ML20084U745
| ML20084U745 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 12/31/1990 |
| From: | Jerrica Johnson COLORADO STATE UNIV., FORT COLLINS, CO |
| To: | |
| Shared Package | |
| ML20084U740 | List: |
| References | |
| NUDOCS 9104220273 | |
| Download: ML20084U745 (137) | |
Text
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' FORT ST. VRAIN s
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l _\ N - PROGRAM l SUMM ARY RE3 ORT h 08e eo
!! 1990 R5 -88 FF e & COLORADO STATE UNIVERSITY
- FORT COLLINS, COLORADO 80523 1
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RADIOLOGICAL ENVIRONMENTAL MONITORING PPOGRAE jb l 6 } k-: ' z i,Q 5'"'
-#,q' ., A '.c.r the Fort St. Vrain Nuclear Generating Station
.- Operated by the Public Service Co. of Colorado i
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"9 Summary Report for the Period
> January 1. 1990 - December 31. 1990
/ ^ I Prepared by: !
Date f(me) E. JohnsoQ Professor Colorado State University Reviewed by: _ melh \ , \Mmm 4. / - 9 / Radiochemistrv "'tpekvisor Date Approved + UA/Aldc .Mll - hk9b l,, NuiilearTrainippandSupportManager Date f "' 9 3 ,
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~ Acknowledaements-Many persons have_ contributed to this project during 1990, and it is.important to. acknowledge their effort. We also wish to thank the' citizens:from whose_ farms, homes, and ranches we collect the environmental samples. 'Wi'chout their cooperation the project would
-not:be_possible.
We:also wisV ta acknowledge' and thank the Colorado Division of Wildlife, Fort Collins regional of fice for- assisting with the fish collection. Without their cooperation, equipment and expertise the
.._ collection 1would not be possible.
In particular.I wish to. acknowledge the efforts of Sharon J. L Clow. - She was the laboratory coordinator-during:the entire period- I of.the:present_ technical specifications and contributed greatly to-the, operation f and success of the project. She is currently l. L,- employed at_ the'. Department of Energy, Albuquerque operations c ..
-office.-
'r
- The persons working _directly on the project have been
- .j n
IL Faye Bruno- . Chief Laboratory Technician ~ ' [' Thomas Miller Student Employee SteveniZiliak Student: Employee
' Char)es Sampier -Chief Electronic Technician V .
} Paul J. Valentinelli' Graduate Student Employee iChristopher Roelle Student Employee L (g g 7 446(HM C James ohnson Profe sorEand Project Director I? .
~
.a . ; 2.
TABLE OF CONTENTS Page No. Acknowledgments 11
- I '. a t o f Table s iv List of Figures vi
- 1. INTRODUCTION 1 II. SURVEII. LANCE DATA FOR 1990 AND INTERPRETATION OF RESULTS A. External Camma Exposure Rates 6 B. Air Sampling Data 10 C. Water Sampling Data 35 D. Milk Data 68 E. Food Products 79 l F. Aquatic Pathways -81 G. Sample Cross-check Data 84 i
H '. Summary and Conclusions 92 III. ENVIRONMENTAL RADIATION SURVEILLANCE PROGRAM AND SCHEDULE 111 l -- I l-l l iii
LIST OF TABLSS Page No. II.A.1 Gamma Exposure Rates. 8 II . B ,l' Concentrations of Long lived Gross Beta Activity in Airborne Particles,
- a. First Quarter, 12
- b. Second Quarter, 13
- c. Third Quarter, 14
- d. Fourth Quarter, 15 II.B.2 Tritium Concentrations in Atmospheric Water Vapor, ,
l l l a. First Quarter, 19 l
- b. Second Quarter, 20 l
/ c. Third Quarter, 21 l l l
- d. Fourth Quarter, 22 l II.B.3 Tritium Concentrations in Air,
- a. First Quarter,- 23
- b. Second Quarter, 24
- c. Third Quarter, 25
- d. Fourth Quarter, .26 l
L II.B.4 Tritium Released in Reactor Effluents. 27 II.B.5 I 131 Concentrations in-Air. g a. First Quarter, 30
- b. Second Quarter, 31
- c. Third Quarter, 32 l d, Fourth Quarter, 33 II.B.6 Radiocesium Concentrations in Ambient Air. 34 L II.C.1 Cross Beta Concentratious in Bi-weekly Composites
!: of Drinking Water. 37 1' l l I L. l -iv i
LIST OF TABLES (Continued) Page No. II.C.2 Tritium Concentrations in Bi weekly Composites of Drinking Water. 38 II.C.3 Radionuclide Concentrations in Bi weekly Composites of Drinking Water. 39 II.C.4 Tritium concentrations in Surface Water. 50 II.C.5 Radionuclide Concentrations in Surface and Effluent Water. 51 II.C.6 Radionuclide Concentrations in Ground Water, 64 II.C.7 Tritium Concentrations in Ground 'later. 65 II.C.8 Maximum Permissible Concentrations in Water, 67 II.D.1 Radionuclide Concentrations in Milk. 71 II.D.2 Tritium Concentrations in Milk. 77 II.E.1 Radionuclide Concentrations in Food Products. 80 II.F.1 Radionuclide Concentrations in Fish. 82 II.F.2 Radionuclide Concentrations in Sediment. 83 II.G 1 EPA Cross-check Data. 87 II .C . 2 Tritium Concentrations in Cross check Data, CSU PSC. 89 II.G.3 . Cross. Beta Concentrations in Water Cross check Data, CSU PSC. 90 II.G 4 Intralaboratory Cross-check Results. 91 II.H.1 Data Summary. 99 II.H.2 Arithmetic inans of Selected Sample Types. 108 III.A.1 Radiological Environmental Monitoring Program. 114 III.A.2 Detection Capabilities for Environmental Sample Analysis, LLD. 116 III.A.3 Reporting Levels, 117 III.B.1 Sampling Locations for Environmental Samples. 118 III.C.1 Land-use Census , 1990. 129 ( l l V
LIST OF FIGURES Page No. Figure II.A.1 Gamma Exposure Rates, 1972 1990 9 Figure II.B.1 Gross Beta Concentrations in Air 16 F1 5 ure II.C.1 Tritium Concentrations at Site F 16, 1984-1990 66 Figure III.B.1 Close-in Sampling Locations 127 Figure III.B.2. ?.djacent and Reference Sampling Locations 128 Figure III.C.1 Land Use Census, 1990 130 l I l' l I L 1-vi
I. Introduction to Radiological Environmental Monitoring Data for the Period January 1, 1990 - December 31, 1990. During 1990 the Fort St. Vrain Nuclear Generating Station i did not operate and.is presently in a defueling phase.
'1he operational phase of' the reactor ended on July 18, 1989. ,
'A complete and detailed listing of radioactivity released by all effluent routes may be found in the Public Service Company of Colorado Semi-annual Ef flues t Release. Reports for
.1990 to the U.S. Nuclear Regulatory Commission. When poss'ible
'in this report, any ' 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.H. Table III.A.2 lists the LLD ~ values achievable by the counting systems used during 1990 on projech samples. -These - l- -
- l. values;are given for typical sample sizes, counting times and --
decay times. -The LLD is, therefore, an a oriori parameter to
-ind :: ate the capability of the . detection system used. - The LLD
~
L -. values in Table III. A.2 m e calculated as suggested in NUREG- ) y 0472.
-Throughout-the report, however, when a sample result is listed' as less - than .a apecified value, that value is the:
calculated MDC (minimum detectable concentration). This approach is analcgous to that of Currie (NUREG/CR-4007): the 1
MDC is the same as S,, the critical signal, and the LLD is equal to S o , the detectable signal. The MDC value applies to the actual sample size, counting time and decay time applicable to that individual sample. It is calculated as: MDC = 2. 3 3 o n /E Y V E* Where: on = Standard deviation of background count rate E = Counting efficiency, c s pCl'3 Y = Chemical yield V = Sample volume (or mass) A = 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 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 the MDC is dependent upon variables such as the background count time and j sample size, the value will be different 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 type. It has been well-documented that environmental radioactivity values exhibit great inherent variability. This is partly du'. to 2
l sampling and analytical variability, but most importantly due to true environmental or biological variability. As a result, the overall variability of the surveillance data is quite largo, and it is necessary to use mean values from a rather large sample population size to make any conclusions about the absolute radioactivity concentrations in any environmental pathway. The arithmetic mean for each cample set is listed in Table II.H.2. All measured values, both positive and negative, are used in the calculatior.s 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 dif ferent, the confidence for the t'.atement is at the 95% ievel (a = 0.05). In this report we have footnoted appropriate tables with the maximum permissible concentration applicable to each radionuclide. We have chosen to list the maximum permissible concentrations as found in Appendix B Table II of 10CFR20. This is the concentration in water or air of each radionuclide which if ingested or inhaled continuously would singularly produce the maximum permissible radiation dose rate to a specified individual member of the general public. That value is 500 mrem / year, but must include the dose from all possible sources, and, therefore, cannot be solely due to reactor i 3
1 effluent. As stated in 10CFR20 these are the maximum concentrations above natural background that a licensee may release to an unrcstricted area. It is assumed that no direct ingestion or inhalation of effluents can occur at the restricted area boundary and that dilution and dispersion decreases the concentration before it reaches nearby residents. This is certainly the case for the Fort St. Vrain environs. There is no specifled maximum permissible dose rate or dose commitment for residents near the Fort St. Vrain reactor from the reactor effluents. Such limits for water cooled reactors are found in 10CFR50 Appendix I. Theso are judged as "As Low as Reasonably Achievable" dose rates from such reactor types and, although not directly applicable to the Fort St. Vrain gas cooled reactor, can be used for comparison purposes. A limit that does apply is the independent maximum
-permissible dose commitment rate set by the E.P.A. (40CFR190) for any specified membcr of the general public from any part of the nuclear fuel cycle. This value is 25 mrsm/ year, the dose rate to the whole body from all contributing radionuclides excluding background and medical radiation dose rate.
Dose commitments are calcule*ed for hypothetical individuals for any mean cencentrations noted in unrestricted areas that are significantly above control mean values. 4
l
.The following is the footnote system used in this report.
- a. Sample lost prior to analysis,
- b. Sample missing at site.
- c. Instrument malfunction,
- d. Eample 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. t 5
II. Surveillance Data for January Through December 1990 and Interpretation of Results 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 III.B.1). Two TLD chips per package are 1 installed at each site and the mean value is reported for that i site. The mean calculated total exposure is then divided by l the number of days that elapsed between pre-exposure and post-exposure annealing to obtain 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. The TLD data indicate that the arithmetic mean measured i l exposure rate in the facility area for all of 1990 was 0.40 I mR/ day. The mean exposure rate was 0.39 mR/ day for the 1 adjacent area-and 0.39 mR/ day for the reference area. These mean values were not'significantly different from each other. The exposure rate measured at all sites is due to a combination of exposure from cosmic rays, from natural gamma-ray emitters in the carth's crust and from ground surface deposition of fission products due to previous world-wide l fallout. ThL variation in measured values is due to true l variation of_the above sources plus the variation due to the 6 l
l l measurement method. The purpose of having two TLD rings i arcund the reactor is not to measure gamma-rays generated from the reactor facility itself, but to document the presence or absence of gamma-ray emitters deposited upon the ground from the reactor ef fluent. Since the inception of power production by the reactor, there has been no detectable increase in the external exposure rate due to reactor releases. Fallout. deposition, both from the Chinese nuclear weapon tests and from the Chernobyl accident, was detected in the past. The TLD system is calibrated by exposing chips to a-scattered gamma-ray flux produced in a cavity surrounded by uranium mill tailings. This produces a gamma-ray spectrum nearly identical to that from natural background meaLared in the reactor environs. The quality control program includes calibration before readout of each quarterly batch of TLD devices. For comparinon purposes, the EPA in EPA 520/5-89-034 Report #58 lists 0.37 i 0.27 mR/ day for the background external exposure rate in Denvar during the period April to June 1990. This is excellent agreement with the results fra this program. Figure II.A.1 shows the measured mean exposure rate in L the Facility Area since the inception of the program. The L i - steady decrease in exposure rate over the period is due to the decay and weathering of fission product deposition from previous atmospheric weapon tests. 7
Table II.A.1 Gammma Exposure Rates. lmR/ day ) 1990 y_. . _ . - . . . . .- -. . . . Facility Area 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter F-1 .39 .44 .34 .43 i F-2 j .39 42 .32 .43 ! F-3 .45 .35 .31 .41 l F-4 .45 .37 .44 .41 F-5 l 40 .40 .31 .47 t 1 F-6 .40 .35 b .41 F-7 .42 .45 .33 .47 F-8 .44 .41 b .47 F-9 .42 .37 .35 .45 i F-10 .43 .40 .36 .41 ' I F-11 .47 .46 .48 45 i F-12 .39 .42 .37 .41 < F-13 .40 .38 .32 .39 l F-14 .42 .41 .28 .41 F-15 .40 .42 .34 .40 F-16 .42 .43 .32 .37 i F-17 .40 .36 .35 .42' l F-18 .45 .38 .42 .47 ) i (1.96o) .42(0.048) .40(0.066) .35(0.103) ,43(0.059) j Adjacent Area A-1 .46- .38 .37 .46 i A-2 .45 .41 .42 b . A-3 .C .40 .38 .46 i A-4 .37 .36 .38 .43 A-5 i b .37 b .36 A-6 .36 .35 .37 .37 A-7 .40 .38 .37 .40 A .42 .42 .3u .a3 ! A-9 .42 .41 .38 .37 A-10 -
.48 .43 .38 .45 A-11 .39 .35 .38 .39 A-12 .39 .34- .40 .43 A-13 .34 .34 .35 . 34
.A-14 .36 .39 .35 .39 A .36 .36 .34 .39 A-16 .44 .38 -. 3 5 .40 A-17 . 44 - .40 .38 .42 +
A-20 .43 .44 .38 .40 i (1.960) .41(0.079) .38(0.060) .37(0.040) .41(0.069) Reference Area l
-R-2 .41 b b 42 R-3 .46 .39 .40 .37 R-4 .37 b .32 .40 R-5 .45 .41 - . 34 .43 )
R-7 .39 b .35 .39 l i-(1.960) 42(0.075) ._40(0.028) .35(0.067) .40(0.047) 1
'b - sample missing at site 8
Figure II.A.1 Gamma Excosure 9ates (mR/ day) (1972 - 1990) 0.75 0.7 -- 0.65 - s 0.0 g
= .
=
s 0.55 - o5 e b
} 7)\;\?.? ,-
[' /= ,. '" ; Lo.a5 e .l\l\e,\,I.j-
% \.
=
y\,.,,i\l.? , \ 7 , o.4 -
\l' . r. '
0.35 -
".f I i'=I\l\.
s.l 73 74 75 76 77 78 79 80 81 82 83 84 85 S6 87 88 89 90 Year 9
i l 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.la-id for esch quarter of 1990. 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 are all new locations as of January 1, 1984 and sufficiently distant to be considered reference (control) locations. (See Table III.B.1).
The reported concentrations are listed in units of femtocuries per cubic meter of ambient ' air, although the measured activity is due to a combination of radionuclides
-almost all of-which are naturally occurring. It should be noted that the current technical specifications no longer
- require measurement of gross alpha activity. All filters, however, are saved indefinitely for later alpha activity-analysis if needed.
The mean gross beta concentration in air for all f acility stations for all of 1990 was 23 fCi/m. 3 For 1989 the mean , value was 26 fCi/m. 3 The mean concentration for 1990 for all reference stations was also 23 fCi/m. 3 These measured mean 10
- . -- = . - . - . . --.- - . . - . - - . - - ~ . - . ~ . - .
- values were obviously' not statistically significant at the 95%
l confidence _ level._ ; The gross beta data for 1990 have been added to the plot of ' air concentrations observed since 1973 (Figure II.B.1)- In this figure the half-yearly maan values for the facility sites -! are plotted with-th. values from the reference sites. The l- contribution from Chernobyl is clearly evident in 1986. .It
- can be observed that overall mean values are not significantly different and that world-wide fallout, principally due to past-Chinese. atmospheric nuclear weapon tests, is the predominant
- contributor.to the measured values over the period shown. !
There has never been,a significant difference observed between = facility. and reference sites. Thus, itL can . be
- concluded that reactor air effluents of particulate-fission L ' products or activation products during operation were not a- 4 source.ofJdose commitment for'the Fort ' St. Vrain environs-L L: . population. This.is expected to be true-as well during the l-
-defueling'-and decommissioning _ phase. ;
_i l1. 11' , y ~ b e,- N n, , m-- ,4 -w --- e -m o -
n;- Table II.B.1 Concentrations 'of..t.ong-lived Gross BetaIParticulate' Activity in Air. (fCi/M )- E :a)~ First Quarter,1990 ^
~
Facility Sites Reference Sites
' Collection Date 'F-7 F-9 F A-19 R R-4 R-11 1/6/90 20(1.2)* 23(1.9).. :21(1.3) 23(1.2 ) '- 20(1.4) 21(1.5) 24(1.6)
-1/13/90 20(1.1) 19(1.3) :19(1.4)- ~ 18(2.0) 20(1.6) -16(1.0) 19(1.5) t 1/20/90- 17(1.2) 24(1.9) 23(1.4) 27(1.3)- :24(1.5)- 23(1.5) 31(1.9)
.1/27/90 '. 27(1.2) . 26(1.4)- .23(1.5) '37(3.7)- '21(1.7) 21(1.1) 25(1.6)
I
'2/3/90 13(1.2) 17fl.6) 18(1.2) 2'J ! J) 20(1.4) 17(1.2) 20(1.5)-
2/10/90 29(1.3) 28(1.5) 23(1.6) 21(1.9) 25(1.8) '20(1.1) 26(1.7) 4 2/17/90 26(1.3) 26(2.0) 25(1.4) 33(1.5) 26(1.7) 25(1.5) 27(1.7) i 2/24/90 20(1.0) 21kl.4) 18(1.3) 13(1.8) 19(1.6) 18(1.1) 19(1.5) 3/3/90 31(1.7) e 29(1.5) 31(1.2) 27(1.7) 26(1.4) 27(1.7) 3/10/90- 21(1.1) 16(0.91) 17(1.3) 20f2.0) 18(1.7) 16(0.93) 21(1.5) 3/17/90 12(1.0) 12(1.1) 13(1.1) 15(0.90) 14(1.3)- 14(1.1) 15(1.4)- e 3/24/90 '18(0.97) 17(0.97)~ 16(1.3) 13(1.9)- 18f2.3) 17(1.0) 17(1.4) 3/31/90 19(1.2)- '20(1.3) 20(1.3) 19(1.0)- 18(1.3) 17(1.1) 21(1.5)
; 21- 21 20 22 21 19 22 1 96 a 11 9.4 8.3 15 7.3 7.3 9.0 MAX: 34 x(1.960): 21(11) MAX: 31 i( 1.96 o) : 21(8.1)
MIN: 12 n: 51 MIN: 14 D:39 l
- 1.96 o (Due to Counting Statistics.)
- e --insufficient weight or volume for, analysis
~
y .- x
^
_ Table II.B.1 Concentrationsf of-Long-lived Gross' Beta Particulate; Activity in Air. (fCf/m )
- b) Secor.d Quarter.1990 .- ..
- Facility: Sites. -Reference Sites Collection :s Date F-7 'F F A-19 R-3' R-4 R 14/7/90' 21(1.?)* 21(1.1) "18(1.3); ~18(2.0). :22(1.8) 22(1.1). 22(1.6) 4/14/90.. 19(1.u) 20(1.0) ~13(1.8): 19(1.1): c. 20(1.1) 19(1.6) 4/21/90: 23(1.3). 25(1.2) '22(1.5) 22(1.1) 14(1.0) 20(1.1) -16(1.5) 4/28/90: 19(1.2)- 15(1.0) 19(1.4)' 18(1.1) 17(1.1) 17(1.0) 19(1.5)
- 5/5/90 19(1.2): .'8(1.0) 17(1.3) 17(1.0) 17(1.1) 17(0.95) 18(1.4)
S/12/90 16(1.2).. ~15(1.0) 16(1.3) 16(1.0)- 18(1.4) 17(1.0) 17(1.4) 5/19/90 25(1.5) 19(1.1) 24(1.5) 21(1.4) 15(1.1) 18(1.0) '23(1.7) b 5/26/90 23(1.4). 24(1.2) 21(1.4) 21(1.1) 25(1.3) 23(1.2) 23(1.6) 6/2/90 5.5(1.0) 14(1.0) 12(1.2) 13(0.93) 12(0.91) 14(0.93) 15(1.3) 6/9/90 _19(1.4) 20(1 19(1.3) 19(1.1) 20(1.2) 29(1.7) 18(1.4) 6/16/90- 17(1.4) 16(1.1) 17(1.3) 15(1.0) '17(1.1) 16(1.0) 18(1.4) 6/23/90- 25(1.5)' 21(1.1) 19(1.4) 19(1.1) 21(1.2) 21(1.1) 21(1.5) ! 6/30/90: -42(1.8)- 30(1.4) :32(1.Gi 28(1.4) 28(1.4) 25(1.3) 20(1.8) 21 20 19- 19- 19 20 20
.96o. 16. 8.9 10- 7.3 '9.0 '8.0 6.9
- MAX: 42 T(1.96o): : 20(11)
MAX: MIN: 5.5 'n : 52- MIN:- '12
- 29. I( 1 ~ 96 ) . 20(7.9 )
n 38
- 1.96o (Due t) . Counting Statistics) .
c ' instrument: mal function i.
- .: . a. . .a . - - .
