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-16805 WCR 19 1/2,_Platteville, Colorado- 80651 N' April 24, 1992-Fort-St. Vrain I Unit No. 1 i+ P-92173' h U.-S. Nuclear Regulatory Commission if | |||
^ | |||
. ATTN: Document Control Desx Washington,.D. C. 20555 Docket No. 50-267 | |||
==SUBJECT:== | |||
.. ANNUAL PADIOLOGICAL ENVIRONMENTAL MONITORING L -REPORT Gentlemen: | |||
,EnclosedI plear:e' find a copy of the Fort St. Vrain Nuclear Q Generating 1 Station Radiological Environmental . Monitoring C; Program Annual Summary-Report for 1991. The report is submitted -in accordance with Section 7.3.1.d of. the Fort | |||
-St. Vrain Technical-Specifications:and 10 CFR 50.4. | |||
=Please contact Mr. M. H. Holmes at (303) 620-1701 if you have any questions regarding the report.- | |||
, Sincerely, | |||
$)Y ' )Ygw./n , | |||
D. W.=Waremboucy Manager, Nucleo Operations DWW/lmg Enclosure. | |||
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010Ci 9205040206 911231 PDR- ADOCK 05000267 | |||
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i P-92171 Page 2 cc: Regional Administrator, Region IV Mr. J. B. Baird Senior Resident Inspector Fort St. Vrain-kr. Robert'M. Quillin, Director Radiation Control Division Colorado Department of Health 4210 East lith Avenue | |||
. Denver, CO 80220 L Dr. Jim Johnson Colorado State University R3diation & Radiation Biology Fort Collins, CO 80521 1 | |||
1 | |||
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PUBLIC SERVICE COMPANY OF | |||
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PROGRAM | |||
==SUMMARY== | |||
REPORT 1991 COLORADO STATE UNIVERSITY FORT COLLINS, COLORADO 80523 | |||
=. . . . . _ . . _ . _ _ - . ~ . . _ _ . . _ . _ . _ . _ . _ _ _ _ _ . _ _ _ _ _ _ . | |||
i RADIOLOGICAL ENVIR0!TMENTAL MOK TORING PROGRAM For the Fort St. Vrain Nuclear Generating Station Operated by the Public Service Co. of Colorado Summary Report for the Period Janusn 1 1991 - Dacember 31. 1901 D | |||
/ d'% 4 /,, / O 2_. - | |||
Prepared by: | |||
J ar E. Johnson,(Professor ' Da't e i Colo. ado State University Reviewed by: llt & b! .lh ASF 4[I4!92.- | |||
Date Ra'11ochemistry SubervUjs Approved by: M hk6 b !/d 2-RadiationProgtionManager Date i | |||
1 | |||
;7 v | |||
6.eknowledaements - | |||
Many persons have contributed to this project during 1991, and it is important to acknowledge their effort. We first thank the citizens from whose farms, homes, and ranches we collect the environmental samples. Without their cooperation the project would not be possible. | |||
We also wish to acknowledge and thank Mr. Robert Keiss and his associates- as well as the Colorado Division of Wildlife, Fort-Collins regional office for assisting with the fish collection. | |||
l Without their cooperation, equipment and expertise the collection | |||
.would not be possible. ' | |||
The persons working directly on the project have been: | |||
Faye Bruno Chief Laboratory Technician Norma Frisby Secretary Thomas Miller Student Employee Steven Ziliak Student-Employee Charles Sampier Chief Electronic Technician Christopher Roelle Student Employee | |||
[ bt9- | |||
* g . | |||
James Johnson PrhfMssor and Project Director. | |||
l i | |||
l i' | |||
l-I . -, , | |||
. . . .. .- . . .. . . . .. w | |||
. TABLE OF CONTENTS Page No. | |||
Acknowled5ments 11 List of Tables- iv List of_ Figures vi I. INTRODUCTION 1 i | |||
II. SURVEILLANCE DATA FOR 1991 ) | |||
AND INTERPRETATION OF RESULTS l l | |||
A. External Camma Exposure Rates. 6 l | |||
B. Air Sampling Data 10 j | |||
:C. Water Sampling Data 35 D. Milk Data 69 E. Food Products 80 F. -Aquatic Pathways 82 G. Sample Cross-check Data 85 H. Summary and Conclusions 93 III. ~ ENVIRONMENTAL RADIATION SURVEILLANCE-PROGRAM AND SC11EDULE 112 | |||
LIST OF TABLES Page 1o. | |||
II.A.1 Gamma Exposure Rates, 8 II.B,1 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 | |||
-t II.B.2 Tritium Concentrations in Atmospher!c Water Vapor. | |||
: a. First Quarter, 19 | |||
: b. Second Quarter, 20 | |||
: c. Thir d Quarter, 21 | |||
: d. Fourth Quarter. 22 II.B.3 Tritium Concentrations in Air, | |||
: a. First Quarter, 23 | |||
: b. Second Quarter, 24 | |||
: c. Third Quarter, 25 _ | |||
: d. Fourth Quarter, 26 II.B.4 Tricium Released in Reactor Effluents. 27 II.B.5 I-131 Concentcations in Air, | |||
: a. First Quarter, 30 | |||
: b. Second Quarter, 31 | |||
: c. Third Quarter, 32 | |||
: d. Fourth Quarter, 33 II.B.6 Radiocesium Concentrations in Ambient Air. 34 | |||
^ | |||
II.C.1 Gross Beta Concentrations in Bi-weekly Composites of Drinking Water. 37 i | |||
T3 | |||
* 1 LIST OF TABLIS (Continued) l Page No. | |||
Tritium Coucentrations in Bi-weekly Composites II ~. C . 2. | |||
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 ) | |||
l 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 Water. 65 II.C.8 Mcximum Permissible Concentrations in Water. 68 | |||
/ | |||
~ | |||
t II . D .' 1 Radionuclide Concentrations in Milk. 72 II.D.2 . Tritium Concentrations in Milk, 78-II.E.1 Radionuclide. concentrations in Food Products. 8l II.F.1 Radionuclide Concentrations in Fish. 83 | |||
'II,F.2 Radionuclide Concentrations in Sediment. 84 II.G.1 EPA Cross-check Data. 88 II.G.2 Tritium Concentrations in Cross-check Data, CSU. Colorado Dept. of Health-PSC, 90 II.G.3 Gross Beta Concentrations in Water Cross check Data,- | |||
CSU-Colorado Dept. of Health PSC. 91 II.G.4 'Intralaboratory Cross-check Results. 92 II.H.1 Data Summary, 100 II.H.2 Arithmetic Means of Selected Sample Types, 109 , | |||
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 i III.B.1 Sampling Locations for Environmental Samples, 118 III.C.1 Land-use Census, 1991, 129 L | |||
V , | |||
LIST OF FIGURES Page No. | |||
Figure - II . A',1- Gamma' Exposure Ratas, 1973 1991 9 | |||
- Figure II.B.1. Cross-Beta Concentrations in Air 16 | |||
. Figure II.C.1 Tritium Concentrations at Site F-16', 1984-1991 66-Figure II.C.2 Tritium Concentrations at Site F-16, 1984-1991 67 | |||
- (Showing weekly sampling reruits beginning in 1991) | |||
Figure.III.B.1 Close-in Sampling Locations 127 _ | |||
Figure IIIIB.2 Adjacent anu Reference Sampling Locations 128 Figure III.C.1 Land Use Census, 1991 130 e | |||
u _- | |||
= _2_____. . . . .. | |||
. - - -~ . . - . _ . - . . , .. .~ - - . . - . -- - . . . . , . . | |||
~ | |||
.I . ; iIntroduction ' tof Radiological Environmental Monitoring | |||
~ Data.for the Period January 1, 1991 - December 31, 1991. | |||
During 1991 the Fort St. Vrain Nuclear Generating Station did not operate and is presently in a defueling phase. | |||
The operational phase of the reactor ended on August 13, 1: 1989. -Fuel removal operations began October 6, 1991. | |||
A complete and' detailed listing of radioactivity released by all effluent routes may be found.in the Public Service Company of Colorado cemi-annual Effluent Release Reports for y | |||
1991 to the U.S. Nuclear Regulatory Commission. When possible . | |||
-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 1991 on project samples. | |||
These values are given.for typical sample sizes, counting times and decay times. The LLD is, therefore, an a priori parameter to | |||
,- -indicate the capability of the detection system used. The-LLD values in Table III. A.2 were calculated as suggested in NUREG- | |||
-0472. | |||
Throughout the report,-however, when a sample result is-listed as less than a specified value, that value is the L . calculated MDC (mini.aum detectable concentration). This. | |||
-approach is analogous to that of Currie (NUREG/CR-4007): | |||
the l | |||
L. | |||
MDC is the same_as S,, the critical signal, and the LLD is equal to S 3, the' detectable signal. The MDC value appliew to the actual : sample size, counting time and decay time | |||
-applicable to that individual sample. It is calculated as: | |||
MDC = 2. 3 3 03 / E Y V e4' Where: on = Standard deviation of background count rate E = Counting efficiency, c s 4 pCid Y = Chemical yield V = Sample volume (or mass) | |||
L 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 - lesc than the actual MDC _ value. .Because . the _ MDC is dependent upon variables such as the b'ackground count time and sample size, the value vil1 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 due to 2 | |||
= | |||
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 i | |||
l large, and it is necessary to use mean values from a rather large sample population size to make any conclusions about the l | |||
absolute radioactivity concentrations in any environmental ! | |||
l pathway. i The arithmetic mean for each sample set is listed in l Table -II.H.2. All measured values, both positive and negative, are used in the calculations of the arithmetic mean. | |||
This is the suggested practice by-Gilbert (Health Physics 40:377, 1964) 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 i | |||
not significantly different, the confidence for the statement is at the 95% level (a = 0.05) (1.960). | |||
-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 l specified individual member of the general public. That value is-500 mrem / year, but must include the dose from all possible < | |||
l sources, and, therefore, cannot be solely due to reactor s | |||
3 | |||
1 effluent. As stated in 10CFR20 these are the maximum concentrations above natural background that a licensee may release to an unrestricted 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 specified 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. These 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 uset .or comparison purposes. | |||
A limit that does apply is the independent naximum permissible dose commitment rate set by the E.P.A. (40CFR190) | |||
-for any specified member of the general public from any part of the nuclear fuel cycle. This value is 25 mrem / year, the dose rate to the whole body from all contributing radionuclides excluding background and medical radiation dose rate. | |||
Dose commitments are calculated for hypothetical individuals for any mean concentrations noted in unrestricted areas that are significantly above control mean values. | |||
] | |||
I The followinglis the-footnote system used in this report. I | |||
: a. Sample-lost prior to. analysis. | |||
: b. -Sample missing at-site, q i | |||
: c. Instrument-malfunction. .) | |||
1 | |||
: d. Sample lost during analysis. I | |||
: e. Insufficient weight or volume for analysis. | |||
4 | |||
: f. Sample-unavailable. j l | |||
: g. Analysis in progress. ] | |||
h.- Sample not collected (actual reason given). | |||
: 1. . Analytical 1 error (actual reason given). | |||
N.A. Not applicable. | |||
e 1 | |||
5 | |||
II. Surveillance Data for January Through December 1991 and | |||
-Interpretation of Results A. External Gamma-ray Exposure Rates 1 | |||
The average measured gamma-ray exposure rates expressed in -- nR/v ay--. 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 installed at each site and the mean value is reported for that | |||
; 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 locatio. | |||
Fading during field exposure is minimized by the post-anrealing readout procedure. | |||
TLs TLD data indicate that the arithmetic mean measured exposure rate.in the facility area for all of 1991 was 0.37 mR/ day. :The mean exposure rate was 0.39 mR/ day for the adjacent area and 0.39 mR/ day for the reference area. These latter mean values were not significantly different from each , | |||
other and identical to the values measured during 1990. | |||
The exposure rate _ measured : at all sites is due to a combination of exposure from cosmic rays, from natural gamma-ray emitters in the earth's crust and from ground surface deposition of fission products due to previous world-wide o | |||
3 fallout. The variation in measured values is due to true l | |||
l-6 l' . .- . ~ .- , | |||
o l | |||
variation of the:above sources plus the variation due to the measurement method. The purpose of having two TLD rings around 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 exttirnal 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 l scattered gamma-ray flux produced in a cavity surrounded by l-uranium mill tailings. This produces a gamma-ray spectrum nearly identical to that from natural background measured in the-. reactor environs. The quality control program includes calibration before readout of each quarterly batch of TLD | |||
-devices. | |||
For comparison purposes, in EPA 520/5 Report #58 lists very _ similar background external exposure rate values in l | |||
Denver. There has always been excellent agreement with the t- results from this program.' | |||
l Figure II.A.1 shows the measured mean exposure rate in the Facility Area - since the inception of the program. The steady decrease.in exposure rate over the period is due to the decay and welthering of fission product deposition from i | |||
-: previous atmospheric weapon tests. | |||
7 l | |||
... Table II.A.1 Gammma Exposure Rates. (mR/ day) 1991 Facility Area -1st Quarter '2nd Quarter 3rd Quarter 4th Quarter | |||
~~ | |||
F-1 0.39 0.34 0.40 0.39 F =0.43 0.35 0.35 0.34 F-3: 0.40 0.37 0.33 0.45 F-4 0.39 0.36 0.33 0.32 F-5 0.41 0,39 0.41 0.26 F-6 0.40 0.34 0.39 0.25 F 0.43 0.40 0.37 0.26 F-8 0.40 0.36 0.39 0.42 F 0.43 0.35 0.36 0.24 F-10 0.43 0.36 0.40 0.36 F-11 0.42 0.36 0.38 0.36 F-12 0.40 0.38 0.27 0.46 F-13 0.39 0.36 0.31 0.44 F-14 0.38 0.39 0.27 0.50 F-15 0.39 0.38 0.37 0.53 F-16 0.40 0.32 0.39 0.26 F-17 0.42 0.35 0.40 0.20 F-18 0.43 0.36 0.38 0.34 7 (1.96o) 0.41 (0.03)* 0.36 (0.04) 0.36 (0.08) 0.35 (0.19) | |||
Adjacent Area ' | |||
A-1 0.43 0.38 0.41 0.58 A 0.41 0.40 0.45 0.57 | |||
. A-3 0.43 0.34 0.42 0.40 A 0.44 0.33 0.38 0.37 A-5 0.39 0.34 0.35 0.43 A-6 0.42 0.37 0.34 0.25 A-7 0.41 0.36 0.40 0.34 A-8 0.39 0.37 0.42 0.35 A-9 0.41 0.38 0.42 0.32 A-10 0.38 b b b | |||
, A-11 0.36 0.35 0.40 0.27 A-12 0.38- 0.39 0.36 0.32 A-13 0.35 0.36 0.33 0.37 A-14 0.37 0.38 0.37 0.58 A 0.41 0.38 0.37 0.35- | |||
.A-16 0.40 0.35 0.37 0.35 A-17 0.42 0.37 0.39 0.57 A-20 0.40 0.38 0.40 b x (1.96o) 0.40 (0.05) 0.37 (0.04) 0.39 (0.06) 0.4t s0.22) | |||
Reference Area R-2 0.33 0.38 0.38 0.53 R-3 -0.40 0.31 0.37 0.35 R-4 0.40 0.35 0.36 0.39 F R-5 0.41 0.34 0.42 b R-7 0.39 b 0.37 0.47 x (1.96o) 0.39 (0.06)- 0.35 (0.06) 0.38 (0.05) 0.44 (0.16) - | |||
L | |||
^ | |||
b - sample missing at site | |||
* 1.96o (Due to Counting Statistics) | |||
Figure _11.A.1 Gamma Excosure Rates (mR/ day) | |||
(1973 - 1991) ' | |||
O.75 | |||
- 0.7 - | |||
a 0.65 - | |||
p . 0,6 - | |||
5 .55 0 - | |||
0,5 e a fjf M | |||
k a<s k,I" jhI,[~["\!f, . 5, \j "4 ' | |||
0.35 - ,a7 fSl | |||
/ - | |||
0.3 '''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''' | |||
74 75 76 77 78 79 80 81 82 83 84 85 86 -87 88 89 90 91 Year 9 | |||
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 each quarter of 1991. 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, however, termed | |||
-a f acility site since the inception of the monitoring prr ram. | |||
The reference sites R-3, R-4, and R-11 were established on 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 stationc for all of 1991 was 25 fCi/m. 2 For 1990 the mean value was 23 f Ci/m .3 The mean concentration for 1990 for all reference stations was 24 fCi/m . 3 These measured mean 10 | |||
- values were obviously not statistically significant at the 95% | |||
confidence-level. | |||
The gross beta data for 1991 have been added to the plot of air concentrations observed since 1973 (Figure II.B.1) . In this figure the half-yearly mean values for the facility sites l are plotted with the values from the reference sites. The contribution from Chernobyl is clearly evident in 1986. It can be observed that overall nean values are not significantly j different from each other. World-wide fallout,-principally due to past Chinese atmospheric nuclear weapon tests, is the l-l predominant contributor above background to tne measured l values over the period shown. - ' | |||
There has never been a significant difference observed between facility and reference sites. Thus, it can be concluded that reactor air effluents of particulate fission products or activation products during operation were not a 4 | |||
source of dose commitment for the Fort St. Vrain environs population. This is expected to be true as well during the defueling and decommissioning phusc. | |||
Y 11 | |||
~ - | |||
n | |||
~ | |||
b | |||
. Table 11.B.1 Concentrations of Long-lived Gross Beta Particulate Activity in Air. (fCi/m 1 l a) First Quarter,1991 I | |||
. . ' Facility Sites Reference Sites Collection , | |||
Date. F-7.- F-9' F-16 A-19 R-3 R-4 R-11 01/05.- 56 (2.1)* 65'(1.8)' 54'(1.8) 66 (2.0) 45 (1.9) 49 {1.9)' .'40 (1.7) 01/12 69'(2.4) 60 (1.8)' 61 (2.0). 69 (1.8) 49 (2.0) 58 (2.0)' LS8 (2.0) ; | |||
01/19 19 (1.5) 18 (1.1) 20 (1.3) 19 (1.1) 14 (1.1) 15 (1.2) 18 (1.3) 01/26 23 (l'.6) 20 (1.3) 25 (1.5) 24 (1.3) 22 (1.4) 19 (1.3) 23 (1.4) l 1 | |||
02/02 31 (1.7) 36.(1.7) 33 (1.7) 39 (1.8)' 28 (1.5) 22 (1.4) 29-(1.5) 02/09 33 (1.7) 29 (1.2) 32 (l'.5) 33 (1.4)- 25 (1.4) 24 (1.4) 29.(1.5) 02/16 31-(1.7) 29 (1.3) 29 (1.5) 29 (1.3)' 16 (1.2) 26 (1.6) 28 (1.6) k | |||
,_. 02/23 19 (1.4) 18'(1.1) 21 (1.4) 20 (1.2) 16 (1.2) 16 (1.3)' 20 (1.5) ; | |||
N 03/02 22 (1.6) 20 (1.2) 21 (1.3)' 21 (1.2) 20 (1.2) 22 (1.5) 21 (1.5) l | |||
: 03/09 13 (1.2) 14 (.94) 15 (1.2) 15 (1.0) 15 (1.2) 13 (1.2) 14 (1.1) l 03/16- 18 (1.2) 18 (1.1) 17 (1.2) 17 (1.1) 18 (1.?) 17 (1.3) 17 (1.4) ! | |||
03/23 23-(1.4) 21 (1.2) 22 (1.3) 22 (1.2) 20 (1.2) 22 (1.5) 22 (1.7) 03/30 18 (1.2) 14 (1.0) 16 (1.1) 17 (1.1) 16 (1.1) 17 (1.4) 17 (2.0) 7 29 .28 28 30 23 25 26 1.960 32 33 28 35 22 26 23 | |||
- MAX: 69 Y (1.96o): 29 (31) MAX: 58 i (1.96o): 25 (23) ! | |||
MIN: 13 n: 52 ~ | |||
MIN: 13 n:-39 - | |||
* 1.96o (Due to Counting Statistics) , | |||
W - _ - . _ _ - - _ _ _ _ - _ _ . _ _ _ _ - - _ - _ - - _ _ _ _ -- . . , ,~.. .- - | |||
Table II,B.1 Concentrations of Long-lived Gross Beta Particulate Activity in Air. '(fCi/m 3) | |||
.b) Second Quarter, 1991 Facility Sites Reference sites Collection Date F-7 F-9 F-16. A-19 R-3 R-4 R-11 04/06 33 (1.9) | |||
* 27 (1.3) .30 (1.5) 31 (2.8) 24 ti.3) 27 (1.7) 25 (1.3) 04/13 16 (1.2) 12 (.89) 14 (1.1) h' 15 (1.1) 16 (1.4) 13 (.92) 04/20 '21 (1.3) 20 (1.1) 19 (1.2) 20 (1.2) 22 (1.1) 22 (1.5) 26 (1.5) 04/27 18 (1.2) 20 (1.1) 20 (1.3) 19 (1.2) 19 (1.1) 20 (1.5) 18 (1.0) 05/04 14 (1.1) 13 (1.0) 14 (1.1) 14 (.94) 12 (.92) 19 (1.5) 14 (1.1) | |||
.05/11 24 (1.4) 19 (1.2) 24 (1.3) 23 (1.4) 28 (1.5) 23 (1.2) 22 (1.6) 05/18 17 (1.3) 14 (1.1) 17 (1.3) 16 (1.0) 15 (1.1) 20 (2.1) 16 (1.1) 05/25 22 (1.3) 18 (1.0) 21 (1.2) 20 (1.0) 19 (1.3) 32 (2.9) 18 (.98) 06/01 23 (1.1) 24 (1.1) 22 (1.3) 21 (1.0) 24 (1.2) 24 (1.1) 21 (1.1) 06/07 15 (1.2) 14'(1.0) 14 (1.3) 14 (1.2) 12 (1.0) 17 (1.1) 16 (1.1) 06/14 25 (1.3) 25 (1.2) 24 (1.4) 21 (1.2) 24 (1.3) 25 (1.2) 26 (1.3) 06/21 24 (1.3) 19 (3.3) 22 (1.3) 20 (1.1) 21 (1.2) 20 (1.2) 21 (l.2) 06/28 24 (1.3) 29 (1.5) 3.771.8) .19 (1.1) 23 (1.3) 25 (1.3) 23 (1.2) i 21 20 19 20 20 22 20 1.96a 10 11 13 8.8 9.9 8.6 8.7 MAX: 33 x (1.96o): 20 (11) MAX: 32 7 (1.96o): 21 (9.1) | |||
MIN: 3.7 n: 51 ' | |||
MIN: 12 n: 39 h - sample not collected (pump not functioning) , | |||
* 1.96o (Due ' to Counting Statistics) w,. e < , _ _ _ - - - - _ . _ _ . - . - - _ - - - . . _ - - - _ - | |||
Table II.B.1; Concentrations of Long-lived Gross 05ta. Particulate Activity in Air. (fCf/m ). , | |||
c) Third Quarter, 1991 Facility Sites Reference Sites Collection Date f-7 F-9 F-16 A-19 R-3 R-4 .R-11. | |||
07/05 20 (1.3)* 23 (1.4)- e 6.1(.78) 23 (1.3) -16 (1.1) 19 (1.1) | |||
-07/12 21 (1.3) 21 (1.2) 24 (2.0) 21 (1.2) 23 (1.3) 21 (1.1) 21 (1.2) 07/19 25 (1.3) 24 (1.2) 18 (1.9) 24 (1.2) 30'(1.5) 25 (1.2) 24 (1.2) 07/26 16 (1.1) 17 (1.0) 16 (1.1) 16 (1.0) 15 (1.1) 16 (1.0) 16 (.97) 03/02 30 (1.4) 29 (1.4) 28 (1.4)- 27'(1.2) 30 (1.4) 29-(1.3) 27 (1.3) 08/09 23 (1.0) 23 (1.1) 22.(1.0) 21 (.94) 24 (1.1) 24 (1.0) 23 (.98) 08/16 26 (1.2) 26 (1.3) 25 (1.2) 24 (1.2) 24 (1.2) 28 (1.2) 25 (1.2) 08/23 25 (1.3) 25 (1.5) 27 (1.3) 22 (1.2) 25 (2.1) 26 (1.2) 27 (1.3) 08/31 28 (1.3) 29 (1.8) 28 (1.3) 27 (1.2) 26 (2.0) 29 (1.3) 23 (1.1) 09/07 .32 (1.4) 20 (3.1) 34 (1.6) 32 (1.4) 34 (2.4) 34 (1.4) 25 (1.3) 09/14 1G (1.1) 17 (1.4) 17 (1.2) 17 (1.0) 20 (2.0) 18 (1.11 18 (1.1) 09/21 22-(1.3) 25 (1.6) 23 (1.3) 22 (1.2) 24 (2.2) 21 (1.1) 21 (1.2) 09/28 27 (1.5) 26 (1.7) 29 (1.5) 26 (1.3) 27 (2.2) 23 (1.2) 23 (1.3) | |||
T 24 23 24 22 25 24 22 1.960 9.1 7.6 11 13 9.3 11 6.6 MAX: 34 7-(1.96o): 23 (10) MAX: 34 x (1.96o); 24 (9.0) | |||
