I-131 present.
Table III.A.2 lists the LLD concentration values for each sample type and radionuclide measured in this report. These LLD values are the actual values pertinent to the sample sizes, counting yields, and counting times used in the project. Typical decay periods were used in the calculations. It should be noted that the LLD values are in all cases equal to or less than those required by the ODCM.
Table F-3 of the ODCM lists the USNRC reporting level for each sample type ;
and radionuclide. No results exceeded the reporting level in 1994.
113
o, o Table F-4 of the ODCM gives the description of each sampling location by number, sector and distance from the reactor. Each of these sampling locations (except certain reference locations) can be identified on scale maps (Figures III.B.1 and III.B.2).
Topographical maps showing greater detail, as well as photographs of principal sampling sites are on file in the CSU laboratory.
During August 1994 the land-use census was again conducted to determine the locations of the nearest residence, the nearest milk animal, and the nearest garden producing broad leaf vegetation in each of the 16 meteorological sectors around the reactor. These locations are shown in Table III.C.1. Figure III.C.1 shows these locations in each sector. At the time of the 1994 census it was verified that the closest permanent residence in Sector 16 was the critical receptor with regards to mean annual l
dose commitment and is at the residence at F-16.
A few residents in the sampling sectors up to a distance of 8 km from the plant have cows or goats that could be used for personal milk consumption. However, from direct discussion with these persons, this is not a com-lon practice and all cow milk produced is transported to commercial processors. The milk produced locally is diluted by a large milk shed, processed and distributed over a large area for consumption.
Elevated radionuclide concentrations in milk samples due to Fort St. Vrain station effluents have never been detected during either the operational or decommissioning 1 phases.
114
l TABLE III.A.1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS LOWER LIMIT OF DETECTION (LLD)
Analysis Water Airborne Fish Milk Food Products Sediment (pCi/f) Particulate (pClikg, wet) (pCi/f) (pCi/kg, wet) (pCi/kg dry) or Gas (fCi/m')
Gross Beta 4 5 N/A N/A N/A N/A 11-3 2000 N/A N/A N/A N/A N/A Cs-134 15 9 130 15 60 150 Cs-137 18 8 150 18 80 180 3
Mn-54 15 N/A 130 N/A N/A N/A Co-60 15 N/A 130 N/A N/A N/A Zn-65 30 N/A 260 N/A N/A N/A NOTE: This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
l
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Table III.C.11994 Land Use Census
- i Sector Nearest Residence Nearest Garden Nearest Milk Animal 1 17578 CR 19% 9102 CR 44 **
' 2 18311 CR 23 18999 CR 23 11258 CR 40 11100 CR 38 11100 CR 38 **
3 4 11247 CR 36 11247 CR 36 11777 CR 36 ,
5 16543 CR 23 16134 CR 23 16134 CR 23 6 11056 CR 32% 11056 CR 32% 11585 CR 32 7 9999 CR 34 *** ** I 8 15883 CR 21 15225 CR 21 15225 CR 21 9 9379 CR 34 9379 CR 34 9033 CR 26 10 9061 CR 34 15449 CR 19 7388 CO 66 11 8745 CR 34 6769 CR 32 4513 CR 32 12 Aristocrat Ranch 16202 CR 15 4665 CR 34 17038 CR 17 17038 CR 17 **
13 17666 CR 17 **
14 8896 CR 19 18100 CR 19 18100 CR 19 **
15 16 17926 CR 19% 17296 CR 19% **
- Census Date: August 19,1994
- No milk animals
- No garden found 3 118 l l
Figure III.C.1 Land Use Census, 1994.
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