(fCi/o ) Table II.B.1 Concentrations of Long-lived Gross Beta Particulate Activity in Air. c) . Third Quarter,1990 _- Facility Sites Reference Sites Collection F-16 A-19 R-3 R-4 R-11 Date F-7 F-9 24 (1.5) 24 (1.6) 6.6 (1.8) 22 (1.2) 24 (1.8) 07/07/90 33 (1.7)* 23 (1.3) 19 (1.4) 25 {1.4) 17 (1.0) 20 (1.0) 20 (1.6) 07/14/90 25 (1.5) 18 (1.2) 2! (1.4) 29 (1.4) 21 (1.2) 21 (1.1) 23 (1.6) 07/21/90 22 (1.5) 19 (1.3) 16 (1.4) 16 (1.0) 17 (1.1) 18 (1.1) 18 (1.6) 07/28/90 18 (1.4) 18 (1.2) 24 (1.1) 20 (1.4) 26 (1.2) 24 (1.7) 08/04/90 28 (1.6) 25 (1.2) 24 (1.6) 28 (1.8) 28 (1.2) 15 (1.2) 27 (1.3) 29 (1.9) 08/11/90 29 (1.7) 24 (1.7) 19 (1.0) 17 (1.2) 20 (1.1) 21 (1.7) 08/18/90 20 (1.5) h 18 (1.6) 21 (1.1) 21 (1.4) 22 (1.2) 22 (1.9)
~ 08/25/90 21 (1.5) 21 (2.7) 22 (1.9) 22 (1.2) 15 (1.1) 20 (1.1) 23 (2.1) 09/01/90 25 (1.7) 23 (2.2) 11 (1.6) 26 (1.5) 27 (1.2) 28 (1.2) 28 (1.3) 24 (2.4) 09/08/90 29 (1.7) 27 (1.6) 33 (1.8) 30 (1.3) 24 (1.2) 31 (1.4) 33 (2.8) 09/15/90 35 (1.9) 34 (1.9) 29 (1.7) 23 (1.2) 29 (1.5) 50 (2.3) 27 (1.5) 09/22/90 D '1.7) 28 (1.7) 27 (1.6) 29 (1.2) 25 (1.2) 29 (1.3) 29 fl.8) 09/29/90 28 11.6) 25 (1.7) f ___ ___ ___
20 26 24 26 24 23 24 i 8.3 12 16 8.1 1.96o 9.8 9.1 12 24(10) MAX: 50 Y (1.96 c): 23(13) f1AX: 35 Y (1.96c): M1M: 6.6 n: 39 tilH: 11 n: 51
- 1.96 o (Due to counting Statistics.)
h _ sample not collected (air pump not functioning)
%d 3
-Table -II.B.1 Concentrations of- Long-lived Gross Reta Particulate Activity in' Af r. (fCf/m )
d) Fourth Quarter,1990 Facility Sites Reference Sites Collection ' Date- F-7 F F_16- A-19
- R-3 R-4 R 10/06/90- 23:(1.6)* 24 (2.C). 24 (1.7) - 24 (1.2) 24-(1.2) 24 (1.3) 24 (1.4) 10/13/90- 20 (1.5) 22 (2.6) 20 (1.5) 1 17-' (0.95) 22 (1.2) 21 (1.2) 21 (1.3) 10/20/90 24 (1.7)- 25 (2.8) 23 (2.0) 19 (1.1) 22 (1.2) 22.(1.2). 23 (1.5 10/27/90 30 (1.7)- 26 (1.2) 30 (1.4) 30 (1.3) 27 (1.2) 26 (1.3) 29 (1.6) 11/03/90_ 34.(1.9) 31'(1.4) 32 (1.5) 31 (1.4) 31 (1.5) 29 (1.4) 10 (1.4) 11/10/90 28 (1.7) 30 (1.3) 25 (1.3) 29 (1.3) 25 (1.2) 33 (1.7) 22 (1.1)
G 11/17/90 30 (1.7) 28 (1.3) 30 (1.5) 29 (1.3) 28 (1.7) 20 (1.3) 24 (1.4) 11/24/90 42 (2.0) 29 (1.4) '30 (1.4) 25 (1.2) 24 (1.3) 40 (1.8) 56 (2.3) 12/01/90 - 23 (1.6) :22 (1.2) 26~(1.4) 18 (1.1) 27 (1.4) 22 (1.3) 43 (2.6) 12/08/90 9.7 (1.3) 14 (1.0) 21 (1.3) 18 (1.1) 54 (3.1) 17 (1.2) 16 (1.1) 12/15/90 29 (1.6) 25 (1.2)- 29 (1.4) 28'(1.2) 21 (1.2) 22 (1.3) 26 (1.3~ 12/22/90 52 (2.5) 37 (1.5) 37 (1.6) 36 (1.4) 33 (1.6) 35 (1.7) 36 (1.7) 12/29/90 49 (2.4) 33.(1.6) 42 (2.0) 43 (1.8) 12 (1.1) 33 (1.8) 34 (1.6) x 30. 27- 28 27 27- 26 28 1.96 o 23- 11 12 15 19 14 23 MAX: '52 T(1.96o): :28(17): MAX: 56 x(1.96 o):27(20) MIN: 9.7 :n: .52 MIN: 10 n:39 1.96o (D' u e to Countin9 Statistics.)'
.._ . _m _ __ _ ___. , - . _ __ _ _ _ _ _ ___ _ . _ . . __ m _____ _ _
Figure-liiB.1 10x
- 900 Gross Beta Concentrations in Air 800 -
700 - W Facility Sampling Station 600 . X=53-
-.500 -
. Reference Samoling Stations l400 - R = 60 300 -
f i 200 - '
\- /-
\- /
i j
; n \ T E \ l 1 v cico - !. \ f-j 90
,80
_[ \ f .l l ll 7.0 l t {_ y\ 60 \ \
,\ j I
SO -E \ .\ j\
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N \ I'
'40 -
} g
< l
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10
'e ' ' ' ' ! ' '
- 1973 '74- '75 76 77 '78 '79 '80 '81 '82 '83 '84 '85 '86 '87. '88 - '89 '90 '91 Time (year) o a
16 1
- 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 activity of tritium in water extracted from'these weekly samples for 1990 is listed in Tables II.B.2a-2d.. - The corresponding tritium concentration in air (pcijm 3) ~ is calculated from the specific activity. data using: Weekly mean temperatures and dew points measured at the i FSV' meteorological. tower. The measuring point'is at a height of 2 m from the surface.- The tritium' air concentrations are
-shown in Table.II.B.3a-3d.
The principle release mode of tritium from the reactor was batch liquid: releases from holding' tanks (system 62) . =The tank water 'is first analyzed and then released with sufficient 4 additional dilution, 1f- necessary,- to meet .10CFR20
. concentration limits. The summary of tritium release by all , -modes is.shown in Table.II.B.4. The summaryfindicates that the total tritium L released - -in . -1990 Dwas 70 percent of that-e released in 1989 by all routes._ This' effluent release was not detected.at_ F-16 Land _-A-19,' two air sampling. sites close to the Goosequill' ditch' effluent path.
Thel mean : values for sites = F-16 and A were stiatistically. the same_ as for all other sites during the ' year. In any-case,: inhalation-is not a significant pathway for' dose te~ humans. The ; milk and _. food product. pathway .is the . only '
-significant- -source of' radiation dose to humans. from ,
.17
l environmental tritium. See results for these pathways in sections II.D and II.E.
- l. Since the same weekly relative humidity is assumed for all sites, Table II.B.3 would show the same site dependence on 1
reactor effluent as Table II.B.2. Only the units used to
- measure tritium in surface air are different.
l f-l 1 l 1 i l 1 1 l i i i i l r-l 18 l
s.g# E o 8 g,d;>tel' %h* IMAGE EVALUATION
, E E, ,- < ,-
,,,,/
, 4 <'4e O
+ .
3 44 i ? tid y fff Oltl I,l [ m ble l11 l.25 1.4 i 1.6 l == 4 150mm
- 4 6" >
4;4
;g/,,,% 3 -
f's*+s ) , y;; A by,7 t s A. .
- m . lL _ _ _ ____ . 7 ~
Table II.B.2 Tritium Concentrations in Atmospheric Water Vapor. (pCf/L) a) First Quarter, 1990 [ Facility Sites Reference Sites Collection R-4 Date F-7 F-9 F-16 A-19 R-3 R-il
< 420 < 420 < 420 < 420 e e 1/6/90 < 420
< 420 < 420 < 420 < 420 e < 420 1/13/90 < 420
< 420 < 420 < 420 < 420 < 420 < 420 < 420 l 1/20/90 i
e < 420 < 420 < 420 < 420 < 420 < 420 1/27/90
< 420 < 420 < 420 < 420 < 420 s 420 < 420 2/3/90
< 420 < 420 < 420 < 420 < 420 < 420 < 420 2/10/90
< 420 < 420 < 420 < 420 e < 420 < 4 20 2/17/90
< 420 e e < 420 e e 2/24/90 e
< 420 < 420 e < 420 e < 420 < 420 3/3/90
< 420 < 420 < 420 < 420 < 420 < 420 < 420 1/10/90
< 420 < 420 c 420 < 420 < 420 < 420 < 420 3/17/90
< 420 < 420 < 420 < 420 < 420 < 420 < 420 1/24/90 3/31/90 < 420 < 420 < 420 < 420 < 420 < 420 e L
e - insuf ficient weight or volume for analysis.
l Tabie II.B.2 Tritium Concentrations in Atmospheric' Water Yapor. (pCi/L) b) - Second - Quarter,71990 Facility. Sites- Reference Sites I Collection
~Date- F-7 F-9-- F-16 A-19 R-3 R-4 R-11
.4/7/90l ' <420 '<420- -<420 < 420 .
<420 <420 <420
'4/14/90 <420 .<420 - <420. . <420 <420 <420- a 4/21/90- <420 <420 :<420
- <420 <420- <420 <420
~
4/28/90- :<420 <420' <420 <420 <420 <420 <420
' 5/5/90. L<430 ' <430. <430 ' <430 <430 <430 <430~
5/12/90- <390' i<390 <390 <390 <390 <390 <390 5/19/90- <420 <420. i<420 <420 .- <420 <420 <420 5/26/90 < 400: <400: <400 <400 <400 <400 <400 6/2/90 <390- -<400 <400 -
<390 <400 <400 <400 6/9/90 <390 <390 .<390 <390' <390 <390 <390 6/16/90 <390. <393 <390 <390 <390 <390 '<390 6/23/90 ' <390 <390 !<390 <390 <390 <390 <390 6/30/90 <390 <390 <400 <390 L <400. <400 <390
- 1. 96'o~ (Due; to . Coun ti ng. S ta ti s ti cs ).
a-sample lost' prior to analysis .
- .- -. _~
. Table II.B.2 Tritium Concentrations in Atmospheric Water Vapor. (pCi/L)
. c)_lhird Qualler,_1990 Facility Sites Reference Sites Collection Date F-7 F-9 F-16 A-19 R-3 R-4 R-Il 07/07/90 < 390 < 390 < 390 < 390 < 390 < 390 < 390 4 07/14/90 < 400 < 400 < 400 < 400 < 400 < 400 < 400 07/21/90 < 390 < 390 < 390 < 390 < 390 < 390 < 390 07/28/90 < 390 < 390 < 390 < 390 < 390 < 390 < 390 '
08/04/90 < 390 < 390 < 390 < 390 < 390 < 390 < 390 m
~
08/11/90 < 390 < 390 < 390 < 390 < 390 < 390 < 390 08/18/90 < 390 < 390 < 390 < 390 < 390 < 390 < 390 08/25/90 < 390 < 390 < 390 e < 390 < 390 < 390 09/01/90 < 390 < 390 < 390 < 390 < 390 < 390 < 390 09/08/90 < 400 < 400 < 400 < 400 < 400 < 400 < 400 09/15/90 < 390 < 390 < 390 < 390 < 390 < 390 < 390 - 09/22/90 < 400 < 400 < 400 < 400 < 400 < 400 < 400 09/29/90 < 390 < 390 < 390 < 390 < 390 < 390 < 390 e - insufficient weight or volume for analysis [
i l l I-(-
- O O O O Q O O O O O O O O
- O O O Ch v Ch O O O Ch - O O l I y er v m v m air y v m air gr er 1 M I l v v v v v v v v v v v v v e I
, c l i e - l= - M O O O O O O O O O O O O O
- Q v C3 O O Ch O Ch O O O Ch - CD C J U s er tr v m v m er v gr m er y mr i
% C CE -
I
- ca v v v v v v v v v v v v v i l U L O O I - w s l @
l CC l l ' i L' O O O O O O O O O O O O O I o m O O O m O Ch O O O Ch - C O l
- c. I 97 mr v m er m tr 4:r v M v tr er i l et CE -
I
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- s O I
ch O O O O :D O :D O CD O O O 1 W - O -O O Ch O Ch O O O Ch - O O i
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^8 w
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- h 6 I m w v v v v v v v v v v v v v g m - 1
= - M i o === r0
- O U 'M i
*J fg Ch Ch- L
#9 m L - O O O O O O O O Q O O O O r & Ch O O O Ch O Ch C O w Ch - O O CD I. C -* I s e 4:r se m v m tr er att m a:r v tr -4 C 4 L L 1 em U. c/ v v v v v v v v v v v v v i a C w -
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- O E C - v.
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- .= O O O O O O - O O O O O O - C a w- N O O O Ch O Ch v CD O Cn - C O
- L i - 47 m:r a:t m 4r m w v mr m at" er er i # a L 3 L O i '
W C v v v v V v N v v v v v V i q) W 'T D.
- O C= e = -
e C
- - O O O O O O O O O O O O O D
- w CB Ch Ch Ch Ch Ch Ch Ch Ch @ Ch Ch Ch e U N N N N N N N % % % % N % O Q GJ @ M O Pa= M O N er - CO LO N Ch
- l -, - C) C - N N O +== - N O O - N N l t . - a % % N % % % % % % N % % N 4 - 1 (U C FC O O O O - - - - N N N N I H yO - - - - -. - - - .N
-- - - - - i ,
i i t-l 1 l 22 j s
Table II.Bi3 Tritium' Concentrations in Atmospheric Water Vapor. (pCf/m3 ) a) First Quarter, 1990 Facility Sites Reference Sites 3
. Collection Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 01/06 < 1.2 < l .2. < 1.2 < 1.2 < 1.2 e e 01/13 < 1.4 < 1.4 < l.4 < 1.4 < 1.4 e < 1.4 01/20 < 1.4 < 1.4 < 1.4 < l.4 < 1.4 < 1.4 < 1.4 01/27 e < 1.0 < 1.0 < 1.0 < 1.0 < 1.0 < 1.0 l i
02/03 < 1.2 < 1. 2 < 1.2 < 1.2 < 1.2 < 1.2 < 1.2 02/10 < 1.4 < 1.4 < 1.4 < 1.4 < 1.4 < 1.4 < 1.4 l' C 02/17 < 1.1 < l.1 < 1.1 < 1.1 e < 1.1 < 1.1 02/24 e < l.6- e e < 1.6 e e 03/03 < 1.7 < 1. 7 e < 1.7 e < 1.7 < 1.7 03/10 < 2.0 < 2.0 < 2.0 < 2.0 < 2.0 < 2.0 < 2.0 03/17 < 1.6 < l.6 '< 1.6 < l.6 < 1. 6 < 1.6 < 1.6 03/24 < 1.7 ' < 1.7 < 1.7 < 1.7 < 1.7 < l .7 < 1.7 03/31 < 2.0 < 2.0 < 2.0 < 2.0 < 2.0 < 2.0 e e - insufficient volume for analysis l
Table II.B.3 Tritium Concentrations in Atmospheric Water Vapor. (pCi/m3 b' Second Quarter.1990 Facility Sites Reference Sites Co11ection Date I-7 F-9 F-16 A-19 R-3 R-4 R-11 04/07 < 2.1 < 2.1 < 2.1 < 2.1 < 2.1 < 2.1 < 2.1 04/14 < 2.2 < 2.2 < 2.2 < 2.2 < 2.2 < 2.2 a 04/21 < 2.5 < 2.5 < 2.5 < 2.5 < 2.5 < 2.5 < 2.5 04/28 < 2.3 < 2.3 < 2.3 < 2.3 < 2.3 < 2.3 < 2.3 05/05 < 1. 7 < 1.7 < 1. 7 < 1. 7 < 1. 7 < 1.7 < 1. 7 05/12 < 1.8 < 1.8 < 1.8 < 1.8 < 1.8 < 1.8 < 1.8 05/19 < 1.9 < 1.9 < 1.9 < 1.9 < 1.9 < 1.9 < 1.9 05/26 < 2.3 < 2.3 < 2.3 < 2.3 < 2.3 < 2.3 < 2.3 06/02 < 2.4 < 2.5 < 2.5 < 2.4 < 2.5 < 2.5 < 2.5 06/09 < 2.7 < 2.7 < 2.7 < 2.7 < 2.7 < 2.7 < 2.7 06/16 < 2.5 < 2.5 < 2.5 < 2.5 < 2.5 < 2.5 < 2.5 06/23 < 2.2 < 2.2 < 2.2 < 2.2 < 2.2 < 2.2 < 2.2 06/30 < 2.8 < 2.8 < 2.9 < 2.8 < 2.9 < 2.9 < 2.8 a - Sample lost prior to analysis
Table II.B.3 Tritium Concentrations in Atmospheric Water vapor. (pci/m3) c) Third Quarter,1990 Facility Sites Reference Sites Collection Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 07/07 < 2.9 < 2.9 < 2.9 < 2.9 < 2.9 < 2.9 < 2.9 < 07/14 < 2.8 < 2.8 < 2.8 < 2.8 < 2.8 < 2.8 < 2.8 07/21 < 2.6 < 2.6 < 2.6 < 2.6 < 2.6 < 2.6 < 2.6 07/28 < 2.7 < 2.7 < 2.7 < 2.7 < 2.7 < 2.7 < 2.7 08/04 < 2.6 < 2.6 < 2.6 < 2.6 < 2.6 < 2.6 < 2.6 08/11 < 2.7 < 2.7 '< 2.7 < 2.7 < 2.7 < 2. 7 < 2.7 m 08/18 < 2.9 <. 2.9 < 2.9 < 2.9 < 2.9 < 2.9 < 2.9 08/25 < 2.0 < 2.0 < 2.0 e < 2.0 < 2.0 < 2.0 09/01 < 3.0 < 3.0
< 3.0 < 3.0 < 3.0 < 3.0 < 3.0 09/08 <-3.3- < 3.3 < 3.3 < 3.3 < 3.3 < 3.3 < 3.3 09/15 .< 2.4 < 2.4 < 2.4 < 2.4 < 2.4 < 2.4 < 2.4 09/22 < 2.6 < 2.6 < 2.6 < 2.6 < 2.6 < 2.6 < 2.6 09/29 < 2.5 < 2.5 < 2.E < 2.5 < 2.5 < 2.5 < 2.5 e . insufficient volume for analysis
J-Table-II.B.3 Tritium Concentrations in Atmospheric Water Vapor. (pCi/m ) d) Fourth Quarter, 1990 l .. *
. Facility Sites Reference Sites Collection Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 10/06 < 2.0 < 2.0 < 2.0 < 2.0 < 2.0 < 2.0 < 2.0 10/13 < 1.6 < 1.6 < 1.6 < 1.6 < 1.6 < 1.6 < 1.6
< 1.4' < 1.4 < 1.4 < 1.4 10/20 . < 1.4 < 1.4 < 1.4 10/27 < 1.5 < 1.5 < 1.5 < 1.5 < 1.5 < 1.5 < 1.5 11/03 < 1. 5 < 1.5 <1.5 < 1.5 < 1.5 < 1.5 < 1.5 g 11/10 '< 1.2 < 1.2
< 1.2 < 1.2 < 1.2 < 1.2 < 1.2 11/17 1.6(1.5)* < 1. 5 < 1.5 < 1.5 < 1.5 < 1.5 < 1.5 11/24 1.3 < 1.3 < 1.3 < 1.3 < 1.3 < 1.3 < 1.3 12/01 < 1.0 < 1.0 < 1.0 < 1.0 < 1.0 < 1.0 < 1.0 12/08 < 0.95 < 0.95 < 0.95 < 0.95 < 0.95 < 0.95 < 0.95 12/15 < 1.2 < 1.2 < 1.2 < 1.2 < 1.2 < 1.2 < 1.2 12/22 < 0.49 .
< 0.49 < 0.49 < 0.49 < 0.49 < 0.49 < 0.49 12/29 < 0.52 < 0.52 < 0.52 < 0.52 < 0.52 < 0.52 < 0.52 E
*1.96o (Due to Counting Statistics)
t i' ' f t i ,'
- i. -
i l t : i ? I t i l Table II.B.4 . Tritium Released (nci)' in Reactor Effluents, 1990 .I
.i I
[. HODE. ~JAN TEB HAR ' 'APR. HAY JUN JUL: AUG. SEP' OCT . tiOV - DEC TOTAL continuous' [ [ l'"' su.pl
'13 4.9' '18 .0.72 0.31 'O.94 3.9' 4.7 1.1 0.65 0.91 1.4 -50 l
.g atch ;
, y Helease , ineactor nuinding 34_ 28 '19 ~3.4- 1.9' 28 2.5 2.4 1.4 0.71 2.5 2.2 105. ..
)
l
- su=vi ,
i t 113tCh I flel l ea se - - - E
- tsystem 62) 19 8-- 170 51 8.5 55 1.6 51 503 135 44 427 492 2135 l t
! .tt caseous ,
stack 28 7.6 543 40- 34 11 11 14 'll 7.6. 12 8.7 728 9 i i TO 253 .211 '.630- ~52 91 42 68 524 14 8 53 '443 504 3018 t
'0 1
i I y _. +.
- 3. Concentrations of Gamma-rav Emittina Radionuclides in Ambient _ Air Tables II.D.5a-5d list the concentrations of I-131 in air as measured by activated charcoal sampling and Ge(Li) gamma-ray spectrum analysis during 1990. Each sample from the seven air sampling stations is counted within 96 hours after collection. A 100 minute count and a sample volume of 800 m3 is required to achieve an MDC of 33 fCi/m'. Radon daughters and Thoron daughters are trapped on the particulate filter ahead of the charcoal trap. Radon-222 daughter in-growth on the charcoal does not provide interference to the region of interest for I-131 using the Ge(L1) high resolution spectrometry system. Any positive I-131 activity is corrected for radioactive decay back to the midpoint of the collection period. Decay correction to the midpoint of the sampling period is appropriate as any I-131 in air would not arrive at the sampling stations at a constant rate, but rather randomly in pulses of short duration compared to the collection period.
This is the case whether the I-131 source term would be a nuclear accident elsewhere, weapons testing f allout or reactor btack effluent. There were only occasional positive values very near the
?