MIN: 6.1 n: 51 , MIN: 15 n: 39 e-- insufficient volume for analysis 1.960 (Due to Countin9 Statistics) | |||
4 4 . | |||
Table II.B.1 Concentrations of Long-lived Gross Beta Particulate Activity in Air. (fCi/m ); | |||
d) Fourth Quarter,.1991 Facility Sites Reference Sites Collection Date F-7 'F-9 F-16 A-19 R-3 R-4 R-11 10/05 28 (1.4)* 28 (1.6) .60(.68) 27 (l'.2) 27 (2.1) 27 (1.3) .29 (1.5) 10/12 4.9(.89) 25 (1.7) 2.0(.66) 1.4(.58) '69 (3.0) 15 (1.1) 15 (1.3) 10/19 27 (l'.5) 28 (1.9) 27-(1.5) 25 (1.3) 40 (2.0) 25'(1.3) 27 (1.7) 10/26 30 (1.5) 32 (1.8) 30 (1.5) 29 (1.4) 34 (2.3) 27 (1.3) 30 (1.6) 11/02 31 (1.4) 32 (1.6) 32 (1.4) 33 (1.3) 35 (2.2) 34 (1.3) 64 (3.3) 11/09 39 (1.6) 37 (1.8) 37 (1.6) 38 (1.6) 34 (2.3)' 26 (1.3) 34 (1.4) 11/16 23 (1.3) 22 (1.5) 24 (1.5) 23 (1.2) 20 (1.8) 20 (1.2) 21 (1.2) | |||
G 11/23 14 (1.0) 14 (1.3) 14 (1.2) 15 (.96) 12 (1.7) 13 (.97) 15 (.97) 11/30 20 (1.3) 20 (1.4) 20 (1.2) 20 (1.1) 20 (1.9) 17 (1.0) 22 (1.1) 12/07 24-(1.4) 25 (1.6) 24 (1.3) 23 (1.2) 20 (1.9) 20 (1.2) 22 (1.2) 12/14 33 (1.6) 36 (1.8) 34 (1.5) 35 (1.5) 28 (2.1) 28 (1.3) 32 (1.4) 12/21 37 (1.6) .41 (2.1) -38 (1.6) 24 (1.4) 39 (2.3) 33 (1.5) 31.(1.4) 12/28 45 (1.8) 48 (2.2) 46 (1.8) 46 (1.6) 41 (2.4) 34 (1.4) 39 (1.5) x 27 30 25 27 32 25 27 1.96a 21 18 26 22 28 14 29 MAX: 48 7 (1.96o): 27 (21)' | |||
M1H: 0.60 n: 52 MAX: 69 T(1.96o): 28 (25) | |||
MIN: 12 n: 39 | |||
* 1.96'o (Due to Counting Statistics) - | |||
r-i l | |||
Figure II.B.1 l | |||
10 2 - Gross Beta Concentrations in Air i 900 - ! | |||
800 - | |||
700 - | |||
600 - o---o Facility Samphng Stations 1 = 49 500 - | |||
Reference Samphng Stations 400 . X=55 300 - | |||
200 - a i / | |||
\ / | |||
\ / | |||
n \- f E \ l 1 N 100 - | |||
\ j f | |||
-Q 90 80 - | |||
(1 ; | |||
j l I | |||
70 -g l g j | |||
(' g 60 \ s o I i l 50 - | |||
\ | |||
I | |||
\ \ | |||
\ l 1 .. | |||
40 - | |||
a \ | |||
{ ; | |||
\ \ | |||
[\ \ | |||
\ | |||
l \,,A 20 ~ | |||
l * | |||
\ | |||
kb { | |||
\j/ \\ k | |||
\\ | |||
10 ' ' ' | |||
' ' ' ' ' ' ' ' ' t 1973'74 '75 '76 '77 '78 '79 '80 '81 '82 '83 '84 '85 '86 '87 '88 '89 '90 '91 '92 Time (year) | |||
J | |||
4 4 | |||
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 1991 is listed in Tables II.B.2a-2d. The corresponding tritium concentration in air (pci/m') is calculated from the specific activity data using weekly mean temperatures and dew points measured at the FSV meteorological tower. The measuring point is at a height of 2 m from the surface. The tritium air concentrations are i | |||
shown in Table II.B.3a-3d. 4 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 additional dilution, if necessary, to meet 10CFR20 concentration limits. The summary of tritium release by all modes is shown in Table II.B.4. The summary indicates that l the total tritium released in 1991 was 3.7X that released in | |||
$ 1990 by all routes. This effluent release was detected at nearly all sampling sites, but principally those close to the | |||
;. Goosequill ditch effluent pathway. | |||
-The mean . values for sites F-16 and A-19 were statistically the same as for all other sites during the year. | |||
In any case, inhalation is not a significant pathway for dose l to humans. | |||
The milk and food product pathway-is the-only l. | |||
L _significant source of radiation dose to humans from i | |||
17 | |||
,*r y- - , | |||
l environmental tritium. See results for these pathways in sections II.D and II.E. | |||
Since the same weekly relative humidity is assumed for all sites, Table II.B.3 shows the same site dependence on reactor effluent as Table II.B.2. Only the units used to measure tritium in surface air are different. | |||
18 | |||
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s i s n l c o i i i c t t 1 a s a 9 F i r 9 0 0 0 0 0 0 0 0 0 0 0 0 0 t t 1 9 0 0 0 0 0 0 1 0 0 9 0 9 0 a n - 4 4 4 4 4 4 4 4 4 3 4 3 4 t e , | |||
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a oa 1 1 1 1 2 2 2 2 3 3 3 3 3 T CD 0 0 0 0 0 0 0 0 0 0 0 0 0 | |||
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1 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 9 0 9 9 9 9 9 | |||
- 4 4 4 4 4 4 3 4 3 3 3 3 3 R | |||
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) e 4 0 0 0 0 0 0 9 0 9 9 9 9 9 L c - 4 4 4 4 4 4 3 4 3 3 3 3 3 | |||
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cp r e | |||
( f e | |||
R r 0 0 0 0 0 0 0 f 0 0 0 0 0 , | |||
o p | |||
3 0 0 0 0 0 0 9 0 9 9 9 9 9 - | |||
- 4 4 4 4 4 4 3 4 3 3 3 3 3 a 3 V. < < < < < < < < < < < < < . | |||
4 r | |||
e - | |||
t m | |||
, a W | |||
9 0 0 0 0 0 0 0 0 0 0 0 0 0 c 1 0 0 0 0 0 0 9 0 9 9 9 9 9 - | |||
i - 4 4 4 4 4 4 3 4 3 3 3 3 3 r A e < < < < < < < < < < < < < | |||
h p | |||
s o s 4 m e t t A i 6 0 0 5 0 0 0 0 0 0 0 0 0 0 S 1 0 0 0 0 0 0 9 0 9 9 9 9 9 . | |||
n - 4 4 4 4 4 4 3 4 3 3 3 3 3 m | |||
i y F t < < < < < < < < < < < < < | |||
s i n l o i i 1 c t 9 a a 9 F r | |||
1 0 0 0 0 0 0 0 0 0 0 0 0 0 w t 9 0 0 0 0 0 0 9 0 9 9 9 9 9 n , - 4 4 4 4 4 4 3 4 3 3 3 3 3 e r F c e < < < < < - | |||
n t o r C a u w m Q u | |||
i d 0 0 0 0 0 0 0 0 0 0 0 0 t n 7 0 0 0 0 0 0 A | |||
' 0 9 9 9 9 9 i o - 4 4 4 4 4 4 ' 4 3 J 3 3 3 r c F T e < < < < < < < < e < < < < + | |||
S 2 | |||
) | |||
b n B. | |||
I i o' | |||
I t c | |||
e e 6 ! | |||
" 0 7 4 1 8 5 1 7 4 1 8 l l e 0 1 2 2 0 1 1 2 0 0 1 2 2 b lt / / / / / / / / / / / / / | |||
a oa 4 4 4 4 5 5 5 5 6 6 6 6 6 T CD 0 0 0 0 0 0 0 0 0 0 0 0 0 v | |||
g ~ | |||
i, l ) j l | |||
F Table II;B.2 Tritium Concentrations in Atmospheric Water Vapor. (pCi/L) c) Third Quarter, 1991 i | |||
Facility Sites Reference Sites Collection Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 07/05 < 380 < 380 < 380' < 380 < 380 < 380 < 380 J7/12 < 390 < 390 < 390 < 390 < 390 < 390 < 390 07/19 < 380 < 380 < 380 < 380 < 380 < 380 < 380 1 | |||
07/26 < 390 < 390 < 390 < 390 < 390 < 390 < 390 , | |||
08/02 < 390 < 390 < 390 < 390 < 390 < 390 < 390 08/09 < 400 < 400 < 460 < 400 < 400 < 400 < 400. ' | |||
D! 08/16 < 390 < 390 < 390 < 390 < 390 < 390 < 390 4 | |||
I 08/23 < 390 < 390 < 390 < 390 < 390 < 390 < 390 08/31 < 400 < 400 < 400 < 400 < 400 < 400 < 400 | |||
,. 09/07 < 400 < 400 < 400 < 400 < 400 < 400 < 400 r | |||
I 09/14 730 (410)* 770 (410) 920 (420) 620 (410) 680 (410) 610 (410) < 390 i ! | |||
i 09/21 650 (370) < 350 800 (370) 960 (370) 710 (370) 620 (360) < 350 09/28 640 (370) 610 (360) 460 (360) 550 (360) 730 (370) < 350 350 (360) | |||
* 1.96o (Due to Counting Statistics) . | |||
r e | |||
me.- - , -m w | |||
i | |||
, e , | |||
Table II.B.2 Tritium Concentrations in Atmospheric Water Vapor. (pCi/L) d) Fourth Quarter,1991 Facility. Sites Reference Sites Collection Date F-7 F-9 F-16 'A-19 R-3 R-4 R-11 L | |||
10/05 < 390 630 (410)* 790 (410) 600 (410) 400 (410) 740 (410) 640 (410) 10/12 < 400 650 (420) < 400 700 (420) < 400 < 400 < 400 10/19 < 400 < 400 < 400 430 (420) < 400 < 400 < 400 10/26 500 (420) < 400 620 (430) 620 (430) 530 (420) 870 (430) < 400 11/02 610 (410) 670 (410) 470 (410) 690 (410) < 390 < 390 730 (420) 11/09 540 (420) < 400 < 400 560 (420) < 400 470 (420) 680 (420) g 11/16 780 (420) < 400 < 400 < 400 < 400 < 400 < 400 11/23 < 400 520 (420) < 400 < 400 < 400 < 400 470 (420) 11/30 < 400 520 (420) 730 (420) < 400 540 (420) < 400 < 400 1 | |||
12/07 < 400 < 400 530 (420) < 400 500(420) < 400 < 400 12/14 < 400 < 400 650 (420) < 4u0 ' | |||
450 (410) 620 (420) 540 (410) I 12/21 < 400 520 (420) 440 (420) < 100 < 400 770 (420) 530 (420) 12/28 < 410 < 410 < 410 550 (430) < 410 < 410 < 410 | |||
* 1.96o (Due to Counting Statistics) 4 . _ _ _ _ _ -- - - | |||
Table !!.B.3 Tritium Concentrations in Atmospheric Water Vapor. (pCi/m') | |||
a) First Quarter,1991 Facility Sites Reference Sites Collection Date -F-7 F-9 F-16 A-19 R-3 R-4 R-11 01/05. <0.9h < 0.92 < 0.92 < 0.92 < 0.92 < 0.92 < 0.92 i | |||
01/12. < 1.1 < 1.1 < 1.1 < 1.1 < 1.1 < 1.1 < I.1 | |||
$ 01/19 < 1.3 < 1. 3 < 1.3 < 1.3 1.3 < 1.3 < 1.3 01/26 < 0.79 '< 0.79 < 0.79 < 0.79 < 0.79 < 0.79 < 0.79 02/02 < 0.87 < 0.87 < 0.07 < 0.87 < 0.87 < 0.87 < 0.87 | |||
! 02/09 < 1.2 < 1.2 < 1.2 < 1.2 < 1.2 < 1.2 < 1.2 j .O 02/16 < 1.4 < 1.4 < 1.4 < 1.4 - < 1.4 < 1.4 < 1.4 i | |||
02/23 < 1.2 < 1.2 < 1.2 < 1.2 1.2 (1.2)* < 1.2 < 1.2 03/02 < 1.0 < 1.0 < 1.0 < 1.0 < 1.0 < 1.0 < 1.0 i 03/09 < I.0 '< 1.0 1.4 (1.1} 1.1 (1.1) 1.0 (1.1) < 1.0 < 1.0 i 1 | |||
; 03/16 < 1.2 < 1.2 < i .2 < 1.2 < 1.2 < 1.2 < 1.2 l I | |||
; 03/23 < 1.2 < 1.2 < 1.2 < 1.2 < 1.2 < 1.2 < 1.2 l 03/30 < 1.2 < 1.2 < 1.2 < 1.2 < 1.2 < 1.2 < 1.2 i | |||
* 1.96o (Due to Counting Statistics) - | |||
5 . | |||
., ,m. _ , .. . - - . , . . _ | |||
Table II.B.3 Tritfira Concentrations in Atmospheric Water Vapor. (pCi/m3 ) | |||
b) Second Quarter, 1991 Facility Sites Reference Sites Collection A-19 R-3 R-4 R-11 Date F-7 F-9 F-16 | |||
< 1.4 < 1.4 < 1.4 < 1.4 < 1.4 < 1.4 04/06 < 1.4 | |||
< 1.4 < 1.4 < 1.4 < 1.4 < 1.4 < 1.4 i 04/13 < 1.4 l | |||
< 1.8 < 1.8 < 1.8 < 1.8 < 1.8 < 1.8 < 1.8 04/20 | |||
< 1.6 < 1.6 < 1.6 < 1.6 < 1.6 < 1.6 < 1.6 04/27 | |||
< 1.6 < 1.6 < 1.6 < 1. 6 < 1.6 < 1.6 < 1.6 l | |||
05/04 | |||
< 2.2 < 2.2 < 2.2 < 2.2 < 2.2 < 2.2 < 2.2 05/11 | |||
< 2.1 < 2.1 < 2.1 < 2.1 < 2.1 < 2.1 < 2.1 05/18 | |||
< 2.9 < 2.9 < 2.9 < 2.9 < 2.9 < 2.9 < 2.9 05/25 | |||
< 3.0 < 3.0 < 3.0 < 3.0 < 3.0 < 3.0 < 3.0 06/01 | |||
< 3.1 < 3.1 < 3.1 < 3.1 < 3.1 < 3.1 < 3.1 06/07 | |||
< 3.0 < 3.0 < 3.0 < 3.0 < 3.0 < 3.0 < 3.0 06/14 | |||
< 2.7 < 2.7 < 2.7 < 2.7 < 2.7 < 2.7 < 2.7 06/21 | |||
< 1.7 < 1.7 < 1.7 < 1.7 < 1. 7 < 1.7 < 1.7 06/28 | |||
y. | |||
(pC1/m3; Table II.B.3 Tritium Concentrations in Atmospheric Water Vapor. | |||
c) Third Quarter, 1991 Facility Sites Reference Sites Collection Date F-7 F-9 F-16 A-19 R-3 .R-4 R-11 07/05 < 2.7 < 2.7 < 2.7 < 2.7 < 2.7 < 2.7 < 2.7 i 07/12 < 3.6 < 3.6 < 3.6 < 3.6 < 3.6 < 3.6 < 3.6 07/19 < 3.4 < 3.4 < 3.4 < 3.4 < 3.4 < 3.4 < 3.4 4 | |||
07/26 < 3.4 < 3.4 < 3.4 < 3.4 < 3.4 < 3.4 < 3.4 08/02 < 3.4 < 3.4 < 3.4 < 3.4 < 3.4 < 3.4 < 3.4 08/09 < 3.5 < 3.5 < 3.5 < 3.5 < 3.5 < 3.5 < 3.5 08/16 < 3.5 < 3.5 < 3.5 < 3.5 < 3.5 < 3.5 < 3.5 i 08/23 < 3.1 < 3.1 < 3.1 < 3.1 < 3.1 < 3.1 < 3.1 ' | |||
08/31 < 3.2 < 3.2 < 3.2 < 3.2 < 3.2 < 3.2 < 3.2 i 09/07 < 3.0 < 3.0 < 3.0 < 3.0 < 3.0 < 3.0 < 3.0 09/14 6.0 (3.4)* 6.3 (3.4) 7.6 (3.4) 5.1 (3.4) 5.6 (3.4) 5.0 (3.4) < 3.2 09/21 3.8 (2.1) < 2.0 4.6 (2.1) 5.5 (2.1) 4.1 (2.1) 3.6 (2.1) < 2.0 1 | |||
09/28 3.2 (1.9) 3.1 (1.8) 2.3 (1.8) 2.8 (1.8) 3.7 (1.9) < 1.8 1.8 (1.8) i | |||
* 1.96o (Due to Counting Statistics) ' | |||
4 | |||
! O p 2 . | |||
1 . | |||
F | |||
^ | |||
Table II.8.3 Tritium Concentrations in Atmospheric Water Vapor. (pCi/m3) d) Fourth Quarter,1991 Facility Sites Reference Sites Collection Date F-7 F- 9 F-16 A-19 R-3 R-4 R-11 10/05 < 2.3 3.7 (2.4) | |||
* 4.6 (2.4) 3.5 (2.4) 2.3 (2.4) 4.3 (2.4) 3.7 (2.4) 10/12 < 1.9 3.0 (1.9) < I .9 3.2 (1.9) < 1.9 < 1.9 < 1.9 10/19 < 1.5 < 1.5 < 1.5 1.6 (1.6) < 1.5 < 1.5 < 1.5 10/26 2.0 (1.7) < 1.6 2.5 (1.7) 2.5 (1.7) 2.1 (1.7) 3.5 (1.7) < 1.6 11/02 1.3 (.91) 1.5 (.91) 1.0 (.91) 1.5 (.91) < 0.86 < 0.86 < 0.86 11/09 2.0 (1.6) < 1.5 < 1.5 2.1 (1.6) < 1.5 1.8 (1.6) 2.5 (1.6) 11/16 3.3 (1.8) < 1.7 < 1.7 < 1.7 < 1.7 < 1. 7 < 1.7 M | |||
11/23 < 1.3 1.7 (1.4) < 1.3 s 1.3 c 1.3 < 1.3 1.5 (1.4) 11/30 < 1.4 1.9 (1.5) 2.6 (1.5) < 1.4 1.9 (1.5) < 1.4 < 1.4 12/07 < 1.3 < 1.3 1.7 (1.3) < 1.3 1.6 (1.3) < 1.3 < 1.3 12/14 < 1. 4 < 1.4 2.2 (1.4) < 1.4 1.5 (1.4) 2.1 (1.4) 1.8 (1.4) 12/21 < 1.4 1.8 (1.4) 1.5 (1.4) < 1.4 < 1.4 2.6 (1.4) 1.8 (1.4) 12/28 < 1.2 < 1.2 < 1.2 1.6 (1.3) < 1.2 < I.2 < 1.2. | |||
* 1.96o (Due to Counting Statistics) | |||
_ ,m,- - | |||
r w ri ,. | |||
1* | |||
e '---'" - " ~ ^ - " ' " ' - ' | |||
' ' " " " " " ^ ~ ' ' ' - - - - - - - ^ ^ ^ - | |||
.~ | |||
f I | |||
3 ble 11.B.4 Trit tum Released (nCI) In Reactor Effluents, 199 1 ttist of JAff flD itAft A rst #1AY Juft Jtat. AtM1 st r oct tioV Dtc los Al i s . ... u . ... s f,,',7',l,'[ ' O.415 0.492 0.568 0.340 0.524 0.486 0.661 1.29 1.55 1.54 2.05 1.06 10.98 , | |||
: n. ., | |||
; g its t t la , | |||
I?et f em te i I | |||
, l,',',7 Q j ',',,', 0.807 0.614 0.394 0.361 0.173 1.02 0.217 11.8 0.328 0.395 0.307 0.350 16.77 | |||
~ r.. . | |||
e ttat a la j 6.38 | |||
" * ' " a 5 *' | |||
r.y . t e. (.., i l'c50 2710 202 32.6 3.31 3.75 .1460 648 1400 3280 70.4 11066 t i t | |||
, m e.... . | |||
11.6 8.53 8.75 10.0 12.6 6.18 12.8 9.51 7.39 3.06 4.76 2.19 97.37 ; | |||
L | |||
'"'^' 1263 2/20 211.7 43.3 16.6 11.4 20.06 1483 657 1405 3287 74.0 11192 1 | |||
(1) Conservative estimate by TSV laboratories. Obtained . in many cases by itDA result X volume. | |||
Y l | |||
P F | |||
,m -. .v.-,, . - , - . _ | |||
.,.m .. , ,, .n. . . . , . , - - . , - . . , - | |||
. . . - , ..-..,,c . . - | |||
: 3. Concentrations of Gamma-rav Emittina Radionuclides in Ambient Air Tables II.B.Sa-5d list the concentrations of I-131 in air as measured- by activated charcoal sampling and Ge(Li) gamma-ray spectrum analysis during 1991. Each sample from the seven air sampling stations is counted within 96 hours after collection. A 100-minuto count and a sample volume of 800 m' is required to achieve an MDC of 33 f ci/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 superior resolution of Go(Li) spectrometry systems. Any 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 an" 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 in the case whether the I-131 source term would be a nuclear accident elsewhere, weapons testing fallout or reactor stack effluent. | |||
There were only occasional positive values very near the MDC value and all are assumed to be false positives. When a gamma-ray from natural background activity interferes'with the region o'f interest of a measured radionuclido, e.g., Cs-134, Ba-La 140, the number of falso positives is higher, implying | |||
~ | |||
a systematic . error. I-131 concentrations due to reactor i | |||
f 28 | |||
- _- _ _ _ - . - - - - . .-_ - - ..~ - .. . - _ . . . - = . _ . - | |||
1 offluent have never been detected in any sample type in the fort St. Vrain environs. There is essentially no fission product I-131 remaining in any of the fuel elements and, therefore, no possible source term. | |||
Table II.B.6 lists measured ambient air concentrations of Cs-134 and Cs-137. These values are from gamma-ray spectrum analyses on weekly air filters composited quarterly from each of the seven air sampling stations. The occasional positive values are either measurement system f also positives or Cs-137 concentrations possibly dos to resuspension of surface soil. | |||
The Cs-137 activity is due to Chernobyl or previous fallout which is bound by clay mineralt 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 gemma-ray spectrum is scanned for evidence cf 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. | |||
[ 29 | |||
-1 Table IT.B.5 lodine-131 Coicentrations in Air. (fti/m 3) a) First Quarter, 1991 Facility Sites Reference Sites Collection-Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 1/02/91 '< 20.0 < 24.0 < 19.0 < 19.0 < 20.0 e 23.0 < 29.0 1/09/91 < 30.0 < 25.0 < 21.0 < 22.0 < 35.0 < 24.0 < 34.0 1/16/91 < 34.0 < 12.0 < 16.0 < 17.0 < 26.0 < 33.0 < 24.0 1/23/91 < 7.9 < 21.0 < 35.0 < 34.0 < 20.0 < 32.0 < 33.0 1/30/91 < 26.0 < 18.0 < 25.0 < 20.0 < 19.0 < 33.0 < 22.0 2/06/91 < 11.0 < 13.0 < 16.0 < 17.0 < 26.0 < 19.0 < 34.0 E$ 2/13/91 '46.0 (33.0)* < 30.0 < 13.0 < 16.0 < 17.0 < 35.0 < 32.0 2/20/91 < 14.0 < 23.0 < 21.0 < 26.0 < 30.0 < 21.0 < 8.9 2/27/91 < 31.0 < 11.0 < 15.0 20.0 (22.0) < 19.0 < 21.0 < 21.0 3/06/91 < 32.0 < 16.0 < 18.0 < 23.0 < 18.0 < 26.0 < 23.0 3/13/91 < 20.0 ' < 21.0 < 23.0 < 17.0 < 35.0. 37.0 (38.0) < 26.0 3/20/91 < 32.0 < 32.0 < 24.0 < 26.0 <.28.0 < 28.0 < 14.0 3/27/91 < 34.0 < 21.0 < 28.0 < 19.0 39.0 (26.0) < 27.0 < 28 0 | |||
*L1.96o (Due to Counting Statistics) t | |||
.y , , , _ , v w. , --. - -v., - | |||
. r , , - - -, , - | |||
3 Table 11.8.5. Iodine-131' Concentrations'in Air. (fCf/m ) | |||
b) Second Quarter,1991 - | |||
Facility Sites Reference Sites Collection | |||
} Date. F-7 F-9 F-16 A-19 R-3 R-4 R-11 4/03/91 < 15.0 < 19.0 < 29.0 < 14.0 < 17.0 < 27.0 < 15.0 | |||
; 4/10/91 < 23.0 < 22.0 < 26.0 h < 24.0 < 14.0 < 19.0 4/17/91 < 7.0 < 9.4 < 32.0 < 14.0 < 12.0 < 32.0 < 26.0 4/24/91 < 25.0 < 24.0' < 28.0 < 27.0 < 18.0 < 14.0 < 15.0 5/01/91 < 23.0 < 24.0 < 31.0 < 16.0 < 20.0 < 23.0 < 19.0 5/08/91 < 16.0 < 7.7 < 16.0 < 13.0 23.0 (22.0) < 25.0 < 5.8 | |||
. O 5/15/91 < 26.0 < 16.0 < 25.0 < 27.0 < 17.0 < 17.0 < 23.0 5/22/91 < 33.0 < 15.0 < 29.0 < 22.0 < 19.0 < 27.0 < 21.0 5/29/91 < 18_0 41.0 (35.0) < 23.0 < 12.0 < 17.0 < 16.0 38.0 (40.0) - | |||
l 1 6/05/91 < 24.0 < 16.0 < 15.0 < 18.0 < 20.0 < 20.0 < 19.0 6/11/91 < 21.0 < 28.0 < 20.0 < 26.0 < 35.0 < 21.0 < 12.0 6/;8/91 < 24.0 < 30.0 < 32.0 < 15.0 < 27.0 < 18.0 < 12.0 ; | |||
6/25/91 < 30.0 < 34.0 29.0 (36.0)'< 20.0 < 22.0 < 14.0 < 11.0 | |||
* 1.96o'(Oue.to Counting Statistics) , | |||
h - sanple not collected (pump not functioning) , | |||
e Table II.B.5 lodine-131 Concentrations in Air. (fCi/m ) | |||
d) Third Quarter, 1991 Facility Sites Reference Sites Collection e. | |||
Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 7/02/91 < 17.0 < 15.0 < 24.0 32.0(35.0[ < 13.0 < 25.0 < 33.0 7/09/91 < 29.0 < 18.0 < 33.0 < 30.0 < 16.0 < 14.0 < 16.0 7/16/91 < 29.0 < 13.0 < 11.0 < 17.0 < 30.0 < 13.0 < 23.0 7/23/91 < 18.0 < 20.0 < 15.0 < 13.0 < 25.0 < 17.0 < 11.0 7/30/91 < 15.0 < 22.0 < 17.0 27.0 (25.0) < 28.0 < 14.0 < 18.0 g; 8/06/91 < 35.0 < 23.0 < 22.0 < 17.0 < 14.0 < 18.0 < 13.0 8/13/91 < 32.0 < 24.0 < 18.0 < 19.0 < 19.0 < 33.0 < 24.0 8/20/91 < 31.0 < 21.0 < 24.0 < 26.0 < 34.0 < 29.0 < 22.0 8/28/9? < 17.0 < 14.0 < 26.0 < 22.0 < 35.0 < 22.0 < 12.0 9/04/91 < 23.0 < 26.0 < 25.0 < 25.0 < 11.0 < 20.0 < 17.0 9/11/91 < 29.0 < 19.0 < 16.0 < 21.0 < 21.0 < 13.0 < 18.0 9/18/91 < 31.0 < 33.0 < 15.0 < 18.0 < 23.0 < 21.0 < 16.0 9/25/91 < 26.0 < 23.0 < 28.0 < 33.0 < 35.0 < 25.0 < 13.0 | |||
* 1.96o (Due to Counting Statistics) | |||
O _ | |||
'I Table II.B.5 Iodine-131 Concer.trations in Air. (fCi/m3 ) | |||
d) Fourth- Quarter, 1991 Facility Sites Reference Sites Collection Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 | |||
, 10/02/91 < 25.0 < 28.0 < 33.0 < 15.0 < 11.0 < 29.0 < 18.0 | |||
; 10/09/91 < 23.0 < 18.0 < 15.0 32.0(30.0} < 35.0 < 22.0 < 12.0 10/16/91 < 17.0 < 30.0 < 33.0 < 26.0' < 19.0 < 20.0 < 34.0 10/23/91 < 10.0 < 9.0 < 14.0 < 19.0 < 29.0 < 23.0 < 9.5 l 10/30/91 < 21.0 < 25.0 < 18.0 < 22.0 < 18.0 < 13.0 < 12.0 | |||
{ 11/06/91 < 20.0 < 19.0 < 12.0 < 26.0 17.0 (19.0) < 11.0 < 13.0 , | |||
11/13/91 < 18.0 < 31.0 < 20.0 < 15.0 < 25.0 < 23.0 -25.0 (23.0) . | |||
11/20/91 < 23.0 < 16.0 <-15.0 19.0 (24.0) < 9.8 < 17.0 < 19.0 11/27/91 < 13.0 < 14.0 | |||
< 34.0 < 15.0 < 16.0 < 20.0 < 18.0 i | |||
12/04/91 < 35.0 < 9.1 < 14.0 < 23.0 < 1.8 < 18.0 < 17.0 12/11/91 < 25.0 < 35.0 < 35.0 < 26.0 < 17.0 < 13.0 < 23.0 ' | |||
12/18/91 < 20.0 < 18.0 < 18.0 < 32.0 < 14.0 < 22.0 34.0 (41.0) 12/25/91 < 32.0 < 22.0 < 24.0 < 22.0 < 28.0 '< 32.0 < 35.0 | |||
* 1.96o (Due to Counting Statistics) l . | |||
t r | |||
w 1 | |||
s | |||
! Table II.B.6 Radiocesium Concentrations in Ambient Air. (fCi/m ) | |||
l 1991 Facility Sites Reference Sites Collection Radio-Date nuclide F-7 F-9 F-16 A-19 R-3 R-4 R-11 4 | |||
1st Cs-134 < 1.6 < 1.3 < 1.8 < 1.9 3.2 (3.2) < 2.4 < 3.5 Quarter Cs-137 < 1.6 1:6 (1.8)* < 1.9 < 2.0 < 2.8 < 2.9 < 3.3 5 2nd Cs-134 < 1.5 < 1.1 < 1.6 < I .1 < 1.2 2.4 (1.6) < 1.5 Quarter Cs-137 < 1.5 < 1.2 < 1.6 < 1.2 < 1.3 1.7 (1.7) 1.5 (1.9) 3rd Cs-134 < 1.0 < 1.1 < 1.3 < 0.57 < 0.69 < 0.72 < 0.74 Quarter Cs-137 < 1.1 < 1.1 < 1.3 < 0.57 1.2 (.84) < 0.71 < 0.77 | |||
-4th Cs-134 < 2.3 < 2.4 < 1.2 < 1.7 < 3.4 2.3 (2.5) < 2.8 Quarter Cs-137 < 2.4 < 2.3 < 1.3 < 1.8 < 3.2 < 1.6 < 2.2 | |||
* 1.96o (Due to Counting Statistics) | |||
Y . - | |||
II.C. Radionuclide Concentration in Water | |||
: 1. Drinkina WatigI Drinking water i.s sampled weekly and composited biweekly at two location.. Location R-6 is the well used for drinking water by the town of Gilcrest, Colorado, and R-3 is a water 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. Water treatment systems for the two water supplies are very different. . | |||
. Table II.C.1 shows gross beta concentrations measured in 1991 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 practices;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 y;2an 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. Concentrations above MDC were detected after the major reactor releases. The yearly arithmetic mean value for the Gilcrest location was 620 2 | |||
e 35 | |||
pCi/L. Assuming this was the only drinking water intak for Gilcrest residents the resultant dose commitment calculation is as follows: | |||