MDC value and all are assumed to be false positives. I-131 concentrations due to reactor effluent have never been detected in any sample type in the Fort St. Vrain environs. Table II.B.6 lists measured ambient air concentrations of Cs-134 and Cs-137. These values are from gamma-ray spectrum 20
analyses on weekly air filters composited quarterly from each of the seven air sampling stations. The occasional positive Cs-137 concentrations measured are likely due to resuspension of surface soil. The Cs-137 activity is due to Chernobyl or previous fallout whien 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 are 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. l f-l l l l l 29
Table II.B.5 : Iodine-131^ Concentrations in Air. .(fCi/m3)
'a) First Quarter, 1990 I
Facility Sites Reference Sites Collection ' Date F-7 F-9' F-16 A-19 R-3 R-4 R-11 1/03/90 < 14.0 < 33.0 < 11.0 < 29.0 < 32.0 < 26.0 < 12.0
< 22.0 < 22.0 - < 33.0 < 11.0 37.0 (29.0)*< 7.7 < 6.9 1/10/90 ,
i 1 1/17/90 < 16.0 < 16.0 < 16.0 < 28.0 < 14.0 < 11.0 < 19.0 1/24/90 < 19.0 < 34.0 < 25.0 < 20.0 < 34.0 < 26.0 < 6.4 1/31/90- < 16.0 < 17.0 < 22.0 < 26.0 < 20.0 <17.0 < 18.0 2/7/90 < 16.0 < 20.0 <
' 30.0 < 26.0 < 8.9 < 9.0 < 16.0 J 2/14/90 < 7.1 < 18.0 < 7.0 < 13.0 < 17.0 < 9.7 < 14.0 gg 2/21/90 < 5.4 < 13.0 < 20.0 < 32.0 < 13.0 < 16.0 < 33.0 2/28/90 < 24.0 < 20.0 < 18.0 < 7.6 < 7.3 < 5.5 < 17.0 3/7/90 < 13.C < 11.0 < 11.0 < 14.0 < 8.8 < 13.0 < 25.0 .
3/14/90 < 23.0 31.0 (38.0) < 22.0 < 15.0 < 16.0 < 18.0 < 14.0 ' 3/21/90 < 9.6 < 7.4~ < 11.0 < 17.0 < 16.0 30.0 (28.0) < 7.1 3/28/90 < 31.0 < 8.9 < 21.0 < 8.2 < 15.0 < 16.0 < 13.0
*1.96c (Due to Counting Statistics)
W 4
Table II.B.5 Iodine-131 Concentrations in Air. b? Second Quarter, 1990 Facility Sites Reference Sites Collection Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 4/04/90 < 20.0 < 8.4 < 8.6 19.0 (20.0: < 24.0 < 24.0 < 26.0 4/11/90 < 8.0 < 13.0 < 13.0 < 11.0 e < 6.9 < 16.0 4/18/90 < 5.4 < 7.7 < 11.0 < 8.7 < 6.8 < 19.0 < 14.0 4/25/90 < 22.0 < 19.0 < 26.0 < 17.0 < 14.0 < 16.0 < 26.0 5/02/90 < 4.9 < 11.0. < 8.2 < 11.0 < 13.0 < 7.9 < 13.0 5/09/90 < 12.0 < 11.0 < 11.0 < 12.0 < 16.0 < 14.0 < 7.4 5/16/90 < 26.0 < 18.0 < 20.0 < 23.0 27.0 (31.0) < 14.0 < 14.0 5/23/90 < 22.0 < 19.0 < 13.0 < 13.0 < 20.0 < 14.0 < 18.0 5/30/90 < 29.0 < 25.0 < 13.0 < 15.0 23.0 (23 0) < 11.0 < 24.0 6/06/90 < 33.0 < 14.0' < 23.0 < 18.0 < 12.0 < 21.0 < 17.0 6/13/90 < 29.0 < 15.0 < 24.0 < 9.1 < 13.0 29.0 (26.0) < 14.0 6/20/90 43.0-(43.0) < 12.0 < 24.0 < 5.6 < 4.7 < 9.6 < 21.0 6/27/90 13.0 (13.0) < 16.0 < 29.0 < 20.0 < 29.0 25.0 (24.0) < 31.0
*1.96o (Due to Counting Statistics) e-insufficient weight or volume for analysis
Table 11.8.5 Iodine-131 Concentrations in Air.- (fCi/m3) d) Third Quarter, 1990 Facility Sites Reference Sites Collection Date F-7. F-9 F-16 A-19 R-3 R-4 R-11 7/04/90' < 19.0 < 14.0 < 15.0 < 13.0 < 26.0 < 10.0 < 8.2 t 7/11/90 < 17.0 < 22.0 < 31.0 < 27.0 14.0(14.0f<15.0 < 30.0 7/18/90 < 20.0 < 17.0 < 21.0 < 14.0 < 21.0 < 23.0 < 24.0 7/25/90 < 17.0 < 32.0 31.0 (34.0) < 7.3 < 19.0 < 15.0 < 22.0 8/01/90 < 31.0 < 12.0 < 11.0 < 18.0 < 27.0 < 13.0 < 31.0 8/08/90 < 25.0 < 26.0 < 19.0 < 13.0 < 22.0 < 9.3 < 32.0 Rl 8/15/90 < 20.0 h < 15.0 < 12.0 < 9.0 < 20.0 < 20.0 8/22/90 < 23.0 < 14.0 < 21.0 < 12.0 < 13.0 < 19.0 < 9.6 8/29/90 < 24.0 < 17.0 < 22.0 29.0 (34.0) < 30.0 < 21.0 < 20.0 9/05/90 < 15.0 < 14.0 < 17.0 < 20.0 < 25.0 < 4.4 26.0 (21.0) 9/12/90 < 35.0 < 17.0 < 9.4 < 5.3 < 4.5 < 16.0 < 35.0 9/19/90 < 24.0 < 7.1 < 27.0 < 13.0 < 29.0 < 18.0 < 8.6 9/26/90 < 7.5 < 27.0 < 19.C < 18.0 < 9.4 < 16.0 < 33.0
*l.96o (Due to Counting Statistics) h - sample not collected (air pump not functioning)
Table II.B.5 Iodine-131 Concentrations in Air. (fCf/nd) d) Fourth Quarter,1990 Facility Sites Reference Sites Collection Oate F-7 F-9 F-16 A-19 R-3 R-4 R-11 10/03/90 36.0 (35.0)*< 23.0 < 13.0 < 34.0 < 34.0 < 29.0 < 34.0 10/10/90 < 17.0 < 27.0 < 23.0 17.0 (16.0) < 22.0 < 33.0 < 5.7 10/17/90 < 17.0 < 15.0' < 18.0 < 4.4 < 34.0 < 22.0 < 18.0 10/24/90 < 13.0 < 19.0 < 11.0 < 24.0 18.0 (20.0) < 21.0 < 24.0 L 10/31/90 < 34.0 < 21.0 < 5.6 < 19.0 < 20.0 -< 13.0 < 23.0 , 11/07/90 < 25.0 < 8.3 < 15.0 < 9.5 < 4.4 < 8.0 < 15.0 I$ 11/14/90 < 11.0 < 35.0 < 17.0 < 18.0 < 29.0 < 16.0 28.0 (29.0) , 11/21/90 < 11.0 < 11.0 < 14.0 < 9.1 < 18.0 < 19.0 49.0-(41.0)
< 26.0 < 18.0 11/28/90 < 22.0 < 14.0 < 20.0 < 24.0 < 24.0 T
12/05/90 < 27.0 30.0 (31.0) < 26.0 33.0 (35.0) < 19.0 < 16.0 < 31.0 12/12/90 < 19.0 < 25.0 < 20.0 < 7.1 < 16.0 < 30.0 < 33.0 12/19/90 < 27.0 < 22.0' < 19.0
. < 14.0 < 21.0 < 24.0 < 23.0 12/26/90 < 30.0 < 23.0 52.0 (40.0) < 18.0 < 30.0 < 15.0 < 30.0
*1.96o (Due to Counting Statistics)
{
l l Table 11.B.6 Radiocesium Concentrations in Ambient Air. (fC1/m3) 1990 Facility Sites Reference Sites Collection Radio- ' Date nuclide F F-9 F-16. A-19 R-3 R-4
?
R-11 1st Cs-134 1.3 (1.3)* < 1.1 < 1.1 < 1.4 < 2.0 < 1.2 < 1.3 ; Quarter Cs-137 < 1.1 < 1.2 < 1.2 < 1.4 < 1.9 < 1.2 < 1.4 1 2nd Cs-134 < 1.4 < 1.5 < 1.3 < 1.7 i
< 1.8 < 0.'72 < 1.6 Quarter Cs-137 < 1.4 < 1.5 1.7 (1.7) < 1.8 < 1.7 < 0.76 < 1.8 3rd Cs-134 < I .7 < 2.3 2.7 (2.8) < 1.2 < 1.6 '
< 0.86 < 2.1 Quarter Cs-137 < 1.9 2.3 (2.6) < 2.2 < 1.2 < 1.6 < 0.9 i
< 2.0 i 4
4th Cs-134 < 1.2 < 1.2 < 1. 3 < 1.3 < 0.5 < 1.2 < 1.'7 , Quarter Cs-137' < 1.4 < 1.2 <.1.4 < 1.3 < 0.5 < 1.3 < 1.7
*l.96c (Due to Counting Statistics) !
.t
[
II.C. Radionuclide Concentration in Water
- 1. Drinkina Water l
Drinking water is sampled weekly and composited biweekly at two locations. Location R-6 is the well used for drinking water by the town of Gilcrest, Coloradv and R-3 is a water i tap located on the CSU dairy farm. The Gilcrest well is the nearest-public water supply that could be affected by the reactor 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. However, water treatment systems for the two water supplies are very different. Table II.C.1 shows gross beta concentrations measured in 1990 from each water supply. As in every past year, the mean for the Gilcrest site was significantly higher than the Reference site in Fort Collins. This is only due to the different water treatment practicos and the different supply sources. The city of Gilcrest does not completely filter its 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, the mean for the entire year for the Gilcrest site was similar to that observed in previous years.
' Table II.C.2 lists measured tritium concentrations in these same two drinking water sources. No concentrations above MDC were detected in either source. The yearly arithmetic mean value for the Gilcrest location was less than 35
-n- g
MDC. The mean yearly concentration measured in the Gilerest supply was statistically the same as in the Fort Collins supply. The EPA limit for community drinking water systems is 20,000 pCi/L for tritium. The two drinking water supplies are also analyzed for fission product and activation product concentrations. A sample of 18 liters is passed through Dowex 1-x8 anion exchange resin and the resin then counted by Go(Li) spectrometry for I-131. A three liter aliquot of the original sample is counted directly for the other gamma-ray emitters. Inspection of Tablo II-C.3 reveals occasional positive values of radionuclido concentration, but with the exception of Cs-137, these are interpreted to be random variations about the detection limit. The Cs-137 is the residuo from the 1986 Chernobyl accident fallout as well as from past world-wide fallout from nuclear weapon testing. 36
_ __ . - ~ _ _ _ . . _ . . _ _ _ _ _ _ _ . . _ Table I!.C.1 Gross Beta Concentrations in Biweekly Composites of 2rinking Water. (pCi/L) Collection Gilerest City R-6 Fort Collins City R-3 Date 90 (Reference) i 12/30 1/06 4.2(2.3)* 0.38(0.55) 1/13 1/20 4.2(2.3) 1.2(0.57) 1/27 2/03 3.7(2.3) 1.0(0.55) 2/10 2/17 4.6(2.4) 1.1(0.57) 2/24 3/3 9.5(2.6) 0.59(0.55) 3/10 3/17 5.1(2.4) 0.70(0.56)
.3/24 3/31 7.1(2.5) 0.94(0.57) 4/7 4/14 5.6(2.4) 0.97(0.57) 4/21~ 4/29 4.0(2.3) 1.2(0.58) 5/5 5/12 4.3(2.4) 0.52(0.55) 5/19 -5/26 4.1(2.3) 0.34(0.53) 6/2 6/9 1.3(2.2) 0.75(0.56) 6/16 6/23 2.4(2.2) 0.34(0.53) 6/30 7/7 1.8(2.2) 0.51(0.54) 7/14 7/21 3.1(2.3) 0.68(0.55) 7/28 8/4 3.3(2.3) 0.74(0.56) 8/11 8/18 2.6(2.3) 0.53(0.54) 8/25 9/1 3.2(2.3) 0.58(0.54) 9/Q 9/15 4.4(2.3) 0.71(0.55) 9/22 '9/29 7.6(2.5) 0.76(0.55) 10/6. 10/13 3.2(2.3) 0.73(0.65) 10/20 10/27- 5.9(2.4) 0.54(0.55) 11/3 11/10 6.6(2.5) 1.1(0.57) 11/17:11/24 5.5(2.4) 1.3(0.59) l 12/1 .12/8 5.1(2.4) 2.3(0.82) l- 12/15:12/22 4.2(2.3) 0.94(0.56)
*1.96 o (Due to Coun ting S ta tis tics )-
L L i 37
h t Table ll.C.2 Tritium' Concentrations in Biweekly Composites of Urinking Water. (pCi/L) Collection Gilcrest City . R-6 Fort Collins City R-3 Date '90 (Reference) 12/30 1/06 <420 <420 1/13 1/20 (420 <420 y 1/27 2/3 <420. <420 ' 2/10 2/17 <420 <420 2/24 3/3 <420 <420 3/10 3/17 <430 <430 ; 3/24 3/31 <420 <420 m 4/7 4/14 <420 <420 '! m 4/21 4/28 <420 <420 5/5 5/12 <390 <390 5/19 5/26 <390 <390 6/2 6/9 <400 <400 , 6/16 .6/23 <390 <390 6/30 7/7 <390 <390 7/14 7/21 <390 <390 7/28 8/4 <390 <390 8/11 8/18 <390 <390 8/25 9/1 <190 <390 *' 9/8 9/15 <400 <400 9/22 9/29 <400 <400 10/6 10/13 <400 <400 10/20 10/27 <400 <400 11/3 11/10 <390' <390 11/17 11/24 <399- <390 12/1 12/8 <400 <400 i 12/15 12/22 <400 <400
i Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCf/L) i I for two weeks ending for two weeks ending for two weeks ending Collection Date 1/3/90 1/17/90 1/31/90 Radionuclide Gilcrest Ft Collins Gilcrest Ft Collins Gilcrest Ft Collins R-6 R-3 R-6 R-3 R-6 R-3
< 0.24 < 0.34 < 0.39 < 0.34 < 0.2 < 0.23 l 1-131 Cs-134 < 2.2 < 2.3 < 2.5 < 2.3 < 2.3 < 1.6 Cs-137 6.4 (4.0)* < 3. 3 < 3.1 3.6 (3.9) 6.0 (3.5) < 1.7 Zr-95 < 5.6 < 5.2
~
< 5.8 < 5.2 < 4.9 < 3.3
$ ?!b-95 < 2.0 < 2.1 < 2.4 < 2.1 < 2.5 1.5 (1.7)
Co-58 < 2.4 <22 < 2.5 < 2.2 < 2.2 < 1.4 14n-54 < 2.3 2.2 (2.6) < 2.5 < 2.2 2.1 (2.7) < 1. 5 Zn-65 < 5.4 < 5.3 < 6.2 < 5.2 < 6.8 < 3.9 Fe-59 < 4.9 < 4.9 < 6.3 < 5.2 < 6.2 5.6 (5.2) t Co-60 < 2.3 < 2.2 < 2.8 < 2.3 3.7 (2.7) < 1.4 Ba-140 < 3.2 < 4.5 < '.1 < 3.4 < 4.1 < 3.9 La-140 < 3.7 < 5.2 < 4.7 < 3.9 < 4.7 < 4.5
*1.96e (Duc to Counting Statistics) l __
Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. . (pC1/L) l Collection for two weeks ending for'two weeks ending for two weeks ending Date 2/14/90 2/28/90 3/14/90 Radionuclide Gilcrest Ft Collins Gilcrest Ft Collins Gilcrest Ft Collins R-6 R-3 R-6 R-3 R-6 R-3 i I-131 < 0.2 < 0.37 < 0.17 < 0.22 < 0.41 < 0.18 Cs-134 < 2.2 < 1.2 < 1.2 < 1.7 1.5 (1.4) < 2.1 Cs-137 2.9 (3.2)* < 1.4 1.6 (1.9) < 1.8 1.7 (1.7) < 3.0
^
Zr-95 < 5.5 < 2.5 < 2.7 < 3.5 < 2.6 < 4.6
$ Hb-95 < 2.1 1.6 (1.4) < 1.3 < 1. 5 < 1.3 < 1.8 Co-58 < 2.1 < 1.1 < 1.2 < 1.5 < 1.1 < 2.1 Mn-54 2.7 (2.7) < 1.2- < 1.3 < 1.5 < 1.2 < 2.1 2n-65 < 5.7 < 2.8 9.4 (4.1) < 3.9 < 3.7 < 4.8 Fe-59 < 5.4 < 3.2 < 3.4 < 3.6 < 3.3 < 4.6 l Co-60 < 2.4 :< 1.1 'I.2 (1.5) < 1.4 < 1.2 < 2.2 l Ba-140 < 3.6
< 2.'O < 2.2 < 3.2 < 2.1 < 4.2 La-140 < 4.1 < 2.3 < 2.5 < 3.7 < 2.4 < 4.9
- j
- l .96 c (Due to Counting Statistics) ,
l [
i Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L) l Collection for two weeks ending for two weeks ending for two weeks ending Date 3/28/90 4/11/90 4/25/90 Radionuclide Gilcrest Ft Collins Gilcrest Ft Collins Gilcrest Ft Collins R-6 R-3 R-6 R-3 R-6 R-3 1-131 < 0.43 < 0.37 < 0.34 < 0.21 < 0.39 < 0.33 Cs-134 < 1.6 < 2.0 < 2.3 < 1.4 < 2.6 < 2.2 O Cs-137 3.0 (2.3) < 2.4 2.8 (3.3) 2.0 (1.9) < 3.1 5.0 (3.3) Zr-95 < 3.3 < 4.9 < 5.4 < 3.0 < 6.1 < 5.1 Nb-95 < 1. 7 < 1.8 < 2.0 < 1.3 < 2.3 < 2.3 C0-58 < 1.5 < 1.8 < 2.1 < 1.3 < 2.4 < 2.1 Mn-54 < 1.6 2.4 (2.4) < 2.2 < 1.3 < 2.5 < 2.2 Zn-65 < 6.7 < 5.3 < 6.4 < 3.8 < 7.0 < 7.5 Fe-59 < 4.0 < 4.6 < 5.2 < 3.5 < 6.2 < 5.0 t Co-60 1.5 (1.8) < 2.1 < 2.4 < 1.3 < 2.8 < 2.2 Ba-140 < 3.2 < 3.1 < 3.6 < 3.1 6.4 (6.2) < 4.5 La-140 < 3.7 < 3.6 < 4.1 < 3.5 7.3 (7.2) < 5.2
*1.96o (Due to Counting. Statistics) _
Table II.C.3 Radionuclide Concentrations in 81-weekly Cornposite of Da-inking Water. (pCi/L) l for two weeks ending for two weeks ending for two weeks ending Collection 6/6/90 Date 5/9/90 5/23/90 , Ft Collins Gilcrest Ft Collins Gilcrest Ft Collins Radionuclide Gilcrest R-6 R-3 Dc5 R-3 R-6 R-3
< 0.3 < 0.17 <0.45 <0.26 0.18 (0.21) < 0.13 I-131
< 2.1 < 2.2 < 1.9 < 1.8 < 1.4 < 2.1 Cs-134
< 2.4 < 2.5 2.9 (2.8) < 2.4 < 1.'7 2.6 (3.0) 0 Cs-137
< 4.8 < 4.1 < 4.6 < 3.2 < 4.6 l Zr-95 < 4.7
< 2.1 < 1.9 2.6 (2.4) 2.9 (2.2) 1.5 (1.7) < 2.0 Nb-95 C0-58 < 2.0 < 2.C < 1.8 < I.7 < I.3 < I.9
< 2.1 < 2.1 2.0 (2.4) 2.0 (2.4) < 1.5 < 2.0 Mn-54
< 5.6 < 5.7 < 5.5 < 5.5 < 4.1 < 5.4 Zn-65
< 4.9 < 4.9 < 5.0 < 3.7 < 5.8 Fe-59 9.1 (6.9)
< 2.0 < 2.1 < 1.9 < 1.8 1.3 (1.7) < 2.0 C0-60
< 3.7 < 3.3 < 3.4 < 3.6 < 2.5 < 3.6 Ba-140
< 4.3 < 3.8 < 3.9 < 4.2 < 2.8 < 4.2 La-140 l
*I.96 o (Due to Counting Statistics) l_
g. 1 i t ,' 't
.i
.j Table II.C.3 Radionuclide' Concentrations in Bi-weekly Composite of Drinking Water. (pCf/L)_
Collection. for two week's ending for two weeks ending for two weeks, ending Date 06/20/90 07/04/90 07/18/90 I 'Radionuclide- Gilcrest' Ft Collins - Gilcrest' Ft Collins ' Gilcrest Ft Collins i R-6' Ra3 .R-6 R-3 R-6 R-3 i 1-131 < 0.45 :< 0.2
< 0.46- < 0.2 < 0.47 < 0.49 Cs-134 <:2.3
< 2.1 '< 1.4
< 1.5 < 2.2 < 1.4 g Cs-137 < 2.8 < 2.5 < 1.7 < 1.8 < 2.7 < 1.7 Zr-95 < 5.2 < 4.5
'6.8-(4.17 < 3.4 < 4.5 < 3.1-hb-95 < 2.5 < 1.9 < 1. 6 < 1.4 6.1 (2.6) < 1.4 Co-58 < 2.2 < 1.9- < 1.4 < 1.5 < 2.0 < 1.3 '
Mn-54 < 2.4 < 2.1 1.6 (1.7) 2.2 (1.8') < 2.3 < 1.4 ' I
.Zn-65 <.6.9 < 5.7 < 5.0 < 3.3 < 6.1 < 3.8 Fe-59 < 6.2 < 5.1 < 3.7: < 3.5 < 5.9' < 3.6 Co-60 < 2.3 < 2.0 < 1.4- 2.1 (1.6) < 2.1 < 1.3 Ba-140 < 5.9 < 3.2 < 2.4 < 2.5 5.1 (5.9) < 2.5 .]
L a-140 -' < 6.8 < 3.7, <.2.8' < 2.3 5.9-(6.8) < 2.9
- j.
- l .96 o (Due to ' Counting' Sta tis tics).
i
e ' l p l Table' II.C.3 Radionuclide Concentrations .in Bi-weekly Compos.ite of Drinking Water. .(pCi/L)= i
- Collection for ts weeks ending for' two weeks ending for two weeks ending j Date: 08/01/90 08/15/90- 08/29/90 '
i Radionnclide Gilcrest Ft Collins Gilcrest Ft Collins Gilcrest Ft Collins . , R-6 R-3 'R-6 , R-3 R-6 R j I-131 <.0.37 < 0.2. < 0.47 < 0.4 0.44 (0.38)* 0.44 (0.48) Cs-134 < 2.2 < 1.4 < 2.7 < 1.4 < 2.1 < 1.4
- 2 Cs-137 < 2.8 < - 1. 6 ' 3.9 (3.7) '2.0 (2.0) 4.0 (3.0) < 1.8- <
Zr-95 < 5.0 .3.4 (3.7)" <.5.6 < 3.3 < 4.7 < 3.0' i Nb-95 < 2.4 < 1.2
< 2.5 < 1.4 < 2.0 < 1.3 i
- C0-58 < 2.1. < 1.3 < 2.5 < 1.3 < 2.0 < 1.3 !
1 r , Mn-54 < 2.5 1.3 (1.6) < 2.2 < 1.4
<'2.0 < 1.4 !
i > f Zn-65 < 7.5 < 3.5 < 7.4 '< 3.9 < 6.1 . < 3.6 Fe-59 ~ < 5.7 .< 3.8 5.8 (7.3) < 4.2 < 5.2 < 3.6 1 i Co-60 '<-2.7 < 1.3
-.<-2.5 < 1.3 < 2.2 < 1.3 j Ba-140 :< 5.4 - < 3.2 < 6.3 < 2.4 < 3.3 < 3.3 La-140 '< 6.2 < 7.2
< 3 .7'- < 2.8 < 3.8 < 3.8 .f:
;I
- l .96 0. (Due to Counting S ta ti's tics) .
i 4 _ _ _
's Table II.C.3 Radionuclide Concentrations in Bi-weekly. Composite of Drinking Water. (pCi/L) l
. Collection for two weeks ending _
for two weeks ending for two weeks ending
- Date 09/12/90 09/26/90- 10/10/90 Radionuclide Gilcrest Ft Collins Gilcrest Ft Collins Gilcrest Ft Collins -
R-6 R-3 R-6 R-3 R-6 R-3 I-131 < 0.4- .< 0.34 < 0.27 < 0.44 < 0.24 < 0.21 Cs-134 < 2.6 < 0.89 < 2.2 < 2.0 < 1.5 < 2.4 Cs-137 4.3 (3.6)* 2.7 (1.3) < 2.6 < 2.5 < 1.9 < 2.8 g; Zr-95 < 5.6 < 2.0 < 5.2 < 4.8 < 3.9 < 5.0 Nb-95 .3.5 (3.7) 1.3 (1.1) < 2.0 2.7 (2.5) < 1.8 < 2.2 Co-58 < 2.4 < 0.8 < 2.2 < 2.0 < 1.6 < 2.5 Mn-54 2.8 (3.1) < 0.91 < 2.2 < 2.0 < 1.6 < 2.3 [ Zn-65 < 9.4 < 2.4 < 6.3 < 5.6 < 4.9 < 7.4 Fe-59 < 6.3 < 2.5 < 4.9 < 5.5 4.9 (5.3) < 6.4 i
.i Co-60 < 2.5 !
< 0.87 2.1 (2.5) < 2.0 < 1.5 3.2 (2.8)
Ba-140 < 4.5 < 2.4 < 3.3 < 3.7 '
< 2.5 < 3.8 La-140 < 5.1 < 2.8 < 3.8 < 4.2
< 2.9 < 4.4
*1.96 e (Due to Counting Sta tis tics) i E
I lable II.C 3 Radionuclide Concentrations in Bi-weekly Conposite of Drinking Water. (pCI/L) l , Collection for two weeks ending for two weeks ending for two weeks ending Date 10/24/90 11/07/90 11/21/90 Radionuclide Gilcrest Ft Collins Gilcrest Ft Collins Gilcrest Ft Collins R-6 R-3 R-6 R-3 R-6 R-3
- I-131 < 0.43 < 0.2 < 0.46 < 0.19 < 0.33 < 9.31 Cs-134 1.6 (1.0)* < 2.2 < 2.0 < 2.8 < 2.3 < 2.0 Cs-137 < 1.9 3.7 (2.9) < 2.4 < 3.2 < 2.9 cn
< 2.5 -
Zr-95 < 3.6 < 4.5 < 4.2 < 5.8 < 5.6 < 4.7 ! t.h-95 1.9 (2.0) < 2.1 < l.8 < 2.3 < 2.3 < l.8 Co-58 1.5 (1.8) < 2.0 < l.8 < 2.5 < 2.1 < I .8 itn-54 < l.6 < 2.1 < l .9 < 2.6 < 2.3 < 2.0 Zn-65 < 5.3 < 6.3' < 5.6 < 7.1 < 6.6 < 5.6 Fe-59 < 3.9 < 5.1 < 5.1- < 6.3 < 5.4
< 4.8 Co-60 < l.3 2.0 (2.2) < 2.6
< l.9 < 2.6 < 1.9 Ba-140 4.0 (4.4) < 5.1 < 3.1 < 4.1 < 3.9 < 3.1 .
La-140 4.6'(5.1) < 5.9 < 3.6 < 4.8 < 4.5 < 3.5 i
- I .96 o (Due to .Coun ting ' Sta tis tics)
i i l Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking 1(ater. (pCf/L) i' I
- Collection for two weeks.ending for two weeks ending Date 12/05/90 12/19/90 T2adionuclide G11 crest Ft Collins Gilcrest Ft Collins R-6 R-3 R-6 R-3 I-131 < 0.5 < 0.39 < 0.49 < 0.13 Cs-134 2.2 (2.3)* < 2.2 < l.0 < 0.88 Cs-137 4.6 (2.7) 4.4 (3.2) 1.6 (1.5) 1.3 (1.3)
O Zr-95 < 4.1 < 5.3 < 2.4 < l.9
!!b-95 < l .7 < 2.1 < 0.95 < 0.82 C0-58 < l.7 < 2.2 < 0.96 < 0.87 fin-54 < l.8 2.4 (2.6) 1.2 (1.3) < 0.88 Zn-65 < 5.4 < 6.1 < 2.8 < 2.5 Fe-59 < 4.9 < 5.0 < 2.7 < 2.0 Co-60 < 1.8 < 2.1 < l.1 < 0.87 Ba-140 < 2.9 < 3.4 < 1. 7 < 1.4 ta-140 < 3.4 < 3.9 < 1.9 < l.6
'I .96 o (Due to Counting Statistics)
l
- 2. Surface Water surface water is collected monthly from five sites. .
-Since the reactor water effluent can be directed to either the St. Vrain Creek or the South Platte River, there are upstream o
and downstream sampling locations on both river courses. ;
$ Table II.C.4 shows tritium concentrations measured during
,' 1990 at the four surface water sites. All of the values were less than MDC. The arithmetic mean value for the downstream t locatiors in 1990 therefore was not significanG y different from the two upstream locations (Table II.H.2) . The EPA lista 300 i-200 pCi/L for tritium measured in surface water samples e from the-South'Platte River at Platteville during January to March 1990. This data is in good agreement with that measured in the REMP-program. Table II.C.5 shows measurements of fission product and activation product concentrations in surf ace' water samplco _t_ collected monthly. There were occasional positive values, but j the mean 'of the downstream sites was - not significantly- LI different from the mean of the upstream sites.during 1990_for + any-- of -- the gamma-ray - emitting , radionuclides measured. - This ' has been the case since the inception of reactor-operations at
-theiFort 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 sample is
- =
48 : 1 _ . ._ .
collected at station A-25. An aliquot of the f arm pond outlet is sampled overy 80 minutos and the composito collected wookly. The weekly compositos are then combined and an61yzed monthly. The results of those samplos are also shown in Tables 11.C.4 and II.C.S. For only January and December v.as there ovidence of measurable tritium release (sco Tablo II.C.4). Mean values for the other radionuclidos woro less than MDC oxcept for Co-137. The correlation of the tritium concentrations with the offluent releano report is high. 49
, ll llll' 1
)
l
- t l )
n i 0 ) 0 e u 6 u g5 4 0 4 l e2 ( 0 0 0 0 0 0 0 0 0 0 ( f s - 0 3 3 2 9 9 0 9 0 0 f oA 0 < 4 4 3 3 4 3 9 0 E o 4 4 3 0 6 < < < < < < < < < < 9 G 1 1 e t t a9 l1 0 0 0 0 0 0 0 0 0 0 0 0 P - 2 3 3 2 0 0 0 9 0 0 9 0 4 4 4 4 4
.F < < < < <
4 4 3 4 4 3 4 s S e t i S m a n e r i
)
a t r1 L s V2 0 0 0 0 0 0 0 : 0 0
/ p - 2 3 3 2 0 0 0
- 0 0 i
U .A ? 0 0 9 0 C 4 4 4 4 4 4 4 3 4 4 3 4 p t < < < < < < < < < < < < ( S r e ) t e s a t c W t i s a0 t e e l1 0 0 0 0 0 0 0 0 0 0 0 s c t P - 2 3 3 2 9 0 0 9 0 0 a 0 9 0 i f r i S .R 4 4 4 4 3 4 4 3 4 4 3 4 t u S a S m t a S n er i t o s s n n n n i o w i t o a i D r0 n t a V2 0 0 0 0 0 0 0 0 0 0 0 0 u r .F
- 2 4
3 4 3 2 0 0 0 9 0 0 9 0 o t 4 4 4 4 4 3 4 4 3 4 C t < < < < < < < < < < < n i < 4 e c o t n n o o r e C. C i y I t y r e r r r u I m c r a b e e D u e a u t m e b b ei l e u r h c 1 e s e b m m ( l t l t n b r i r y n y u g t p o e e c bi oa a e a p l t v c ar a u u u e c o e 6 TT CD J F M A M J J A S O N D 9 I . l 8 l (ll lll ll
1 2 w
'd Table II.C.5 Radionuclide Concentrations In Surface Water. (pC1/L) h
?
Collection Date: 1/13/90 Downstream Sites Upstream Sites Effluent St. Vrain S. Platte St. Vrain S. Platte Goosequill Radio R-10 A-21 F-19 A-25
-nuclide F-20 Cs-134 < 2.0 < 3.0 < 2.3 < 2.6 < 1.2 Cs-137 < 3.1 7.1 (5.3)* < 2.8 < 3.2 < 1.4 .
Zr-95 < 4.7 < 6.7 < 5.4 < 6.4 5.1(3.4) Nb-95 < 1.8 < 2.8 < 2.1 < 2.3 < I.2 e, Co-58 < 2.0 < 2.8 < 2.2 < 2.5 < I.1
~
Mn-54 < 2.0 < 3.0 < 2.3 < 2.6 < 1.1 Zn-65 < 4.8 < 7.1 < 5.4 < 6.2 < 2.8 Fe-59 < 4.6
< 7.0 < 5.2 6.8 (8.0) < 2.8 Co-60 < 2.0 < 3.1 < 2.5 < 2.7 < 1.2 Ba-140 < 4.2 < 4.4 < 3.7 < 6.5 < 3.7 La-140 < 4.8 < 5.0 < 4.2 < 7.5 < 4.3 l
i . 960 (Due to Countin9 Statistics) I
-- - n - s -:
Table II.C.5 Radionuclide Concentrations In Surface Water. (pC1/L)
- Collection Date
- 2/10/90 Downstream Sites Upstream Sites Ef fluent Radio St. Vrain S. Platte St. Vrain S. Platte Goosequill
-nuclide F-20 R-10 A-21 F-19 A-25 ,
! Cs-134 < 2.5 2.0 (2.4) < 1.6 < 2.3 < 1.6 ' Cs-137 4.4 (3.8)* < 2.4 < 1.8 4.5 (4.1) 5.6(2.9) - Zr-95 < 6.0 < 4.4 < 3.5 < 5.3 < 4.2 Nb-95 < 2.4 < 1.9 < 1.6 < 2.3 < 1.5 Co-58 < 2.3 < 1.7 < 1.4 < 2.2 < 1_5 E Mn-54 < 2.6 < 2.0 2.3 {1.8) < 2.3 < 1.7 J Zn-65 < 6.4 < 5.6 < 4.2 < 5.7 < 4.0 Fe-59 < 6.0 < 5.4 < 3.8 < 5.4 < 3.5 Co-60 < 2.7 < 2.0 < 1.5 < 2.4 < 1.7 3 Ba-140 < 4.5 < 3.4 < 2.7 < 3.7 < 2.4 ta-140 < 5.1 < 3.9 < 3.1 < 4.3 < 2.7 J' 1 i i
+1.960 (Due to Counting Statistics) a
. s Table II.C.5 Radionuclide Concentrations In Surface Water. (pCf/L) Collection Date: 3/10/90 Downstream Sites- Upstream Sites E f fluent Radio St. Vrain S. Platte St. Vrain S. Platte Goosequill
-nuclide F-20 R-10 A-21 F-19 A-25 Cs-134 < 2.2 < 2.0 < 1.2 < 2.1 < 2.2 Cs-137 3.2 (3.2)* < 2.9 < 1.6 < 2.6 < 2.6 -
Zr-95 < 5.1 < 4.4 < 2.9 < 5.0 < 5.7 Nb-95 < 2.1 < 1.8 3.5 (1.5) < I.9 < 2.0 Co-58 < 2.0 < 1.9 < 1.2 < I .9 < 2.0 m Mn-54 < 2.2 < 1.9 1.4 (1.6) 2.4 (2.5) < 2.2 Zn-65 < 5.1 < 4.8 7.7 (4.0) < 5.0 < 5.8 Fe-59 < 5.1 < 4.5 < 3.7 < 5.1 < 5.0 Co-60 < 2.4 < 2.0 < 1.2 < 2.3 < 2.2 Ba-140 4.2 (4.5) < 2.8 < 2.3 < 3.4 4 3.4 La-140 4.8 (5.2) < 3.3 < 2.6 < 3.9 < 3.9
*l.96e (Due to Counting Statistics)
x Table II.C.5 Radionuclide Concentrations In Surface Water. (pCf/L) Collection Date: 4/14/90 Downstream Sites Upstream Sites Effluent Radio St. Vrain S. Platte St. Vrain S. Platte Gooseguill
-nuclide F-20 R-10 A-21 F-19 A-25 Cs-134 < 2.1 < l.3 < l.5 < l.5 < 1.8 2.1 (1.8)* 1.9 (2.2) 2.7 (2.2) < 2.1 Cs-137 < 2.6 cn Zr-95 < 4.5 < 2.7 < 3.3 4.3 (4.2) < 3.7 Nb-95 < 2.2 < I.2 < l.6 < l.4 < 1.5 Co-58 < 2.0 < 1.1 < l.4 < 1. 4 < l .9 Mn-54 < 2.2 < 1.3 < l.5 < l.5 < l.7 Zn-65 < 6.5 < 3.4 < 4.6 < 4.1 < 4.7 Fe-59 < 5.5 < 2.8 < 3.8 < 3.5 < 5.0 C0-60 < 2.1 < l.2 < l.5 < l .6 < I.7 Ba-140 < 4.1 < 2.0 < 3.0 < 2.4 < 2.8 La-140 < 4.8 < 2.3 < 3.5 < 2.8 < 3.2 l *l.96o (Due to Countin9 Statistics)
Table II.C.5 Radionuclide Concentrations In Surface Water. (pCf/L) Collection Date: 5/12/90 Downstream Sites Upstream Sites E f fluent Radio St. Vrain S. Platte St. Vrain S. Platte Goosequill
.nuclide F-20 R-10 A-21 F-19 A-25 Cs-134 < 2.5 < l.3 < 2.4 < 2.2 <2.1 Cs-137 < 3.1 < I.6 < 2.9 < 2.5 <2.6 -
- Zr-95 < 5.9 < 2.9 < 5.7 < 4.7 <5.4 Nb-95 < 2.2 < 1.2 < 2.2 < 2.1 <2.2 00-58 < 2.3 < l.2 < 2.2 < 2.0 <l.9 Mn-54 < 2.5 < I.3 < 2.4 < 2.1 <2.2 Zn-65 < 6.8 < 3.4 < 6.4 < 6.2 <5.6
- Fe-59 < 5.9 < 3.3 < 5.6 < 4.9 <5.0 Co-60 < 2.8 < 1.3 < 2.6 < 2.1 <2.1 Ba-140 < 4.2 < 2.4 < 3.8 < 3.4 <3.4
! La-140 < 4.8 < 2.7 < 4.4 < 3.9 43.9
*l.96o (Due to Counting Statistics) 1 4
~ ~
-n __ _________._--.----_____.1
2 Table II.C.5 Radionuclide Concentrations In Surface Water. (pCi/L) Collection Date: 6/09/90 Downstream Sites Upstream Sites Effluent St. Vrain S. Platte Goosequill Radio St. Vrain S. Platte A-25
-nuclide F-20 R-10 A-21 F-19 Cs-134 < 2.0 < 3.0 < 3.2 2.1 (2.4) < l.2 2"
Cs-137 < 2.3 < 3.6 4.7 (4.9) 3.8 (3.0) 1.8 (1.8) l
< 4.1 < 6. 3 < 7.6 < 4.6 < 3.5 i
Zr-95 Nb-95 < l.7 < 2.7 < 3.0 < 1.9 < I.2 C0-58 < 1.9 < 2.9 < 3.1 2.4 (2.3) < I.4 Mn-54 < 1.9 < 2.8 < 3.4 < 2.0 < I.2
< 5.1 < B.3 < 8.9 < 5.7 < 3.9 Zn-65 Fe-59 < 5.1 < 6.8 < 7.7 < 4.9 7.3 (5.4)
Co-60 < 2.1 3.4 (3.5) < 3.6 < 2.0 < I.2
< 3.3 < 5.6 < 6.4 < 3.3 < 2.0 Ba-140
< 3.8 < 6.4 < 7.4 < 3.8 < 2.3 La-140 l
t
*1.96o (Due to Counting Statistics)
a. Table II.C.5 Radionuclide Concentrations In Surface Water. (pCi/L) Collection Date: 7/14/90 i Downstream Sites Upstream Sites Effluent Radio St. Vrain S. Platte St. Vrain S. Platte Goosequill
-nuclide F-20 R-10 A-21 F-19 A-25 Cs-134- < 2.3 < 2.0 "
< 2.2 < 2.0 < l.4 Cs-137 3.3 ( 3.4)* 4.2 (2.9) 2.9 (3.2) < 2.3 < I .7 m
'Zr-95 < 5.5 5.2 (5.3) < 5.3 < 4.2 4.2 (4.2) im-95 < 2.1 < 1.8 < 2.0 < l.9 1.8 (1.8)
Co-58 < 2.1 < l.9 2.7 (2.5) < I .8 < I .5 fin-54 < 2.3 < 2.0 < 2.2 < 1.9 < 1.4 Zn-65. < 6.5 < 5.7 < 6.1 < 5.3 < 3.7 Fe-59 < 5.6 < 4.6 < 5.1 < 4.5 4.5 (5.5) 00-60 < 2.6 < 2.1 < 2.4 < l .9 < l.3 Ba-140 < 3.8 < 3.2 < 4.0 < 3.4 < 2.4 La-140 < 4.4 < 3.7 < 4.6 < 3.9 < 2. 7
*1.96o (Due to Counting Sta tistics)
i . 3. l j l Table II.C.5 Radionuclide Concentrations In Surface Water. (pCi/L) i Collection Date: 8/11/90 Downstream Sites Upstream Sites Effluent Radio St. Vrain S. Platte St. Vrain S. Platte Goosequill
-nuclide F-20 R-10 A-21 F-19 A-25 i
Cs-134 < 2.4 < 2.0 < 2.4 < 2.2 < 1.2 ! Cs-137 < 2.9 4.6 (3.0)* < 2.9 < 2.7 < 1.5
'Zr-95 < 5.7 < 4.5 < 5.7 < 4.5 < 2.7 4
Nb-95 < 2.2 < 2.0 < 2.2 3.4 (2.7) < 1.2 Co-58 < 2.2 < 1.9 < 2.2 < 2.0 < 1.1 Mn-54 2.5 (2.8) < 2.0 < 2.4 2.5 (2.7) 1.7 (1.5) y, 2n-65 < 6.5 < 5. 7 - < 6.9 < 6.7 < 3.6 m Fe-59 < 5.8 < 4.7
< 5.5 < 5.5 < 3.2 l
4 Co-60 < 2.5 < 2.0 < 2.6 < 2.3 1.3 (1.4) Ba-140 7.0 (5.3) < 3.8 < 4.3 < 4.5 < 2.1 La-140 8.1 (6.1) < 4.3 < 4.9 < 5.2 < 2.4 l
*1.96c (Due to Counting Statistics)
z Table II.C.5 Radionuclide Concentrations In Surface Water. (pCi/L) Collection Date: 9/08/90 Downstream Sites Upstream Sites Effluent Radio St. Vrain 5. Platte St. Vrain S. Platte Goosequill
-nuclide F-20 R-10 A-21 F-19 A-25
< 3.4 l Cs-134 < 1.4 < 2.1 < 2.3 1.4 (1.7)
Cs-137 3.1 (2.1) < 2.6 < 2.5 < 1.8 < 4.2 Zr-95 < 3.2 < 5.1 < 4.7 < 3.1 < 8.0 ; Nb-95 2.1 (1.8) < 2.1 < 2.0 < 1.5 < 3.2 Co-58 1.3 (1.6) < 1.9 < 2.1 < 1.3 < 3.8 l Mn-54 < 1.4 < 2.2 < 2.2 < 1.4 < 3.5 c, Zn-65 < 4.3 < 6.9 < 5.5 < 4.6 < 9.0 u) Fe-59 < 3.4 < 6.0 < 5.5 < 3.8 < 11.0 Co-60 < 1.4 < 2.4 < 2.1 < 1.4 < 3.8 Ba-140 < 2.5 < 4.7 7.2 (5.6) 3.5 (3.6) < 5.7 La-140 < 2.8 < 5.4 8.3 (6.5) 4.0 (4.1) < 6.5
+1.96c (Due to Counting Statistics)
l A 'l Table II.C.5 Radionuclide Concentrations In Surface Water. (pCi/L) I Collection Date: 10/13/90 1 Downstream Sites Upstream Sites Effluent , Radio St. Vrain S. Platte St. Vrain S. Platte Goosequill
-nuclide F-20 R-10 A-21 F-19 A-25
- Cs-134 < 3.5 c 3.3 < 2.3 < 2.0 < 2.4 Cs-137 <42 '
< 3.9 < 2.6 < 2.6 3.0 (3.2)* l Zr-95 < 7.6 < 7.7 < 5.0 4.8 (5.8) < 4.9 <
Nb-95 < 3.2 < 2.9 < 2.0 3.5 (2.6) < 2.3 Co-58 < 3.2 < 3.0 < 2.1 < 1.9 < 2.1 Mn-54 < 3.5 < 3.3- < 2.2 < 2.0 < 2.2 m Zn-65 < 10.0 < 8.9 < 6.2- < 6.3 < 7.0 o Fe-59 < 9.0 < 8.4 7.0 (6.7) < 5.6 < 6.7 Co-60 3.4 (4.0) < 3.6 < 2.2 2.5 (2.3) < 2.1 Ba-140 < 5.3 8.8 (8.6) < 4.9 < 3.5 < 4.0 La-140 < 6.1 10.0 (9.9) < 5.7 < 4.0 < 4.7
*1.96c'(Due to Counting Statistics) 1 4
4
, .~ m _ . .