Assuming 2 L/ day intake of drinking water, water from milk of a family milk cow and vegetables from a local garden irrigated with the well water, the yearly intake is 1250 L/ year. The adult committed effectivo dose equivalent is: | |||
121QL x 620 DC.i x 6.3 x 10 4 mrea = 0.049 mrom. | |||
year L pCi This is an insignificant dose commitment. The EPA limit for community drinking whter systems is currently 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 Ge(Li) spectrometry for I-131. A three liter aliquot of the original sample is counted directly for the other gamma-ray emitters. | |||
- Inspection of Table II-C.3 reveals occasional positive i | |||
values of radionuclide concentration, but with the exception of Cs-137, these are interpreted to be random variations about the detection limit. The Cs-137 is the residue from the 1986 Chernobyl accident fallout as well as from past world-wide fallout from nuclear weapon testing. | |||
36 | |||
Table 11.C.1 Gross Beta Concentrations in Biweekly Composites of Drinking Water. (pCi/L) | |||
Collection Gilcrest City R-6 Fort Collins City R-3 Date 1991 (Reference) 12/29 01/05 6.3 (2.5)* .84 (0.56) 01/12 01/19 5.1 (2.4) .67 (0.55) 01/26 02/02 S.1 (2.4) 1.4 (0.59) 02/09 02/16 6.8 (2.5) 1.6 (0.60) 02/23 03/02 5.6 (2.4) 1.5 (0.59) 03/09 03/16 5.1 (2.4) 1.4 (0.59) 03/23 03/30 5.6 (2.4) 1.0 (0.57) 04/06 04/13 4.4 (2.3) .90 (0.56) | |||
-04/20 04/27 4.' (2.3) .89 (0.56) 05/04 05/11 8.3 (2.6) 1.0 (0.57) 05/18 05/25 3.3 (2.2) 1.3 (0.58) 06/01 06/07 4.0 (2.3) .90 (0.57) 06/14 06/21 3.3 (2.3) .53 (0.55) - | |||
06/28 07/12 5.5 (2.4) .53 (0.55) 07/12 07/19 3.7 (2.3) .44 (0.54) 07/26 08/02 4.2 (2.3) .71 (0.56) 08/09 08/16 3.4 (2.3) .53 (0.54) 08/23 08/30 9.4 (2.7) .64 (0.55) 09/07 09/14 3.1 (2.3) .67 (0.56) 09/21 09/28 10 (2.7) .90 (0.57) 10/07 10/14 -5.3 (2.4) 1.4 (0.56) 10/21 10/28 8.7 (2.5) 1.5 (0.60) 11/02 11/09 13 (2.8) .92 (0.56) 11/16 11/23 6.6 (2.5) .63 (0.55) 11/30-12/07 5.8 (2.4) 1.1 (0.58) 12/14 12/21 4.6 (2.3) .91 (0.57) | |||
*1.96o (Due to Counting Statistics) i l | |||
I 37 | |||
. I Table !!.C.2 Tritium Concentrations in Biweekly Composites of Drinking Water. (pCi/L) | |||
Collection Gilcrest City R-6 Fort Collins City R-3 Date 1991 (Reference) 12/29 01/05 < 400 < 400 01/12 01/19 < 400 < 400 01/26 02/02 < 400 < 400 02/09 02/16 < 400 < 400 02/23 03/02 < 400 < 400 03/09 03/16 < 400 < 400 03/23 03/30 < 400 < 400 04/06 04/13 < 400 < 400 04/20 04/27 < 400 < 400 05/04 05/11 < 390 < 390 05/18 05/25 < 390 < 390 06/01 06/07 < 390 < 390 06/15 06/22 < 390 < 390 06/29 07/06 < 380 < 380 07/13 07/20 < 390 < 390 07/27 68/03 < 390 < 390 08/10 08/17 < 390 < 390 08/24 09/31 < 400 < 400 09/07 09/14 490 (360)* < 350 09/21 09/28 640 (420) < 400 10/05 10/12 < 400 < 400 10/19 10/26 < 400 < 400 11/02 11/09 560 (420) < 400 11/16 11/23 760 (420) 410 (410) 11/30 12/07 600 (420) < 400 12/14 12/21 660 (420) 730 (420) i | |||
*1.960 (Due ta Counting Statistics) | |||
L l | |||
Table II.C.3 Radionuclide Concentrations in Bi-wakly Composite of Drinking Water. (pCi/L) | |||
Collection for two weeks ending for two weeks cading for tvn weeks ending | |||
; Date 02JAN91 16JAN91 30JANQ1 Radionuclide Gilcrest Ft Collins Gilcrest Ft Collins GilcrNs1 Ft Col' lins R R-3 R-6 R-3 R-6 R-3 I | |||
I-131 < 0.39 < 0.37 < 0.28 < 0.12 < 0.33 < 0.47 Cs-134 < 2.0 < 3.0 e < 2.1 < 2.0 < 1.6 < 2.S Cs-137 < 2.5 < 3.7 5.4 (3.0)* < 2.5 < 1.9 < 3.1 i lg Zr-95 < 4.5 < 6.7 < 4.5 < 4.3 < 3.7 < 5.8 Nb-95 < 1.9 < 3.0 < 1.9 < 1.9 < 1.5 < 2.3 Co-58 < 2.0 < 2.9 < 1.9 < 1.8 | |||
. < 1.4 < 2.3 ; | |||
Mn-54 < 2.1 < 3.0 < 2.1 3.3 (2.4) < 1.5 < 2.5 2n-65 < 5.9 < 7.6 < 5.8 < 5.5 < 4.9 < 6.9 Fe-59 < 4.7 < 7.8 < 4.7 < 4.7 < 4.2 < 6.1 Co-60 < 2.1 < 2.9 < 2.0 < 2.0 < 1.5 3.3 (3.2) | |||
Ba-140 < 5.0 < 4.9 < 3.2 < 3.1 < 4.3 < 4.0 La-140 < 5.7 < 5.6 < 3.7 < 3.6 < 4.9 < 4.6 l | |||
* 1.96 o (Due to Counting Statistics) , | |||
l | |||
.- - -- , _ _ _ - _ _ - _ _ _ _ - _ - _ _ _ - _ - ._ - ] | |||
Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drieking Water. (pCi/L) | |||
Collection for two weeks ending for two weeks ending for t weeks ending Date 13FEB91 27FEB91 13 MAR 91 Radionuclide Gilcrest Ft Callins Gficrest Ft Collins uficrest Ft Collins R-6 R-3 R-6 R-3 R-6 R-3 I-131 < 0.3 < 0.19 < 0.28 < 0.18 < 0.41 < 0.5 Ij Cs-134 < 2.1 < 2.4 < 2.1 < 2.2 < 2.4 < 2.0 Cs-137 3.3 (3.0)* 4.2 (3.5) < 2.5 < 2.5 i 2.9 (3.5) < 2.3 | |||
$ Zr-95 < 4.8 < 5.6 < 5.3 < 4.7 < 6.2 < 4.6 Mb-95 < 1.9 < 2.3 < 1.9 < 2.0 < 2.2 < 1.8 Co-58 < 2.0 < 2.2 < 1.9 < 2.0 < 2.2 < 1.8 Mn-54 < 2.1 < 2.4 < 2.1 < 2.1 < 2.4 < 2.0 Zn-65 < 5.8 < 6.7 < 5.P- < 6.0 < 6.7 < 5.8 Fe-59 9.2 (6.2) < 6.1 < 5.7 < 4.9 _ < 6.6 < 4.5 | |||
< Co-60 < 2.2 < 2.C < 2.2 < 2.1 < 2.6 < 1.9 Ba-140 < 3.3 < 4.0 < 6.4 < 3.4 < 3.9 < 5.5 La-140 < 3.8 < 4.6 < 7.4 < 3.9 < 4.4 < 6.4 | |||
* 1.96 o (Due to Counting Statistics) | |||
x Table .II.C,3 Radionuclide Concentrations in Bi-weekly Co@osite of Drinking nfater. (pC1/L) | |||
Collection for two weeks ending | |||
~ | |||
for two weeks ending for two weeks ending Date- 27 MAR 91 10APR91 24APR91 4 | |||
Radionuclide Gilcrest Ft Collins Gilcrest Ft Collins Gilcrest Ft Collins Ro R-3 R-6 R-3 R-6 R-3 1-131 < 0.35 < 0.32 < 0.33 < 0.35 < 0.40 < 0.32 I | |||
-Cs-134 < 2.5 < 2.2 < 1.6 < 1.5 < 2.3 < 1.8 Cs-137 < 3.0 < 2.6 : 4.4 (2.4)* < 1.9 < 2.8 < 2.2 i Zr-95 < 5.6 < 5.0 - < 3.8 < 3.6 < 5.3 < 4.0 Nb-95 < 2.2 < 2.0 < 1.5 < 1.4 < 2.0 < 1.7 Co-58 < 2.3 < 2.0 < 1.5 < 1.5 < 2.1 < 1.7 Mn-54 < 2.5 < 2.1 < 1.6 < 1. 5 2.4 (2.7) < 1.8 l Zn-65 < 7.0 < 6.4 < 4.5. < 4.6 < 6.2 < 5.6 Fe-59 < 5.7 < 4.9 < 4,4 < 3.5 < 5.8 < 4.2 Co-60 < 2.6 < 2.1 < 1.8 < 1.5 < 2.5 < 1.8 Ba-140 < 6.1 < 3.4 < 2.6 < 2.4 < 3.7 < 4.1 La-140 < 7.1 < 3.9 < 3.0 < 2.8 < 4.2 < 4.7 | |||
* 1.96o (Due to Counting Statistics) | |||
O L___ _ | |||
Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L) | |||
Collection for two weeks ending- for two weeks ending for two weeks ending , | |||
Date 08MAY91 22MAY91 05JUN91 Radionuclide Gilcrest Ft Collins Gilcrest Ft Collins Gilcrest Ft Collins R-6 R-3 R-6 R-3 R-6 R-3 I-131 < 0.35 < 0.49 < 0.37 < 0.39 | |||
. < 0.24 0.52 (0.5)* | |||
Cs-134 < 2.1 < 1.9 < 3.1 < 2.1 3.4 (2.7) < 2.4 Cs-137 3.8 (3.2) < 2.3 < 3.6 < 2.5 < 2.7 < 2.9 0 Zr-95 < 5.1 4.5 (5.3) < 6.6 < 4.4 < 5.0 < 5.6 Nb-95 < 2.0 < 1.7 < 2.8 < 1.8 < 2.1 < 2.1 Co-58 < 2.1 < 1.9 < 2.8 < 1.9 < 2.2 < 2.2 Mn-54 < 2.2 2.7 (2.3) < 3.0 < 2.0 < 2.2 < 2.4 Zn-65 < 5.9 < 5.1 < 8.2 < 5.9 < 6.4 < 6.6 i | |||
Fe-59 < 5.1 < 4.5 < 6.9 < 5.0 < 5.2 < 5.7 Co-60 < 2.3 < 1.9 < 3.1 < 2.0 < 2.3 < 2.6 t Ba-140 < 3.5 < 4.6 < 4.8 < 4.9 < 6.3 < 6.4 La-140 < 4.1 < 5.3 < 5.5 < 5.6 < 7.2 < 7.4 i | |||
* 1.96o (Due' to Counting Statistics) | |||
~ | |||
5 h | |||
4 Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L) | |||
Collection for two weeks ending for two weeks ending for two weeks ending Date 18JUN91 03 jut.91 16JUL91 Radionuclide Gilcrest Ft Collins Gilcrest' Ft Collins Gilcrest Ft Collins R-6 R-3 R-6 R-3 R-6 R-3 1-131 < 0.19 < 0.3 < 0.37 < 0.33 < 0.48 < 0.38 Cs-134 < 1.2 < 2.1 4.0 (4.2) 2.1 (2.4) < 1.2 < 0.96 Cs-137 1.7 (1.7)* < 2.5 4.9 (5.0) 3.8 (2.9) < 1.4 2.2 (1.4) | |||
, Zr-95' < 2.6 < 4.5 < 8.2 < 5.0 < 2.7 < 2.1 Nb-95 < 1.1 < 1.9 < 3.2 < 1.8 < 1.0 < 0.89 Co-58 < 1.2 < 1.9 < 3.1 < 1.8 < 1.1 < 0.97 Mn-54 < 1.2 < 2.0 < 3.4 < 2.0 < 1.2 < 0.96 Zn-65 < 3.3 < .5.5 < 9.1 < 5.4 < 3.1 < 2.6 Fe-59 < 2.8 < 4.8 < 8.8 < 5.0 < 2.6 < 2.2 Co-60 < 1.2 < 2.1 < 3.6 < 2.2 < !.2 < 0.93 I | |||
Ba-140 < 3.4 < 5.5 | |||
~ | |||
< 7.9 < 4.6 < 1.9 < 1.5 La-140 < 3.9 < 6.3 < 9.1 < 5.3 < 2.1 < 1.7 | |||
* 1.96o (Due to Counting Statistics) , | |||
_________________.____...-.-m -_m | |||
Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCf/L) | |||
Collection for two weeks ending for two weeks ending for two weeks ending Date- 26JUL91 13AUG91 '23AUG91 Radionuclide Gilcrest ' Ft Collins Gilcrest Ft Collins Gilcrest Ft Collins R-6 R-3 R-6 R-3 R-6 R-3 I-131 ~< 0.25 < 0.31 < 0.19 < 0.32 < 0.38 < 0.41 Cs-134 a < 1.7 < 2.9 < 1.2 2.8 (2.0) < 2.1 Cs-137 a 3.8 (2.5)* < 3.4 2.4 (1.7) < 2.0 3.0 (3.0) | |||
Zr-95 a < 4.3 < 6.3 < 2.8 < 3.5 < 4.7 g Nb-95 a < 1.7 < 2.7 < 1.1 < 1. 5 < 1.9 Co-58 a < 1.6 - 2.9 < 1.1 1.7 (2.0) < 1.9 Mn-54 a < 1.7 < 2.8 < 1.2 < 1.7 < 2.0 In-65 a < 4.8 < 7.9 < 3.2 < 4.6 < 5.4 Fe-59 a < 3.9 < 6.7 < 2.7 < 4.3 < 4.8 Co-60 a < 1.7 < 2.9 < 1.1 < 1.6 2.3 (2.4) | |||
Ba-140 a- < 2.7 < 4.6 < Z.1 < 2.6 < 5.0 i La-140 a < 3.1 < 5.3 < 3.6 < 3.0 < 5. 7 | |||
* 1.96o (Due to Counting Statistics) a - sample lost prior to analysis , | |||
~ - . _ _ _ - - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ | |||
Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L) | |||
Collection for two weeks ending for two weeks endin9 for two weeks ending Oate- 11SEP91 25SEP91 090CT91 Radionuclide Gilcrest Ft Collins Gilcrest Ft Collins Gilcrest Ft Collins R-6 R-3 R-6 R-3 R-6 R' I-131 < 0.25 < 0.21 < 0.37 < 0.3 < 0.34 < 0.38 Cs-134 < 1.8 < 1.6 < 1.5 < 2.0 < 1.7 < 1.9 Cs-137 2.4 (2.5)* < 1.9 < 1.8 < 2.5 < 2.1 3.5 (2.9) an m | |||
Zr-95 < 4.4 < 3.6 < 3.6 < 4.4 < 3.7 < 5.2 Nb-95 < 1.6 < 1.4 < 1.4 < 2.0 < 1. 5 < 1.9 Co-58 < 1.6 < 1.4 < 1.4 < 1.8 < 1.7 < 1.8 Mn-54 1.9 (2.1) < 1.5 < 1.5 < 2.0 < 1.7 2.7 (2.4) | |||
Zn-65 < 4.9 < 4.2 < 4.2 < 5.6 < 4.6 < 5.5 Fe-59 < 4.0 < 3.6 < 3.5 < 5.6 < 4.5 < 4.7 j Co-60 < 1.7 < 1. 7 < 1.6 < 2.0 < 1.7 < 2.2 Ba-140 < 5.9 3.4 (3.2) < 5.2 < 6.5 < 2.6 < 3.3 La-140 < 6.8 3.9 (3.6) < 6.0 < 7.5 < 3.0 < 3.8 | |||
* 1.96o (Due to Counting Statistics) 6 | |||
Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L) | |||
Collection for two weeks ending for two weeks ending for two weeks ending Date 230CT91 05NOV91 20NOV91 Radionuclide Gilcrest Ft Collins Gilcrest Ft Collins Gilcrest Ft Collins R-6 R-3 R-6 R-3 R-6 R-3 I-131 < 0.21 < 0.37 < 0.46 < 0.39 < 0.4 < 0.36 Cs-134 < 3.3 < 2.1 < 2.1 < 1.7 < 2.2 < 1.8 Cs-137 < 4.1 < 2.5 < 2.5 < 2.1 < 2.6 < 2.2 - | |||
$ Zr-95 < 7.2 < 4.4 <.6 < 3.7 < 5.1 < 4.0 Nb-95 < 2.8 < 1.9 < 2.0 < 1.6 < 2.0 < 1.6 Co-58 < 3.3 < 1.9 < 1.9 < 1.7 < 2.0 < 1.6 Mn-54 < 3.1 < ?.0 < 2.1 < 1.7 < 2.1 < 1.8 Zn.65 < 9.0 < 5.9 < 5.7 < 4.6 < 6.3 < 5.1 Fe-59 < 7.2 < 5.3 < 4.8 < 4.4 5.3 (6.3)* < 4.1 Co-60 < 3.0 < 2.0 3.8 (2.6) < 1.7 < 2.3 < 1.7 Ba-140 < 5.1 < 4.9 < 3.2 < 4.8 < 3.5 < 2.8 La-140 < 5.9 < 5.6 < 3.7 < 5.5 < 4.0 < 3.2 i | |||
* 1.96o (Due to Counting Statistics) . | |||
4 Table II.C.3 Ra'ionuclide Concentrations'in Bi eekly w Composite of Drinking Water. (pC1/L) | |||
Collection for two weeks ending for two weeks ending Date 04DEC91 18DEC91 Radionuclide Gilcrest Ft Collins G1frrest Ft Collins R-6 R-3 i-6 R-3 I-131 < 0.24 < 0.34 < 0.35 < 0.50 Cs-134 < 2.3 < 2.6 < 2.3 < 2.4 Cs-137 < 2.8 < 3.2 6.0 (3.3)* < 2.9 3 Zr-95 < 6.0 < 6.3 < 5.3 < 7.5 Hb-95 < 2.1 < 2.4 < 2.0 < 2.2 Co-58 < 2.3 < 2.4 < 2.0 < 2.8 Mn-54 3.8 (2.8) < 2.6 < 2.4 < 2.5 Zn-65 < 6.3 < 7.2 < 6.1 < 6.5 Fe-59 < 5.3 < 6.2 < 5.3 < 5.8 Co-60 < 2.5 < 2.8 < 2.4 < 2.6 t | |||
Ba-140 < 3.6 < 4.3 < 7.5 < 3.9 La-140 < 4.1 < 4.9 1 < 7.5 < 4.4 | |||
~~_ . | |||
* 1.96 o (Due t1 Counting Stet.istics) - | |||
* w r ~ ,-- | |||
'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 anF downstream sampling locations on both river courses. | |||
Table II.C.4 shows tritium conce.itrations measured during 1991 at the four surface water sites and the effluent route site. The arithmetic mean value for the downstream locations in 1991 was not, however, significantly dif ferent from the two upstream locations (Table II.H.2). | |||
: l. , | |||
l Table II.C.5 shows measurements of fission product and activation product concentrations in surface water samples. | |||
collected monthly. There were occasional positive values, but the mean of the downstream sites was not significantly different from the mean of the upstream sites during 1991 for any of-the gamma-ray emitting radionuclides measured. This has been the case since the inception of reactor operations at the Fort St. Vrain site. The occasional positive values are either. fallout Cs-137_, which can be. expected, or values close s, | |||
to-the uncertainty-limits and assumed to be false positives. | |||
In_ addition-to the monthly sampling of the South Platte River and S t . --V r a i n Creek, a continuous _ water sample it collected at station A-25. An aliquot of the farm pond outlet is sampled every 80 minutes and the composite -collected weekly. The weekly composites are then combined and analyzed monthly. The results of these samples are also shown in-Tables II'. C . 4 and II.C.S. For January through April and t-l | |||
-48 | |||
September and- through _ December there was evidence of measurable tritium release (see Table II.C.4). - | |||
Mean values r for the other radionuclides were less than MDC except for cc-137. The correlation of the tritium concentrations with the effluent release report is good. | |||
t 1 m | |||
/ | |||
49 | |||
Table II.C.4 (pCi/L) | |||
Tritium Concentrations in Surface Water. | |||
Downstream Sites Upstream Sites Ef fluent S. Platte St. Vrain S. Platte Goosequill Collection St. Vrain F- 19 A-25 Date F-20 R-10 A-21 January < 400 < 400 < 400 < 400 3500 (460)* - | |||
February < 410 < 410 < 410 < 410 2300 (450) | |||
< 390 420 (400) < 390 < 390 1100 (420) | |||
March April < 400 < 400 < 400 < 400 430 (420) | |||
< 390 < 390 < 390 < 390 < 400 May | |||
< 390 < 390 < 390 < 390 < 390 | |||
$ June | |||
< 380 < 380 < 380 < 380 < 390 July | |||
< 400 < 400 < 400 < 400 < 400 August September < 350 370 (360) 380 (360) 420 (360) 1300 (430) | |||
October < 400 < 400 530 (420) < 400 1000 (430i November 560 (420) < 400 < 400 < 400 8300 (510) f 550 (420) 760 (420) 570 (420) 860 (420) 2000 (450) p December | |||
* 1.96o (Due to Counting Statistics) | |||
x. | |||
2 t | |||
Table II.C.5 Radionuclide Concentrations In Surface Water. (pCi/L) | |||
Collection Date: 1/12/91 Downstream Sites Upstream Sites Effluent Radio St. Vrain 5. Platte St. Vrain S. Platte Goosequill | |||
-nuclide F-20 R-10 A F-19 A-25 Cs-134 < 2.4 < 2.0 < 3.5 < 2.0 < 1.7 Cs-137 4.4 (3.5)* 3.1 (2.9) < 4.4 < 2.4 < 2.1 Zr-95 < 5.8 5.3 (5.5) < 8.0 < 4.7 < 4.4 Nb-95 < 2.1 < 1.9 3.6 (3.9) < 1.8 < 1.6 Co-58 < 2.3 < 1. 9 < 3.4 < 1.8 < 1. 5 Mn-54 < 2.4 < 2.0 < 3.6 < 2.0 < 1.7 | |||
$ Zn-65 < 6.5 < 5.6 < 10.0 < 5.3 < 4.7 Fe-59 < 5.5 < 4.3 < 8.4 < 4.6 < 5.0 Co-60 < 2.6 < 2.0 < 3.5 < 2.2 < 1.6 Ba-140 < 3.9 < 3.2 < 5.7 < 3.3 6.1 (7.3) | |||
La-140 < 4.4 < 3.7 < 6.5 < 3.7 7.0 (8.4) | |||
+1.960 (Due to Counting Statistics) e 4 | |||
_ _ . _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ __ - __ o_ _ __ _ _ _ _.._ _ _ _ ___ . _ _ _ _ _ _ . _ _ _ _ _ _ | |||
; 3 . | |||
I l | |||
Table II.C.5 Radionuclide' Concentrations In Surface Water. (pCi/L) | |||
Collection Date: 2/09/91 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 < 1.5 < 3.0 < 2.1 < 2.0 < 1.0 Cs-137 3.1 (2.2)* < 3.6 < 2.6 4.1 (2.9) 2.6 (1.5) | |||
Zr-95 < 3.3 < 6.6 < 4.6 < 4.6 < 2.5 Nb-95 < 1.4 < 2.8 < 1.9 < 1.9 < 0.90 Co-58 < 1.4 < 2.8 < 2.1 < 2.0 < 1.1 Mn-54 < 1.5 < 3.0 < 2.1 < 2.0 1.1 (1.2) | |||
< 2.8 lm Zn-65 < 4.2 < 8.4 < 5.8 < 5.9 Fe-59 < 3.6 < 7.4 < 5.0 < 4.9 < 2.3 Co-60 < 1. 5 < 2.9 < 2.1 < 1.9- < 0.98 Ba-140 < 2.4 < 6.6 < 5.2 < 4.5 < 3.5 l < 4.1 La-140 < 2.8 < 7.6 < 6.0 < 5.1 l | |||
l | |||
*1.96c (Due to Counting Statistics) | |||
j 7 | |||
~ | |||
Table II.C.5 Radionuclide Concentrations In Surface Water. (pCf/L) | |||
Collection Date:.3/09/91 1 | |||
Downstream Sites Upstream Sites Ef fluent Radio St. Vrain S. Platte St. Vrain S. Platte Goosequill | |||
-nuclide F-20 R-10 A F-19 A-25 Cs-134 < 1. 2 < 2.2 < 2.6 < 1.3 < 3.3 Cs-137 < 1.5 < 2.7 5.3-(3.7)* < 1.6 6.6 (4.5) | |||
Zr-95 < 2.9 < 4.8 < 5.5 < 2.8 < 8.3 Nb-95 < 1.1 < 2.2 < 2.5 < 1.2 < 3.0 m Co-58 < 1.1 < 2.2 < 2.5 < 1.2 < 3.0 | |||
" Mn-54 < 1.3 < 2.2 < 2.5 1.E (1.6) 4.1 (3.8) | |||
Zn-65 < 3.4 < 7.7 < 8.7 < 3.8 < 8.9 Fe-59 < 2.8 ' < 5.1 8.6 (7.6) < 4.3 < 7.3 Co-60 < l.3 < 2.1 <-2.4 < 1.3 < 2.9 Da-140 7.8 (8.8) < 3.6_ < 6.4 < 2.0 < 4.8~ | |||
La-140- 9.0 (10) < 4.2 < 7.3 < 2.3 < 5.5 | |||
* 1.960 (Due to Counting Statistics) 4 | |||
= - ~ . . a. -uw-- - - - +~ -- - | |||
- =.. -- -- - - - - . .- - _ . - - . | |||
. . _ - - - - -_ -_ - - = - . - . - | |||
. + | |||
Table II.C.5 Radicia>011de Concentrations In Surface Water. (pCf/L) | |||
Collectim Date: 4/1V91 Downstream Sites Upstream Sites Ef fluent Radio .-St. Vrain S. Platte St. Yrain S. Platte Goosequill | |||
-nuclide F-20 R-10 A-21 F-19 A-25 Cs-134 < 2.2 ' < 3.0 < 2.4 < 3.5 < 2.0 Cs-137 ' < 2.6 < 3.7 < 2.9 < 4.2 < 2.4 Zr-95 < 4.6 < 6.9 < 5.6 < 8.6 < 4.6 Nb-95 < 2.1 < 3.1 < 2.2 < 3.1 < 1.9 Co-58 < 2.0 4.3 (3.5)* < 2.2 < 3.2 < 1.8 Mn-54 < 2.1 < 3.0 < 2.4 < 3.5 < 2.0 Zn-65 < 6.5 < 9.3 < 6.7 < 9.6 < 5.7 Fe-59 < 5.3 < 7.5 < 5.6 < 8.5 < 4.6 | |||
$ Co-60 < 2.1 < 3.1 < 2.6 < 3.7 < 2.1 Ba-140 < 3.4 < 6.3 < 5.2 < 5.6 < 3.2 La-140 <-3.9 < 7.2 < 5.9 < 6.5 < 3.7 | |||
*l.96a (Due to Counting Sta tis tics) | |||
.- .w.. | |||
e' Table II.C.5 Radionuclide' Concentrations In Surface' Water. (pC1/L) . | |||
Collection Date: .5/11/91-. | |||
Downstream Sites Upstream Sites Effluent ' | |||
Radio St. Vrain _S. Platte St. Vrain S. Platte Goosequill | |||
-nuclide F-2C' 'R-10. ~A-21 F-19 A-25 Cs-134 <-2.0 < 1. 5 < 2.4- < 1.8 < 1.2 Cs-137- < 2.4 <-1.9 < 2.9 < 2.2 3.4 (1.7) | |||
'Zr-95 5.5 (5.6)* < 3.3 < 5.6 < 4.2 < 2.5 Nb-95 < 1.8 < 1.4 < 2.0 < 1.6 < 1.0 Co-58 < 1.9 < 1.5 < 2.1- < 1.6 < 1.2 Mn-54 < 2.0 < 1.5 < 2.3 < 1.8 < 1.1 Zn <.5.4 < 4.1 < 6.3 < 4.9 < 3.1 Fe-59 < 4.6 < 3.5 < 6.2 < 4.6 | |||
< 3.3 FA Co-60 < 1.9 2.4 (1.8) < 2.5 < 1.9 < 1.1 Ba-140 < 4.8 < 3.5 < 3.8 < 2.9 5.5 (5.1) | |||
La-140 < 5.5 < 4.0 < 4.4 < 3.4 6.3 (5.9) | |||
*1.96o (Due to Counting Statistics) | |||
_.___.______________._____m | |||
iO | |||
: 3. . | |||
Table II.C.5 Radionuclide Contentrations In Sueface Water. (pC1/L) | |||
Collection Date: 6/07/91 Downstream Sites Upstream Sites Effluent | |||
-Radio St. '! rain 5. Platte St. Vrain S. Platte Goosequill | |||
-nuclide F-20 R-10 A F-19 A-25 Cs-134 < I .7 < 2.5 < 2.0 < 3.0 < 1.7 Cs-137 < 2.1 < 3.0 < 2.5 4.3 (4.4)* 2.6..(2.4) | |||
'Zr-95 '< 3.7 < 5.4 < 4.7 < 7.0 < 3.0 Nb-95 < 1.6 < 2.3 < 1.8 < 2.7 < 1.5 m Co-58 .< 1.6 .< 2.3 | |||
* < 2.0 < 3.0 < 1.9 Mn-54 < 1. 7 < 2.4. < 2.0 < 3.0 < 1.7 Zn-65 < 4.6 < 6.9 < 5.6 < 7.9 < 4.3 Fe-59 < 3.8 c 6.3 8.5 (6.3) < 6.9 < 5.3 Co-60 < 1.7 < 2. 5 < 2.1 < 3.3 < 1.6 Ba-140 < 2.7 < 6.5 < 3.3 < 4.9 < 2.6 La-140 <.3.1 < 7.4 < 3.8 < 5.6 < 3.0 | |||
*1.96o (Due to Counting Statistics) | |||
h= | |||
j Table II.C.5 Radionuclide Concentrations In Surface Water. (pCi/L) | |||
Collection Date: 7/12/91 Downstream Sites Upstream Sites l Effluent Radio St. Vrain. S. Platte St. Vrain S. Platte Goosequill | |||
-nuclide F-20 R-10 A-21 F-19 A-25 Cs-134 < 2.0 < 2.0 < 2.3 < 1.7 < 2.2 Cs-137 < 2.4 < 2.4 < 2.9 2.8 (2.4)* < 2.6 Zr-95 < 4.6 < 4.3 < 5.3 < 3.7 < 5.0 Nb-95 < 1.8 < 1.7 < 2.1 < 1.5 < 1.9 Co-58 < 1.8 < 1.8 < 2.2 < 1.6 < 2.5: | |||
u' | |||
" Mn-54 < 2.0 < 1.9 < 2.3 < 1.7 < 2.2 Zn-65 < 5.4 < 5.4 < 6.3 < 4.5 < 5.7 Fe-59 < 4.6 < 4.6 < 5.3 < 3.9 < 4.9 Co-60 < 2.1 < 1.9 2.7 (2.9) < 1.6 . < 2.3 Ba-140 < 3.2 < 3.1 < 5.4 < 2.7 < 3.5 La-140 ..< 3.7 < 3.5 < 6.2 < 3.1 < 4.0 | |||
*1.960 (Due to Counting Statistics) | |||
E | |||
g | |||
' r. | |||
i Table II.C.5 Radionuclide Concentrations In Surface Water. (pCi/L) | |||
Collection Date: 8/09/91 I | |||
Downstream Sites Upstream Sites Effluent - | |||
Radio St. Vrain 5, Platte St. Vrain S. Platte Goosequill | |||
-nuclide F-20 R-10 A F A-25 Cs-134 < 1. 9 < 2.0 < 2.3 < 2.3 | |||
< 2.4 Cs-137 3.0 (2.7) * '< 2.4 4.9 (3.3) < 2.9 < 2.9 Zr-95 < 4.1 < 4.2 < 5.2 < 5.3 < 6.6 Nb-95 < 1.7 < 1.8 < 2.0 < 2.1 < 2.2 (n-C0-58 < 1. 7 < 1.8 < 2.1 < 2.1 < 2.2 Mn-54 < 1.9 < 1.9 3.0 (2,5) < 2.3 < 2.4 Zn-65 < 5.2 < 5.6 < 5.9 < 6.4 < 6.3 Fe-59 < 4.3- < 4.6 < 5.3 < 5.5 < 5.6 C0-60 < 1. 9 < 1.9 < 2.4 < 2.5 < 2.6 Ba-140 < 3.0 < 3.1 < 3.8 5.3 (4.5) < 3.9 La-140 < 3.4 < 3.5 < 4.4 6.1 (5.2) < 4.4 | |||
*1.96o (Due to Countin9 Statistics) | |||
g y | |||
T | |||
~H , . | |||
.u- . | |||
f | |||
, Table II.C.5.RSdionuclide Concentrations 11nLSurface Water..(pC1'L)- . / . | |||
Collection Date:-9/14/91! - | |||
Downstream Sites . Upstream Sites' Ef fluent- , | |||
Radio- St. Vrain S. Platte? ' St.'Yrain S. Platte Goosequill | |||
-nuclide F-20 R210 'A-21~ F-19' A-25 Cs-134 < 1.9 < 3.1- <- 2.0 : .< 2.1 < 1.2 Cs-137' '3.8 (2.7)* < 3.7 4.5 (2.9) < 2.5 < 1.4 Zr-95 -<:4.1 | |||
< 6.6- < 4.7 - ''< 4.5 <:2.5 Nb-95 < 1.7- .< 2.7 1. 8 .. < 2.0 < 1.0 - | |||
' (n : | |||
Co-58 ' < 1.7 < 2.8 - < 1. 9 ~ < 1.9 < 1.1 Mn-54 < 1.9 < 2.9 | |||
< 2.0- < 2.0- < 1.2 7n-65 < 5.0 < 7.'4 -< 5.4 < 6.0 | |||
< 3.1 Fe-59 (.4.3- | |||
'< 6.9_ 7.3 (5.8) < 5. I ' < 2.7 Co-60. 6.8 (2.4) < 3.0- < 2.1. ' < 2.0 '< 1.1 Ba-140 < 4.9 <'4.6 < 4.2 | |||