Table II.C.5 Radionuclide Concentrations Ir Surface Water. (pCf/L) Collection Date: 11/10/90 Downstream Sites Upstream Sites Ef fluent t Radio St. Vrain S. Platte St. Vrain 5. Platte Goosequill
-nuclide F-20 R-10 A-21 F -19 A-25 Cs-134 < 2.4 < 1.2 < 2.8 < 1.5 3.6 (2.7)
Cs-137 < 2.9 < 1.5 3.9 (4.1)* 3.9 (2.1) < 2.7 Zr-95 < 5.9 < 2.9 < 6.5 < 3.4 < 5.2 Nb-95 < 2.2 < 1.2 < 2.6 < 1.3 < 2.0 Co-58 < 2.4 < 1.2 < 2.9 < 1.3 < 2.2 Mn-54 < 2.4 < 1.2 < 2.8 3.4 (I.8) < 2.3 cn
~
Zn-65 < 6.8 < 3.5 < 7.3 < 4.0 < 6.2 Fe-59 < 6.7 < 2.9 < 7.7 5.5 (4.5) < 5.2 Co-60 < 2.2 < 1.2 < 3.0 < 1.6 < 2.4 Ba-140 < 3.7 < 1.9 < 4.6 < 2.4 < 6.5 La-140 < 4.3
< 2.2 < 5.3 < 2.8 < 7.5 i
*I.96c (Due to Counting Statistics) i
-_ - -_-_ ____ __-.='-
l Table II.C 5 Radionuclide Concentrations In Surface Water. (pCi/L) 1 l Collection Date: 12/08/90 Downstream Sites Upstream Sits- Ef fluent Rad 6 St. Vrain S. Platte St. Vrain S. Platte Goosequill
-nuclide F-20 R-10 A-21 F-19 A-25 Cs-134 < 3.0 < 2.6 < 2.6 < 2.6 < 2.1 i
Cs-137 < 3.7 < 3.1 4.5 (3.8)* 6.5 (3.8) 2.5 (3.0) 4 Zr-95 < 7.6 < 5.9 < 6.3 < 5.9 < 4.5 Nb-95 < 3.0 < 2.5 < 2.4 < 2.9 < I.9
- Co-58 3.8 (3.6) < 2.3 < 2.6 < 2.6 < 1.9 Mn-54 < 3.0 < 2.6 < 2.6 < 2.6 < 2.1 j , Zn-65 < 8.8 < 6.9 < 7.0 < 9.0 < 5.8 '
! ro Fe-59 < 6.9 < 5.9 < 6.9 < 6.1 < 4.8 Co-60 < 3.2 < 2.8 < 2.6 < 2.6 < 2.0 i Ba-140 < 7.8 < 4.1 < 4.1 < 6.6 < 3.3 1 La-140 < 8.9 < 4.8 < 4.7 < 7.6 < 3.8 d i
'1.96c (Due to Counting Statistics) i i
l 1
- 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 reactor down the hydrological gradient, and at R-5, a voll at a persona 3 rouldence in the town of Millikon. Tablo II.C.6 lists the measured concentrations of flosion products and activation products in ground water. The Cs-137 results are not surprising due to residuo of Chernobyl fallout, and the other results abovo HDC are assumed to be statistically falso positivo values. Table II.C.7 shows tritium concentrations in the samo well water samples. The results indicato short-lived contamination of the aquifer supplying F-16 well. This well is not used for drinking water purposes and thereforo dono commitment calculations are not warranted. Figuro II.C.1 shows monsured tritium concentrations in the F-16 well since 1984. To' test the mean life time of tritium in the aquifer we have initiated weekly sampling of this site boginning early in 1991. 63
Table II.C.6 Radionuclide Concentrations in Ground Water. (pCf/L) Ist 2nd 3rd 4th Guarter 03/29 Quarter 05/26 Quarter 08/18 Quarter 11/17 Radio- R-5 nuclide F-16 R-5 F-16 R-5 F-16 R-5 F-16
< 2.4 < 2.7 < 1.6 < 2.6 < 2.3 < 1.8 < 1.4 < 1.2 Cs-134 Cs-137 5.9 (3.5)* 17.0 (4.0) 5.6 (2.4) 3.5 (3.8) 3.0 (3.4) 7.9 (2.6) < 1.7 2.0 (1.7)
Zr-95 < 5.4 < 6.0 < 3.7 < 6.2 < 5.1 < 4.0 < 3.2 < 2.5 Nb-95 < 2.5 '7.3 (4.0) < 2.0 < 2.6 2.5 (2.8) 4.8 (2.8) < 1.3 < 1.1 j Co-58 2.9 (2.7) < 2.5 < 1.5 < 2.3 < 2.1 < I.7 < 1.3 < 1.0 Mn-54 < 2.4 5.9 (3.3) 2.0 (2.1) 2.7 (3.1) < 2.3 < I.9 1.4 (1.6) < I.1 Zn-65 < 8.7 < 13.0 < 6.7 < 8.2 < 7.6 < 9.1 < 3.8 < 3.4 I Fe-59 < 5.7 " 6.2 < 4.2 < 6.4 < 5.9 < 4.3 < 3.4 < 2.7 f l Co-60 < 2.4 3.5 (3.1) 1.8 (1.8) 5.1 (3.2) < 2.1 2.0 (2.0) < 1.5 2.7 (1.3) } i Ba-140 < 4.2 10.0 (5.5) < 3.6 < 4.2 < 4.3 7.9 (4.2) < 3.0 < I.8 La-140 < 4.9 12.0 (6.4) < 4.1 < 4.8 < 4.9 9.0 (4.9) < 3.4 < 2.1
+1.96o (Due to Counting Statistics)
jIiif 7 1 0 r/ 5 0 e1 t
- 4 t1 I <
r a: ud Qet ) 0 hc 0 t e 6 4 rl 1 ( ul - 0 oo F 0 4 fC 3 1 8 0 L 1 5 9 / r/ - 3 i e8 t I < C t P r: ad ue ) Qt 0 c 5 0 de 6 4 9 rl 1 ( 9 il - 0 1 h o T 0 T C 3 r 1 t e a 6 0 W r2 e/ 5 9 3 d t5 1 1 < n r ) u a: s o ud fo r Qet 7 s G 0 it d c a n ne 6 2 4 t i ol 1
- ( s cl n eo T 0 g m SC 0 n i 8 i t
t n i u r 9 0 o T Z 5 3 4 c r/ -
< 0 e3 1 1
1 7 t r: e ad o C. ue ) t I Qt ( I c 0 t c 6 3 o l e sI rI 1
- 4 G b i o F < 9 a FC 1 T
- w llll fI l
Figure ll.C.1 "ritium Concentrations at Location 6 For 1984-1990 5 4 - d s'" U 34 C C 3 - 3 Ci 5F4 v - C 6 1 - p-e a
/ \ l- /
w' N._._.-
~._._._._.
"s._ _ .- m ~ . - /
0 1984 1985 1986 1987 1988 1989 1990 Year 66
i Table II.C 8 P.aximua Permissible Concentrations in Drinking Water. (10CFR20, Appendix B, Table II) 11 - 3 3'x 106 pCi/L i I-131 2 3 x 10 pCi/L I Cs-134 3 9 x 10 pCi/L Cs-137 2 x 10' pCi/L e Ir-95 6 x 10 pCi/L r Nb-95 1 x 10~ pCi/L Co-58 1 x 10 pCi/L 5 Hn-54 1 x 10 pCi/L 5 Zn-55 1 x 10 pCi/L Fe-59 6 x 10 pCi/L Co-60 4 5 x 10 pCi/L 4 Ba-140 3 x 10 pCi/L 4 La-140 2 x 10 pCi/L 4 5 4
II.D. Milk The dairy food chain is the critical pathway for possible radiation dose commitment around any nuclear facility. This is true for both chronic and acute releases. The critical individual would be an inf ant consuming milk produced from cows grazing local pastures. Milk is the critical pathway for possible dose commitment to humans from environmental contamination of H-3, I-131, Co-137 and Sr-90. For this reason milk is sampled extensively to document the prosence or absence of radioactivity due to reactor operations. A three liter milk sample is counted for determination of Cs-137, Co-134 and Ba-La-140. To measure I-131 at the required LLD of 1.0 pCi/L, an 18 liter sample is concentrated by anion exchange and the resin counted by gamma-ray spectroscopy. The method of treating the milk is modified from that of McCurdy and Hellor, Health Physics 38: 203-213, 1980. There are no dairios (or personal milk cows) in the f acility area,1.6 km radius. The six dairies in the adjacent area, 1.6-8 km' radius, were selected as they are located in the highest X/Q areas (refor to updated FSAR). The description of these locations can be found in Tablo III.B.1 and Figure III .B.2. The single reference location dairy, R-8, is 22.5 km West of the reactor in the least predominant wind direction. Herd management practices are virtually identical at all dairy locations. The cows in the milking herd are never on pasture but under dry-lot management typical of Eastern Colorado. b 68
l l Table II.D.1 lists the concentrations of all radionuclidos that are invostigated in milk samples. During 1990, olevated concentrations of I-131 were again consistently ) l observed only at site A-22. The source of this I-131 is from nuclear modicino thyroid therapy practice in the Denvor hospitals. The releases enter the S. Platte River just North of Denver. A-22 dairy uses irrigation ditch water for its herd during the summer and fall rather than well water. The ditch (Independenco) receives S. Platte water upstream of FSV. This observation was first made in 1985 and discussed at length in the 1985 REMP summary report. A manuscript describing this observation and the magnitude of the I-131 concentrations has boon submitted for publication in the Health Physics Journal. Note that A-22 drops out of the sampling program each November, December and January in order to meet milk collection system quotas. K-natural, 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 contro13od and independent of K intake. K-nat is measured in all milk samplos as a quality control measure for the other radionuclidos determined in the same sample by gamma-ray spectrometry, but K-nat concentrations are no longer reported in Table II.D.1. Table II.D.2 lists measured tritium concentrations in milk. Significant elevated tritium concentrations in milk due to reactor effluents have never been observed during the operational or defueling phase of the reactor. This implies l l l 69
the tritium from reactor offluents is not contributing any 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. Contamination of milk samples by any radionuclide due to reactor of fluents has never boon observed during the operational or defueling phases of Fort St. Vrain. 70
Table II.D.1 Radionuclide Concentrations In Milk. (pCi/L). L LOCATION A-6 A-18 A-22 A-23 A-24 A-26 R-8 Collection Datt 1/06/90' 1/13/90 1/13/90 1/13/90 1/06/90 1/13/90 1/20/90
~
I-131 < 0.19 < 0.41 < 0.32 < 0.3 < 0.38 < 0.42 < 0.31 Cs-134 < 3.8 < 3.3 .
< 3.5 < 2.3 < 4.1 < 2.6 < 2.5 Cs-137 < 5.6 < 4.9 < 4.5 < 3.5 < 5.0 3.4 (3.77 < 3.0 i
Ba-140 < 5.5 6.7 (8.0) < 5.8 < 4.5 7.9 (8.5) < 4.1 < 4.7 La-140 < 6.3 7.7 (9.1) < 6.7 < 5.2 9.0 (9.8) < 4.8 < 5.4 Collection Date 2/24/90 2/03/90 2/03/90 2/03/90 2/24/90 2/16/90 2/17/90
~.--
131 < 0.2 < 0.27 < 0.44 < 0.35 < 0.2.4 < 0.31 0.36 (0.37) Cs-134 2.9 (2.8) < 2.4 < 3.8 < 2.7 < 1.6 < 1.4 < 1.5 Cs-137 < 2.9 3.5 (3.3) 5.6 (5.6) < 2.9 < 1.8 2.6 (1.9) < 1. 7 Ba-140 < 3.7 < 4.9 < 6.1 < 5.0 < 2.8 < 2.7 < 2.5 La-140 < 4.3 < 5.6 < 7.0 < 5.7 < 3.2 < 3.1 < 2.9 Collection Date 3/17/90 3/10/90 3/03/90 3/03/90 3/31/90 3/17/90 3/24/90 1-131 < 0.22 < 0.19 < 0.23 < 0.2 < 0.21 < 0.27 < 0.21 Cs-134 < 2.6 < 2.5 < 2.5 < 2.7 < 2.1 < 1.4 < 2.6 Cs-137 < 3.0 3.9 (4.4) < 3.7 < 3.3 < 2.5 < 1.6 < 3.1 Ba-140 < 4.5 < 3.9 < 2.9 < 4.3 < 3.9 < 2.1 < 4.7 La-140 < 5.2 < 4.5 < 4.5 < 5.0 < 4.4 < 2.5 < 5.4
- 1.96o (Due to Counting Statistics.)
(pCi/L). Table II.D.1 Radionuclide Concentrations In Milk. A-22 A-23 A-24 A-26 R-8 LOCATION A-6 A-18 4/07/90 4/07/90 4/07/90 4/28/90 4/14/90 4/14/90 Collection Date 4/21/90
< 0.19 < 0.3 < 0.2 < 0.34 < 0.38 I-131 < 0.21 < 0.24
< 2.1 3.2 (2.8) < 3.8 < 2.6 < t.9 < 1.8 Cs-134 < 2.4
< 2.8 < 2.5 3.9 (3.2) < 4.6 4.6 (3.8) < 2.3 3.7 (3.1)
Cs-137
< 4.3 12.0 (9.1) < 4.2 < 3.0 < 2.5 Ba-140 <3.5 < 4.0
< 4.4 < 4.5 < 4.9 14.0 (10.0) < 4.8 < 3.5 < 2.9 La-140 5/05/90 5/05/90 5/05/90 5/12/90 5/12/03 5/05/90 g Collection Date 5/12/90
< 0.21 1.3 (0.52) < 0.41 < 0.23 0.59 (0.55) < 1.7 I-131 < 0.26
< 2.5 < 3.8 < 3.6 < 1.7 < 4.0 < 3.0 Cs-134 < 1.5
< 3.9 < 5.3 < 4.4 < 1.9 < 4.B < 3.2 Cs-137 < 1.8 5.2 (5.1) < 5.0 < 6.3 < 3.2 < 6.3 < 4.6 Ba-140 3.7 (3.2) 6.0 (5.8) < 5.8 < 7.3 < 3.7 < 7.3 < 5.3 La-340 4.2 (3.7) 5/19/90 5/19/90 5/19/90 5/26/90 5/26/90 5/19/90 Collection Date 5/26/90
< 0.33 2.9 (0.49) 0.73 (0.57) < 0.33 < 0.41 < 0.31 1-131 < 0.64
< 1.8 < 2.4 < 3.0 < 2.6 < 1.7 < 2.4 Cs-134 < 2.5
< 3.6 < 2.1 5.0 (4.2) < 4.6 < 3.1 < 2.0 < 2.9 Cs-137 Ba-140 < 3.7 < 2.9 < 3.4 < 5.0 < 4.7 < Z.6 < 3.7
< 5.5 < 3.0 < 4.3
< 4.3 < 3.3 < 3.9 < 5.8 La-140
- 1.96c (Due to Counting Statistics.)
Table II.D.1 Radionuclide Concentrations In Milk. (pCf/L). LOCATION A-6 A-18 A-22 A-23 A-24 A-26 R-8 Collection Date 6/16/90 6/02/90 6/02/90 6/02/90 6/09/90 6/09/90 6/02/90 I-131 < 0.21 < 0.21 < 0.35 < 0.41 < 0.5 < 0.32 < 0.27 i Cs-134 < 2.6 < 2.8 < 3.3 2.7 (3,3)* < 1.6 < 2.4 < 2.6
- Cs-137 < 3.0 < 3.4 5.5'(4.5) < 3.1 < 2.0 < 2.8 <38 Ba-140 < 4.2 < 4.4 < 5.0 < 4.2 .
< 2.9 < 4.2 < 3.8 i La-140 < 4.9 < 5.1 < 5.7 < 4.8 < 3.3 < 4.8 < 4.4 g Collection Date 6/30/90 6/16/90 6/16/90 6/16/90 6/23/90 6/23/90 6/16/90 j I-131 < 0.5 < 0.32 2.5 (0.32) < 0.18 < 0.17 < 0.28 < 0.24 Cs-134 < 1.9 < 2.8 < 2.7 < 2.0 < 2.1 < 1.6 < 2.3 Cs-137 < 2.3 < 3.4 < 3.2 2.4 (2.7) < 2.5 < 2.0 5.3 (4.0)
Ba-140 < 2.9 7.7 (6.1) < 4.3 < 3.4 < 4.1 4.6 (3.5) < 3.3 La-140 < 3.4 8.9 (7.0) < 5.0 < 3.9 < 4.8 5.3 (4.0) < 3.8 Collection Date 7/14/90 7/07/90 7/07/90 7/07/90 7/14/90 7/14/90 7/07/90 1-131 < 0.31 < 0.49 6.5 (0.63) 0.4 (0.46) < 0<43 < 0.22 < 0.24 Cs-134 < 1.7 < 3.2 < 2.0 < 2.3 < 2.6 < 1.7 < 1.7 Cs-137 < 2.0 < 3.4 2.8 (3.1) < 3.4 < 2.9 < 1.9 < 2.0 Ba-140 < 2.6 5.9 (6.0) 6.2 (5.2) < 4.1 < 4.2 < 2.6 < 3.1 La-14G < 3.0 6.8 (6.0) 7.2 (6.0) < 4.7 < 4.9 < 3.0 < 3.5
- 1.96 0 (Due to Counting Sta tistics.)
Table II.D.1 Radionuclide Concentrations In Milk. (pCi/L). A-6 A-18 A-22 A-23 A-24 A-26 R-3 LOCATION - Collection Date 7/28/90 7/21/90 7/21/90 7/21/90 7/28/9G 7/28/90 7/21/90 I-131 < 0.2 < 0.2 7.3 (0.7)* 0.31 (0.37) < 0.3 < 0.19 - < 0.36 Cs-134 < 2.2 < 2.4 < 2.3 < 2.5 < 3.2 < 2.5 3.5 (3.6) Cs-137 1.2 (3.8)' s 3.4 < 3.3 < 3.0 < 3.7 < 3.0 6.2 (4.4) Ba-!40 3.9 (3.9) < 3.4 < 4.0 < 4.0 < 4.8 < 3.9 < 4.8 La-140 1.5 (4.5) < 4.0 < 4.6 < 4.6 < 5.5 < 4.5 < 5.5 Collection Date 8/11/90 8/04/90 8/04/90 8/04/90 8/11/90 8/11/90 S/04/90
- l 1131 < 0.18 < 0.29 15.0 (0.53) < 0.41 < 0.19 < 0.2 0.29 (0.33)
Cs-134 < 1.5 < 3.0 < 2.5 < 1. 7 < 3.2 < I.5 < 3.7 Cs-137 < 1.7 < 3.2 3.8 (3.4) 5.1 (2.4) < 3.6 < 1.8 5.4 (5.4) Ba-140 5.6 (3.3) < 5.1 < 5.1 < 3.3 < 5.1 < 3.1 11.0 (9.2) h-140 7.6 (3.8) < 5.8 < 5.9 < 3.8 < 5.8 < 3.6 13.0 (11.0) Collection Date 8/25/90 8/18/90 8/18/90 8/18/90 8/25/90 8/25/90 8/18/90 I-131 < 0.33 < 0.45 5.5 (0.71) < 0.42 < 0.23 < 0.2 < 0.35 Cs-134 < 3.9 < 2.3 < 3.0 < 3.4 < 1.6 2.8 (2.3) < 2.5 Cs-137 < 4.7 < 3.4 < 4.5 < 3.9 1.9 (2.2) < 2.9 < 3.1 8a-140 < 6.1 < 3.4 < 6.0 < 5.2 4.2 (3.6) 5.4 (4.3) < 4.0 La-140 < 7.1 < 3.9 < 6.8 < 6.0 4.9 (4.1) 6.2 (4.9) < 4.6
- 1.96 c (Due to Counting Statistics.)