'<'3.3- < 1.8- | |||
.La-140 < 5 .'7 < 5.3 < 4.9' < 3.8' .< 2.0' | |||
*1.96o (Due - to . Coun ti n9 'S ta ti s ti cs )' | |||
1 < | |||
1 e Y | |||
Table II.C.5 Radionuclide Concentrations In Surface Water. (pCi/L) | |||
Collection Date: 10/12/91 Downstream Sites Upstream Sites Effluent , | |||
Radio St.'Vrain S. Platte St. Vrain. S. Platte Goosequill | |||
-nuclide F-20 R-10 A-21 F A-25 Cs-134 2.2 (2.3)* < 2.0 < 2.4 < 2.2 < 1.1 Cs-137 4.0'(2.7) < 2.5 < 3.0 < 2.6 < 1.4 Zr-95 < 4.4 < 5.0 < 5.6 < 4.7 < 3.4 Nb-95 < 1.8 < 1.9 < 2.1 < 2.0 < 1.1 Co-58 < 1.8 < 2.0 < 2.4 < 2.0 < 1.3 cr- Mn-54 3.2 (2.3) < 2.1 < 2.4 < 2.1 1.6 (1.4) | |||
Zn-65 < 5.3 < 5.4 < 6.6 < 5.9 < 3.1 Fe-59 < 4.3 < 4.6 < 5.6 < 5.3 < 3.8 Co-60 < 1.9 < 2.2 3.2 (3.1) < 2.1 5.0 (1.5) | |||
-Ba-140 <'4.5 < 3.3 < 3.9 < 3.3 < 6.5 La-140 < 5.2 < 3.8 < 4.4 < 3.8 < 7.5 | |||
*1.96o (Due to Counting Statistics) r | |||
,,- _ _ _- __ ______.__.__._m_ _ _ _ _ . . - . - _ _ . _ . _ _ _ . _ _ . . _ _ . _ _ _ _ | |||
t | |||
. h-Table II.C.5 Radionuclide. Concentrations In Surface Water. (pCf /L) | |||
Collection Date: 11/09/91' 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 <-1.9 < 2.3 < 2.1- < 2.0 < 2.1 Cs-137- 3.3 (2.7)* < 2.8 2.8'(3.0) 3.4 (2.9) < 2.6 Zr-95 < 4.4 < 5.8 < 4.6 < 4.7- < 4.9 Nb < 1.7 < 2.2 < 1.9 < 1.8 < 1.9 Co-58 < 1.9 < 2.3 < 2.1 < 1.9 < 1.9 O Mn-54 < 1.9 < 2.3 < 2.1 < 1.9 < 2.1 Zn-65 < 4.9 < 6.2 < 5.5 < 5.4 < 5.9 Fe-59 < 4.3 < 6.1 < 4.7 < 5.2 < 6.7 Co-60 4.0 (2.4) < 2.4 < 2.0 < 1.9 < 2.3 Ba-140 < 5.8 < 3.7 < 3.3 < 5.0 < 3.4 La-140 < 6.6 < 4.3 < 3.8 < 5.3 < 3.9 | |||
* 1.96c (Due to Counting Statistics) u.,.m. w_. - - - - | |||
m e # | |||
Table II.C.5 Radionuclide Concentrations In' Surface Water. (pCi/L) | |||
Collection Dated 12/14/91 - | |||
-Downstream Sttes Upstream' Sites- Effluent Radio St..Yrain S. Platte St. Vrain S. Platte Goosequill | |||
-nuclide F-20 R-10 A-21 F-19 A-25: | |||
Cs-134 < 2.3 < 2.2 < 2.5 < 2.1 < 2.2 Cs-137 2.9-(3.4)* 6.0 (3.1) < 3.0 < 2.6 < 2.7 Zr-95 < 5.5 | |||
' < 5.1 < 5.8 < 4.8 < 5.1 . | |||
Nb-95 < 2.2 < 2.0 < 2.2 | |||
< 1.9 < 2.0 cn | |||
'" Co-58 < 2.6 < 2.4 < 2.3 < 1.9 < 2.0 2.7 (2.9) | |||
Mn-54 < 2.2' 3.6 (3.1) 2.7-(2.6) < 2.2 I Zn-65 < 6.4 < 5.9- <-6.8 < 5.7 < 6.0 i Fe-59 < 5.4 < 6.8 < 5.7 < 4.8 < 4.9 Co-60 < 2.5 < 2.3 < 2.6 < 2.3 < 2.4 Ba-140 <-3.8 < 3.5 < 4.0 | |||
< 3.3 < 3.5 La-140 -< 4.4 < 4.1 < 4.6 <-3.8 < 4.1 | |||
*1.'96o (Due to Counting Statistics) | |||
__ ,__m.__ . . _- __ . _ _ . _ _ _ _ _ - . - - -- . _ - - --- | |||
: 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 well at a_ personal residence in the town of Milliken. Table II.C.6 lists the measured concentrations of fission products and activation products in ground water. The Cs-137 results are not surprising due to residue of Chernobyl fallout, and the other results above MDC are assumed to be statistically false positive values. | |||
Table II.C.7 shows tritium concentrationis in the same well water samples. The results indicate short-lived cor.tamination of the aquifer supplying F-16 well. This well is not used for drinking water purposes and therefore dose commitment calculations are not ' warranted. Figure II.C.1 shows' measured 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 beginning early in 1991. The mean lifetime of tritium in the F-16 aquifer appears to be very short. See Figure _II.C.2. | |||
For comparison purposes:we include Table II.C.8 which lists the Maximum Permissible Concentrations in drinking water from 10CFR20. | |||
1 63 | |||
4 Table II.C.6 Radionuclide Concentrations in Ground Water. (pCf/L) 2nd 3rd 4th ist-Quarter 11 MAY 91 Quarter 09 AUG 91 Quarter 09 NOV 91 Quarter 16 FEB 91 Radio- F-16 R-5 R-5 F-16 R-5 F-16 R-5 nuclide F-16 | |||
< 2.2 < 1.8 < 2.1 < 2.1 < 2.0 < 2.2 < 2.1 Cs-134 < 3.4 | |||
< 2.2 4.1 (3.1) 3.7 (3.1) < 2.4 < 2.7 < 2.6 Cs-137 7.7 (4.6)* 6.5 (3.2) | |||
< 4.2 < 4.8 < 4.7 < 4.7 < 5. 7 < 4.5 Zr-95 < 6.9 < 4.9 | |||
< 2.1 < 1.7 < 2.0 < 2.1 < 1.9 < 2.2 < 2.0 Nb-95 < 3.1 | |||
$ < 2.0 < 1. 7 < 1.9 < 2.0 < 1.9 < 2.2 < 2.1 Co-58 < 3.1 | |||
< 3.1 < 2.2 < 1.8 < 2.1 4.0 (2.6) < 2.0 < 2.2 < 2.1 Mn-54 | |||
< 7.5 < 5.1 < 6.5 < 6.3 < 5.6 < 5.8 < 5.8 Zn-65 < 10.0 | |||
< 5.2 <43 < 5.0 < 5.1 < 4.6 < 5.0 < 4.8 Fe-59 < 7.8 | |||
< 2.2 < 1.7 < 2.2 2.7 (2.4) < 2.1 3.1 (2.7) < 2.1 Co-60 < 3.0 | |||
< 4.4 < 2.8 < 3.4 < 3.7 < 3.3 < 6.4 < 3.3 Ed-140 < 6.5 | |||
< 5.0 < 3.3 < 3.9 < 4.2 < 3.7 < 7.4 < 3.8 La-140 < 7.5 l | |||
*1.960 (Due to Cour, ting S ta tistics) | |||
~ - | |||
- _ . v, - m - ,. . | |||
m. | |||
6 | |||
- 6 9 | |||
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p rs ad | |||
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e a l W rl 5 0 e/ - 9 d t5 R 3 n r0 < ) | |||
u a: s o ud c r Qe it G t s d c it n ne 6 0 a i ol 1 9 t s | |||
cl - 3 n eo F < g a | |||
t SC n i it t n i u r 9 0 0 o | |||
c T 5 r/ - 0 o | |||
e2 t0 R 4 | |||
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r: e C. | |||
ad u ue D I Qt ( | |||
' I c 0 t e 6 0 o e sl 1 4 | |||
l rl - G b i o F < 9 a rC 1 T | |||
* 1 | |||
R_ | |||
a Figure !!.C.1 ' | |||
[ | |||
Tritium Concentrations at Location F-16 For 1984-1991 j 10000 'p l | |||
l | |||
.--s ' | |||
n | |||
.4 / | |||
\ ~ | |||
u ! .. \ | |||
& i c | |||
S 1000 - | |||
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a -w i | |||
Ns _ _, Ne. | |||
: g. , , . , ,,, ,,,,.,,,...,,,., ,r - ' - ** | |||
1984- 1985 1986 -1987- 1988 1989 1990 1991-Year . | |||
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- 1 F i n ' | |||
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t n i a i g , | |||
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9 8 | |||
n9 s 9 1 | |||
o9t l t 1 us i | |||
t ae r4r 8 8 a r | |||
n8g ' | |||
9 e e9n i . | |||
1 Y l | |||
c1 p n r m o | |||
CF y o a s | |||
7 8 | |||
. l 9 | |||
m kee 1 | |||
u - | |||
i t | |||
i w | |||
r g 6 8 | |||
T i n * - | |||
9 1 | |||
w e 2 o C. | |||
h I | |||
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r 9 - | |||
u g 1 i . | |||
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- - - r~- h _ , - - - - - _ - | |||
' 8 4 | |||
0 0 0 0 0 0 0 0 0 09 0 0 0 0 0 0 0 0 0 01 0 0 0 0 0 0 8 6 4 2 0 8 6 4 2 1 1 | |||
IhOS co | |||
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? | |||
Tahir II.C.8 Maximum Permissible Concentrations in Drinking Water. ' | |||
'(10CFR20, . Aprendix B, ~ Table ~ II) 11 - 3 . 3 x 106'pCi/L.' | |||
2 I-131 3.x.10 pCi/L 3 | |||
Cs-134 9 x 10 pCf/L 4 | |||
Cs-137 2 x 10 pCi/L 4 | |||
g Zr-95 6 x 10 pC1/L Hb-95 1 x 10 pC1/L 5 | |||
Co-58 1 x 10 pCi/L l 5 | |||
Mn-54 1 x 10 pCi/L 5 | |||
Zn-65 1 x 10 pCi/L l | |||
Fe-59' 6 x 10 pCi/L 4 | |||
Co-60 5 x 10 pCi/L Ba-140 3 x 104 'pCf/L | |||
.La-140 2 x 10* pCi/L t | |||
l' | |||
'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 infant consuming milk produced from cows grazing local pastures. Milk is the critical pathway E 3r possible dose commitment to humans from environmental contamination of H-3. I-131, Cs-137- and Sr-90. For this reason milk is sampled extensively to document the presence or absence of radioactivity due to reactor operations. A three liter milk sample is counted for determination of- Cs-137, Cs-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 Mellor, Health Physics 38: 203-213, 1980. | |||
There - are no dairies (or personal milk cows) in the | |||
; facility' 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 (refer- to updated FSAR). The description of these locations can be found in Table 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 o n ' p ". a t u r e - b u t under dry-lot management typical of EatTcern Colorado. | |||
69 | |||
-- = . - | |||
r Table II.D.1 lists the concentrations of all radionuclides that-are investigated in milk samples. During 1991, elevated concentrations of I-131 were again consistently ' | |||
observed only at site A-22. The source of this I-131 is from nuclear medicine thyroid therapy practice in the Denver 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 (Independence) 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 t | |||
l describing this observation and the magnitude of the I-131 l | |||
concentrations has been submitted for publication in the Health Physics Journal. Note that A-22 drops out of the sampling program each year in order to meet milk collection Y | |||
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 controlled and independent of K intake. K-nat is measured -in - all milk samples as a quality control measure for the other radionuclides determined . | |||
l-in the same sample by gamma-ray spectrometry, but K-nat concentrations are no longer reported in Table II.D.1. | |||
t Table II.D.2 lists measured tritium concentrations in milk. Significant elevated tritium concentrations in milk due L to reactor effluents have never been observed during the oper.ational or defueling phase of the reactor. This implies 7 | |||
d | |||
the. tritium from_ reactor effluents is not contributing any radiation dose to huinans via the milk pathway. Tritium conce'ntrations 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 | |||
;' t ; 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 effluents has never been observed during the operational or defueling phases of Fort St. Vrain. | |||
!~ | |||
t-l 71 | |||
v Table II.D.1 Radionuclide Concentrations In Milk. (pCf/L). | |||
A-23 A-24 A-26 R-8 LOCATIDH A-6 A-18 A-22 h 1/05/91 1/12/91 1/12/91 1/12/91 Collection Date 1/12/91 1/05/91 | |||
< 0.33 < 0.43 < 0.21 < 0.5 1-131 < 0.49 < 0.29 h l | |||
< 2.7 < 3.5 < 1.7 < 2.3 Cs-134 < 2.1 < 2.1 h | |||
< 3.2 < 5.1 4.1 (2.9)* < 3.5 Cs-137 < 2.6 < 2.5 h | |||
< 4.3 h < 4.2 < 5.1 < 3.3 < 3.5 Ba-140 < 3.4 | |||
< 4.9 h < 4.8 < 5.9 < 3.8 < 4.0 ld-140 < 3.9 2/09/91 h 2/02/91 2/09/91 2/09/91 2/02/91 Collection Date 2/09/91 | |||
< 0.4 h < 0.25 < 0.44 < 0.23 < 0.17 M I-131 < 0.35 | |||
< 2.5 < 3.4 < 2. 3 < 3.7 < 2.4 Cs-134 3.0 (2.8) h | |||
< 3.5 < 3.1 h < 4.9 < 3.3 < 4.4 4.2 (4.1) | |||
Cs-137 | |||
< 3.4 < 5.1 h < 4.7 < 4.2 < 5.9 < 4.2 Ba-140 | |||
< 5.9 < 5.5 < 4.9 < 6.8 < 4.8 ta < 3.9 h | |||
___. -140 3/09/91 3/02/91 3/02/91 3/09/91 3/09/91 3/02/91 Collection Date 3/02/91 | |||
< 0.46 < 0.27 < 0.4 < 0. 5 < 0.41 < 0.48 1-131 < 0.31 2.5 (2.8) < 2.5 < 2.4 < 4.0 < 2.3 < 2.7 Cs-134 < l.5 2.3 (2.3) < 3.4 < 3.6 < 3.5 < 5.9 3.6 (4.0) 4.4 (3.9) | |||
Cs-137 | |||
< 2.5 < 3.4 < 3.5 9.4 (5.3) < 5.9 < 4.6 < 4.3 Ba-140 | |||
< 3.9 < 4.1 11.0 (6.1) < 6.8 < 5.3 < 5.0 La-140 < 2.8 h - sample not collected (at dairy owner's request) | |||
* 1.96c (Due to Counting Statistics) t_ _ _ _ _ _ _ _ | |||
u Table II.D.1LRadionuclide Concentrations In' Milk.- (pCi/L). .- | |||
LOCATION 'A-6 A A-22' 'A-23 .A-24 .A-26 R-8 Collection Date. 4/06/91: :4/13/91- ~ 4/06/91' 4/06/91 4/13/91- 4/13/91: ;4/06/91 1-131 < 0.31' < 0.45 < 0.37 < 0.45'- .< 0.5 < 0.35 <'0.37-Cs-134 < 2.3 < 2.4: < 2.3~ < 2.5L < 2.6i ~< 2.3- J< ' 2.4' Cs-137 < 3.5 < 3.71 5.9 (4.0) < 3.1 < 3 . 2 .- < 3.5- ,< 3.5 - | |||
~Ba-140 4.0(417)* < 4.3 < 4.3 .< 4.0 < 4.9 < 4.3- < 4.4 La-140 4.5 (5.4) ' < 4.9 < 5.0 < 4.6' < 5.6' < 4.9. < 5.0 Collection Date 5/04/91- 5/11/91 -5/04/91 5/04/91- 5/11/91 5/18/91- 5/04/91 1-131 0.48 (0.53) < 0.28 2.3 (0.65) ,< 0.41 < 0.48, < 0.19- < 0.34 U Cs 134 < 2.5 < 2.3 2.8-(3.1) < 2.6 < 2.5 < 2.7 < 2.3 Cs-137 ^< 3.1 < 3.4 < 3.1 4.2 (3.7) < 3.1 < 3.2 < 3.5 i Ba-140 < 4.1 <.4.2 < 5.3 < 4.1 < 4.0 < 4.3 4.6 (5.3) | |||
La-140 < 4.7 <.4.8 < 6.1 < 4.7 < 4.6 < 4.9 5.3 (6.1) | |||
Collection Date 5/18/91 5/25/91 5/18/91 5/18/91 5/25/91 5/25/91 5/18/91 ! | |||
I-131 < 0.'32 < 0.35 < 0.47 < 0.29 < 0.43 < 0.43 < 0.5 Cs-134 < 2.2 < 2.2 2.4 (2.3) 2.2 (2.6) < 2.4 < 2.4 < 1.8 Cs-137 < 3.2 < 3.2 3.1 (2.7) <.3.2 e 3.0 < 2.8 2.6 (3.1) q | |||
< 4.4 < 3.1 < 3.1 < 3.1 < 4.0 < 3.7 < 3.7 Ba-140 La-140- < 5.0 < 3.6 < 3.5 < 3.6 < 4.5 < 4.3 < 4.2 4 | |||
* l.96o (Due. to Counting Statistics.) | |||
Table II.D.1 Radionuclide Concentrations In Milk. (pCi/L). | |||
LOCATION A-6 A-18 A A-23 A A-26 R-8 | |||
~ | |||
Collection Date 6/01/91 6/07/91 6/01/91 6/01/91 6/07/91 6/07/91 6/08/91 1-131 < 0.3 < 0.3 2.1 (.62)* .< 0.3 < 0.4 < 0.5 0.4 (.43) | |||
Cs-134 < 2.2- < 2.3 < 3.6 < 2.3 < 2.8 < 3.1 < 2.3 Cs-137 < 3.3 < 3.4 < 5.1 < 3.3 5.6 (5.0) < 3.9 < 3.4 Ba-140 < 3.2' < 4.4 < 6.4 < 3.3 < 4.t < 5.1 < 4.2 La-140 < 3.6 < 5.0 < 7.4 | |||
. < 3.8 < 4.8 < 5.9 < 4.8 | |||
" Collection Date 6/14/91 6/21/91 h 6/14/91 6/21/91 6/21/91 6/21/91 I-131 < 0.35 < 0.49 h < 0.45 < 0.33 < 0.18 < 0.36 | |||
% Cs-134 < 2.5 < 2.0 h < 2.5 < 2.0. < 2.0 < 1.5 Cs-137 < 3.0 c 2.4 h < 3.0 < 2.9 < 2.9 < 1.8 Ba-140 < 4.1 < 3.1 h < 5.0 < 6.5 < 2.8 < 3.6 La-140 < 4.8 .< 3.6 h < 5.7 < 7.5 < 3.2 < 4.1 Collection Date 7/12/91 7/12/91 h 7/12/a1 7/12/91 7/19/91 7/12/91 1-131 < 0.49 < 0.34 h < 0.27 < 0.19 < 0.2 < 0.34 Cs-134 < 2.4 < 1.9 h < 2.1 < 2.5 < 2.5 < 2.7 Cs-137 < 3.6 < 2.8 h 4.9 (3.0) < 3.1 < 2.9 <-3.3 Ba-140 < 3.5 < 2.7 h < 3.3 < 4.1 < 3.9 < 4.8 | |||
-140 < 4.1 < 3.2 h < 3.8 < 4.7 < 4.5 < 5.6 | |||
* 1.96o (Due to Counting Statistics) h - sample not collected (at dairy owner's request) 1 ? | |||
u _ _ -- . - - - | |||
. 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 7/19/91 '7/26/91 h 7/19/91 7/26/91 7/26/91 7/26/91 1-131 < 0.36 - .< 0.4 h < 0.42 < 0.44 < 0.2 '< 0.5 Cs-134 y2.4 < 2.4 h < 2.3 < 2.3 < 2.3 3.1 (2.7) | |||
Cs-137 4.1 (3.6)* 4.2 (3.5) h < 3.3 < 3. 3 < 3.4 3.7 (3.8) | |||
Ba-140 ' < 4.8 < 5.0 < 3.7 < 4.5 < 3.4 < 3.2 h | |||
La-140 < 5.5 < 5.7 h < 4.2 < 5.2 < 3.9 | |||
. < 3.6 Collection Date 8/09/91 8/02/91 h 8/09/91 8/09/91 8/09/91 8/02/91 y 1-131 .< 0.47 < 0.41 h < 0.43 < 0.2 < 0.44 < 0.22 Cs-134 < 2.3 < 2.0 h < 1.9 < 2.0 < 2.6 < 3.3 Cs-137 3.5 (4.1)- 3.7 (2.9) h 4.1 (3.3) 3.5 (2.9) < 3.1 5.3 (5.9) | |||
Ba-140- < 3.3 < 3.9 h < 3.5 < 3.2 < 4.2 < 4.9 | |||
< 3.8 La-140 < 4.5 h < 4.0 < 3.6 < 4.8- < 5.6 Collection Date 8/16/91 8/23/91 h 8/16/91 8/23/91 8/31/91 8/16/91 1-131 < 0.2 < 0.48 h < 0.29 < 0.22 < 0.16 < 0.18 Cs-134 < 2.0 < 2.3 h < 2.3 < 2.5 < 2.2 < 2.1 Cs-137 < 2.9 5.6 (4.0) h 6.4 (4.1) < 3.1 3.6 (3.2) < 2. 7 Ba-140 < 2.8 < 3.7 h < 3.4 < 4.4 < 3.5 < 3.6 La-140 < 3.2 < 4.2 h < 4:0 < 5.1 < 4.0 < 4.2 | |||
* 1.96o (Due to Caunting Statistics.) . | |||
h - sample not collected (at dairy owner's request) . | |||
& ~. | |||
h[ ?DX &% ~ ' ' V2 ,r Q= s , | |||
Table 11,0.1 Radionuclide concentrations la Milk. iptfit). | |||
A-23 A-2A A-2E R-8 LOCATION A-6 A $8 A-22 h 9/07/91 9/21/91 9/14/91 9/14/91 l Collection DMe : 9/n7bl 9/14/91 | |||
< 0.4 < 0.5 h < 0.3 < 0.3 < 0.2 0.5 (.49) | |||
I-131 | |||
< 2.0 < l.1 < 2.3 < 2.3 Cs-134 < 2.3 < 2.5 h | |||
< 3.0 h < 2.9 1.6 (1.9) < 3.4 < 3.3 Cs-137 < 2.9 | |||
< 4.0 h < 3.7 2.2 (2.5) < 3.4 < 3.4 Ba-140 < 3.7' | |||
< 4.3 < 4.6 h < 4.3 2.5 (2.9) < 3.9 < 3.9 La-140 h 9/21/91 9/28/91 9/28/91 9/28/91 Collection Date 9/21/91 9/28/91 | |||
< 0.22 h < 0.44 < C.5 < 0.48 < 0.48 1-131 < 0.32 | |||
< 2.4 h 1.2 (1.4) < 2.4 < 2.6 < 2.4 5 Cs-134 < 2.4 | |||
< 3.5 < 3.5 h 1.9 (1.7) 5.6 (4.1) < 3.1 3.5 (3.4) | |||
Cs-137 | |||
< 3.4 < 2.6 < 3.4 < 4.2 < 4.5 Ba-140 < 4.5 h | |||
< 3.9 h < 3.0 < 3.9 < 4.8 < 5.1 La-140 < 5.2 10/05/91 h 10/09/91 10/12/91 10/12/91 10/19/91 Collection Date 10/05/91 h < 0.44 < 0.49 < 0.39 < 0.31 1-131 < 0.26 < 0.' | |||
<z0 h < 2.5 < 2.6 < 2.7 < 2.0 Cs-134 < 2.7 | |||
< 3.2 < 3.0 h < 3.0 < 3.6 < 3.2 2.9 (3.0) | |||
Cs-137 | |||
< 4.3 7.5 (5.3) h < 3.9 < 3.7 < 4.2 < 3.3 Ba-140 8.5 (6.1) h < 4.5 < 4.3 < 4.8 < 3.8 J, La-140 < 5.0 | |||
* 1.96o (Due to Counting Statistics) h - sample not coll:cted ;' dairy owner's request) | |||
I | |||
: Table II.D.1 Radionuclide Concentrations 'In Miik. (pCi/L). , | |||
LOCATION A-6 A *8 A-22 'A-23 A-24 A-26 R-8 : | |||
Collection Date 11/02/91- 11/02/91- 11/02/91' 11/02/91- 11/09/91 11/09/91 '11/09/91 | |||
.-131 0.47 (0.53)* < 0.39' h < 0.5 < 0.3 < 0.2 < 0.32 Cs-134- < 2.4 < 2.5 h < 2.2 - < 1.8 < 4.1 < 3.4 Cs-137' < 3.4 < 3.0 h < 3.3 3.6 (3.1) < 5.8 < 4.9 Ba-140' < 4.2 < 3.9 h < 3.2 < 2.6 < 6.0 < 4.9 La-140 < 4.8 < 4.5 h < 3.7 - < 2.9 < 6.9 < 5.7 ; | |||
i Collection Date 12/14/91- 12/07/91 12/07/91 12/07/91 12/14/91 12/21/91 12/14/91 ' | |||
1-131 < 0.33 < 0.34 h < 0.34- .< 0.46 < 0.44 < 0.33 Cs-134 < 2.5 < 2.4 h < 2.9 < 2.5 3.1 (3.2) < 1.5 ! | |||
Cs-137 -< 3.0 < 2.9 h < 3.4 < 3.0 < 3.2 3.2 {2.2) | |||
Ba-140 < 3.9 < 3.9 h < 4.6 < 4.1 < 4.3 '< 2.5 - | |||
La 'A0 < 4.5 < 4.5 h < 5.3 < 4.7 < 4.9 < 2.8 ' | |||
t | |||
* 1.96o (Due to Counting Statistics) - | |||
h - sample not collected (at dairy owner * , request) . | |||
! , ! !' ll17 t ti , | |||
i . | |||
e ) ) | |||
c 0 0 n 6 1 e 0 0 0 0 0 0 0 0 0 0 0 0 3 4 _ | |||
r 8 0 1 0 0 0 0 9 8 9 9 0 9 ( ( | |||
e - 4 4 4 4 4 4 3 3 3 3 4 3 f R 0 0 e < < < < < < < < < < < < 6 4 R 4 4 - | |||
) | |||
0 6 0 0 0 0 0 0 0 0 0 0 0 0 6 | |||
3 0 - | |||
2 0 1 0 0 0 0 9 8 9 9 9 0 ( 0 | |||
- 4 4 4 4 4 4 3 3 3 3 3 4 4 A 0 | |||
< < < < < < < < 1 < _ | |||
4 | |||
) - | |||
0 1 =_ | |||
- 4 0 0 0 0 0 0 0 0 0 0 0 0 0 4 2 0 1 0 0 0 0 9 8 9 9 9 9 5 ( | |||
- 4 4 4 4 4 4 3 3 3 3 3 3 3 A 0 | |||
< < < < < < < < < < < < < 7 4 | |||
) | |||
. L | |||
/ 3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 ) | |||
f s 2 0 1 0 0 0 0 9 9 9 9 9 9 5 5 t C e - 4 4 4 4 4 4 3 3 3 3 3 3 3 3 s p t A e | |||
( i < < < < < < < < < < < < < < u S q e | |||
k | |||
. t n | |||
r l e s c | |||
're i | |||
M a 2 0 0 0 0 0 0 j 2 0 0 0 0 9 8 n d - 4 4 4 4 3 3 n i A A ) | |||
w h h < < < < < < h h h h h h . | |||
o s s n c y o i t | |||
r i i t | |||
a 1 | |||
9 i s a d | |||
r 9 8 0 0 0 0 0 0 0 0 0 0 0 0 0 0 t t 1 1 0 1 0 0 0 0 9 8 9 9 0 9 5 0 a t _ | |||
n - 4 4 4 4 4 4 3 3 3 3 4 3 3 4 t a e A S ( | |||
c < < < < < < < < < < < < < < | |||
n g d _ | |||
C o i n e t t c u | |||
m nu e l | |||
i 0 0 0 0 0 0 0 0 0 0 0 0 0 0 o l t 6 0 1 0 0 0 0 9 9 9 9 9 9 5 5 C o i | |||
r | |||
- 4 4 4 4 4 4 3 3 3 3 3 3 3 3 o c A _ | |||
T < < < < < < < < < < < < < < t t o | |||
2 eu n D. | |||
n D e o Y R R ( l I i E E p | |||
_ I t Y R B B o m c R A - | |||
T T M M 6 a | |||
. l e e l e A | |||
U U | |||
R H | |||
C L | |||
I E E Y Y S | |||
U S | |||
U E | |||
T E | |||
T 9 s b l t N B R R Y Y N N L L G G P P 1 - _ | |||
a oa A E A P A A U U U U U U E E T CD J F M A M M J J J J A A S S | |||
* h u | |||
y Table II.D.2 Tritium Concentrations in Milk. (pC1/L) 1991 Adjacent Sites Refererce Collection Date A-6 - A-18. A-22 A A-24 A-26 R-8~ | |||
OCTOBER 500 (410)* 830 (420) h 600 (410) < 400 '< 400 < 400 fl0VEMBER '< 400 < 400 'h 570 (420) < 400 < 400 < 400 DECEMBER- 570 (420) < 400 -h < 400 540-(420) 490 (420) 790 (420) | |||
I! | |||
i i | |||
* 1.96. (Due to Counting Statistics) * ! | |||
h - sample not. collected (at dairy owner's request)- , | |||
i | |||
%. , , '-~6- v--* - _ 4- - . _ _ _ _ _ _ _ _ _ _ - _ _ - - - - - - - - - - - - - . . - - - - - - - - - . - - - - - - - - _ --- -- | |||
II.E. Food Products , | |||
Food sampling -locations were selected from areas possibly irrigated by surface 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. Locatjons and available ; | |||
produce of ten change due to owner steeds, harvest time, harvest l | |||
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 1991 harvest. Two of the food samples showed detectable Cs-137 from past Chernobyl fallout i deposition and the one result with positive I-131 is assumed to be a false 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. 1-131 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 observed, presumably due to surface L | |||
soil deposits. | |||
80 | |||
:f | |||
1 : :! # ! ;;[ t! I! ;ir a 5 > L' | |||
) | |||
) ) | |||
g 7 0 | |||
6 _ | |||
k 3 0 0 0 0 0 - | |||
/ 1 8 9 2 8 - | |||
f - 4 ( 7 0 ( 0 C s 1 7 1 1 8 1 _ | |||
p C 0 0 | |||
( < < < < < < | |||
2 1 s 1 3 t | |||
c u | |||
_ d _ | |||
_ o ) | |||
r 0 P 4 | |||
* 3 0 4 0 d 1 5 5 1 9 3 9 . | |||
o - 2 ( 2 o s 1 6 5 6 1 7 6 F C 0 i | |||
n 7 1 | |||
s n - | |||
i o * | |||
) . | |||
t 0 ) | |||
a s r 1 0 0 6 0 0 0 c k 3 1 8 8 i n 1 1 2 7 ( 2 1 1 t e 9 - 1 1 1 6 1 2 6 s c / I 0 i n 4 < < < < < < | |||
< t o 2 7 a . | |||
_ C / 1 t 9 S e . | |||
_ d e S g i t R n l a N E i c D E O P t u P L P n , | |||
n n e U S S L E u . | |||
o o p O E E E P S o i i y L O 0 M R S C d t T A T 1 R I E N a c T A A E L N P O o - | |||
R e d N T M T I R P I t l o A O D A H O E N 1 l o C P T W C C P O e o F u C D E. ( | |||
_ I n I | |||
i o o 6 | |||
e t 9 a | |||
J l | |||
b a | |||
c o | |||
8 9 | |||
7 | |||
/ | |||
2- .. 29 8 | |||
0 3 | |||
1 3 | |||
2 1 | |||
1 A A A A A | |||
_ T L A A R + | |||
r | |||
... ... - . - - . - - - - . . ~ - . - -..-.- - - --..--~.-.~ ~ . - . _ - | |||
-+ | |||
l l | |||
II . F . - Aquatic Pathways Table II.F.1 shows radionuclido concentrations measured ' | |||
in fish samples collected at F-19, A-25 and R-10 on two dates ! | |||
in 1991. The fish were collected by shocking and netting and l the composite sample was homogenized without cleaning and analy*ed on a wet weight basis. The positive values of co-137 l were assumed to be due to fallout. l Table II.F.2 shows the measured concentrations of both { | |||
Ce-137 and Cs-134 in surface sediment collected at R-10, the i downstream location. There was measurable activity of Cs-137 clearly due to the Chernobyl fallout. The cesium ions are beund nearly irreversibly by the clay mineral matrix in the , | |||
sediment. The concentrations observed in 1991 were statjstically the same as observed in 1990. | |||
observation -for p.m hirala fluminna, 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 ! | |||
1 Asia.- The freshwater clams are now found in large river systems in 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 hava indicated no evidence of Corbicula at any ; | |||
L of the sampling sites of the reactor surface water coursos, i | |||
1 j1 L:- | |||
I j; 82 l V M- W 'TT --PV-54 V,17wWm se M-y ~ 41 WP--.wr - | |||
if e- g- qyry, -r''r'-NY'W'S-J | |||
^ - | |||
Table II.F.1 Radionuclide Concentrations in Fish. (pC f /kg) | |||
Collection Date First Half Second Half Upstream E f fluent Downstream Upstream Ef fit:ent Downstream Radionuclide F-19 A-25 R-10 F-19 A-25 R-10 Cs-134 | |||
: < 5.6 < 4.3 < S.7 < 5.5 < 6.0 < 6.3 Cs-137 | |||
< 6.6 < 5.2 < 6.7 < 6.2 7.2 (8.4)* 16.0 (8.2) i | |||
: Co-58 | |||
!- < 5.8 < 4.5 < 5.8 < 5.0 < 5.4 < 6.3 Mn-54 | |||
< 5.6 < 4.3 < 5.7 < 5.2 < S.8 < 6.0 | |||
$ In-65 | |||
< 16.0 < 12.0 < 16.0 < 15.0 < 17.0 < 21.0 { | |||
Fe-59 | |||
< 8.8 < 8.4 < 9.1 < 8.8 < 15.0 < 10.0 Co-60 | |||
; < 6.1 < 4.4 < 6.0 < 5.7 < 6.2 < 6.9 | |||
* 1.96o (Due to Counting Statistics) | |||
I b | |||
e,- _ _ -r - e . - - ,mm _ _ . - - - _ - _ . - - - - _ - - - - - - - _ - - - - . - - _ . _ _ . . _ _ . . _ - . - - - . _ . . . - . . - - - | |||
:o; 1 i | |||
l II.F.2 l RadionJclide Concentrations in -Sediment from location R10. (pCi/kg) | |||
Radionuclide Collection Date 6/28/91 Cs-134 < 10.0 Cs-137 54.0 (12.0) | |||
* j Radionuclide Collection Date 10/19/91 | |||
.. Cs-134 < 11.0 Cs-137 83.0 (13.0)- | |||
1.96o (Due to Counting Statistics) 4 F | |||
F I | |||
l. | |||
i 84 i L | |||
1 J | |||
, . . .. . - ~ - . - - - - . - . - . _ - - - . . - _ . . . . - . . . - . - . _ . . | |||
l 4 | |||
j i | |||
.T.I.G. Samplo 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 studioc program is the principal crosscheck. | |||
This involves the analysis of a variety of environmental media containing various leveln of radionuclides. The media, type of analysis and frequency of analysis for the EPA program are summarized below. .- | |||
lipJillun Analysis (radionuclide) Freauency Water 11 - 3 Triannually Water Gross beta, gross alpha Semiannually Water Co-60, Zn~65, Cs-13 4, Co-13 7 Triannually Water I-131 Somiannually | |||
, Air partic- Cs-137, gross beta, Stmiannually 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 noted that during 1989, our laboratory became certitied by the EPA for drinking water analysis. | |||
Table II.G.1 gives the EPA crosscheck data for 1991. The EPA uses the parameter, Estimated Laboratory Precision (ELP), | |||
calculated as one standard deviation for one datermination. | |||
85 | |||
i l | |||
1 l | |||
The normalized deviation of our mean from the known is calculated as: | |||
CSU mean value - EPA knpyn valva o/n Wheret o = standard deviation of the mean of all participating laboratory results n = number of analyses by our .aboratory, normally n=3 , | |||
The control limit is determined by the mean range of all results and three standard deviations of the range. If any result exceeds two standard deviations from the mean (warning level), the result is unacceptable. Whenever our mean value falls outside this limit, the calculations are rechecked and the sample reanalyzed if possible. During 1991 all results except 13 were within the warning level. The resulte exceeding the warning level have the notation (n) in Table II.G.I. | |||
Table II.G.2 lists independent results for H-3 in water samples split between this laboratory and the laboratory at the Fort St. Vrain Generating Station. The comparison between - | |||
laboratories in general was acceptable. , | |||
' Table II.G.3 lists the results of gross beta analyses of the split water samples. The procedural differences between , | |||
l 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 i' | |||
crosscheck program. Replicate samples are independently analyzed. The- replicate results are- not statistically l | |||
1 l' 86 | |||
+ | |||
.x different and imply that the precision of the methods is acceptable. | |||
During 1991 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 often recalculated by hand and those done during 1991 were all verified to be correct. , | |||
I b | |||
v 9 | |||
h 9 | |||
87 | |||
Tablo ll.G.1 EPA Cecus* Check Dato $umesry. 1991. | |||
Radio- CSU EFA 1 E.L.P.* Wormalized Deviation Date suclide Value Value f rcn kno.sn** | |||
WA1EP TRIT 1DM spCl/L) | |||
Feb 22 M3 4367 4418 442 0.20 Jun 21 H3 12000 124B0 1248 0.67 Oct 18 M3 2700 2454 352 1.21 WATER, Alpha /Jeta (pci/L) | |||
Jan 25 alpha 10.33 5.0 $.0 1.83 beta 5.67 5.0 5.0 0.23 May 17 alpha 11.67 24.0 6.0 3.56 (1) beta 29.00 46.0 5.0 5.89 (2) | |||
Sep 20 alpha 14.00 10 3 5.0 1.39 beta 15.00 20 3 5.0 1. 73 WATER, 1 131 (pCl/L) | |||
Feb 15 1 131 77.67 75.0 8.0 0.58 Aug 09 I 131 18.67 20.0 6.0 0.34 WATER, Perfornance (pci/L) | |||
Apr 16 alpha 23.67 54.0 14.0 3. 75 (3) beta 102.00 115.0 17.0 1.32 Cs 134 43.33 24.0 5.0 6.70 (4) | |||
Cs 137 48.33 25.0 5.0 8.La (5) | |||
Oct 22 alpha 81.00 82.0 21.0 -0.D8 bets 45.00 65.0 10.0 3.46 (6) | |||
Cs 134 10.67 10.0 5.0 0.23 Cs 137 15.67 11.0 5.0 1.62 WATER, Gamma (pcl/L) | |||
Feb 8 Co 60 38.33 40.0 5.0 0.58 Zn 65 133.00 149.0 15.0 1.85 Cs 134 4.67 8.0 5.0 i.15 Cs 137 10.67 8.0 5.0 0.9i Ba 133 16.33 75.0 8.0 12.70 (7) | |||
Jun 07 Co 60 9.00 10.0 5.0 0.35 2n 65 83.00 108.0 11.0 3.94 (8) | |||
Cs 134 11.67 15.0 5.0 1.15 Cs 137 15.33 14.0 5.0 0.46 Ba 133 16.33 62.0 6.0 -13.io (9) | |||
Oct & Co 60 21.33 29.0 5.0 2.66 2n 65 42.67 73.0 7.0 7.51 (10) | |||
Cs 134 7.67 10.0 5.0 0.61 Cs 137 10.00 10.0 5.0 0.G0 Ba 133 83.67 98.0 10.0 2.48 i | |||
I | |||
* E.L.P. = Expected laboratory precision. | |||
** Wormalized deviation s (CSU mean EPA known)/(dn); if this value falls between upper & lower warning levels, the accuracy is acceptacle. | |||
88 l | |||
Table II.G.1 EPA Cross Check Data Summary, 1991. (contiroed) | |||
Radio | |||
* CSU EPA 1 E.L.P.* Wormalized Deviation Date ruclida Value Value f rorn known** | |||
MILK (pCf/L) | |||
Apr 26 l 131 73.33 60.0 6.0 3.85 (ii) ca.137 52.33 49.0 5.0 1.15 K 40 1521.67 1650.0 83.0 2.68 (12) | |||
AIR FILTERS (pC1/L) | |||
Mar 29 alpha 22.67 25.0 6.0 0.67 beta 124.00 124.0 6.0 0.00 Ct 137 99.00 40.0 5.0 20.44 (13) | |||
Aug 30 alpha 22.67 25.0 5.0 0.67 bets 90.33 92.0 10.0 0.29 C4 137 30.67 30.0 5.0 0.23 I i | |||
- l | |||
* E.L.P. = fapeeted Laboratory precision. | |||
" NormelIZed A. ' ation a (CSU mean EPA known)/(a[n), if th{s value f aits between upper & tower warning levels, the accuracy la acceptable. | |||
89 | |||
.. _ h l 1 | |||
' Tame II .G.2 , | |||
Tritium Crosscheck Analyses on Split Water samplen Determined by Colorado state University and P4Lic SeryIce Company. 1991 , | |||
Collection Sanple Tritita Concentrations pct /L t Date Location CSU PSC 4 | |||
Jan 12 A 25 3500 (460)* 3970 (506) | |||
Jan 12 A 21 <400 <366 Jan 2 E 41 <400 <366 f | |||
Feb 09 A-25 2300 (450) 2620 (476) | |||
.Feb 09 A 21 <410 <355 , | |||
Feb 13 E 41 <400 <358 Mar 09 A 25- 1100 (400) 1620 (456) | |||
Mar 09 A 21 <390 <355 Mar 13 E 41 <390 <355-Apr-13 A 25 690 (400) 1400 (448) | |||
Apr 13 A 21 <400 <352 Apr 03 E 41 <400 523 (432) , | |||
'May 11 A 25 <400 <352 | |||
. May 11 A 21 <390 <352 May 08 E 41 <400 <352 Jun 07 A 25 <390 <361 Jun 07 A 21 <390 <361 Jun 05 E 41 <390 <361 Jul 12 A 25 - < 390 <347 Jul.12 A 21 < 380 358 Jul 03 E-41 < 380 <347 Aug 09 A 25 < 400 <3f7 Aug 09 A 21 < 400 <35/- | |||
Aug 07 E 41 < 400 <357 Sep 14 A 25 1500 (380) 911-(457) | |||
Sep 14 A 21 3A0 (360) <368 Sep 04 E 41- < 400 <368 Oct 12 A 25 1400 (430) 838 (446) | |||
Oct 12 A 21 530 (420) 586 (442) | |||
Oct 02 E-41 < 400 - 392 (438) | |||
Nov 09 A 25 5700 (480)- 5900 (525)- | |||
Nov 09 A 21 -< 400 <357-Nov 06 E 41 450 (410) <357 | |||
'Dec 14 A 25 2300 (450) 1730 s459) | |||
Dec-14 A 21 570 (420) <357 Dec 04 E 41 < 400 <357 l | |||
l | |||
* 1.960 (Due to C unting Statistics.) | |||
-90' . | |||
. . _ . _ . _ _ _ _ _ . _ _._m_ _ _ . . .._ _ | |||
Table !!.G.3 Gross Beta Crosscheck Analyses an Split Water Samples Determined by colorado State university and Public Service Company of Colorado. 1991 Collection Sanple Gross Beta Concentrations pCl/L Date Location CSU PSC Jan 12 A 25 14 (5.9)* 24.00 (8.00) | |||
Jan 12. A 21 9.2 (5.7) 14.00 (7.00) | |||
Jan 2 E 41 11 (5.7) 15.00 (8.00) | |||
Feb 09 A 25 19 (6.2) 11.70 (6.96) | |||
Feb 09 A 21 16 (6.0) 8.16 (6.70) | |||
Feb 20 E 41 15 (5.9)- 12.00 (6.89) | |||
Mar 09. A 25 18 (6.1) 8.45 (6.61) | |||
Mar 09 A 21 19 (6.2) 12.40 (6.92) | |||
Mar 13 E 41 18 (6.0) 7.49 (6.58) | |||
-Apr-13 A 25 22 (6.4) 20.30 (7.15) | |||
Apr 13 A 21 13 (5.9) 12.50 (6.79). | |||
! Apr 03 E 41 13 (5.9) 12.10 (6.63) e May 11 A 25 20 (6.2) 16.80 (6.82) | |||
May 11 A 21 12 (5.9) 13.30 (6.75) | |||
May 08 E 41 11 (5.8) 15.30 (6.79) | |||
Jun 07 A 25 11 (5.8) < 5.46 Jun 07 A 21 9.7 (5.7) 9.09 (7.06) | |||
Jun 05 .E 41 5.3 (5.5). 5.13 (6.89)- | |||
Jul 12 A 25 19 (6.1) 16.70 Jul 12 A 21 14 (5.9) 7.94 Jul 03 E 41- 2.8 (5.4)- 11.20 Aug 09 A 25 -14 (5.9) -9.36 Aug 09 A 21 12-(5.9) 12.90 Aug 07 E 41 7.9 (5.6) 10.60 Sep 14 A 25 10 (5.8) 19.30 (7.12) | |||
Sep 14 A 21 13 (6.0) 15.50 (7.03) | |||
Sep 04 E 41 9.9 (5.8) 14.50 (6.87) oct 12 A 25 10 (5.8) 9.19 (7.30) oct 12 A 21 9.6 (5.8) <5.82 oct 62 E 41. 10 (5.8) 11.00 (7.52) l Nov 09 A 25 17 (6.1) <5.40 l Nov 09 A 21 9.5 (5.8) 8.91 (7.04) ) | |||
Nov 06 E 41 12 (5.8) 13.70 (7.26) | |||
Dee:14 A 25 9.1.(5,7) 9.85 (6.64) | |||
Dec 14. A 21 9.8 (5.8) 11.90 (6.81) | |||
'Dec 04 E 41 11 (5.8) 11.60 (6.71) | |||
* 1.960 (Due to Counting Statistics.) | |||
i b 91 _. -- . | |||
c | |||
'lable II.C.4 Int rainteratory Cross-Check Result s. (pCf /1.) . | |||
(Rep 1Icate .%alysis of Sa tw* Sa sple) - | |||
lit inkin g Water i'ad to- _Ist Quarter 2nd Quarter 3rd Quarter 4th Quarter nuctIde A B' A B A B A D Cs-134 <2.I <2.2 3.4,(2.7) <2.7 <2.9 <2.1 <l.9 <2.2 Cs-137 .<2.5 5.6 (3.1)* <2.7 <3.3 <3.4 3.7 (2.9) 3.5 (2.9) <2.7 Zr-95 <5.3 <4.7 <5.0 <7.0 <6.3 <4.4 <5 2 . <5.3 Hb-95 <l.9 <2.1 <2.1 <2.4 <2.7 <1.8 <l.9 <2.1 ' | |||
Co-58 <l.9 <2.3 <2.2- <2.8 <2.9 <2.1 <l.8 -:2.2 | |||
!!n-54 <2.1 <2.3 <E.2 <2.8 <2.8 <2.1 2.7 (2.4) 2.5 (2.7) | |||
Zn-65 <5.8 <6.5. <6.4 <7.2 <7.9 <5.5 <5.5 <5.9 - | |||
Te-59 <5.7 <5.0 <5.2 <7.3 <6.7 <4.7 <4.7 <5.3 l g Co-60 <2.2 <2.1 <2.3- <2.9 <2.9 <2.0 <2.2 | |||
<3.3 | |||
<2.4 | |||
<3.7 Ba-140 <6.4- <3.5 <6.3 <4.4 <4.6.. <3.1 La-140 <7.4 <4.1 <7.2 <5.1 <5.3 <3.6 3.8 <4.2 i Gross Beta 5.6 (2.4) 6.0 (2.4) 4.0 (2.3) 5.6 (2.5) 3.4 (2.3) 3.1 (2.3) 13 G.8) 11 (2.7) 11 - 3 <400 <400' <400 <400 <390 <390 <400 < @) | |||
i tiLik i nadio- 1st Quarter 2nd quarter 3rd Quarter 4th Quarter nue1ide _A _ B A B A B A _b_ | |||
.I Cs-134 <2.3 <2.4 <2.5 <2.3- <2.3 <2.3 <2.0 <2.2 Cs-137 5.9 (4.0) <2.9 <3.0 <3.3 3.5 (4.1) 5.2 (3.3) 2.9 (3.0) <3.2 Ba-140 <4.3 <3.8 <4.1 <4.2 <3.3 <3.7 <3.3 <3.1 ; | |||
La-140 <5.0 <4.4 <4.8 <4.9 <3.8 <4.3 <3.8 <3.6 11- 3 <400 <400 <400 <400 <390 <390 <400 <400 g.gr..es .c we wmeaM+ m.-m ew | |||
* 1.960 (1?oe 1o Cotintin g S tat istics.) - l | |||
. m 'y ,~ ~ , , , . . , , , , w-~ w ,, - . , - - - _~+e-n.,-.~-- , .,-...._-c - | |||
--~c__ . - _ _ . _ _ _ | |||
. l i | |||
1 1 . 11 . Summary and conclusions ' | |||
Table 11.H.1 summarizes the radiation and environmental i radioactivity measurements conducted during 1991 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 nay 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 I1.11.1 are only the means of the values [ | |||
greater than MDC , . the statistically minimum detectable I concentration. The range also-is given only for-detectable measurements. The mean and range values, therefore, are not the true means or ranges if any of the values in the sample population were less than MDC. The format of Table II.H.1 is a requirement of the NRC. | |||
Inspection of Table II.H.1 reveals that (except for I-131 i | |||
, at site ' | |||
-22) there were no individual measurements that exceeded the Reporting Level (RL) (see Table III.A.3). The i | |||
Chernobyl fallout was still observable in several sample ; | |||
types. | |||
For the category of gross beta concentrations in drinking | |||
. water, the mean for the Gilcrest well was again significantly greater than for the reference supply located in Fort Collins. | |||
The-following conclusions seem valid, | |||
: a. None of the ' individual fission product or activation product. radionuclides measured were 93 | |||
1 | |||
) | |||
signifienntly higher in the Gilcrest drinking water. | |||
: b. Tritium concentrations measured at Gilcrest were. | |||
however, statistically greater than those in Fort Collins. This is due to FSV tritium release. 1 However, the resultant dose commitment is insignificant, | |||
: c. The city of Gilcrest does not filter and treat its l water to the same degree as Fort Collins. This has been verified and evidenced by the f act that the ; | |||
gamma-ray spectra of the cuspended 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 lOJs filtration C' the water. | |||
For the category of tritium in surface water, as has been the case since reactor operation, elevated concentrations were noted at station A-25, the outlet of the (Goosequill) farm l- pond. A-25 is directly in~the principal effluent route and i | |||
elevated' concentrations should be expected, to correlate with release schedules. Downstream surf ace water concentrations of tritium have occasionally been elevated, but there is l | |||
l | |||
significant dilution before any human use of this water, f | |||
During 1991 elevated tritium concentrations were not obrarved downstream and the mean values for the first and second half s | |||
of 1991 were not significantly different. | |||
l i | |||
I *.31 was observed again in milk samples, but again only l i | |||
f rom Dairy A-22. Because the reactor did not release any | |||
{ | |||
significant fission products during 1991, the source of the I-131 concentrations in milk could not be reactor effluent. It . | |||
was documented in the 1985 annual report that the source of l | |||
the I-131 concentrations during that year was not due to the 1 | |||
reactor but due to nuclear medicine use and release upstream of the reactor. This was an important observation as I-131 id certainly a critical radionuclide in human dose commitment possibilities, a fact of which 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 source of the I-131 observed again in milk samples during 1991. Irrigation water samples confirmed this conclusion. | |||
(' | |||
Cs-137 was also observed in many environmental' samples | |||
[ due to the Chernobyl fallout. | |||
Tritium concentrations from well water site F-16 do appear to be increasing with time. This could be due to ll l | |||
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 in not used for drinking water purposes and elevated tritium concentrations have not been observed in any food chain sample. | |||
Table 11.11.2 presents an additional summary of mean values for selected sample types. The sample types and radionuclides were chosen on the basis of their importance in documenting possible radiation dose to humans. Air and surf ace water would be the predominant environmental transport _ | |||
routes ano drinking water and milk would be the predominant sources of radiation dose if significant radioactivity release from FSV occurred. Table II.H.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 s presented in the body of this report contain only positive calculated values above the minimum detectable concontration (MDC) levels. Any calculated values loss than zero or less than the minimum detectable concentration (MDC) are listed as less than the actual MDC for that sample analysis, llowever, the actual result in all cases was used in the calculation f or the arithmetic mean values for the period. Therefore, all 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 I 1 . 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 96 | |||
r, l | |||
contain less than zero radioactivity, due to the random nature of radioactive decay, it is statistically possible to obtain sample count rates-less than background and hence a negative result. It is equally true that many sample types do in fact have zero concentrations of certain radionuclides. Therefore, f | |||
to obtain the correct mean value from the distribution of analytical results, all positive results must be averaged with all negative results. If the negative results were omitted, the resulting arithmetic mean would be falsely biased high. | |||
From the values presented in Tables II.H.1 and II.H.2 and the tabular data of the report, the following observations and conclusions may be drawn: * | |||
: 1. Tritium was again the only radionuclide that was detected in significant concentrations _in - any of . | |||
the. effluent pathways that could be attributeo to the reactor. Since the tritium is released as tritiated water, the dilution by the surrounding hydrosphere is_ great. Although in 1991, tritium could be detected in the effluent pathway, the mean values of downstream surface water were not l statistically greater than upstream concentrations. | |||
l 4 Aotin-every previous report, it was again apparent that for most sample types the variability observed around the mean values was great. This variability l is due to counting statistics and methodological variation, but principally due to true t 1 'ironmental variation (often termed sampling L 97 E . - - . _ . . _ _ . , - _ . . _ . . - | |||
crror). It must be recognized and accounted for in i | |||
analysis of z.ny set of environmental data before meaningful conclusions can be drawn. | |||
: 3. Thr "hernobyl accident f allout 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 sample types because the fallout deposition was considerably greater during the pre-operational period. | |||
: 4. The prompt and sensitive 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 decommissioning. | |||
It can be concluded from the deta collected by the 98 | |||
7[! | |||
environnental monitoring program that the radiation dose commitments calculated for the closest inhabitants or other parts of the nearby ecosystems due to current reactor effluents are negligible. | |||
Natural background radiation and the dose commitment from atmospheric fallout are the only known significant sources of radiation dose to the , | |||
residents of the area. | |||
During the current 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. - | |||
l t | |||
t-l 1' | |||
l 99 | |||
, . - _ _ _.___ _. __ _ . _ . . . _ _ - ._. _.-.. _ u: | |||
Table II.H.1 Environmental Radiological Monitoring Program Annual sistmary Fort St. Vrain Nuclear Generating Facility, Platteville, Colorado Locations with Highest Reference Nuniper of Medium or Pathway Type and Facility Adjacent location Annual Mean Location Nonroutine Sarrples (Unit of Total Nunber Location Mean(f)g Reported of Analyses Mean(f)g Mean(f)g Name Mean (f) measurement) Range Measurements Performed Range Range Distance & Range Direction 0.46 (4/4) G. ,(18/18) 0 Direct Radiation TLD (158) 0.3 72/72) 0.39 (68/68) A2 uCR42 (0.20-0.53) (0.25-0.58) & WCR255 (0.40-0.57) (0.31-0.53) | |||
(r*/ day) 6.8 km 25 (207/207) F-7 Farm 25 (52/52) 24 (156/156) O Air, Gross # (363) (12-69) | |||
(0.60-69) CR21 & CR34 (4.9-69) | |||
Particgtetes 1.5 km 145* | |||
(fCi/m ) | |||
Gansna spectrometry Cs-134 (28) < 2.4 R-3 Csu 3.2 (1/4) 2.6 (3/12) 0 Vet Hosp. (2.3-3.2) 45 km 330-Cs-137 (28) 1.6 (1/16) R-4 US 66 1.7 (1/4) 1.5 (3/12) 0 | |||
& US 287 (1.2-1.7) 21 km F-7 Farra 46 (1/52) 30 (7/156) 0 31 (8/207) | |||
Air,Cgarcoat I-131 (363) (17-39) | |||
(19-46) CR21 & CR34 (pCi/m ) 1.5 km 145* | |||
F-7 Farm 636 (7/52) 583 (24/156) 0 Air, Atmospheric H-3 (364) 621 (37/208) | |||
(430-960) CRES 8, CR34 (540-780) (350-870) | |||
Watergapor 1.5 km 145-(pCi/m ) | |||
beenandrarsebasedupondetectablemeasurementsonly. | |||