Table II.D.1 Radionuclide Concentrations in MI'k.. (pCf/L). A-6 A-18 A-22 A-23 A-24 A-26 R-8 LOCATION Collection Date 9/08/90 9/01/90 9/01/90 9/01/90 9/08/90 9/08/90 9/01/90
< 0.23 < 0.27 1.1 (0.62) * < 0.19 < 0.19 < 0.37 < 0.4 i-131
< 2.8 < 2.6 < 1.8 < 0.86 < 1.8 < 2.7 < 2.7 Cs-134
< 3.5 < 3.0 < 2.1 1.6 (1.2) 2.4 (2.4) 7.1 (4.8) < 2.8 Cs-137
< 5.1
~
< 4.9 7.0 (4.1) < 1.3 < 2.7 < 6.5 < 5.6 Ba-140
< 5.9 < 5.6 8.1 (4.8) < 1.5 < 3.1 < 7.4 < 6.5 La-140 Collection Date 9/22/90 9/15/90 9/15/90 9/15/90 9/22/90 9/22/90 9/22/90 a m
w
< 0.37 < 0.5 1.9 (0.62) < 0.29 0.64 (0.45) < 0.11 < 0.21 I-131 Cs-134 < 2.5 < 1.8 < 2. 7 < 1.7 < 1.8 < 2.5 < 2.7 Cs-137 < 3.2 < 2.1 < 3.3 2.1 (2.4) < 2.0 4.2 (3.6) < 3.2 Ba-140 < 4.9 4.4 (3.8) < 5.4 < 2.7 < 2.9 < 4.0 < 5.0 La-140 < 5.6 5.1 (4.4) < 6.2 < 3.1 < 3.3 < 4.6 < 5.7 Collection Date 10/06/90 9/29/90 9/29/90 9/29/90 10/06/90 10/13/90 10/06/90 1131 < 0.31 < 0.21 7.6 (0.51) < 0.38 < 0.27 < 0.25 0.3 (0.27)
Cs-134 < 2.7 < 1.4 < 1.7 < 2.1 < 1.9 < 1.8 < 2.8 Cs-137 < 3.5 4.3 (2.1) < 2.2 < 2.5 3.5 (2.7) 2.7 (2.6) < 3.4 Ba-140 < 6.2 < 3.1 < 2.9 < 3.3 < 3.8 < 3.9 < 5.3 La-140 < 7.1 < 3.6 < 3.4 < 3.8 < 4.3 < 4.5 < 6.0
- 1.96o (Due ' to Counting Sta tistics.)
um Table II.D.1 Radionuclide Concentrations In Milk. (pCi/L). l A-22 A-23 A-24 A-26 R-8 10 CAT 10N A-6 A-18 h 11/10/90 11/10/90 11/10/90 11/03/90 Collection Date 11/03/90 11/03/90
< 0.2 < 0.29 < 0.49 < 0.17- < 0.43 I-131 < 0.25 h
< 2.5 h < 2. 3 < 3.9 < 2.3 < 3.6 Cs-134 < 2.2 4.1 (3.4)* < 4.8 < 2. 7 c 4.4 )
Cs-137 < 2.7 < 3.0 h
< 3.5 < 5.3 h < 3.8 11.0 (10.0) < 3.6 10.0 (8.8)
Ba-140 r
< 4.0 < 6.1 h < 4.4 13.0 (12.0) < 4.1 12.0 (10.0)
! b-140 l 12/01/90 h 12/01/90 12/08/90 12/08/90 12/01/90 , Collection Date 12/08/90
< 0.49 < 0.32 h < 0.32 < 0.4 < 0.47 < 0.33 I-131
$ < 3.5 h < 2.4 < 2.8 < 3.0 < 4.2 Cs-134 < 2.5
< 3.1 6.8 (6.0) h < 3.5 < 4.1 < 3.6 < 5.0 i Cs-137 l
< 4.1 < 5.0 h < 6.0 < 4.0 < 4.8 < 6.7 Ba-140
< 5.8 < 6.9 < 4.7 < 5.5 < 7.7 La-140 < 4.7 h
- 1.96o(Due to Countin9 Sta tis tics. )
h - sample not collected (at dairy owner's request)-
Table II.D.2 Tritium Concentrations in Milk. (pCi/L) Adjacent Sites Reference Collection A-24 A-26 R-8 Date A-6 A-18 A-22 A-23
< 420 < 420 < 420 < 420 < 420 < 420 JAN < 420
< 420 < 420 < 420 < 420 d < 420 FEB < 420
< 430 < 430 < 420 550(440)* < 420 < 430 480(440)
MAR l
< 420 < 420 < 420 < 420 < 420 < 420 APR < 420
< 400 < 400 < 400 < 400 < 400 < 400
% MAY < 400 w
< 420 < 420 < 420 < 390 < 390 < 420 MAY < 390
< 400 < 390 < 390 < 390 < 400 < 400 < 390 JUN
< 400 < 400 < 390 < 400 < 400 < 400 < 400 JUN
< 400 < 390 < 390 < 390 < 400 < 400 < 390 JUL
< 390 < 390 r
JUL < 390 < 390 < 390 < 390 < 390
< 390 < 390 < 390 < 390 < 390 < 390 < 390 l AUG
< 390 < 390 < 390 < 390 < 390 < 390 < 390 AUG
< 390 < 390 < 390 < 390 < 390 < 390 < 390 SEP SEP < 390 < 390 < 390 < 390 < 390 < 390 < 390
- 1.96o (Due to Counting Statistics.)
d - sample lost during analysis __ d d
Table II.D.2 Tritium Concentrations in Milk. (pCf/L) d). Fourth Quarter, 1990 Adjacent Sites Reference Collection Date A-6 A-18 A-22 A-23 A-24 A-26 R-8 OCT < 400 < 400 < 400 < 400 < 400 < 400 < 400 NOV < 35'O < 390 h < 390 < 390 < 390 < 390 DEC < 400 < 390 h < 390 < 400 < 400 < 390 1 l l h - sample not collected (at dairy owner's request)
l l II.E. Food Products Food sampling locations were selected from areas possibly irrigated by surf ace water downstream of the FSV discharge point or by well water from the aquifer most likely to be contaminated by scopage from the farm pond. The locations of these food product collection sites are described in Table III.B.1. One sample of each principal class of food products was collected from these locations. Locations and available produce of ten change due to owner needs, harvest time, harvest size, etc. Each sample is homogenized without drying immediately after collection. The sample is then counted by gamma-ray spectroscopy. Table II.E.1 lists the date of collection and the results for the 1990 harvest. Three of the food samples showed detectable Cs-137 from past Chernobyl fallout deposition and the one result with positive I-131 is assumed to be a falso positive, or due to activity released into the S. Platte river from Denver hospitals. It is not possible to determine the actual source, but in any case it could not be due to Fort St. Vrain effluents. I-131 was never observed in any - ef fluent pathway during the operational phase of the reactor and due to decay there was no I-131 in the core inventory at the sample collection time. The gamma-ray spectra were scanned for other radionuclides, but only the naturally occurring were obeerved, presumably due to surface soil deposits. t 79
1
- i
{ Table ll.E.1 Radionuclide Concentrations in Food Products (pCi/kg) l i Collection Date 07 SEP 90 !
-Location Food Type 1-131 Cs-134 Cs-137 R-6 Mellons <7.9 <8.1 <12 A-27 Corn 17(13)* <9.5 <14 R-6 Potatoes <9.8 <7.9 <11 R-6 Onions <8.0 <7.5 <9.1 R-6 Red Onions <17 <14' <16 R-6 Peppers <13 <14 21(24)
A-27 Watermellon <4.5 <3.5 8.3(6.2) l A-27 Cucumbers <19 <12 <15 A-27 Zucchini <16 <11 <16 l
- 1.96o (Due to countin9 statistics.)
l' l l l I 1 1? I l 80 L
II.F. Aquatic Pathways ; Table II.F.1 shows radionuclide concentrations measured in fish samples collected at F-19, A-25 and R-10 on two dates in 1990. -The fish were collected by shocking and netting-and the composite sample was homogenized without cleaning and analyzed on a wet weight basis. The positive values of Cs-137 were assumed to be due to f allout. The cs-134 value above MDC ! was assumed to be f alse -positive. No fish samples were available-at the upstream site for the last half of 1990.- Table --II'.F.2. shows the measured concentrations of both Cs-137'and Cs-134 in surface sediment collected at R-10, the downstream location. There was measurable activity of Cs-137 clearly due to-the--Chernobyl: fallout.. The-cesium ions are bound nearly irreversibly by the clay. mineral matrix.in the 4 sediment. The concentrations observed in 1990 were :j statistically less than observed =in 1989. Observation for Corbicula fluminea, a-- species of
- freshwater clam,. was conducted at all fish sampling : sites.
These : monitoring - dates- coincided with -the fish collection - dates.- Corbicula have been introduced to North America-from
-As'ia. : The- = freshwater clams are - now :-- found in large riverz
' systems . in c the - U' S.
. from : coast to coast. The Colorado Division of Wildlife has stated that Corbicula have been found in Northern-Colorado at Boyd Lake, some 30 miles from the Fort St. Vrain Nuclear _ Generating Station. However, to this date, our--samplings have indicated no evidence of Corbicula at any of the sampling sites of the reactor surface water courses.
l 81 L
Table II.F.1 Radionuclide Concentrations in Fish. (pCf/kg) Collection Date First italf Second Half Upstream Ef fluent De-i. dream Upstream E f fluent Downstream A-25 R-10 F-19 A-25 R-10 Radionuclide F-19 Cs-134 < 6.3 < 16 l 6.2 (7.2)* < 6.0 < 4.7 l l Cs-137 < 7.6 35 (21)
< 6.7 < 6.0 5.7 (6.7)
Co-58
< 5.3 < 6.1 < 4.6 < 5.8 < 14 m
Mn-54
< 5.8 < 6.0 < 4.7 < 6.5 < 16 Zn-65 < 44
< 17 < 17 .< 13 < 18 Fe-59 < 25
< 9.4 < l '. < 8.4 < 13 Co-60
< 6.2 < 6.4 < 5.0 < 6.5 < 16
- 1.960 (Due to Counting Statistics.)
II.F.2 Radionuclide Concentrations in Sediment from location R10. (pCi/kg) Radionuclide Collection Date 6/23/90 Cs-134 19 (22) Cs-137 69 (22) c) Radionuclide Collection Date 12/22/90 Cs-134 < 8.0 l Cs-137 48 (9.5) l *1.96c (Due to Counting Statistics) l i _ _ _ _ _ ~
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 reactor, Colorado State University participates in a number of interlaboratory and intralaboratory 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 analysis and frequency of analysis for the EPA program are summarized below. Medium Analysis (radionuclide) Freouency Water H-3 Triannually Water Gross beta, gross alpha semiannually Water Co-60, Zn-65, Cs-134, Cs-137 Triannually Water I-131 Semiannually Air partic- Cs-137, gross beta, Semiannually ulate filters gross alpha Milk I-131, 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 not.ed that during 1989, our laboratory became certified by the EPA for drinking water analysis. Table II.G.1 gives the EPA crosscheck data for 1990. The EPA uses the parameter, Estimated Laboratory Precision (ELP) , calculated as one standard deviation for one determination, 84
. -_.m._ . _ . . . _ . . _ _ . . _ _-
1 The normalized deviation of our mean from the known is > calculated as: CSU mean value - EPA known value on 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 rango. If any result exceeds two standard deviations from the mean (warning
~ level), the result is unacceptable.- Whenever our mean value falls outsidesthis limit, the calculations are rechecked and the sample reanalyzed if possible. During 1990 all'results except 8 were within the warning level. The results exceeding the warning ~ level have the notation (n) in Table II.G.I. If
~
possible, the corrected values are shown in the table. The recheck = process and conclusion are -given below - for - these samples.
- 1. No apparent reason for aberrant ~ result.
- 2. The ~ laboratory. 'was changing buildings on campus during this period and the alpha gas-flow system -
~
was inoperative.
- 3. No-apparent reason for aberrant result.
- 4. 2n-65 correction due to Bi-214 was too high. .This
_- was corrected at end of year.
- 5. Ba-133 count yield was 'in error. This- was corrected after Oct. 5 result,
- 6. Zn-65 correction due to Bi-214 was too high. This l
l 85 l
l was corrected at end of year.
- 7. Zn-65 correction due to Bi-214 was too high. This was corrected at end of year.
- 8. Ba-133 count yield was in error. This was corrected after Oct. 5 result.
Table II.G.2 lists independent results for H-3 in water ~ samples split between this laboratory and the laboratory t .. the Fort St. Vrain Generating Station. The comparison between
- l 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 1990 approximately 10% of all laboratory calculations that partly involve technician input were recalculated by a different technician. No input or calculation errors were detected. This result gives further credence to the laboratory results which are not solely computer calculated and listed. Computer calculations are of ten recalculated by hand and those done during 1990 were all verified to be correct. 1 86
Tablo ll.C.1 EPA Cross Check D:ta Stenary. 1990. Radio- CSU EPA 1 E.L.P.* Normalized Deviation Date nuclide Value Value from known** WATER, TRITIUM (pCi/L) Feb 23 H3 5800 4976 498 2.87 (1) Jun 22 H3 2533- 2933 358 1.93 Oct 19 H3 7167 7203 720 0.09 WATER, Alpha / Beta (pCl/L) Jan 26 alpha - - - - beta 13 12.0 5.0 0.35 May 11 alpha -- - - - (2) beta 8.0 15 5.0 2.42 Sep 21 alpha - - - -- beta 9.0 10 5.0 0.35 WATER, 1 131 (pCl/L) s Aug 10 1 131 44 39 6 1.54 WATER, Performance (pCl/L) Apr 17 alpha 146 90 23 4.22 (3) beta 47 52 5.0 1.73 Cs 134 14 15 5.0 0.35 Cs 137 16 15 5.0 0.23 Oct 30 alpha 49 62 16 1.44 beta 46 53 5.0 2.31 Cs 134 7.7 7.0 5.0 0.23 Cs 137 8.0 5.0 5.0 1.04 WATER, Gaane (pCi/L) Feb 9 Co 60 14 15 5.0 -0.46 2n 65 109 139 14 3.73 (4) Cs 134 15 18 5.0 1.15 Cs 137 20 18 5.0 0.81 88 133 23 74 7.0 12.7 (5) Jun 8 Co-60 23 24 5.0 0.46 2n 65 120 148 15 3.23 (6) Cs 134 22 24 5.0 -0.81 Cs 137 20 20 5.0 0.12 Be 133 91 99 10 1.39 Oct 5 Co 60 13 20 5.0 2.54 Zn 65 74 115 12 5.97 (7) Cs 134 11 12 5.0 -0.35 Cs-137 13 12 5.0 0.23 Be 133 33 110 11 -12.1 (8)
- E.L.P. = Expected laboratory precision.
** Normalized deviation = (CSU mean EPA known)/(a/ n); if this value falls between upper & lower warning levels, the accuracy is acceptable.
(2) Alpha system inoperative during period. 87 ___________ __ ___ __ __ _ _ _ ____ __
Table it.G.1 EPA cross Check Data Surunary. 1990. (continued) Radio- CSU EPA i E.L.P.* Normalized Deviation Date nuclide Value Value from known** MILK (pCl/L) Apr 27 Cs 137 25 24 5.0 0.23 K 40 1550 1550 78 0.0 sep 28 Cs 137 21 20 5.0 0.23 K 40 1600 1700 85 2.04 AIR FILTERS (pCl/L) Har 30 alpha 5.0 5.0 5.0 0.0 beta 31 31 5.0 0.12 Cs 137 13 10 5.0 0.92 Aug 30 alpha -- - - - (2) beta 61 62 5.0 0.46 Cs-137 23 20 5.0 1.15
- E.L.P. = Expected laboratory precision.
** Wormalized deviation * (CSU mean EPA known)/(0/ n), if this value falls between upper & lower warnin0 levels, the accuracy is acceptable.
(2) Alpha system inoperative during period. 88
Table ll.G.2 Trititan Crosscheck Analyses on Split Water Sanples Determined by Colorado State University ard Pdalic Service Conpany. 1990 Collection Sample Tritium Concentrations pCl/L Date Location CSU PSC Jan 13 A 25 1200 (450)* 2360 (390) Jan 13 A 21 s420 <299 Jan % E 41 <420 844 (370) Feb 10 A 25 480 (450) Feb 10 A 21 <430 Feb 21 E 41 <420 Mar 10 A 25 1100 (450) 1490 (371) Har 10 A 21 <430 <293 Mar 14 E 41 <420 <293 Apr 14 A 25 <420 450 (453) Apr 14 A 21 <420 479 (453) Apr 4 E 41 <430 <371 May 12 A 25 <420 <T2.80 May 12 A 21 <420 (72.80 May 14 E 41 <420 Jun 9 A 25 <390 <362 Jun 9 A 21 <400 <362 Jun 9 E 41 <390 <362 Jul 14- A 25 <400 371 (426) Jul 14 A 21 <400 <350 Jul 11 E 41 <390 407 (427) Aug 11 A 25 <390 <360 Aug 11 A 21 <390 <360 Aug i E 41 <390 <360 Sep 8 A 25 <400 432 (434) Sep 8 A-21 <400 <356 Sep 5 E 41 <400 <356 Oct 13 A 25 <390 364 (438) Oct 13 A 21 <400 <360-Oct 17 E 41 <390 <360 , Nov 11 A 25 <390 394 (434) Nov 11 A 21 <390 <356 Nov 14 E 41 <400 <356 Dec 8 A 25 1900 (400) 2630 (481) Dec 8 A 21 <400 <363 Dec 5 E 41 <400 398 (442)
- 1.960 (Due to Counting Statistics.)
l 89
Table ll.G.3 Cross Beta Crosscheck Analyses on Split Water Sanples Detennined by 6 Colorado State University ard Public Service Conpany of Colorado. 1990 Collection Sample Gross bate Concentrations pCi/L Date Location CSU PSC Jan 13 A 25 14 (6.0)* 15.30 (6.34) Jan 13 A 21 8.6 (5.7) 14.40 (6.33) Jan 3 E 41 9.1 (5.7) 14.10 (6.24) Feb 10 A 25 12 (5.6) Feb 10 A 21 9.2 (5.5) Feb 21 E 41 9.1 (5.5) Mar 10 A 25 11 (5.5) 11.30 (6.64) Har 10 A 21 15 (5.7) 10.80 (6.77) Har 14 E 41 12 (4.1) 11.20 (6.66) Apr 14 A 25 13 (5.9) 11.00 (7.00) ) l Apr 14 A*21 6.0 (5.5) 9.00 (7.00) l Apr 4 E 41 12 (5.8) 10.00 (7.00) May 12 A 25 8.7 (5.6) 12.50 (6.85) May 12 A 21 6.3 (5.6) 18.80 (7.19) May 14 E 41 10 (5.7) Jun 9 A 25 26 (6.5) 17.00 (7.00) Jun 9 A 21 8.6 (5.6) 9.00 (6.00) Jun 9 E 41 2.8 (5.3) 11.00 (6.00) Jul 14 A 25 3.4 (5.4) 16.00 (7.00) Jul 14 A 21 5.5 (5.5) 15.00 (7.00). Jul 11 E 41 4.3 (5.4) 10.00 (7.00) Aug 11 A 25 8.4 (5.5) 16,60 (6.47) Aug 11 A 21 5.6 (5.5) 21.00 (6.98) Aug 1 E 41- :,,1 (5.4) 18.50 (6.61) l Sep 8 A 25 2.8 (2.2) 12.00 (7.00) i Sep 8 A 21 1.3 (2.1) <6.00 l Sep 5 E 41 2.8 (2.2) 8.00 (7.00) l Oct 13 A 25 13 (5.9) 17.20 (6.94) l j oct 13 A 21 9.4 (5.7) 17.30 (6,97) Oct 17 E 41 8.6 (5.6) 19.70 (7.10) Nov 11 A 25 16 (6.0) 23.00 (7.00) Nov 11 A 21 14 (5.9) 20.00 (7.00) Nov 14 E 41 10 (5.7) 22.00 (7.00) Dec 8 A-25 13 (5.8) 14.20 (6.77) Dec 8 A 21 15 (5.9) 15.20 (6.92) Dec 5 E 41 14 (5.8) 16.50 (6.94)
- 1.960 (Due to Counting Statistics.)
90
latile ll.G.4 Intralatiora tory Crosscliect flesul ts, (pCi/L), (iteplicate Analysts of Same Sanrple)
~~ ~ ~ ~ ~ ~ - ~
Drinting ifater (It-6) Itailio- Ist Quarter 2n:1 Quarter 3rilQuarter 4tii1]uarter A B A 11 A !! I!ue i iile A 11
<2.1 1.5(1.4)* <l.9 <l.5 <2.1 <2.3 2.2(2.3) <2.2 Es-134 Cs-131 <2.6 1.7(1.1) 2.9(2.8) 2.0(2.2) 4 o(3.0) <2./ 4.6(2.7) 3.3(3.2)
<4.8 <2.6 <4.1 <3.2 <4,/ <$ o <4.1 <5./
fr.95
<l.9 <l.3 2.6(2.4) <l.4 <2.0 <2.5 <l.7 <2.0 1113 9 5
<2.1 <l.1 <l.8 <l.4 <2.0 <2.2 <l.I <2.1 i to-58
<2.1 <l.2 2.0(2.4) <l.5 <2.0 <2.2 <l.8 <2.2 fiu-54 <6.2
<5.2 <4.5 <5.5 <4. 2 <6.1 </.5 <5.4 In 65 S <4.8 <3.3 <4.9 6.l(4.5) <5.2 <5.9 <4.9 <5.9 le-59 < i .fi <2.4 to-60 <2.3 <l.2 <l.9 <l.5 <2.2 <2.2
<2.I <3.4 <3.6 <3.3 <3./ <2.9 <3.6 Ita-140 <3.4
<3.9 <2.4 <3.9 <4 .1 <3.8 <4.2 <3.4 <4.I Ia-140 5.l(2.4) 5.l(2.2)
Giuss I? eta 5.l(2.4) 2.2(2.3) 2.3(1.8) 2.4(1.8) 3.2(2.3) 3.2(2.3)
<390 <390 <390 <400 <400 11 3 <430 <420 <390 Ililk (A-23) 1st fluarter 2 nil Qucrier 3iil Quarier 4 11 f}ua. r t e r
<3.0 <2.1 <2.1 <2.3 <2.5 <2.9 Es-131 <2.5 <l.4
<2 5 <3 2 <4.2
<3.0 <l.6 <4.6 <2.6 <3.I Cs-13/ <5.0 <3.6 <4.I <5.5
<5.3 <2.I <5.0 <3.5 ILi-140 <5.7 <3.9 <4.7 <5.5
<6.I <2.5 <5.8 <4.0 -
Ia-140 <390 <390 <400 <409
<430 <430 -420 +420 11- 3 I.96 o (Due to countin9 statistics. )
l 1 1 . 11 . Summary and Conclusions Table 11.11.1 summarizes the radiation and environmental radioactivity measurements conducted during 1990 in the environs of the Fort St. Vrain Nuclear Generating Station, owned and operated by Public Service Company of Colorado. The values for each sample type may be compared to pre-operational and operational periods for this reactor, 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.11.1 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.11.1 is a requirement of the NRC. Inspection of Table 1I.11.1 reveals that (except for I-131 at site A-22) there were no individual measurements that exceeded the Reporting Level (RL) (see Table III.A.3). The Chernobyl fallout was still observable in several sample types. For the category of gross beta concentrations in drinking water, ths mean for the Gilcrest well was again significantly greater than for the reference supply located in Fort Collins. This dif ference cannot be due to reactor ef fluent activity for the following reasons: 92
- a. None of the individual fission product or activation product radionuclides measured were significantly higher in the Gilcrest drinking water,
- b. Tritium concentrations seasured at Gilcrest were statistically the same as those in Fort Collins.
- c. The city of Gilcrest does not filter and treat its 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. The suspended solids are higher in Gilcrest water samples due to less filtration of the water.
For the category of tritium in surf ace water, as has been the case since reactor operation, elevated concentrations were noted at station A-25, the outlet of the (Goosequill) farm pond. A-25 is directly in the principal effluent route and elevated concentrations should be expected, to correlate with release schedules. Elevated concentrations of tritium have never been observed, however, in any human food source in direct or indirect contact with the farm pond water. 93
Downstream surface water concentrations of tritium have occasionally been elevated, but there is significant dilution before any human use of this water. During 1990 elevated tritium concentrations were not observed downstream t.nd the mean values for the first and second half of 1990 were not significantly different. I-131 was observed again in milk samples, but again only f rom Dairy A-22. Because the reactor did not release any significant fission products during 1990, the source of the I-131 concentrations in milk could not be reactor offluent. It was documented in the 1985 annual raport that the source of the I-131 concentrations during thet year was not due to the reactor but due to nuclear medicina use and release upstream of the reactor. This was an important observation as I-131 is certainly a critical radionuclide in human dose commitment possibilities, a fact of whtun the general public is aware. This discovery prompted increased monitoring for I-131. Upstream nuclear medicine releases of I-131 is, therefore, the only likely scarce of the I-131 observed again in milk samples during 1990. Irrigation water samples confirmed this conclusion. An additional continuous water sampler on the Platte River outlet of the Denver Metro Sewage District plant revealed the same variation in I-131 concentrations observed at A-22. This further confirms that the Denver hospitals are the source of the I-131. Cs-137 was also observed in many environmental samples due to the Chernobyl fallout. 94
Tritium concentrations from well water site F-16 do appear to be increasing with time. This could be due to migration to the aquifer from the farm pond drainage. Typically lateral water 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. Table II .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 in documenting possible radiat. ion dose to humans. Air and surf ace water would be the predominant environmental transport routes and drinking water and milk would be the predominant sources of radiation dose if significant radioactivity release from FSV occurred. Table II !!.2 also allows comparison to the three most recent years of operation. The arithmetic means in Table 11.11.2 were calculated for all sample results. It should be noted 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 (MDC) are listed as less than the actual MDC for that sample analysis. Ilowever, the actual result in all cases was used in the calculation for the arithmetic mean values for the period. Therefore, all 95
- - . - .. . . . - - - . - _ . - - - . - - - - . - . . ~ . . - - - . - . - . - -
values, negative as-well as 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 II.11.2 cannot -be calculated directly from the tabular values in the report. It must be emphasized that while it is true that no sample can contain less than zero radioactivity, due to the random nature i of radioactive decay, it is statistically _possible to obtain ! sample count rates less than_ background and hence a negative i 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.l!.2 and the tabular data of the report,- the following observations and conclusions may be drawn: 4
- 1. Tritium was again - the only radionuclide that was detected in significant concentrations in any7of the effluent pathways that could be attributed to-the reactor.- Since the - tritium. is released _ as ,
tritiated water, the dilution by - the surrounding. hydrosphere is great. Although in 1990, tritium could be detected in the effluent pathway, the mean l values of downstream surface water were not statistically greater than upstream concentrations. , 96
The tritium concentrations measured in. milk produced by the nearest dairy herd were also all less than MDC.
- 2. As in overy previous report, it was again apparent that for most sample types the variability observed around the mean values was great. This variability is 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 analysis of any set of environmental data before meaningful conclusions can be drawn.
- 3. The Chernobyl accident 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. It is the variation in fallout deposition, in addition to the variation in naturally occurring radionuclides, that mandates the large number of environmental samples to detect any possible radioactivity due to reactor effluents. A simple comparison of pre-operational and operational values is of little value for most 97
sample types because the fallout deposition was considerably greater during the pre-operational period.
- 4. The prompt and sensitivo detection of the Chinese weapon test and 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 reactor operation.
It can be concluded from the data collected by the environmental monitoring program that the radiation dose commitments calculated for the closest inhabitants or other parts of the nearby ecosystems due to current reactor ef fluents are negligible. Natural background radiation and the dose commitment from atmospheric f allout are the only known significant sources of radiation dose to the residents of the area. During the current defueling phase of the reactor it is concluded that this Radiation Environmental Monitoring Program will be more than adequate to detect and quantify any possible routine or accidental release of radioactivity. 98
lable ll.H.1 Eiwirotznental Radiological Honitoring Program Annual Sternary Fort St. Vrain Nuclear Generating Facility, Platteville, Colorado 1 Adjacent- Locations with Highest Reference Nunber of Hediten or Pathway Type and Facility Locations- Location Annual Mean L c tion Nonroutine I Samples (Unit of Total Nunber Hean(f)g measurement) of Analyses Mean (f) Hean(f)g Name Mean (f)b Reported Range Range Distance & Range Range Measurcnents Performed Direction 0.47 (4/4) 0.39 (16/16) 0 Direct Radiation TLD (155) 0.40 (70/70) 0.39 (69/69) F-11 WCR19 (nR/ day) (0.28-0.48) (0.34-0.48) & UCR3 (0.45-0.48) (0.32-0.46) 1.2 km F-7 Farm 25 (52/52) 23 (155/155) 0 Air, GrossB (361) 23 (206/206) (5.5-52) CR21 & CR34 (5.5-52) (6.6-56) Particglates 1.5 km 145* l (fCi/m )
'fo Gamma Spectrometry F-16 3-Bar 2.7 (1/4) <2.1 0 l Cs-134 (28) 2.0 (2/16)
(1.3-2.7) Ranch 1.2 km 0* l 1 F-9 Farm 2.3 (1/4) <2.0 0 Cs-137 (28) 2.0 (2/16) (1.7-2.3) CK19% & CR34 1.5 km 185* l F-16 3-sar 42 (2/52) 28 (11/155) 0 Air,Cgarcoat I-131 (362) 30 (11/207) (13-52) Ranch (31-52) (14-49) (pci/m ) 1.2 km 0* F-7 Farm 420 (1/52) <430 0 Air, Atinospheric H-3 (350) 420 (1/202) CR21 & CR34 uatergapor 1.5 km 145* (pci/m ) bHean and range based upon detectable measurements only. Fraction (f) of detectable measurements at specified locations is indicated in parentheses.
Tabte 11.11.1 Environmental Radiologicat Monitoring Program Annual Stma.ary Fort St. Vrain Nuclear Generating Facility, Plattevitte, Colorado Adjacent locations with Highest Reference Ntsrber of Meditsn or Pathway Type and Facility Nonroutine location Location Annual Mean L cation Samples (Unit of Total Nunber Mean(f)g Reported of Anatyses Hean(f)g Hean (f)g Name Mean (f)b measurement) Range Hessurements Performed Range Range Distance & Range Direction R-6 Gilcrest 4.5 (26/26) 0.86 (26/26) 0 Drinking uater GrossS (52) 4.5 (26/26) (pci/L) (1.3-9.5) City water (1.3-9.5) (0.34-2.3) 9.3 km 60*
<430 0 11-3 (52) <430 ---
y Ganma Spectrometry a 1-131 (52) 0.31 (2/26) R-3 Ft. Collins 0.44 (1/26) 0.44 (1/26) 0 (0.18-0.44) City Water 45 im 330* R-6 Gilcrest 1.8 (3/26) <2.8 0 Cs-134 (52) 1.8 (3/26) (1.5-2.2) City Water (1.5-2.2) 9.3 km 60* Cs-137 (52) 3.5 (13/26) R-6, Gilcrest 3.5 (13/26) 3.0 (9/26) 0 (1.6-6.4) City Water (1.6-6.4) (1.3-5.0) 9.3 km 60* Zr-95 (52) 6.8 (1/26) R-6, Gilcrest 6.8 (1/26) 3.4 (1/26) O City water I
?.3 km 60*
3.1 (5/26) 2.0 (5/26) 0 Nb-95 (52) 3.1 (5/26) R-6, Gilcrest (1.5-6.1) City uater (1.5-6.1) (1.3-2.9) 9.3 km 60-bean and range based upon detectable measurenents only. Fraction (f) of detectable measurements at specified locations is indicated in parentheses.
L i Table i1.H.1' Environmental Radiological Monitoring Program Annual:Sunenary;. ~ ; Fort'St. Vrain Nuclear. Generating Facitity,.Ptattevitle, Colorado' ,
. . .. :I Mediun or; Pathway Type and. Facility.- Adjacent- Locations with Highest - Reference Ntmber of j Samples (Unit of Total Ntaber location -
Location Annual Mean. *'" " '" Mean(f)g. .. Mean(f)g measurement) . of Analyses ' Name. Mean (f)b Mean(f)b : Reported' 't Performed- Range. - Range Distance & Range Range Measurements ' Direction ! Drinking Water Co-58 (52) -1.5(1/26). R-6 Gilcrest 1.5 (1/26) <2.5 0 City Water , 9.3.km 60* 'f 4 Mn-54 (52)' 2.1 (6/26) R-3 Ft. Col (ins 2.1'(6/26) 2.1 (6/26) -0
.(1.2-2.8) City Water (1.2-2.8) (1.3-2.4) >
45 km 330* ;
~
o l s Zn-65 (52) 9.4.(1/,26)- R-6 Gilcrest 9.4 (1/26) <7.5 0 l City Water -l 1 9.3 km 60*
^
Fe-59 (52) 6.6-(3/26) R-6 Gilcrest . 6.6 (3/26) 5.6 (1/26). O
.(4.9-9.1) City Water (4.9-9.1) ;
9.3 km 60* 4 Co-60'(52) 2.0 (6/26). R-3 ft. Col 1 ins 2.7 (2/26) 2.7(2/26) 0 l (1.2-3.7) City Water (2.1-3.2) (2.1-3.2) .. 45 km 330* , 1 Ba-140 (52) 5.2.(3/26)' R-6 Gilcrest. 5.2 (3/26) <5.1 0 1 (4.0-6.4) City Water (4.0-6.4) ! 9.3 km 60- !
't La-140 (52) 519 (3/26) R-6 Gilcrest 5.9 (3/26) <5.9 0 (4.6-7.3) City Water (4.6-7.3) 9.3 km 60* t t
j b Hean and range based upon detectable measurements only. Fraction'(f) of detectable measurements.at:specified locations is indicated in parentheses. 9 .- .mce. . 9- - .w- ?+' , . - 7-ws- y
Table II.H.1 Envirorvnental Radiological Monitoring Program Annual Stmnary Fort St. Vrain Nuclear Generating Facility, Plattevitte, Colorado l Meditsn or Pathway Type and Facility Adjacent Locations with Highest Reference Ntsrber of Sanples (Unit of Total Ntznber Location Location Annual Mean l catior Nonroutine measurement) of Ana1yses Mean (f)g Mean(f)g Name Mean (f)b Mean(f)g Reported Performed Range Range Distance & Range Range Measurements ; Direction ' Surface Uater H-3 (60) 1 50 (2/36) A-25 Goosequitt 1750-(2/12) <430 0 (pCi/L) (1600-1900) 2.2 km 20* (1600-1900) Ganma Spectrometry Cs-134 (60) 2.8 (2/36) A-25 Goosequitt 3.6 (1/12) 1.8(2/24) 0 (2.0-3.6) 2.2 km 20* (1.4-6.5)
~
o m Cs-137 (60) 3.7 (12/36) R-10 S. Platte 4.5 (4/12) 3.9 (10/24) 0 (1.8-7.1) at CO 60 ( 2.1 - 7.1 ) (1.9-6.5) 10 km 290* Zr-95 (60) 4.8 (3/36) R-10 S. Platte 5.2 (1/12) 4.6 (2/24) 0 (4.2-5.2) at CO 60 (4.3-4.8) 10 km 290* Nb-95 (60) 2.0 (2/36) F-19 S. Platte 3.5 (2/12) 3.5 (3/24) 0 s (1.8-2.1) 1.2 km 90* (3.4-3.5) (3.4-3.5) - Co-58 (60) 2.6 (2/36) F-20 St. Vrain 2.6 (2/12) 2.6(2/24) 0 ' (1.3-3.8) 1.5 km 345* (1.3-3.8) (2.4-2.7) 1 Mn-54 (60) 2.1 (2/36) F-19 S. Platte 2.8 (3/12) 2.4(5/24) 0 (1.7-2.5) 1.2 km 90* (2.4-3.4) (1.4-3.4) Zn-65 (60) <10 A-21 St. Vrain 7.7 (1/12) 7.7 (1/24) 0 i Bridge 2.4 km ' 220* beanandrangebasedupondetectablemeasurementsonly. Fraction (f) of detectable measurements at specified locations is indicated in parentheses.
! jl . f , ;
s e t. i f n e oid-t e s i rut r 0 0 0 0 0 aor u 0 0 0 0 bros r npa ts oee NNRM
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oS yof e e o a a t s s r b uat r T T oP F C B L H c C C Z N i t e d c vr p ee no S st ae EF y a i bd _ af r h wo c a ef go t t r G n _ 1 ai) e r a) P nt t e rf Un a t ( H. r( e W a d o V nn sen I I e) ) ao e mer cL dL n/ nt i _ ul u a/ ac l ips f i ui b dn a rc oc ea - T a eae MS w up S( rp G( M r b F 5"
l Table II.H.1 Envirorwental Radiological Monitoring Program Annual Sumary i Fort St. Vrain No; tear Generating Facility, Platteville, Colerado j I I Meditsm or Pathway Type and Facility ' Adjacent locations with t'ighest Reference Ntm6er of ; 4 Sanples (Unit of Total Ntabes- Locati Locati Annual Mean L cati Nonroutine , measurement) of Ana1yses Mean(g) f Mean(g)f Name Mean (f)b Mean f(g) Reported I l Performed Range Range Distance & Ra.xje R mge Measurements t Direction ; 1 t i , Ground tiater Ganma Spntrometry j (pCi/L) Co-58 (8) 2.9 (1/4) F-16 3-Bar 2.9 (1/4) <2.5 0 j Ranch 1.2 im 0* . i Mn-54 (8) 1.7 (2/4) R-5 Mitiken 4.3 (2/4) 4.3 (2/4) 0 o .(1.4-2.0) 9.5 km 11* (2.7-5.9) (2.7-5.9) b \l Zn-65 (8) <8.7 --- ---
<13 0 Fe-59 (8) <5.9 --- ---
<6.4 0
, Co-60 (8) 1.8 (1/4) R-5 Mitiken 3.3 (4/4) 3.3 (4/4) 0 9.5 km 11* (2.0-5.1) (2.0-5.1) > Ba-140 (8) <4.3 R-5 Mitiken 9.0 (2/4) 9.0 (2/4) 0 9.5 km 11* ( 7.9-10) ( 7.9- 10) La-140 (8) <4.9 R-5 Mitiken 11 (2/4) 11 (2/4) 0
, 9.5 km 11* (9.0-12) (9.0-12) 4 .
{ beanandrr.agebasedupondetectablemeasurementeonly. j Fractions (f) of detectable measurements at specified locations is indicated in parentheses. 4 ( i r I t
+ ,
1 i Table II.H.1 Erwironmental Radiological Monitoring Program Arwmat Strunary
-Fort St. Vrain Nuclear Generating Facility, Platteville, Colorado i
f Meditsn or Pathway - Type ard [ Facility Adjacent Locations with Highest Reference Nted>er of l Sanples (Unit of Total Ntmber . Locati Locations Arunat Mean locati N)nroutine , i measurement) of Analyses Mean if) Mean (f) Name Mean (f) Mean (f g) Reported Performed Rattge Range Distance & Range Range Measurements
- Direction Sediment Gansna Socctrometry !
(pCi/kg. dry) l Cs-134 (2) 19 (1/2) R-10 S. Platte 1? (1/2) --- 0 ' at CO 60 10 nm 290*
- Cs-137 (2) 59 (2/2) R-10 S. Platte 59 (2/2) ---
0 l g (48-69) at CO 60 (48-69) - " m 10 6m 290* 1 Mi'E d-3 (116) 550 (1/99) A-23 Leroy 550 (1/17) 480 (1/16) O !' (pCi/L) oderbaugh Dairy I l 4.1 nm 83*
- Ganma Spectrometry I-131 (116)' 3.6 (15/99) A-22 Percy 5.2 (10/17) 0.32 (3/17) 0 l (0.31-15) Odenbaugh Dairy (1.1-15) (0.29-0.36) 5 km 90* l i
I Cs-134 (116)' 2.9 '4/99) R-8 Gorreman 3.5 (1/17) 3.5 (1/17) 0 (2.7-3.2) Dairy j 23 &m 3 Cs-137 (116) 3.9 (25/97) R-8 Gorzeman 5.2 (4/17) 5.2 (4/16) 0 i (1.6-7.1) Dairy (3.7-6.21 ( 3. 7-6. 2 ) ) 23 6m
- Hean and range based tron detectable easurements only.
Fraction (f) of detectable measurement;. at specified locations is irdicated in parentheses l i i ! a
Table il H.1 Envirotunental Radiological Monitoring Program Armal Stsunary
- Fort St Vrain Nuclear Generating Facility, Platteville, Colorado Meditsa or' Pathway Type and facility Adjacent Locations with Highest Reference Ntrber of Sanples (Unit of Total Ntsber Locati Locati Arvual Mean Locatiog Norwout ine measurement) of Analyses Mean (f g) Mean (f g) Name Mean ( f ) Mean (f) Reported Performed Range Range Distance & Range Range Measur ements Direction Milk Ganno Spectrometry (pCi/L)
Ba-140 (*16) 6.4 (16/99) A-23 Leroy 12 (1/17) 11 (2/16) 0 (3.7-12) odebaugh Dairy (10-11) , 4.1 km 83* ta-140 (116) 7.4 (15/99) A-23 teroy 14 (1/17) 13 (2/16) 0 g (4.2-14) oderbaugh Dairy (12-13) e 4.1 km 83*
. Food Products Gansna Spac t ronet ry
! (pCi/kg, wet) 1-131 (9) 17 (1/9) A-27 UCR25 17 (1/4) --- 0
& UCR38 4.3 km Cs-134 (9) <14 --- --- ---
0 Cs-137 (9) 15 (2/9) R-6 Hernandez 21 (1/5) --- 0 (8.3-21) Gilcrest 9.6 &m 60* b Mean and range based upon detectable measuremmts only. Fraction (f) of detectable measurements at specified locations is indicated in parentheses. 4
=
T abl e I 1.11.1 Evivirornw ntal Radiological Monitoring Program Arwurat seem3ry f ot t St . Vr a irt Nuc l ear Gef es at irig f ac il i t y, Pl a t t ev i l l e, Colera4) Tyre atwl Facility Adjacent Locat ims with liighest Peference Ninier of Mediesta or Pathway Arsumt Hearn Locatior NMir o'st irse Sartples (ifnit of lotal Nieder locat ioeng Locatiorg Mean(f)g Rc;virted eneasur emnt ) of AnaIyses Mean (f) Meart (f) Narre Mean (f) Ratige Rattge Distance & Ratge Range Meastrr emnt s Per foiand Dir ect ion Fish Garmia Srect ronet ry (PCi/Fg, wet) 0 Cs-134 (5) <16 T-17 S. Platte 6.2 (1/1) 6.2 (1/1) 1.2 nm 90* 20 (2/2) <6.7 o Cs-137 (5) 20 (2/4) R-10 s. Platte (5. 7- 35 ) et to 60 (5. 7-35 )
"!O km 2?rr o ---
<5.3 0
" Co-58 (5) <14 ---
l
<5.8 0 Mn-54 (5) <16 ---
l
--- <f7 0 i Zn-65 (5) 444 ---
<?.4 0 Fe-59 (5)
<25
<6.2 0 Co-60 (5) <16 ---
Ihean aval rarne based spon detectable wasurecents only. T action (f) of detectabte neastirer:ents at specified Iocatiotr. is irxlicated in parentheses.
- -.. . - - - .- = . - . --- =
i i ;. I-i
?
t l Table 1 1 . 11 . 2 Summary Table of Arittimetic Means and ' Standard Deviations for Selected Sample Types. l , t l I r t l' 1987 1988. 1989 1990 i 2 o R 'o 2 o 2 o ! t Atmosplieric Water Vapor (pCi/L) [
- 11 - 3 j Facility. <230 470 43 <256 285 j Reference <230 172 <420 <299 288 t
, ~ ; O y e .
I ' co I 3 f Air (fCi/m ) I
~ Gross Beta !
Facility 26 26 26 23 12 i Reference 25 24 24 23 12 ,. i t I-131 I Faci 1ity. 1.1 1.9 2.2 1.5 3 [ Reference .1. 2 <4.5 .2 . 2 1.4 9 ; t t t l Cs-137 j l Facility .O.33- 0.73' O.32 0.55 0.92 ! i Reference' -0.44' 1.0- 0.46 -0.22 'O.66 ! l > . t j [ 1 i i i i * [ t i I
r 4 i i I j. !4
. Table 11.11.2 Summary Table of Arithmetic Means and Standard Deviations
- for Selected . Sample Types. !
5 . L i 1987 1988 1989 1990 ! R o 2 o R a i o }. t
'. Drinking , Water (pci/I.)