Fraction (f) of detectable measurements at specified locations is indicated in parentheses. | |||
t- | |||
Table II.H.1 Envirorvnental Radiologicat 'tonitoring Program Annual Sunenary Fort St. Vrain Nuclear Generating Facility, Plattevitte, Colorado Meditse or Pathway - Type and Facility Adjacent Locations with Highest Reference Ntsnber of Sarples (Unit of Total Nunber Location Location Annual Mean L cation Nonroutine measurement) of Analyses Mean(f)g Mean(f)g Name Mean (f)b Mean(f)g Reported Performed Range Range Distance & Range Range Measurements Direction Drinking Water Gross # (52) 5.8 (26/26) R-6 Gilcrest 5.8 (26/26) 0.95 (26/26) 0 (pci/t.) (3.1-13) City Water (3.1-13) (0.44-1.6) ' | |||
9.3 km 60* | |||
H-3 (52) 618 (6/26) R-6 Gilcrest. 618 (6/26) 570 (2/26) 0 (490-760) City Water (490-760) (410-730) 9.3 km 60* | |||
Gama spectrometry | |||
_ I-131 (52) < 0.46 R-3 ft. Col 1 ins 0.52 (1/26) 0.52 (1/26) 0 o | |||
~ City Water 45 km 330* | |||
Cs-134 (52) 3.4 (3/26) R-6 Gilerest 3.4 (3/26) 2.1 (1/26) 0 (2.8-4.0) City Water (2.8-4.0) 9.3 km 60* | |||
Cs-137 (52) 3.9 (9/26) R-6 Giterest 3.9 (9/26) 3.3 (7/26) 0 (1.7-6.0) City water (1.7-6.0) (2.2-4.2) 9.3 km 60* | |||
Zr-95 (52) < 7.2 R-3 Ft. Collins 4.5 (1/26) 4.5 (1/26) O City Water 45 km 330' Nb-95 (52) < 2.8 --- --- | |||
< 2.0 0 beenandrangebasedupondetectablemeasurementsonly. | |||
Fraction (f) of detectal;,le measurements at specified locations is indicated in parentheses. | |||
Table II.H.1 Environmental Radiological Monitoring Program Amual Strmary 4 | |||
Fort St. Vrain Hoclear Generating Facility, Platteville, Colorado Mediun or Pathway Type and Facility Adjacent Locations with Highest Reference Munber of Sanples (Unit of Tota! Pamber Locati Locaticg Annual Mean Locatiog Nonroutine measurement) of Analyses Mean(g)f Mean (f) Name Mean (f) Mean (f) Reported Perfornied Range , Range Distance & Range Range Measurementt Direction | |||
.i i Drinking water Co-58 (52) 1.7(1/26) R-6 Gilcrest 1.7 (1/2o) < 2.8 0 City Water | |||
, 9.3 km 60* | |||
Mn-54 (52) 2.7 (3/26) R-3 Ft. Coliins 2.9 (3/2oi 2.9 (3/26) 0 (1.9-3.8) City uater (2.7-3.3) (2.7-3.3) 45 km 330* | |||
, Zn-65 (52) < 9.0 --- --- --- | |||
0 h Fe-59 (52) 7.3 (2/26) R-6 Gilcrest 7.6 (2/26) < 6.2 0 (5.3-9.2) City Water (5.3-9.2) 9.3 km 60* | |||
Co-60 (52) 3.8 (1/26) R-6 Gilcrest 3.8 (1/26) 2.87 (2/26) O City water (2.31-3.23) T 9.3 km 60* | |||
Ba-140 (52) < 7.5 R-3 Ft. Collins 3.4 (1/26) 3.4 (1/26) O City Water 45 km 330* ; | |||
La-140 (52) < 7.5 R-3 Ft. Collins 3.9 (1/26) 3.9 (1/26) 0 (4.6-7.3' City water 45 km 330* | |||
beanandrangebasedupondetectablemeasurementsonly. | |||
Traction (f) of detectable measurements at specified locations is indicated in parentheses. | |||
I | |||
: w. _ . _ _ _ - _ - - | |||
Table II.H.1 Envirorinental Radiological Monitoring Program Annual suonary ^ | |||
Fort St..Vrain Nuclear Generating Facility, Plattevitte, Colorado Medius or Pathway Type and Facility Adjacent. - Locations with Highest Reference Nuiber of sanples (Unit of Total Nunber Location Location Annual Mean Location Nonroutine measurement) of Ana1yses Mean(f)g Kean(f)g Name Mean (f) Mean(f)g Reported Performed Range Range Distance & Range Range Measurements Direction surface Water H-3 (60) 1747 (12/36) A-25 Goosequill 2786 (7/12) 552 (5/24) 0 (pCi/L) 070-8300) 2.2 km 2r (1000-8300) (380-860) | |||
Gama spectrometry Cs-134 (60) 2.2 (1/36) F-20 St. Vrain 2.2 (1/12) < 3.5 0 1.5 km 345* | |||
Cs-137 (60) 3.8 (13/36) R-10 s. Platte 4.6 (2/12) 4.0 (8/24) 0 (2.6-6.6) at CO 6G (3.1-6.0) (2.8-5.3) 5 w | |||
10 km 290* | |||
Zr-95 (60) 5.4 (2/36) F-20 st. Vrain 5.5 (1/12) < 8.6 0 ' | |||
(5.3-5.5) 1.5 km 345* | |||
Nb-95 (60) < 3.1 A-21 St. Vrain 3.6 (1/12) 3.6 (1/24) O Bridge 2.4 km 220' Co-58 (60) 4.3 (1/36) R-10 s. Plaite 4.3 (1/12) < 3.4 e at CO 60 10 km 290* | |||
Mn-54 (60) 3.0 (6/36) A-21 St. Vrain 3.3 (2/12) 2.3(2/24) 0 (1.6-4.1) Bridge 2.4 km (3.0-3.6) (1.5-3.0) 220* | |||
Zn-65 (60) < 9.6 --- --- | |||
< 10 0 beanandrangebasedtpondetectablemeasurementsonly. | |||
* Fraction (f) of detectable measurements at specified locations is indicated in parentheses. | |||
____.-____.m___ _ . _ _ _ . _ __ _ _ _ _ _ _ _ _ _ m | |||
r | |||
~ | |||
-Table II.H.1 ' Environmental' Radiological Monitoring Program Annual Summary | |||
-Fort St. Vrain Nuclear Generating Facility,.'Platteville, Colorado , | |||
Medium or Pathway Type and: Facility- Adjacent; Locations with HigHst Reference- Nund)er of. | |||
' Sanples (Unit of Total Ntatier Locationg Locat f org _ Annual Mean- Locatior Nonroutine-measuremerit) of Analyses Mean (f) .Mean (f) | |||
Name Me f,@ Mean(f)g Reported Performed: -Range Distance & Measurements Range: ' | |||
nge- Range Direction-Surface Water Ganens Spectrometry | |||
"(pci/L) | |||
Fe-59-(60) < 7.5, A-21 St. Vrain 8.1 (3/24) 8.1 (3/24) 0 Bridge 2.4 km (7.3-8.6) (7.3-8.6) 220-Co-60 (66; 4.6'(4/36) F-20 St. Vrain 5.4'(2/12) 3.0 (2/24)' 0 (2.4-5.8) 1.5 km 345* (4.0-6.8) (2.7-3.2) | |||
_- Ba *40 (6u) 6.2-(4/36) 'F-20 St. Vrain 7.8 (1/12) < 6.4 0 g (5.3-7.8) 1.5 km 345* | |||
La-140 (60) 7.1 (4/36) F-20 St. Vrain 9.0 (1/12) < 7.5 0 | |||
-(6.1-9.0) 1.5 km 345' Ground Water H-3 (8) 1950 (2/4) F-16 3-Bar 1950 (?!6) < 400 0 (pci/L) .(1600-2300) . Ranch (1600-2500); | |||
'1.2 km 0* | |||
Gamma Spectrometry Cs-134 (8) < 3.4 --- --- | |||
< 2.2 0 Cs-137 (8)' 5.7 (2/4) F-16 3-Bar 5.7-(2/4) 5.3 (2/4) 0 (3.7-7.7) Ranch (3.7-7.7) (4.1-6.5) | |||
'1.2 km 0* | |||
Zr-95 (8) < 6.9 --- --- | |||
< 4.9 0 Mb-95 (8) < 3.1 --- --- | |||
< 2.1 .0 | |||
., y beanandrangebasedtpondetectablemeasurementsonly. | |||
Fraction (f) of detectable' measurements at specified locations is indicated in parentheses. | |||
j; Table II.H.1 Environmental Radiological Monitoring vrogram Annual Stannary Fort St. Vrain Nuclear Generating Facility, Platteville, Colorado Medium or Pathway Type arvj Facility M t -ceo Locations with Highest Reference' 4taber of Samples (Urtit of Total Ntaber Locat ; p- . | |||
24 g Annual Mean . Locati Nonroutine measurement) of Analyses Mean ~2)g' He - .f) Name Mean (f)" Mean(g)- | |||
f Reported , | |||
Performed Range m .ge Distance & Range Range Measurements Direction Ground Water Game Spectrometry (pci/L) | |||
Co-58 (8) < 3.1 --- --- | |||
< 2.1 0 Mn-54 (8) 4.0 (1/4) F-16 3-Bar- 4.0 (1/4) < 2.2 0 Ranch 1.2 km O' Zn-65 (8) < 10 --- --- | |||
< 7.5 0 h Fe-59 (8) < 7.8 --- --- | |||
< 5.2 0 Co-60 (8) 2.9 (2/4) F *6 3-Bar 2.9 (2/4) < 2.2 0 (2.7-3.1) Ranch (2.7-3.1) 1.2 km 0* | |||
Ba-140 (8) < 6.5 --- --- | |||
< 4.4 0 La-140 (M < 7.5 --- --- | |||
< 5.0 0 keanandrangebasedupondetectablemeasurementsonly. | |||
Fraction (f) of detectable measurements at specified locations is indicated in parentheses. | |||
6 | |||
r < | |||
p y | |||
~ ' | |||
' Table;II.H.1' Environmental Radictogical' Monitoring Program' Annual Staunary Fort St. Vrain Nuclear Generating Facility, Platteville, Colorado ^ | |||
. Meditas or Pathways -Type and' . Facility ' Adjacent- Locations with' Highest " Reference? Number of - | |||
'.Se@tes (Unit of ' riotal - Nuuber . | |||
Locatlon Location . Annual'Mean . Location measurement). 'of Analyses - Mean(f)g' Mean(f)g . | |||
: tlame Mean (f) iMean(f)g' - Nonroutine' Reported-- | |||
' Performed' Range Range. | |||
Distance & Range. LRange | |||
- Measurements Direction Sediment ~ . Gamune spectrometry . | |||
.(pci/kg. dry) | |||
Cs-134"(2) . < 11 | |||
--- --- .--- -'O-g- Cs-137.'(2) 69 (2/2) R-10 S. Platte 69 (2/2) --- | |||
O (54-83) at'to 60 (54-83) - | |||
10 km 290* | |||
. Milk H-3 (108) 587 (9/91) A-18 Boos 830 (1/1/) 563 (3/16) O' I5 (pCi/L) (410-830) Dairy (440-790)- | |||
4.7 km-Gansna spectrometry 1-131 (108)' 1.6.(3/91) A-22 Percy 2.2 (2/17) 0.45 (2/17) 'O (0.47-2.3) odenbaugh Dairy (2.1-2.3). (0.39-0.51). | |||
5 km 90* | |||
Cs-134~(108) '2.5 (7/91) A-26 Dochef f 3.1 (1/17) 3.1 (1/17) 0 (1.2-3.1) Dairy 6.8 km Cs-137 (108)- 4 1 (21/91) A-22 Percy 4.5 (2/17). 3.7 (8/17) 0 (1.6-6.4) Odenbaugh Dairy (3.1'5.9) | |||
(2.6-5.3) 5 km 90* ' | |||
han'andrangebasedupondetectablemeasurementsonly. | |||
Fraction (f) of detectable measurements at.specified locations is' indicated ir. parentheses. | |||
}- i y 3 ,, "v i g-- y .-- w ,.iy.- | |||
.Tabte II.H.1- 'EnvironmentaliRadiotogical Monitoring' Program Annual Sunnary' - | |||
Fort $ti Vrain Nuclear Generating Facility,'Platteville, Colorado _ | |||
~ | |||
' Medits or Pathway Type and . Fac!1ity. . Adjacent - Locations with Highest Reference' Number o'f. | |||
Sanptes -(Unit of ' - Total Ntaber- Locati Annual-Mean L catlon Nonroutine measurement)- of. Analyses- Mean(g).'.. | |||
f -Locatlog) | |||
Mean (f - Name Mean (f)b Mean (f)g' ~ Reported-Performed -Rangen Range. Distance & Range Range: Measurements Direction Milk Gagna Spectrometry (pCi/L) . . | |||
Ba-140'(108) 5.8 (4/91) A-23 Leroy- 9.4 (1/17) 4.6 (1/17) 0 (2.2-9.4) odenbaugh Dalry 4.1 km 83* | |||
La-140 (108) 6.7 (4/91) A-23 Leroy 11 (1/17) 5.3 (1/17) 0 (2.5-11) Odenbaugh Dairy 4.1 km 83* | |||
g" - | |||
Food Products Ganna Spectrometry (pCi/kg, wet) . . | |||
1-131.(8) 17 (1/8) R-6 Hernandez. 17 (1/6) --- | |||
0 Gilcrest | |||
- 9.6 km 60* | |||
Cs-134 (9) 17.(1/8) R-6 Hernandez 17 (1/6) --- | |||
0 Gilcrest 9.6 km 60* | |||
Cs-137 (9) 31 (1/8) A-27 WCR25 31 (1/7' --- | |||
0 | |||
& WCR38 . | |||
4.3 km beanandrangebasedupondetectablemeasurementsonly. | |||
Fraction (f) of detectable measurements at specified locations is indicrited in parentheses. | |||
.- 1 | |||
. . - . _ . - _ - - - - - - - - - _ _ . _ _ _ - - - . - _ _ _ _ w , . , , - | |||
Table II.H.1 Environmental Radiological Monitoring Program Annual Strvnary Fort St. Vrain Nuclear Generating Facility, Platteville, Colorado Medium or Pathway Type and Facility Adjacent Locations with Highest Reference Nunber of samples (Unit of Total Nunber Location Location Annual Mean L cati Wonroutine measurement) of Analyses Mean (f)g Mean(f)g Nane Mean (f)b Mean (f g) Reported Performed Range Rante Distance & Range Range Measurements Direction Fish Ganma Spectrometry (pci/kg, wet) | |||
Cs-134 (6) < 6.0 --- --- | |||
< 6.3 0 cs-137 (6) 7.? (1/4) R-10 S. Platte 16 (1/2) 16 (1/2) O at CO 60 10 km 290* | |||
Co-58 (6) < 5.8 --- --- | |||
< 6.3 0 5 | |||
on Mn-54 (6) < 5.8 --- --- | |||
< 6.0 0 Zn-65 (6) < 17 --- --- | |||
< 21 0 | |||
[ | |||
Fe-59 (6) < 15 --- --- | |||
< 10 0 Co-60 (6) < 6.2 --- --- | |||
< 6.9 0 bean and rcnge based upon detectable sensurements only. | |||
Fraction (f) of detectable measurements at specified locations is indicated in parentheses. | |||
l | |||
9 Table 11.11.2 Summary Table of Arithmetic. Means and S' t andard Deviations for Selected Sample Types. | |||
1988' 1989 1990 1991-R. R R a R o Atmospheric Water Vapor (pci/L) 11 - 3 Facility 470 43 <256 285 <9.4 395 Reference 172 <420 <299 288 <80 395 | |||
$ Air (fCi/m 3) | |||
Gross Beta Facility 26 26 23 12 29 31 Reference 24 24 23 12 25 23 I-131 Facility 1.9 2.2 1.5 3 1.6 13 Reference <4.5 2.2 1.4. 9 0.52 14 Cs-137 Facility 0.73 0.32 0.55 0.92 0.12 0.69 Reference 1.0 0.46 0.22 0.66 0.911 1.3 a | |||
e | |||
o Table II.31.2 Summary Table of Arithmetic Means'and Standard Deviations for Selected sample Types. | |||
1988 1989 1990 1991 R R R o R o Drinking Water (pC1/L) 11 - 3 Gilcrest 370 <390 <238 317 32 4G5 Ft. Col 1 ins 120 <390 <215 288 <48 345 Gross Beta Gilcrest 6.8 5.8 4.5 1.8 5.8 2.4 | |||
.{ Ft. Collins 1.1 0.98 0.86 0.39 0.95 0.35 I-131 Gilcrest 0.099 0.068 0.017 0.19 <0.0028 0.16 Ft. Collins 0.083 0.14 0.046 0.24 <0.022 0.20 Cs-137 Gilcrest 1.7 2.2 1.3 1.4 2.2 1.6 Ft. Collins 1.4 1.8 2.4 1.8 1.7 1.2 0 | |||
- - - . ~ __ | |||
~ | |||
s p' | |||
: Table II.II.2 : : Summary: Table'of Arithmetic'Means and Standard! Deviations foriselected Sample Types. | |||
1988: .1989 1990 1991- | |||
"R R 'R' o'' R. .o. | |||
Surface ; Water ' (pci/L) . | |||
11 - 3 Effluent. 31000~ 29000 303- 623' 1499 2496 Downstream 430 - <390 . <371 397 6.2 ,427-tJpstream- 430 - <390 <415 352 20- 419 Cs-137 Effluent 1.9 1.3- 1.4 1.9 1.7 2.0 t* Downstream 2.5 1.8' 2.1- 1.9: 2.3 1.7 Upstream 11.4 L2.0- 2.2 1.9 2.0 1.9 Milk (pci/L) 11 - 3 Adjacent 70' <390' <280 330 <133 362 Reference < | |||
'220 <390 <290 340 '<110 398, I-131 Adjacent 'O.046 0.57 0.53. 2.0 0.070 0.39 Reference <0.17- <0.50 0.0060 0.33 <0.0028 0.24 Cs-137 Adjacent 2. 7 . - l '. 5 1.5- '2.0 1.9. 1.8 Reference '3.3 1.5 16 2.3 2.4 1.9-e | |||
III.: Radiological Environmental Monitoring Program A. Sample. Collection and Analysis Schedule j | |||
l | |||
-Table- III.A.1 outlines the sampling design, the i 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 f erent in certain aspects from the previous schedule, has as its l | |||
' tent the same objective. | |||
. That objective is to document the L radiation and radioactivity levels in the critical pathways of l-l possible dose to humans. Such data is necessary to prove that 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 1991, there were no changes in the sampling program. | |||
Table III.'B.1 gives the description of each sampling location by number, sector and distance from the reactor. | |||
Each of"these sampling locations. (except certain reference | |||
. locations) can-be identified on scale maps (Figures III.B.1 and--III.B.2). Topographical maps chowing greater detail,.as well as photographs of princ.f pal sampling sites are on file in | |||
!; the CSU laboratory. | |||
During September 1991 the land-use census was again i conducted to determine the locations of the nearest residence, l | |||
l. | |||
l L 112 n | |||
the nearest milk animal, and the nearest garden producing broad leaf vegetation in each of the 16 meteorological sectors around 'the reactor.. Thesa locations are shown in Table . | |||
III.C.1. Figura III.C.1 shows these locations in each sector. | |||
At the- time of the 1991 census it was verified that the closest permanent residence in Sector 16 was the critical receptor with reaards to nean annual dose commitment and ir at the Russell farm F-16. | |||
A few residents in the sampling sectors up to a distance of 8 km from the plant have cows or goats that could be used l | |||
for personal milk consumption. However, from direct discussion with these persons, this is not a common practice l | |||
and all cow milk produced is transported to commercial processors. The milk produced locally is diluted by a large milk shed, processed and distributed over a large area for | |||
. consumption. For this reason the elevated 1-131 in milk from A-22 would never be detected in the composited milk supply. | |||
l Table III. A.2 lists the LLD concentration values for each j sample type and radionuclide measured in this repert. These LLD ~ values are the actual values- pertinent to the sample sizes, counting yields, and counting times used in the project. - . Typical decay periods were used in the calculations. | |||
It should be noted that the LLD values are in all cases equal | |||
<- to or less than those required by the technical l' specifications. | |||
[ Table III.A.3 lists the UCNRC reporting level for each l sample type and radionuclide. | |||
113 | |||
e e | |||
= | |||
u E a | |||
= h= 0 C m C A we= w *= w | |||
= | |||
*. a C U -mc = | |||
e | |||
- w = | |||
Te >C: e e- e km Cgee ==e= A h. hw = | |||
h e Osw bscw = =h = w u wh==uC cuusu b e= e e Cm eOwweQ . -e u= c C4- 26 i | |||
g =e =we=h 2 ac604 w ed eC | |||
. C =bem e 9=s=c w C = a Wh ah=wxed eVw w e 40 m e= Q== emu We=he =E -o 9 he za6 e ==4g F 4 Ew . | |||
=c ceCObe= e ww- e o= g 9 ( C =wou= we . e w we c c L= Q awm om 16 eo | |||
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t 7 , gj _ .a 3 | |||
y , .7 i-Tatsle'Ill.A.2. Delectibn' CapabiliLies for Envtronmental: Sample. Analysis | |||
-Lower Limit of Detection!(LtD) | |||
Fish . Milk' . Ercod' Products- SedimentL Analysis; TWater- ! Airliorne Particulate. '(pC l/kg. .. dry) | |||
: (pCl/L)._ forLGas-(IC1/m3) ~(pCi/kg, wet). (pCi/L). : (pCi/kg,' wet) | |||
Gross lieta -3.86. l3.25 3 r494' 494 11 .i 1-131 0.890 : 66;. 4 0.890 .56.8 Cs-134 '5.58 -8.06 19,5 .5.53 44.4' .90.6 Cs-137 5.34 7.86. 18.5 5.3d 44.6 100- | |||
/r-95 7.96 M tib-95 4.24: | |||
.C0-58 3.66 12.8 Hn-54 .3.64 12.7 Zn-65 7.92 e | |||
fe-59 B.30 31.4 Co-60 3.74 14.5 lla-140 8.87 8.07 , | |||
La-140 10.2 :10.2 i | |||
* As suggested in 14UREG-0472. All values =are 'at or below values listed in Table 8.2-2. of . Technical Specifications. | |||
.i s | |||
M- ,. - | |||
, _. __ __.__________._m. _ _ _ _ _ . _ _ _ _ _ . _ . | |||
_J'w<-'. | |||
Table III .A. 3. Reporting Levels (RL)- for flonroutine Operating Reports Reporting Level (RL) | |||
' Analysis Water Fish Milk Broad Leaf Vegetation : | |||
(pC1/L) AirborneParg)iculateorGas. | |||
~(ICl/m (pC1/kg, wet) (pCl/L) (pCf /.kg. wet) | |||
- fl-3 2 x 10 (*} | |||
4 Mn-54 1 x 10 3 3 x 10 fe-59 4 x 10 1 x 10 1 x 10 3 4 | |||
Co-58 3 x 10 | |||
:h Co-60 3 x 10 1 x 10 Zn-65 3 x 10 2 x 10 4 x 10 2 fib-95, Zr-95 1 x 10 2-2 I-131 2 .9 x 10 3 J | |||
Cs-134 30 1 x 10 4 1 x 10 60 1 x 10 3 Cs-137 50 2 x 10 4 2 x 10 3 70 2 x 10 3 2 | |||
Ba-140, 2 x 10 3 x 10 La-140 | |||
: a. For drinking water samples. -This is 40CfR Part 141 value. | |||
4 | |||
4 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, Pathway km Direct Radiation F-1 Pole by gate to Goosequill road on dirt extension of 1 1.3 CR 21. | |||
F-2 21st pole N of ditch on dirt extension of CR 21 just 2 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. | |||
g; 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 11th 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 1st pole W of pump house or N side of road 0.4 km E 8 1.3 of CR 19h, F-9 Pole E of first shed at intersection of CR 19 9 1.5 and CR 34. | |||
F-10 Po3.e on NW corner of intersection of dirt extension 10 1.5 of-CR 19 and 34. , | |||
.s. | |||
1 | |||
.i ' | |||
1 Table'.III.B.1 Radiological 2nvironmentcl Monitoring' Program'(continued)' | |||
sampling, Site Descriptions 1 (F:-Facility 1 Area.f0-l'.6 km. 'A:'. Adjacent Area'1.6-8 km. 'l: Reference-Area) | |||
Exposure Site No. ' Location' Description '(see map) Sector.' ' Distance, Pathway- km Direct Radiation F-11 7t.h pole N of intersection of dirt extension 'of CR '19 11' . 1.2 xwith 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 Aristocrat Brangus office.. , | |||
F-13 Tak'e 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.36h & 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 Centor, on N end of' cross beam over' entrance. 13 0.2 F-18 . Pole. closest to house on SW corner, 17250 CR'19k. 16 0.8 The address of'17250 is taped to the Mountain Bell underground cable warning post. | |||
t O | |||
, -. , , . -r | |||
N ' ?YS | |||
?pty , | |||
r r 7 9 m - | |||
7 TableiIII.B.1.; Radiological'EnvironmentalLNonitoring Program.,(continued) ' | |||
1 | |||
*i | |||
: sampling site' Descriptions-4 | |||
:(F:; Facility'AreacO-1.6'km..:A:: Adjacent Area-1.6-8/)ca. R:' Reference' Area)' g Exposure -Site No. 1 Location Description (see map); ' Sector Distance,: | |||
:' Pathway, 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 25%. 2 6.8-3 ~ | |||
A-3 : Pole on NE.. corner'of.. intersection'of CR.42 and CO 60.. 3 7.5 A 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 ] | |||
3 SW' corner.of.. Intersection. | |||
. 2 A-6 Pole =on.SLsidelof CR 32 near drive to dairy 13278 CR 6' .. 7 . '1 ' | |||
32. | |||
~ | |||
, 'A-7 'Niles Miller dairy. 'O.4 km E of US 85 on 12854 CR 30. | |||
TLD'i'sTlocated.on pole at.NE corner of house. 7 7.3 : | |||
A-8, -OnL CO 66 '(CR30)' farm on S side of' road (address 9476) 8 '4.7: I Fole in frent'of house. | |||
~ | |||
l A Corner.of CO.66 (CR 30) and CR 19, . Miller produce. | |||
~ | |||
9 4.6 i | |||
-stand. -:Second pole S on'CR 19, on E side of road. | |||
A-10. Pole on SE. corner at intersection'CR 26 & CR 15. 10 7.8 A'-11 At intersection of.CO 66 and'CR 13,' 2nd pole N of 'll 7.2 | |||
~ | |||
j intersection on E side of CR13. | |||
l 4 | |||
i b | |||
s._ . . , _ _ _ _._ _ _ __ __ | |||
a g' - re Table III.B.1-l Radiological iEnvironmental. Monitoring Program-(continued).' | |||
sampling site' Descriptions A: .- Adj acent, Area'' l. 6-8 ! km. . R: Reference' Area). | |||
~ | |||
i 1(F: . Facility-Area 0-1.6"km.- . | |||
Exposure' Site. 'No. - Location Description (see map). Sector. . Distance, 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-silage' pits E side of CR 13 13 '5.8-2'.9 km N of.CR.34. | |||
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 N | |||
A-16 -Intersection of CR 44'and CR 19,..SW corner. '16 6.8 | |||
,A-17 Platte"ille. school ~(S edge of town on Main St.) 6 5.9 pole on:NWicorner just outside school intramural field. | |||
A-20 1st pole' N 'of'. white pi'.ket fence ~ and driveway 9 2.5 | |||
.into turkey farm on S end of building that is parallel with"CR 19. | |||
9 | |||
:[ . | |||
Table'III.B.2- 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)- | |||
t | |||
. Exposure. Site No. Location Description (see map) - Sector. Distance, Pathway .km Direct-Radiation R-1 Milliken School, on-CR121\. ' TLD.is located.on pole 9.3' whichl-is' located at SE. corner of Lola park, across the street from school. | |||
R-2 Johnstown. School'(Letford Elementary), turnjleft at 10.8 school crossing on. Idaho St. onto Jay Ave. and proceed to school. TLD is located on pole at SE corner of main entrance 1to school on W side of town. | |||
) R-3'- CSU dairy farm on'W' Drake, N o'f' Vet Hospital, Ft. 45.1-Collins, CO. ' Pole is E'of hay barn next to railroad tracks. | |||
R-4 Air sampler corner US 287 and CO 66, Longmont Dairy 20.5 Store. TLD is located on pole directly behind air-sampler. | |||
R-7 Behind Gilcrest School quonset auditorium, pole 9.3 on SW end of school property, just before garage. | |||
Waterborne Sediment from Shoreline R-10 Sediment from'S. Platte River-at bridge'on CO'60.- 10.1 | |||
.m ___. _ . _ _ _ _ - | |||
- _ _ . _ . _ _ . _ _ _ _ _ _ _ _ __2 _ _ _ _ _ _ _ _ __ - _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ . . . _ . _ _ _ . . _ _ _ . . _ * | |||
" ~ | |||
+ | |||
t-Table III.B'.1 Radiological-Environmental Monitoring-Program sampling Site Descriptions. | |||
(F: . Facility'AreaLO-1.6 km. . ~A: Adjacent: Area 1.6-8 km. R:: Reference Area)' | |||
Exposure Site'No. Location Description (see map)" Sector -Distance,. | |||
: Pathway. ikm' Airborne F Farm at' intersection of CR'21 and CR 34.- Air 7 .1. 5 sampler'is located'on west 7 side of shop. . Silica gel.inside buildingfon N end.of workbench. | |||
F-9 First:shed along1 drive ~at end of Rd 19 intersection 9. "1. 5 with Rd 34. Silica' gel is located in~shed. | |||
F-16 Potato cellar at 3 Bar Ranch.(Russell's). Silica 16 1.2' | |||
-. . gel.in mailbox on tree toL6 of pump.. | |||
E$ | |||
A-19 Hunting cabin between Goosequill ditch and Platte 1 1.7' River. Air sampler is on W side of cabin, silica , | |||
gel'is in box on' tree north of air sampler. | |||
R-3 Colorado State University Dairy, W. Drake Rd., Ft. 45.1' Collins, CO..W' side of shed directly N of main dairyfbuilding. : Silica gel inside; mailbox. | |||
R-4' IntersectionLoffUS 66 and.US.287, E side of dairy 20.5 store, north edge of Longmont. . Silica. gel is in mailbox' attached to. utility pole. | |||
R-11 Air sampler.is located in alley bchind PSC office, 10.5' ., | |||
next to garage. ~ Silica 1 gel is-located next to air sampler in mailbox and on top of post, 13 1/2. Parish St., Johnston, CO. | |||
p . | |||
2_.__ .--. a . . . ~ ~ . , ~ - + - | |||
4 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) i Sector Distance, Exposure Site No. Location Description (see map) km Pathway Waterborne 4 1.2 Surface F-19 S. Platte at dam located on dirt road E of pump house #3 directly E of reactor. | |||
16 1.5 F-20 St. Vrain creek on Rd. 19\ 0.3 km from discharge into St. Vrain creek. Directly N of reactor. | |||
11 2.4 A-21 St. Vrain creek at bridge on Rd. 34, E of Rd. 19. | |||
Continuous sampler located 1 2.2 A-25 Goosequill Pond outlet. | |||
hk in green box adjacent to the green shed on the N end of the pond. | |||
Platte river at bridge on CO 60 where highway 10.1 R-10 S. | |||
has just turned and headed South. | |||
1.2 Ground F-16 Well behind residence at 3 Bar Ranch (Russell's), 1 17578 WCR 19 1/2. | |||
9.5 R-5 Well at 108 S. Grace, Milliken. | |||
45.1 Drinking R-3 CSU dairy W Drake Rd., Ft. Collins, CO, N of Vet Hospital. Water sample is ta}'.en trok hydrant inside the entrance to the milking parlor. | |||
9.3 R-6 Gilcrest U.S. Post Office located on Birch St. and Rd. 40 off of Hwy 85. Water taken from utility sink inside Post Office. . | |||
A u. | |||
4 Table:III.B.1 ' Radiological Environmental'.' Monitoring Program '(continued) sampling'eite Descriptions (F: Facil3ty 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 Ingestion ' | |||
Milk A-6 Hendrickson' Dairy, 13278 Rd. 32 (Grand Ave.) 6 7.1 | |||
'l.6:km E"of US 85. | |||
A-18 Boos Dairy,.11258 W Rd. 40, W of US 85 behind 2 4.7-modular home. | |||
A-22 Percy-Odenbaugh Dairy, S on dirt rd from "LcRoy & 5' 3.2 | |||
. - Paul Odenbaugh' Dairy" sign. Dairy sign on WCR 36, s E of Rd 23.. Dairy sign is located next to mailbox of Mike Thomasi. | |||
A-23 .Leroy Odenbaugh Dairy, 11733 Rd'3'6, 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 Jim Docheff l> airy, east of. Road 13 on R'' 32, at 11 9.4 | |||
-4513 WCR 32. | |||
R-8 Borba Dairy, 2252'S. CR 7, take the Hwy. 402 exit for 22.5 Loveland from I-25, travel west 1.6 km to Cty. Rd. 7. Turn south and go to second dairy on left. | |||
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 | |||
, , + | |||
s b | |||
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) | |||
Sector- Distance, Exposure Site No. Location Description (see map) km Pathway Food 4 4.3 Products A-27 Fields on SE corner of intersection of WCR 25 and WCR 38. | |||
2 5.3 A-20 Residence 11399 WCR 40%. | |||
9.6 R-6 Hernandez Produce Stand, Highway 85, Gilcrest. | |||
L% | |||
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k Figure Ill.B.2 Adjacent and Ref erence Sampiing Locations hi l M- l - | |||
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6 Table III.C.1 1991 Land Use Census | |||
* n Sector Nearest Nearest Nearect Milk Residence Garden Animal 1 17578 CR 19\ 9626 CR 44 *** | |||
2 18311 CR 23 18999 CR 23 11283 CR 40\ | |||
v' 3 11100 CR 38 11100 CR 38 11165 CR 38 4 11247 CR Tc 11777 CR 36 11777 CR 36 5~ 16543 CR 23 16134 CR 23 16134 CR 23 i | |||
l 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 21 9 9456 CR 34** 9456 CR 34** 9033 CR 26 10 9061 CR 34 15449 CR 19 7388 CO 66 11 8745 CR 34 G769 CR 32 4513 CR 32 12 Aristocrat 6519 CR 34 5492 CR 34 Ranch 13 17038 CR 17 17038 CR 17 *** | |||
14 8896 CR 19 8896 CR 19 *** | |||
I 15 9115 CR 38 9115 CR 38 *** | |||
16 9239 CR 30 9102 CR 44** 18986 CR 19 | |||
* Census Data: Sept. 24, 1991 | |||
** New Location | |||
*** No milk animals | |||
[ 120 | |||
e O | |||
Figure III.C.1 Land Use Census, 1991 f f')Ck . -{ :',/, ~''f~' | |||
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Latest revision as of 12:07, 12 May 2020
| ML20095J928 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 12/31/1991 |
| From: | Warembourg D PUBLIC SERVICE CO. OF COLORADO |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| P-92171, NUDOCS 9205040206 | |
| Download: ML20095J928 (139) | |
Text
{{#Wiki_filter:' ~ p Mcf pf V as# Public Service' ;%"#L-~ b.
-16805 WCR 19 1/2,_Platteville, Colorado- 80651 N' April 24, 1992-Fort-St. Vrain I Unit No. 1 i+ P-92173' h U.-S. Nuclear Regulatory Commission if
^
. ATTN: Document Control Desx Washington,.D. C. 20555 Docket No. 50-267
SUBJECT:
.. ANNUAL PADIOLOGICAL ENVIRONMENTAL MONITORING L -REPORT Gentlemen:
,EnclosedI plear:e' find a copy of the Fort St. Vrain Nuclear Q Generating 1 Station Radiological Environmental . Monitoring C; Program Annual Summary-Report for 1991. The report is submitted -in accordance with Section 7.3.1.d of. the Fort
-St. Vrain Technical-Specifications:and 10 CFR 50.4.
=Please contact Mr. M. H. Holmes at (303) 620-1701 if you have any questions regarding the report.-
, Sincerely,
$)Y ' )Ygw./n ,
D. W.=Waremboucy Manager, Nucleo Operations DWW/lmg Enclosure.
- (
010Ci 9205040206 911231 PDR- ADOCK 05000267
%M s 'R_ PDR /j w
7; ,. s.' ). i P-92171 Page 2 cc: Regional Administrator, Region IV Mr. J. B. Baird Senior Resident Inspector Fort St. Vrain-kr. Robert'M. Quillin, Director Radiation Control Division Colorado Department of Health 4210 East lith Avenue
. Denver, CO 80220 L Dr. Jim Johnson Colorado State University R3diation & Radiation Biology Fort Collins, CO 80521 1
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PUBLIC SERVICE COMPANY OF
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PROGRAM
SUMMARY
REPORT 1991 COLORADO STATE UNIVERSITY FORT COLLINS, COLORADO 80523 =. . . . . _ . . _ . _ _ - . ~ . . _ _ . . _ . _ . _ . _ . _ _ _ _ _ . _ _ _ _ _ _ .
i RADIOLOGICAL ENVIR0!TMENTAL MOK TORING PROGRAM For the Fort St. Vrain Nuclear Generating Station Operated by the Public Service Co. of Colorado Summary Report for the Period Janusn 1 1991 - Dacember 31. 1901 D
/ d'% 4 /,, / O 2_. -
Prepared by: J ar E. Johnson,(Professor ' Da't e i Colo. ado State University Reviewed by: llt & b! .lh ASF 4[I4!92.- Date Ra'11ochemistry SubervUjs Approved by: M hk6 b !/d 2-RadiationProgtionManager Date i 1
- 7 v
6.eknowledaements - Many persons have contributed to this project during 1991, and it is important to acknowledge their effort. We first thank the citizens from whose farms, homes, and ranches we collect the environmental samples. Without their cooperation the project would not be possible. We also wish to acknowledge and thank Mr. Robert Keiss and his associates- as well as the Colorado Division of Wildlife, Fort-Collins regional office for assisting with the fish collection. l Without their cooperation, equipment and expertise the collection
.would not be possible. '
The persons working directly on the project have been: Faye Bruno Chief Laboratory Technician Norma Frisby Secretary Thomas Miller Student Employee Steven Ziliak Student-Employee Charles Sampier Chief Electronic Technician Christopher Roelle Student Employee [ bt9-
- g .
James Johnson PrhfMssor and Project Director. l i l i' l-I . -, ,
. . . .. .- . . .. . . . .. w
. TABLE OF CONTENTS Page No.
Acknowled5ments 11 List of Tables- iv List of_ Figures vi I. INTRODUCTION 1 i II. SURVEILLANCE DATA FOR 1991 ) AND INTERPRETATION OF RESULTS l l A. External Camma Exposure Rates. 6 l B. Air Sampling Data 10 j
- C. Water Sampling Data 35 D. Milk Data 69 E. Food Products 80 F. -Aquatic Pathways 82 G. Sample Cross-check Data 85 H. Summary and Conclusions 93 III. ~ ENVIRONMENTAL RADIATION SURVEILLANCE-PROGRAM AND SC11EDULE 112
LIST OF TABLES Page 1o. II.A.1 Gamma Exposure Rates, 8 II.B,1 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
-t II.B.2 Tritium Concentrations in Atmospher!c Water Vapor.
- a. First Quarter, 19
- b. Second Quarter, 20
- c. Thir d Quarter, 21
- d. Fourth Quarter. 22 II.B.3 Tritium Concentrations in Air,
- a. First Quarter, 23
- b. Second Quarter, 24
- c. Third Quarter, 25 _
- d. Fourth Quarter, 26 II.B.4 Tricium Released in Reactor Effluents. 27 II.B.5 I-131 Concentcations in Air,
- a. First Quarter, 30
- b. Second Quarter, 31
- c. Third Quarter, 32
- d. Fourth Quarter, 33 II.B.6 Radiocesium Concentrations in Ambient Air. 34
^
II.C.1 Gross Beta Concentrations in Bi-weekly Composites of Drinking Water. 37 i
T3
- 1 LIST OF TABLIS (Continued) l Page No.
Tritium Coucentrations in Bi-weekly Composites II ~. C . 2. 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 )
l 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 Water. 65 II.C.8 Mcximum Permissible Concentrations in Water. 68
/
~
t II . D .' 1 Radionuclide Concentrations in Milk. 72 II.D.2 . Tritium Concentrations in Milk, 78-II.E.1 Radionuclide. concentrations in Food Products. 8l II.F.1 Radionuclide Concentrations in Fish. 83
'II,F.2 Radionuclide Concentrations in Sediment. 84 II.G.1 EPA Cross-check Data. 88 II.G.2 Tritium Concentrations in Cross-check Data, CSU. Colorado Dept. of Health-PSC, 90 II.G.3 Gross Beta Concentrations in Water Cross check Data,-
CSU-Colorado Dept. of Health PSC. 91 II.G.4 'Intralaboratory Cross-check Results. 92 II.H.1 Data Summary, 100 II.H.2 Arithmetic Means of Selected Sample Types, 109 , 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 i III.B.1 Sampling Locations for Environmental Samples, 118 III.C.1 Land-use Census, 1991, 129 L V ,
LIST OF FIGURES Page No. Figure - II . A',1- Gamma' Exposure Ratas, 1973 1991 9
- Figure II.B.1. Cross-Beta Concentrations in Air 16
. Figure II.C.1 Tritium Concentrations at Site F-16', 1984-1991 66-Figure II.C.2 Tritium Concentrations at Site F-16, 1984-1991 67
- (Showing weekly sampling reruits beginning in 1991)
Figure.III.B.1 Close-in Sampling Locations 127 _ Figure IIIIB.2 Adjacent anu Reference Sampling Locations 128 Figure III.C.1 Land Use Census, 1991 130 e u _-
= _2_____. . . . ..
. - - -~ . . - . _ . - . . , .. .~ - - . . - . -- - . . . . , . .
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.I . ; iIntroduction ' tof Radiological Environmental Monitoring
~ Data.for the Period January 1, 1991 - December 31, 1991.
During 1991 the Fort St. Vrain Nuclear Generating Station did not operate and is presently in a defueling phase. The operational phase of the reactor ended on August 13, 1: 1989. -Fuel removal operations began October 6, 1991. A complete and' detailed listing of radioactivity released by all effluent routes may be found.in the Public Service Company of Colorado cemi-annual Effluent Release Reports for y 1991 to the U.S. Nuclear Regulatory Commission. When possible .
-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 1991 on project samples. These values are given.for typical sample sizes, counting times and decay times. The LLD is, therefore, an a priori parameter to ,- -indicate the capability of the detection system used. The-LLD values in Table III. A.2 were calculated as suggested in NUREG-
-0472.
Throughout the report,-however, when a sample result is-listed as less than a specified value, that value is the L . calculated MDC (mini.aum detectable concentration). This.
-approach is analogous to that of Currie (NUREG/CR-4007):
the l
L. MDC is the same_as S,, the critical signal, and the LLD is equal to S 3, the' detectable signal. The MDC value appliew to the actual : sample size, counting time and decay time
-applicable to that individual sample. It is calculated as:
MDC = 2. 3 3 03 / E Y V e4' Where: on = Standard deviation of background count rate E = Counting efficiency, c s 4 pCid Y = Chemical yield V = Sample volume (or mass) L 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 - lesc than the actual MDC _ value. .Because . the _ MDC is dependent upon variables such as the b'ackground count time and sample size, the value vil1 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 due to 2
=
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 i l large, and it is necessary to use mean values from a rather large sample population size to make any conclusions about the l absolute radioactivity concentrations in any environmental ! l pathway. i The arithmetic mean for each sample set is listed in l Table -II.H.2. All measured values, both positive and negative, are used in the calculations of the arithmetic mean. This is the suggested practice by-Gilbert (Health Physics 40:377, 1964) 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 i not significantly different, the confidence for the statement is at the 95% level (a = 0.05) (1.960).
-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 l specified individual member of the general public. That value is-500 mrem / year, but must include the dose from all possible < l sources, and, therefore, cannot be solely due to reactor s 3
1 effluent. As stated in 10CFR20 these are the maximum concentrations above natural background that a licensee may release to an unrestricted 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 specified 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. These 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 uset .or comparison purposes. A limit that does apply is the independent naximum permissible dose commitment rate set by the E.P.A. (40CFR190)
-for any specified member of the general public from any part of the nuclear fuel cycle. This value is 25 mrem / year, the dose rate to the whole body from all contributing radionuclides excluding background and medical radiation dose rate.
Dose commitments are calculated for hypothetical individuals for any mean concentrations noted in unrestricted areas that are significantly above control mean values.
]
I The followinglis the-footnote system used in this report. I
- a. Sample-lost prior to. analysis.
- b. -Sample missing at-site, q i
- c. Instrument-malfunction. .)
1
- d. Sample lost during analysis. I
- e. Insufficient weight or volume for analysis.
4
- f. Sample-unavailable. j l
- g. Analysis in progress. ]
h.- Sample not collected (actual reason given).
- 1. . Analytical 1 error (actual reason given).
N.A. Not applicable. e 1 5
II. Surveillance Data for January Through December 1991 and
-Interpretation of Results A. External Gamma-ray Exposure Rates 1
The average measured gamma-ray exposure rates expressed in -- nR/v ay--. 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 installed at each site and the mean value is reported for that
- 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 locatio. Fading during field exposure is minimized by the post-anrealing readout procedure. TLs TLD data indicate that the arithmetic mean measured exposure rate.in the facility area for all of 1991 was 0.37 mR/ day. :The mean exposure rate was 0.39 mR/ day for the adjacent area and 0.39 mR/ day for the reference area. These latter mean values were not significantly different from each , other and identical to the values measured during 1990. The exposure rate _ measured : at all sites is due to a combination of exposure from cosmic rays, from natural gamma-ray emitters in the earth's crust and from ground surface deposition of fission products due to previous world-wide o 3 fallout. The variation in measured values is due to true l l-6 l' . .- . ~ .- ,
o l variation of the:above sources plus the variation due to the measurement method. The purpose of having two TLD rings around 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 exttirnal 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 l scattered gamma-ray flux produced in a cavity surrounded by l-uranium mill tailings. This produces a gamma-ray spectrum nearly identical to that from natural background measured in the-. reactor environs. The quality control program includes calibration before readout of each quarterly batch of TLD
-devices.
For comparison purposes, in EPA 520/5 Report #58 lists very _ similar background external exposure rate values in l Denver. There has always been excellent agreement with the t- results from this program.' l Figure II.A.1 shows the measured mean exposure rate in the Facility Area - since the inception of the program. The steady decrease.in exposure rate over the period is due to the decay and welthering of fission product deposition from i
-: previous atmospheric weapon tests.
7 l
... Table II.A.1 Gammma Exposure Rates. (mR/ day) 1991 Facility Area -1st Quarter '2nd Quarter 3rd Quarter 4th Quarter
~~
F-1 0.39 0.34 0.40 0.39 F =0.43 0.35 0.35 0.34 F-3: 0.40 0.37 0.33 0.45 F-4 0.39 0.36 0.33 0.32 F-5 0.41 0,39 0.41 0.26 F-6 0.40 0.34 0.39 0.25 F 0.43 0.40 0.37 0.26 F-8 0.40 0.36 0.39 0.42 F 0.43 0.35 0.36 0.24 F-10 0.43 0.36 0.40 0.36 F-11 0.42 0.36 0.38 0.36 F-12 0.40 0.38 0.27 0.46 F-13 0.39 0.36 0.31 0.44 F-14 0.38 0.39 0.27 0.50 F-15 0.39 0.38 0.37 0.53 F-16 0.40 0.32 0.39 0.26 F-17 0.42 0.35 0.40 0.20 F-18 0.43 0.36 0.38 0.34 7 (1.96o) 0.41 (0.03)* 0.36 (0.04) 0.36 (0.08) 0.35 (0.19) Adjacent Area ' A-1 0.43 0.38 0.41 0.58 A 0.41 0.40 0.45 0.57 . A-3 0.43 0.34 0.42 0.40 A 0.44 0.33 0.38 0.37 A-5 0.39 0.34 0.35 0.43 A-6 0.42 0.37 0.34 0.25 A-7 0.41 0.36 0.40 0.34 A-8 0.39 0.37 0.42 0.35 A-9 0.41 0.38 0.42 0.32 A-10 0.38 b b b , A-11 0.36 0.35 0.40 0.27 A-12 0.38- 0.39 0.36 0.32 A-13 0.35 0.36 0.33 0.37 A-14 0.37 0.38 0.37 0.58 A 0.41 0.38 0.37 0.35-
.A-16 0.40 0.35 0.37 0.35 A-17 0.42 0.37 0.39 0.57 A-20 0.40 0.38 0.40 b x (1.96o) 0.40 (0.05) 0.37 (0.04) 0.39 (0.06) 0.4t s0.22)
Reference Area R-2 0.33 0.38 0.38 0.53 R-3 -0.40 0.31 0.37 0.35 R-4 0.40 0.35 0.36 0.39 F R-5 0.41 0.34 0.42 b R-7 0.39 b 0.37 0.47 x (1.96o) 0.39 (0.06)- 0.35 (0.06) 0.38 (0.05) 0.44 (0.16) - L ^ b - sample missing at site
- 1.96o (Due to Counting Statistics)
Figure _11.A.1 Gamma Excosure Rates (mR/ day) (1973 - 1991) ' O.75
- 0.7 -
a 0.65 - p . 0,6 - 5 .55 0 - 0,5 e a fjf M k a<s k,I" jhI,[~["\!f, . 5, \j "4 ' 0.35 - ,a7 fSl
/ -
0.3 ''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''' 74 75 76 77 78 79 80 81 82 83 84 85 86 -87 88 89 90 91 Year 9
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 each quarter of 1991. 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, however, termed
-a f acility site since the inception of the monitoring prr ram.