11-3 ! i ! Gilcrest 75 370 <390 <238 317 i Ft. Collins <230- 120 <390 <215 288 I < ~ Gross. Beta !
.o e Gilcrest 5.1 6.8 5.a 4.5 1.8 l Ft. ColIins 0.79 1.1 0.98 0.86 0.39 i
I
' i, I-131 t
. Gilcrest 0.052 0.099 0.068 0.017 0.19 I Ft.. Col 1 ins 0.071 0.083 0.14' O.046 0 24 ! l l Cs-137 { i Gilcrest' 2.1 1.7 2.2 1.3 1.4 ! I Ft. Collins 1.1 1.4 1.8 2.4 1.8 !
; I s- !
4 i I i , f r
< f
- i 1
Table ' II . II. 2 Summary Table of. Arithmetic Means and Standard Deviations for Selected' Sample Types.. i $. .1987 1988 1989 1990
.R a R a R o R o j Surface Water (pci/L) 11 - 3
. Effluent 7700 31000 29000 303 623 !~ Downstream 21 430 <390 <371 397 ) Upstream .<230 430 <390 <415 352 1 1 l ' - Cs-137 E' Effluent 1.7 1.9 1.3 1.4 1.9 l Downstream 0.01 2.5 1.8 2.1 1.9 Upstream 0.32 1.4 2.0' 2.2 1.9 l I l Milk (pCi/L) i 11 - 3 l Adjacent <230 70 <390 <280 330
'Heference <230 <220 <390 <290 340 I-131 l Adjacent 0.15 0.046 0.57 0.S3 2.0
- Reference 0.02 <0.17 <0.50 0.0060 0.33 i- Cs-137 Adjacente 3.2 2.7 1.5 1.5 2.0 Reference' 3.6 3.3 1.5 16 2.3 i
i' i' ?
- - . . - . . -- - = ~ _ - _ -. .-:--~. . . - - . _ . -._ _- .. ._ --. . _ . -
i l III.. Radiological Environmental Monitoring Program-l A. Sample Collection and Analysis Schedule , 1 Table III.A.1 outlines the sampling design, the collection frequency and the type of analysis for all environmental samples. It should be repeated -that this schedule was only adopted January 1,1984, and while dif ferent i in certain aspects from the previous- schedule, has as its intent the same' objective. That objective is to document the i 4 radiation and radioactivity levels in the critical pathways of l possible dose to humans. Such data is necessary to prove that I reactor radioactivity effluents produce environmental - concentrations -that are within appropriate environmental protection -limits and at the same time are as low as reasonably achievable. During 1990, there was the following change in the sampling program: F 'A-26 dairy (Feichtner, 15152 WCR13, Longmont)-went - e out of business.- The-new A-26 location in-1990 was the Dochef t dairy, approximately: 1 mile west of F Feichtner's. The'Docheff address'is 4513 WCR_32,- L g -Longmont, 00. . Table III.B.1 gives the description of 'each - sampling location by number, sector and distance from the reactor.- t Each ofl these sampling locations (except certain reference locations) can be identified on scale maps-(Figures-III.D.1 111- t
and III.B.2). Topographical maps showing greator detail, as voll as photographs of principal campling sites are on file in the CSU Inboratory. During September 1990 the land-uso connus was conducted to determine the locations of the nearest residenco, the j 1 nearest milk animal, and the nearest garden producing broad leaf vogotation in each of the 16 meteorological sectors around the reactor. Those locations by address are shown in Tablo III.C.1. Figure III.c.1 shows those locations in cach sector. At the time of the 1990 consus it was verified that the closest, permanent residence in Sector 16 was the critical receptor with regards to mean annual doso commitment and is at the Russell farm F-16. A few residents in the sampling sectors up to a distanco - of 8 km from the plant have cows or goats that could be used for personal milk consumption. However, from direct discussion with those persons, this is not a common practico and all cow milk produced is transported to commercial processors. The milk produced locally is diluted by a largo milk - shed, processed and _ distributed over -a- largo area for consumption. For this reason the elevated I-131 in milk from A-22 would never be detected in the composited milk supply. Tablo III. A.2 lists the LLD concentration values for each sample type and radionuclido measured in this report. These LLD values are the actual values portinent to the samplo sizes,- counting yields, and counting timos used in the project. Typical decay periods were used in the calculations. l 112
. - . - . . . . . . - . ~ . . . - - - . ..-. ....-.- . -
,i a l It should be noted that the LLD values are in all cases equal ' i to or less than those required by the technical 3 specifications. Table III.A.3 lists the USNRC reporting level for each sample type and radionuclide. I 4 4 a 4 4 i i I 113_. L. . .- . .. - ._ -. -. .. -
Table III.A.1 Operational Radiological Environmental Monitoring Program SempIIng Type end f reqseency 8bember of Geoples of Analysis fpposure Pathway and locetlens Collection frequency essd/or Seeple 9 AIEBofVa[ Contlntrous sempler operetten Redfolodine Centster: Irltlete Omide Samples from seven locationst
~ with eseple collection weekly Analyze weekly for l-Ill Sedigindino and or se required by duet loedlag, liquid scintillet8an restloulates f our semplos free off-site tocations vfilchover is more frequent, couaittag for tritium en
[In allf ferent sectore) of tIso highest water veper estracted calculated annual everage ground from ellice get on eeth level D/Q ond eleborne X/4. seeple collected. one semple from ties vicinity or e Particsslate 5eepler: community Inowlps tino histrest calculated Crose bete radioactivity annual overeSe ground level D/Q. f ol lowlsul f i l t e r cleewre. coopeal te (by f oce t ten) Two semples from control location for geese l 15 to 30 kilomotors (10 to 20 mIIest quarterly.jogopic distent and in tlie least prevalent , wind direction. Ceems dose q*eertmety. Quarterfy espesure. estpfCI DADIAfsO4 f orty stations with two or more dosimeters or one Instrument for moesuring and recording dose tote )
,, continuunsly to be pieced as follows: t es
- 1) en Inner ring or stettons in tfie i
general eree of tive site boundary and ses e.eter r ieeg in sl e 4 to 5 ofto rense from tiie site witti e station In eacts soctor of escle ring {l6 sectore w 2 risegs = 32 stettons). Ifm betence of t ies stations, eight, shall be placed Ist special Interest stees sucts en population centers, nearby resldences, scisou l s, and in two or three stees to servo es control stations. l W4 f i nnOF fil semples collected monthly. Comme fseteric enetys3s Sierf ace One soepte upstrose, eacts st room, one end trittue contlly. l soggelo dowtis t ream. Ceeme Isotopic enssysis One s o ng. 8 e in l eme.f i s t e s t ee of Comp ette a s epl e ove r one and composite for tritium 5.e r r a c e Week period. The weekly d i sclie rge. compositet wili be coetsined ansva t ti t y. (Ieen Fossd) for tino monthly seople. a esople for any med f ue, geese laatopic f( grass i.ete activity in sir or wate,,r ,ledivi
.rro, sed en ti.e Lrester tisen ten tjees the yearly seen of contret et e.e,ies.
e.el,sie s.,. .d be
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no . I.e.t.pte fd rs.doct. On. . ..p 8. e. . .acle prissoir.8 et... .t At tt .t 94.tv..t. f d pe.d ct. r e .ny .e.. wt.f css 8. S te ig.t.d by v.t er 8ee wielet. S tatie8d ' pl.nt w..e.. h... b... dt.ch.rg... I i l
- 1. tle.d.s ee.py e.e.t.le d 8s. W.ye.8 4.ty eseed. 8. tery d i
d... 8.s t 8 4.. c t ee.l e t.d t.r tl . I.ee. .s g.se .e.d .g. g e.e.p es. 8 se, tee. 18 tt e .et. t p.t. t.r. p.rt icset er to 49 site.
- l
9 l 5 I i I i_ Table III.A.2 Detection Capabilities for Environmental Sample Analysis ( 1 Lower limit of Celection (LLD)* Analysis Mater Airborne Particulate Fish Illik Food Products Sediment (pC1/t) or Gas (ICl/m 3 ) (pCf /kg wet) (pct /t) (pCl/1,9 wet) (pC f /kg. dry ) c.ross neta 3.06 3.25 11 - 1 494
-- I-131 0.09 66.4 0.09 56.0 ;; Cs-114 S.50 0.06 19.5 4.90 44.4 90.6 Cs-ITI 6.60 7.86 18.5 6.14 44.6 100 !
Ir-95 10.12 lib-95 4.12 . Co-$n 4.60 12.0 fin-54 4.60 12.7 7n-65 10.94 23.6 re-59 0.40 31.4 Co-60 4.40 14.5 Da-140 6.66 0.00 La-140 7.66 9.16
- As suggested in IIUREG-0472. All values are at or below values IIsted in Table 8.2-2 of technical specifications.
Tao s e Il f. A. 3 Reporting Levels for Nonroutine Operating Reports l
. gitmI1nc trytts ton nonneurist ortnarinc nrron n Ef raflTInG t EVEL f ntt lis t o r Altbortse Fertinulate or Cas Ilsh Hilk Broad Leaf Vegatetton Aestysts (pCl/ f] (pCI/m3).- (pCl/kg, wet) (pCI/fj (pCI,&g, wet]
l 8s( a ) ' 41- 3 2m 10 3 % i the-54 1m to 3x to 2 4 In-59 4m to I w to 3 4 l Co-SS 1x 10 3x 10 2 4 Ce,- 60 3m in 1 m to w Z % y In-65 3x to 2m 10 2 ses,-95, Z r- 95 8: M to 2 s-13s 2 0.9 3 1m to 3 3 Cs-834 30 10 1 w to 60 Iw 10 3 3 Cs-83F 30 20 2 x to 70 2m to 2 % De- 18e0, t s- t %0 2 m to 3 x to e for drinking vetor samples. This Is 40CTR Fort 141 value.
- i 1 ;
] ! l Table III.B.l.. Radiological Environmental Monitoring Program (continued) sampling site Descriptions (F: Facility Area 0-1.6 km. A: Adjacent Area 1.6-8 km. R: Reference Area) , . Exposure Site No. Location Description (see map) Sector Distance,; I Pathway I km ;
- Direct Radiation F-1 ' Pole by gate to Goosequill road on dirt extension of 1 1.3 4 CR 21.
F-2 21st pole N .of ditch on dirt extension of CR 21 'just 2 1.1 1 before road drops down to river bottom.
~
F-3 17th pole N of ditch on dirt extension of CR 21 or
- 3 0.7 first pole N of E-W road.
F-4 15th pole N of ditch on dirt extension of CR 21, S of 4 0.7 pump road, midway between F-3 and F-5. F-5 lith pole N of ditch on dirt extension of CR 21, near 5 0.6 drive to pump house. F-6 8th pole N of ditch on dirt extension of CR 21, 6 0.8 by E-W concrete ditch, S of bridge. F-7 Old dairy barn, 1st pole N after crossing ditch on 7 1.2 dirt extension of CR 21. F-8 lat pole W of pump house on N side of road 0.4 km E 8 1.3 of CR 191 F-9 Pole E of first shed at intersection of CR 191 9 1.5 and CR 34. F-10 Pole on NW corner of intersection of dirt extension =10 1.5 of CR 19 and 34.
l Table III.B.1 Radiological Environmental Monitoring Program (continued) Sampling Site Descriptions (F: Facility Area 0-1.6 km. A: Adjacent Area 1.6-P km. R: Reference Area) Location Description (see map) Sector Distance, Exposure Site No. km Pathway _._ j Direct Radiation F-11 7th pole H of intersection of dirt extension of CR 19 11 1.2 l I with CR 34. F-12 0.5 km S of FSV Visitor Center take dirt road W 12 1.0 across field, go into farmyard of Aristocrat Brangus. (If chain across road enter from CR 36). TLD is [ located on pole at SE corner of corral across from o Aristocrat Brangus office. F-13 Take first dirt road S of Visitor Center. Go W across 13 0.5 railroad tracks, follow dirt road to metal staircase going down off dike. TLD is taped to railing. F-14 2nd pole 0.1 km S intersection CR 361 & Rd 19. 14 1.5 F-15 2nd pole 0.7 km S of intersection of CR 38 on CR 19. 15 1.5 F-16 Pole at NE corner of potato cellar at 3 Bar Ranch 1 1.2 (Russell's). F-17 Visitor Center, on N end of cross beam over entrance. 13 0.2 F-18 Pole closest to house on SW corner, 17250 CR 191 16 0.8 I The address of 17250 is taped to the Mountain Bell underground cable warning post.
Table III.B.1 Radiological Environmental Monitoring Program (continued) Sampling Site Descriptions (F: Facility Area 0-1.6 km. A: Adjacent Area 1.6-8 km. R: Reference Area) Exposure Site No. Location Description (see map) Sector Pathway Distance ( km Direct Radiation A-1 Pole on NW corner of intersection of CR 44 and CR 21. 1 6.7 A-2 Pole on NE corner intersection of CR 42 and CR 251 2 6.8 A-3 Pole on NE corner of intersection of CR 42 and CO 60. 3 7.5 y A-4 1st pole NE of intersection of CR 29 and CR 38, take 4 7.4 CR 29 E out of Gilcrest to CR 38. A-5 SE corner of CR 34 and CR 29. Taped to road sign on 5 7.2 SW corner of intersection. A-6 Pole on S side of CR 32 near drive to dairy 13278 CR 6 7.1 32. A-7 Niles Miller dairy. O.4 km E of US a5 on 12854 CR 30. TLD is located on pole at NE corner of house. 7 7.3 A-8 On CO 66 (CR30) farm on S side of road (address 9476) 8 4.7 Pole in front of house. A-9 Corner of CO 66 (CR 30) and CR 19, Miller produce 9 4.6 stand. Second pole S on CR 19, on E side of road. A-10 Pole on SE corner at intersection CR 261 & CR 15. 10 7.8 A-11 At intersection of CO 66 and CR 13, 2nd pole N of 11 7.2 intersection on E side of CR13.
Table III.B.1 Radiological Environmental Monitoring Program (continued) Sampling Site Descriptions (F: Facility Area 0-1.6 km. A:. Adjacent Area 1.6-8 km. R: Reference Area) Exposure Site No. location Description (see map) Sector Distance,l Pathway km Direct Radiation A-12 On CR 34, pole E of house N of Lake Thomas 2 km from 12 7.2 I-25. A-13 Pole opposite lake, N of milage pits E side of CR 13 13 5.8 2.9 km N of CR 34. N A-14 Intersection of CR 13 and CR 40, NW corner. 14 6.9 A-15 Intersection of CR 42 and CR 15, NW corner. 15 6.7 A-16 Intersection of CR 44 and CR 19, SW corner. 16 6.8 A-17 Platteville school (S edge of town on Main St.) 6 5.9 pole on NW corner just outside school intramural field. A-20 let pole N of white picket fence and driveway 9 2.5 into turkey farm on S and of building that is parallel with CR 19.
,_ - , , . ,.% .=-e- -rww.',,
,w ww... - -E e; -'
t. i-1,' Table III.B.1 Radiological Environmental Monitoring Program (continued) , sampling site Descriptions l r j-(F: Facility Area 0-1.6 km. A: Adjacent Area 1.6-8 km. R: Reference Area) t l Exposure Site No. Incation Description (see map) Sector Distance a
- Pathway _ km ,
i i i Direct l Radiation R-1 Milliken School, on CR 21%. TLD is located on pole 9.3
- which is located at SE corner of Lola park, across j the street from school.
t I, t i R Johnstown School (Ietford Elementary), turn lef t at 10.8 ! school crossing on Idaho St. onto Jay Ave. and proceed I g to school. TLD is located on pole at SE corner of main ' im. entrance to school on W side of town. i
- i I
R-3 CSU dairy farm on W Drake, N of Vet Hospital, Ft. 45.1 Collins, CO.. Pole is E of hay barn next to ' railroad tracks. l
' R-4 Air sampler corner US 287 and CO 66, Longmont Dairy 20.5 [
Store. TLD is located on pole directly behind air [ j sampler. i j R-7 Behind Gilcrest School quonset auditorium, pole 9.3 ) on SW end of school property, just before garage.
- l Waterborne I i
, Sediment from Shoreline [ } R-10 Sediment from S. Platte River at bridge on CO 60. 10.1 l l ,
b t I 1 i I l' e l 1
Table III.B.1 Radiological Environmental Monitoring Program } sampling site Descriptions (F: Facility Area 0-1.6 km. A: Adjacent Area 1.6-8 km. R: Reference Area) Location Description (see map) Sector Distance, Exposure Site No. km Pathway 7 1.5 Airborne F-7 Farm at intersection of CR 21 and CR 34. Air sampler is located on west side of shop. Silica ' gel inside building on N end of. workbench. F-9 First shed along drive at end of Rd 191 intersection 9 1.5 with Rd 34. Silica gel is located in shed. 16 1.2 F-16 Potato cellar at 3 Bar Ranch (Russell's) . Silica gel in mailbox on tree to S of pump. , Hunting cabin between Goosequill ditch and Platte 1 1.7 A-19 River. Air sampler is on W side of cabin, silica gel is in box on tree north of air sampler. Colorado State University Dairy, W. Drake Rd., Ft. 45.1 R-3 Collins, CO. W side of shed directly H of main dairy building. Silica gel inside mailbox. Intersection of US 66 and US 287, E side of dairy 20.5 R-4 store, north edge of Longmont. Silica gel is in mailbox attached to utility pole. R-ll Air sampler is located in alley behind PSC office, 10.5 next to garage. Silica gel is located next to air sampler in mailbox and on top of post, 13 1/2 Parish St., Johnston, CO.
~ __,
'1 Tablo III.D.1 Radiological Environmental Monitoring Program (continued) Sampling Site Descriptions (F: Facility Area 0-1.6 km. A: Adjacent Area 1.6-8 km. R: Reference Area) Exposure Site No. Location Description (see map) Sector Distance, Pathway km Waterborne Surface l'-19 S. Platte at dam located on dirt road E of pump 4 1.2 house #3 directly E of reactor.. F-20 St. Vrain creek on Rd. 191 0.3 km from discharge 16 1.5 into St. Vrain creek. Directly N of reactor. U a A-21 St. Vrain creek at bridge on Rd. 34, E of Rd. 19. 11 2.4 A-25 Goosequill Pond outlet. Continuous sampler located 1 2.2 in green box adjacent to the green shed on the N end of the pond. R-lO S. Platte river at bridge on CO 60 where highway 10.1 has just turned and headed South. Ground F-16 Well behind residence at 3 Bar Ranch (Russell's), 1 1.2 17578 WCR 19 1/2. R-5 Well at 108 S. Grace, Milliken. 9.5 Drinking R-3 CSU dairy W Drake Rd., Ft. Collins, CO, N of 45.1 Vet Hospital. Water sample is taken from hydrant inside the entrance to the milking parlor. R-6 Gilcrest U.S. Post Office located on Birch St. and 9.3 Rd. 40 off of Hwy 85. Water taken from utility sir.k inside Post Office.
Table III.B.1 Radiological Environmental Monitoring Program (continued) sampling Site Descriptions (F: Facility Area 0-1.6 km. A: Adjacent Area 1.6-8 bs. R: Reference Area) Exposure Site No. Location Description (see map) Sector Distance, Pathway km Ingestion Milk A-6 Hendrickson Dairy, 13278 Rd. 32 (Grand Ave.) 6 7.1 1.6 km E of US 85. . A-18 Boos Dairy, 11258 W Rd. 40, W of US 85 behind 2 4.7 _ nodular home. ro A-22 Percy Odenbaugh Dairy, S on dirt rd from "LeRoy & 5 3.2 Paul Odenbaugh Dairy" sign. Dairy sign on WCR 36, E of Rd 23. Dairy sign is located next to mailbox of Mike Thomas. A-23 Leroy Odenbaugh Dairy, 11733 Rd 36, W of Rd 25. 4 4.1 A-24 Marostica Dairy, 20718 Rd 17, 4 miles S of CO 60. 16 6.9 A-26 L & F Dairy (Flechtner), E of Rd 13 on Rd 32. 11 7.8 6165 WCR 32. R-8 Gorzman Dairy, 2056 S. CR 17, located off exit $255 22.5 W of I-25 dirctly H of Johnson's Corner restaurant. Fish F-19 S. Platte at dam located on dirt Rd E of pump 4 1.1 house #3 directly E of reactor. A-25 Goosequill pond outlet. 1 2.2 R-10 S. Platte river at bridge on CO 60. 10.1
~_ _._. __
1 l 3-
'l I
3 .. 1 Table III.B.1 Radiological Environmental Monitoring Program (continued)
- Sampling Site Descriptions (F
- : Facility Area 0-1.6'km. A: Adjacent Area 1.6-8 km. R: Reference Area) l Exposure Site No. . Incation Description (see map) Sector Distance o Pathway ka i
] Food Products. A-27 Fields on SE corner of ' intersection 4 4.3 of WCR 25 and WCR 38. A-28 Residence 11399.WCR 401 2 5.3 l R-6 Hernandez Produce Stand, Highway 85, Gilcrest. 9.6
.i l
4 l e i I l a _s. -. _ --
Figure !!I.B.1
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l Tablo III.C.1 1990 Land Uso consus* l Sector Nearost Nearest Nearent Mll). - Rosidence Garden Animal i 1 17578 CR 191/2 9626 CR 44** *** i 1 2 18311 CR 23 18999 CR 23 11283 CR 40-1/2 ) 3 11100 CR 38 11100 CR 38 11165 CR 38 4 11247 CR 36 11777 CR 36 11777 CR 36** , 5 16543 CR 23 16134 CR 23 16134 CR 23 6 11056 CR 32 11585 CR 32** 11585 CR 32** 7 9999 CR 34 9999 CR 34** *** ; 8 15883 CR 21 14605 CR 21 15152 CR 13** ; 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** l N- 12 Aristocrat 6519 CR-34 5492 CR 34 ! Ranch 13 '17038 CR 17** 17038 CR 17 *** 1 14 8896 CR 19. 8896 CR 19 *** 15 9115 CR 38 9115.CR 38** *** ! 16 9239 CR-30 19751 CR-19** 18986 CR 19**
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* 'Consus-Date Sept. 7, 1990
, ** Now Location l *** No' milk animals 129
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