The reference sites R-3, R-4, and R-11 were established on 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 stationc for all of 1991 was 25 fCi/m. 2 For 1990 the mean value was 23 f Ci/m .3 The mean concentration for 1990 for all reference stations was 24 fCi/m . 3 These measured mean 10
- values were obviously not statistically significant at the 95%
confidence-level. The gross beta data for 1991 have been added to the plot of air concentrations observed since 1973 (Figure II.B.1) . In this figure the half-yearly mean values for the facility sites l are plotted with the values from the reference sites. The contribution from Chernobyl is clearly evident in 1986. It can be observed that overall nean values are not significantly j different from each other. World-wide fallout,-principally due to past Chinese atmospheric nuclear weapon tests, is the l-l predominant contributor above background to tne measured l values over the period shown. - ' There has never been a significant difference observed between facility and reference sites. Thus, it can be concluded that reactor air effluents of particulate fission products or activation products during operation were not a 4 source of dose commitment for the Fort St. Vrain environs population. This is expected to be true as well during the defueling and decommissioning phusc. Y 11
~ -
n
~
b
. Table 11.B.1 Concentrations of Long-lived Gross Beta Particulate Activity in Air. (fCi/m 1 l a) First Quarter,1991 I
. . ' Facility Sites Reference Sites Collection ,
Date. F-7.- F-9' F-16 A-19 R-3 R-4 R-11 01/05.- 56 (2.1)* 65'(1.8)' 54'(1.8) 66 (2.0) 45 (1.9) 49 {1.9)' .'40 (1.7) 01/12 69'(2.4) 60 (1.8)' 61 (2.0). 69 (1.8) 49 (2.0) 58 (2.0)' LS8 (2.0) ; 01/19 19 (1.5) 18 (1.1) 20 (1.3) 19 (1.1) 14 (1.1) 15 (1.2) 18 (1.3) 01/26 23 (l'.6) 20 (1.3) 25 (1.5) 24 (1.3) 22 (1.4) 19 (1.3) 23 (1.4) l 1 02/02 31 (1.7) 36.(1.7) 33 (1.7) 39 (1.8)' 28 (1.5) 22 (1.4) 29-(1.5) 02/09 33 (1.7) 29 (1.2) 32 (l'.5) 33 (1.4)- 25 (1.4) 24 (1.4) 29.(1.5) 02/16 31-(1.7) 29 (1.3) 29 (1.5) 29 (1.3)' 16 (1.2) 26 (1.6) 28 (1.6) k
,_. 02/23 19 (1.4) 18'(1.1) 21 (1.4) 20 (1.2) 16 (1.2) 16 (1.3)' 20 (1.5) ;
N 03/02 22 (1.6) 20 (1.2) 21 (1.3)' 21 (1.2) 20 (1.2) 22 (1.5) 21 (1.5) l
- 03/09 13 (1.2) 14 (.94) 15 (1.2) 15 (1.0) 15 (1.2) 13 (1.2) 14 (1.1) l 03/16- 18 (1.2) 18 (1.1) 17 (1.2) 17 (1.1) 18 (1.?) 17 (1.3) 17 (1.4) !
03/23 23-(1.4) 21 (1.2) 22 (1.3) 22 (1.2) 20 (1.2) 22 (1.5) 22 (1.7) 03/30 18 (1.2) 14 (1.0) 16 (1.1) 17 (1.1) 16 (1.1) 17 (1.4) 17 (2.0) 7 29 .28 28 30 23 25 26 1.960 32 33 28 35 22 26 23 - MAX: 69 Y (1.96o): 29 (31) MAX: 58 i (1.96o): 25 (23) ! MIN: 13 n: 52 ~ MIN: 13 n:-39 -
- 1.96o (Due to Counting Statistics) ,
W - _ - . _ _ - - _ _ _ _ - _ _ . _ _ _ _ - - _ - _ - - _ _ _ _ -- . . , ,~.. .- -
Table II,B.1 Concentrations of Long-lived Gross Beta Particulate Activity in Air. '(fCi/m 3)
.b) Second Quarter, 1991 Facility Sites Reference sites Collection Date F-7 F-9 F-16. A-19 R-3 R-4 R-11 04/06 33 (1.9)
- 27 (1.3) .30 (1.5) 31 (2.8) 24 ti.3) 27 (1.7) 25 (1.3) 04/13 16 (1.2) 12 (.89) 14 (1.1) h' 15 (1.1) 16 (1.4) 13 (.92) 04/20 '21 (1.3) 20 (1.1) 19 (1.2) 20 (1.2) 22 (1.1) 22 (1.5) 26 (1.5) 04/27 18 (1.2) 20 (1.1) 20 (1.3) 19 (1.2) 19 (1.1) 20 (1.5) 18 (1.0) 05/04 14 (1.1) 13 (1.0) 14 (1.1) 14 (.94) 12 (.92) 19 (1.5) 14 (1.1)
.05/11 24 (1.4) 19 (1.2) 24 (1.3) 23 (1.4) 28 (1.5) 23 (1.2) 22 (1.6) 05/18 17 (1.3) 14 (1.1) 17 (1.3) 16 (1.0) 15 (1.1) 20 (2.1) 16 (1.1) 05/25 22 (1.3) 18 (1.0) 21 (1.2) 20 (1.0) 19 (1.3) 32 (2.9) 18 (.98) 06/01 23 (1.1) 24 (1.1) 22 (1.3) 21 (1.0) 24 (1.2) 24 (1.1) 21 (1.1) 06/07 15 (1.2) 14'(1.0) 14 (1.3) 14 (1.2) 12 (1.0) 17 (1.1) 16 (1.1) 06/14 25 (1.3) 25 (1.2) 24 (1.4) 21 (1.2) 24 (1.3) 25 (1.2) 26 (1.3) 06/21 24 (1.3) 19 (3.3) 22 (1.3) 20 (1.1) 21 (1.2) 20 (1.2) 21 (l.2) 06/28 24 (1.3) 29 (1.5) 3.771.8) .19 (1.1) 23 (1.3) 25 (1.3) 23 (1.2) i 21 20 19 20 20 22 20 1.96a 10 11 13 8.8 9.9 8.6 8.7 MAX: 33 x (1.96o): 20 (11) MAX: 32 7 (1.96o): 21 (9.1)
MIN: 3.7 n: 51 ' MIN: 12 n: 39 h - sample not collected (pump not functioning) ,
- 1.96o (Due ' to Counting Statistics) w,. e < , _ _ _ - - - - _ . _ _ . - . - - _ - - - . . _ - - - _ -
Table II.B.1; Concentrations of Long-lived Gross 05ta. Particulate Activity in Air. (fCf/m ). , c) Third Quarter, 1991 Facility Sites Reference Sites Collection Date f-7 F-9 F-16 A-19 R-3 R-4 .R-11. 07/05 20 (1.3)* 23 (1.4)- e 6.1(.78) 23 (1.3) -16 (1.1) 19 (1.1)
-07/12 21 (1.3) 21 (1.2) 24 (2.0) 21 (1.2) 23 (1.3) 21 (1.1) 21 (1.2) 07/19 25 (1.3) 24 (1.2) 18 (1.9) 24 (1.2) 30'(1.5) 25 (1.2) 24 (1.2) 07/26 16 (1.1) 17 (1.0) 16 (1.1) 16 (1.0) 15 (1.1) 16 (1.0) 16 (.97) 03/02 30 (1.4) 29 (1.4) 28 (1.4)- 27'(1.2) 30 (1.4) 29-(1.3) 27 (1.3) 08/09 23 (1.0) 23 (1.1) 22.(1.0) 21 (.94) 24 (1.1) 24 (1.0) 23 (.98) 08/16 26 (1.2) 26 (1.3) 25 (1.2) 24 (1.2) 24 (1.2) 28 (1.2) 25 (1.2) 08/23 25 (1.3) 25 (1.5) 27 (1.3) 22 (1.2) 25 (2.1) 26 (1.2) 27 (1.3) 08/31 28 (1.3) 29 (1.8) 28 (1.3) 27 (1.2) 26 (2.0) 29 (1.3) 23 (1.1) 09/07 .32 (1.4) 20 (3.1) 34 (1.6) 32 (1.4) 34 (2.4) 34 (1.4) 25 (1.3) 09/14 1G (1.1) 17 (1.4) 17 (1.2) 17 (1.0) 20 (2.0) 18 (1.11 18 (1.1) 09/21 22-(1.3) 25 (1.6) 23 (1.3) 22 (1.2) 24 (2.2) 21 (1.1) 21 (1.2) 09/28 27 (1.5) 26 (1.7) 29 (1.5) 26 (1.3) 27 (2.2) 23 (1.2) 23 (1.3)
T 24 23 24 22 25 24 22 1.960 9.1 7.6 11 13 9.3 11 6.6 MAX: 34 7-(1.96o): 23 (10) MAX: 34 x (1.96o); 24 (9.0) MIN: 6.1 n: 51 , MIN: 15 n: 39 e-- insufficient volume for analysis 1.960 (Due to Countin9 Statistics)
4 4 . Table II.B.1 Concentrations of Long-lived Gross Beta Particulate Activity in Air. (fCi/m ); d) Fourth Quarter,.1991 Facility Sites Reference Sites Collection Date F-7 'F-9 F-16 A-19 R-3 R-4 R-11 10/05 28 (1.4)* 28 (1.6) .60(.68) 27 (l'.2) 27 (2.1) 27 (1.3) .29 (1.5) 10/12 4.9(.89) 25 (1.7) 2.0(.66) 1.4(.58) '69 (3.0) 15 (1.1) 15 (1.3) 10/19 27 (l'.5) 28 (1.9) 27-(1.5) 25 (1.3) 40 (2.0) 25'(1.3) 27 (1.7) 10/26 30 (1.5) 32 (1.8) 30 (1.5) 29 (1.4) 34 (2.3) 27 (1.3) 30 (1.6) 11/02 31 (1.4) 32 (1.6) 32 (1.4) 33 (1.3) 35 (2.2) 34 (1.3) 64 (3.3) 11/09 39 (1.6) 37 (1.8) 37 (1.6) 38 (1.6) 34 (2.3)' 26 (1.3) 34 (1.4) 11/16 23 (1.3) 22 (1.5) 24 (1.5) 23 (1.2) 20 (1.8) 20 (1.2) 21 (1.2) G 11/23 14 (1.0) 14 (1.3) 14 (1.2) 15 (.96) 12 (1.7) 13 (.97) 15 (.97) 11/30 20 (1.3) 20 (1.4) 20 (1.2) 20 (1.1) 20 (1.9) 17 (1.0) 22 (1.1) 12/07 24-(1.4) 25 (1.6) 24 (1.3) 23 (1.2) 20 (1.9) 20 (1.2) 22 (1.2) 12/14 33 (1.6) 36 (1.8) 34 (1.5) 35 (1.5) 28 (2.1) 28 (1.3) 32 (1.4) 12/21 37 (1.6) .41 (2.1) -38 (1.6) 24 (1.4) 39 (2.3) 33 (1.5) 31.(1.4) 12/28 45 (1.8) 48 (2.2) 46 (1.8) 46 (1.6) 41 (2.4) 34 (1.4) 39 (1.5) x 27 30 25 27 32 25 27 1.96a 21 18 26 22 28 14 29 MAX: 48 7 (1.96o): 27 (21)' M1H: 0.60 n: 52 MAX: 69 T(1.96o): 28 (25) MIN: 12 n: 39
- 1.96'o (Due to Counting Statistics) -
r-i l Figure II.B.1 l 10 2 - Gross Beta Concentrations in Air i 900 - ! 800 - 700 - 600 - o---o Facility Samphng Stations 1 = 49 500 - Reference Samphng Stations 400 . X=55 300 - 200 - a i /
\ /
\ /
n \- f E \ l 1 N 100 -
\ j f
-Q 90 80 -
(1 ; j l I 70 -g l g j (' g 60 \ s o I i l 50 -
\
I
\ \
\ l 1 ..
40 - a \ { ;
\ \
[\ \
\
l \,,A 20 ~ l *
\
kb {
\j/ \\ k
\\
10 ' ' '
' ' ' ' ' ' ' ' ' t 1973'74 '75 '76 '77 '78 '79 '80 '81 '82 '83 '84 '85 '86 '87 '88 '89 '90 '91 '92 Time (year)
J
4 4 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 1991 is listed in Tables II.B.2a-2d. The corresponding tritium concentration in air (pci/m') is calculated from the specific activity data using weekly mean temperatures and dew points measured at the FSV meteorological tower. The measuring point is at a height of 2 m from the surface. The tritium air concentrations are i shown in Table II.B.3a-3d. 4 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 additional dilution, if necessary, to meet 10CFR20 concentration limits. The summary of tritium release by all modes is shown in Table II.B.4. The summary indicates that l the total tritium released in 1991 was 3.7X that released in
$ 1990 by all routes. This effluent release was detected at nearly all sampling sites, but principally those close to the
- . Goosequill ditch effluent pathway.
-The mean . values for sites F-16 and A-19 were statistically the same as for all other sites during the year.
In any case, inhalation is not a significant pathway for dose l to humans. The milk and food product pathway-is the-only l. L _significant source of radiation dose to humans from i 17
,*r y- - ,
l environmental tritium. See results for these pathways in sections II.D and II.E. Since the same weekly relative humidity is assumed for all sites, Table II.B.3 shows the same site dependence on reactor effluent as Table II.B.2. Only the units used to measure tritium in surface air are different. 18
1 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 1 0 0 9 0 9 0
- 4 4 4 4 4 4 4 4 4 3 4 3 4 R
s e t" i S 0 0 0 0 0 0 0 0 0 0 0 0 0
) e 4 0 0 0 0 0 0 1 0 0 9 0 9 0 L c - 4 4 4 4 4 4 4 4 4 3 4 3 4
/ n R 1 e < < < < < < < < < < < < <
C r p e ( f
- e ) )
R 0 0
. 2 0 r- 0 0 0 0 0 0 0 4 0 4 0 0 0
_ o 3 0 0 0 0 0 0 1 ( 0 ( 0 9 0 p - 4 4 4 4 4 4 4 0 4 0 4 3 4 a R 1 9 V < < < < < < < 4 < 3 < < '< r.
- e. .
t ) a 0 W 1 9 0 0 0 0 0 0 0 0 0 4 0 0 0 c 1 0 0 0 0 0 0 0 0 0 ( 0 9 0 i - 4 4 4 4 4 4 4 4 4 0 4 3 4 r A 3 e < < < < < < < < < 4 < < < h . p. s o s ) m e 0 t t 1 A i 6 0 0 0 0 0 0 0 0 0 4 0 0 0 S 1 0 0 0 0 0 0 1 0 0 ( 0 9 0 n - 4 4 4 4 4 4 4 4 4 0 4 3 4 i y F ' 3 t < < < < < < < < < 5 < < < ) s i s n l c o i i i c t t 1 a s a 9 F i r 9 0 0 0 0 0 0 0 0 0 0 0 0 0 t t 1 9 0 0 0 0 0 0 1 0 0 9 0 9 0 a n - 4 4 4 4 4 4 4 4 4 3 4 3 4 t e , F S c r < < < < < < < < < < < < < n e g . o t n C r i a t m u n u Q u i t 0 0 0 0 0 0 0 0 0 0 0 0 0 o t 7 0 0 0 0 0 0 1 0 0 9 0 9 0 C _ i s - 4 4 4 4 4 4 4 4 A 3 4 3 4 r r F o T i < < < < < < < < < < < < < t F 2 e
) u a n D B.
1 i o' ( 1 t o c 6 e e 5 2 9 6 2 9 t 3 2 9 6 3 0 9 l b l e l t 0
/ / /
1 1 2
/ /
0 ^
/
I
/
2
/
0
/
0 1 2 3 1
/ / / /
a oa 1 1 1 1 2 2 2 2 3 3 3 3 3 T CD 0 0 0 0 0 0 0 0 0 0 0 0 0
- 3 b
.1 -
+ '. a _
1 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 9 0 9 9 9 9 9
- 4 4 4 4 4 4 3 4 3 3 3 3 3 R
s e , t i S , 0 0 0 0 0 0 0 0 0 0 0 0 0
) e 4 0 0 0 0 0 0 9 0 9 9 9 9 9 L c - 4 4 4 4 4 4 3 4 3 3 3 3 3
/ n R i e < < < < < < < < < < < <
cp r e ( f e R r 0 0 0 0 0 0 0 f 0 0 0 0 0 , o p 3 0 0 0 0 0 0 9 0 9 9 9 9 9 -
- 4 4 4 4 4 4 3 4 3 3 3 3 3 a 3 V. < < < < < < < < < < < < < .
4 r e - t m
, a W
9 0 0 0 0 0 0 0 0 0 0 0 0 0 c 1 0 0 0 0 0 0 9 0 9 9 9 9 9 - i - 4 4 4 4 4 4 3 4 3 3 3 3 3 r A e < < < < < < < < < < < < < h p s o s 4 m e t t A i 6 0 0 5 0 0 0 0 0 0 0 0 0 0 S 1 0 0 0 0 0 0 9 0 9 9 9 9 9 . n - 4 4 4 4 4 4 3 4 3 3 3 3 3 m i y F t < < < < < < < < < < < < < s i n l o i i 1 c t 9 a a 9 F r 1 0 0 0 0 0 0 0 0 0 0 0 0 0 w t 9 0 0 0 0 0 0 9 0 9 9 9 9 9 n , - 4 4 4 4 4 4 3 4 3 3 3 3 3 e r F c e < < < < < - n t o r C a u w m Q u i d 0 0 0 0 0 0 0 0 0 0 0 0 t n 7 0 0 0 0 0 0 A
' 0 9 9 9 9 9 i o - 4 4 4 4 4 4 ' 4 3 J 3 3 3 r c F T e < < < < < < < < e < < < < +
S 2
)
b n B. I i o' I t c e e 6 !
" 0 7 4 1 8 5 1 7 4 1 8 l l e 0 1 2 2 0 1 1 2 0 0 1 2 2 b lt / / / / / / / / / / / / /
a oa 4 4 4 4 5 5 5 5 6 6 6 6 6 T CD 0 0 0 0 0 0 0 0 0 0 0 0 0 v g ~ i, l ) j l
F Table II;B.2 Tritium Concentrations in Atmospheric Water Vapor. (pCi/L) c) Third Quarter, 1991 i Facility Sites Reference Sites Collection Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 07/05 < 380 < 380 < 380' < 380 < 380 < 380 < 380 J7/12 < 390 < 390 < 390 < 390 < 390 < 390 < 390 07/19 < 380 < 380 < 380 < 380 < 380 < 380 < 380 1 07/26 < 390 < 390 < 390 < 390 < 390 < 390 < 390 , 08/02 < 390 < 390 < 390 < 390 < 390 < 390 < 390 08/09 < 400 < 400 < 460 < 400 < 400 < 400 < 400. ' D! 08/16 < 390 < 390 < 390 < 390 < 390 < 390 < 390 4 I 08/23 < 390 < 390 < 390 < 390 < 390 < 390 < 390 08/31 < 400 < 400 < 400 < 400 < 400 < 400 < 400
,. 09/07 < 400 < 400 < 400 < 400 < 400 < 400 < 400 r
I 09/14 730 (410)* 770 (410) 920 (420) 620 (410) 680 (410) 610 (410) < 390 i ! i 09/21 650 (370) < 350 800 (370) 960 (370) 710 (370) 620 (360) < 350 09/28 640 (370) 610 (360) 460 (360) 550 (360) 730 (370) < 350 350 (360)
- 1.96o (Due to Counting Statistics) .
r e me.- - , -m w
i
, e ,
Table II.B.2 Tritium Concentrations in Atmospheric Water Vapor. (pCi/L) d) Fourth Quarter,1991 Facility. Sites Reference Sites Collection Date F-7 F-9 F-16 'A-19 R-3 R-4 R-11 L 10/05 < 390 630 (410)* 790 (410) 600 (410) 400 (410) 740 (410) 640 (410) 10/12 < 400 650 (420) < 400 700 (420) < 400 < 400 < 400 10/19 < 400 < 400 < 400 430 (420) < 400 < 400 < 400 10/26 500 (420) < 400 620 (430) 620 (430) 530 (420) 870 (430) < 400 11/02 610 (410) 670 (410) 470 (410) 690 (410) < 390 < 390 730 (420) 11/09 540 (420) < 400 < 400 560 (420) < 400 470 (420) 680 (420) g 11/16 780 (420) < 400 < 400 < 400 < 400 < 400 < 400 11/23 < 400 520 (420) < 400 < 400 < 400 < 400 470 (420) 11/30 < 400 520 (420) 730 (420) < 400 540 (420) < 400 < 400 1 12/07 < 400 < 400 530 (420) < 400 500(420) < 400 < 400 12/14 < 400 < 400 650 (420) < 4u0 ' 450 (410) 620 (420) 540 (410) I 12/21 < 400 520 (420) 440 (420) < 100 < 400 770 (420) 530 (420) 12/28 < 410 < 410 < 410 550 (430) < 410 < 410 < 410
- 1.96o (Due to Counting Statistics) 4 . _ _ _ _ _ -- - -
Table !!.B.3 Tritium Concentrations in Atmospheric Water Vapor. (pCi/m') a) First Quarter,1991 Facility Sites Reference Sites Collection Date -F-7 F-9 F-16 A-19 R-3 R-4 R-11 01/05. <0.9h < 0.92 < 0.92 < 0.92 < 0.92 < 0.92 < 0.92 i 01/12. < 1.1 < 1.1 < 1.1 < 1.1 < 1.1 < 1.1 < I.1 $ 01/19 < 1.3 < 1. 3 < 1.3 < 1.3 1.3 < 1.3 < 1.3 01/26 < 0.79 '< 0.79 < 0.79 < 0.79 < 0.79 < 0.79 < 0.79 02/02 < 0.87 < 0.87 < 0.07 < 0.87 < 0.87 < 0.87 < 0.87 ! 02/09 < 1.2 < 1.2 < 1.2 < 1.2 < 1.2 < 1.2 < 1.2 j .O 02/16 < 1.4 < 1.4 < 1.4 < 1.4 - < 1.4 < 1.4 < 1.4 i 02/23 < 1.2 < 1.2 < 1.2 < 1.2 1.2 (1.2)* < 1.2 < 1.2 03/02 < 1.0 < 1.0 < 1.0 < 1.0 < 1.0 < 1.0 < 1.0 i 03/09 < I.0 '< 1.0 1.4 (1.1} 1.1 (1.1) 1.0 (1.1) < 1.0 < 1.0 i 1
- 03/16 < 1.2 < 1.2 < i .2 < 1.2 < 1.2 < 1.2 < 1.2 l I
- 03/23 < 1.2 < 1.2 < 1.2 < 1.2 < 1.2 < 1.2 < 1.2 l 03/30 < 1.2 < 1.2 < 1.2 < 1.2 < 1.2 < 1.2 < 1.2 i
- 1.96o (Due to Counting Statistics) -
5 .
., ,m. _ , .. . - - . , . . _
Table II.B.3 Tritfira Concentrations in Atmospheric Water Vapor. (pCi/m3 ) b) Second Quarter, 1991 Facility Sites Reference Sites Collection A-19 R-3 R-4 R-11 Date F-7 F-9 F-16
< 1.4 < 1.4 < 1.4 < 1.4 < 1.4 < 1.4 04/06 < 1.4
< 1.4 < 1.4 < 1.4 < 1.4 < 1.4 < 1.4 i 04/13 < 1.4 l
< 1.8 < 1.8 < 1.8 < 1.8 < 1.8 < 1.8 < 1.8 04/20
< 1.6 < 1.6 < 1.6 < 1.6 < 1.6 < 1.6 < 1.6 04/27
< 1.6 < 1.6 < 1.6 < 1. 6 < 1.6 < 1.6 < 1.6 l
05/04
< 2.2 < 2.2 < 2.2 < 2.2 < 2.2 < 2.2 < 2.2 05/11
< 2.1 < 2.1 < 2.1 < 2.1 < 2.1 < 2.1 < 2.1 05/18
< 2.9 < 2.9 < 2.9 < 2.9 < 2.9 < 2.9 < 2.9 05/25
< 3.0 < 3.0 < 3.0 < 3.0 < 3.0 < 3.0 < 3.0 06/01
< 3.1 < 3.1 < 3.1 < 3.1 < 3.1 < 3.1 < 3.1 06/07
< 3.0 < 3.0 < 3.0 < 3.0 < 3.0 < 3.0 < 3.0 06/14
< 2.7 < 2.7 < 2.7 < 2.7 < 2.7 < 2.7 < 2.7 06/21
< 1.7 < 1.7 < 1.7 < 1.7 < 1. 7 < 1.7 < 1.7 06/28
y. (pC1/m3; Table II.B.3 Tritium Concentrations in Atmospheric Water Vapor. c) Third Quarter, 1991 Facility Sites Reference Sites Collection Date F-7 F-9 F-16 A-19 R-3 .R-4 R-11 07/05 < 2.7 < 2.7 < 2.7 < 2.7 < 2.7 < 2.7 < 2.7 i 07/12 < 3.6 < 3.6 < 3.6 < 3.6 < 3.6 < 3.6 < 3.6 07/19 < 3.4 < 3.4 < 3.4 < 3.4 < 3.4 < 3.4 < 3.4 4 07/26 < 3.4 < 3.4 < 3.4 < 3.4 < 3.4 < 3.4 < 3.4 08/02 < 3.4 < 3.4 < 3.4 < 3.4 < 3.4 < 3.4 < 3.4 08/09 < 3.5 < 3.5 < 3.5 < 3.5 < 3.5 < 3.5 < 3.5 08/16 < 3.5 < 3.5 < 3.5 < 3.5 < 3.5 < 3.5 < 3.5 i 08/23 < 3.1 < 3.1 < 3.1 < 3.1 < 3.1 < 3.1 < 3.1 ' 08/31 < 3.2 < 3.2 < 3.2 < 3.2 < 3.2 < 3.2 < 3.2 i 09/07 < 3.0 < 3.0 < 3.0 < 3.0 < 3.0 < 3.0 < 3.0 09/14 6.0 (3.4)* 6.3 (3.4) 7.6 (3.4) 5.1 (3.4) 5.6 (3.4) 5.0 (3.4) < 3.2 09/21 3.8 (2.1) < 2.0 4.6 (2.1) 5.5 (2.1) 4.1 (2.1) 3.6 (2.1) < 2.0 1 09/28 3.2 (1.9) 3.1 (1.8) 2.3 (1.8) 2.8 (1.8) 3.7 (1.9) < 1.8 1.8 (1.8) i
- 1.96o (Due to Counting Statistics) '
4
! O p 2 .
1 .
F
^
Table II.8.3 Tritium Concentrations in Atmospheric Water Vapor. (pCi/m3) d) Fourth Quarter,1991 Facility Sites Reference Sites Collection Date F-7 F- 9 F-16 A-19 R-3 R-4 R-11 10/05 < 2.3 3.7 (2.4)
- 4.6 (2.4) 3.5 (2.4) 2.3 (2.4) 4.3 (2.4) 3.7 (2.4) 10/12 < 1.9 3.0 (1.9) < I .9 3.2 (1.9) < 1.9 < 1.9 < 1.9 10/19 < 1.5 < 1.5 < 1.5 1.6 (1.6) < 1.5 < 1.5 < 1.5 10/26 2.0 (1.7) < 1.6 2.5 (1.7) 2.5 (1.7) 2.1 (1.7) 3.5 (1.7) < 1.6 11/02 1.3 (.91) 1.5 (.91) 1.0 (.91) 1.5 (.91) < 0.86 < 0.86 < 0.86 11/09 2.0 (1.6) < 1.5 < 1.5 2.1 (1.6) < 1.5 1.8 (1.6) 2.5 (1.6) 11/16 3.3 (1.8) < 1.7 < 1.7 < 1.7 < 1.7 < 1. 7 < 1.7 M
11/23 < 1.3 1.7 (1.4) < 1.3 s 1.3 c 1.3 < 1.3 1.5 (1.4) 11/30 < 1.4 1.9 (1.5) 2.6 (1.5) < 1.4 1.9 (1.5) < 1.4 < 1.4 12/07 < 1.3 < 1.3 1.7 (1.3) < 1.3 1.6 (1.3) < 1.3 < 1.3 12/14 < 1. 4 < 1.4 2.2 (1.4) < 1.4 1.5 (1.4) 2.1 (1.4) 1.8 (1.4) 12/21 < 1.4 1.8 (1.4) 1.5 (1.4) < 1.4 < 1.4 2.6 (1.4) 1.8 (1.4) 12/28 < 1.2 < 1.2 < 1.2 1.6 (1.3) < 1.2 < I.2 < 1.2.
- 1.96o (Due to Counting Statistics)
_ ,m,- - r w ri ,. 1* e '---'" - " ~ ^ - " ' " ' - '
' ' " " " " " ^ ~ ' ' ' - - - - - - - ^ ^ ^ -
.~
f I 3 ble 11.B.4 Trit tum Released (nCI) In Reactor Effluents, 199 1 ttist of JAff flD itAft A rst #1AY Juft Jtat. AtM1 st r oct tioV Dtc los Al i s . ... u . ... s f,,',7',l,'[ ' O.415 0.492 0.568 0.340 0.524 0.486 0.661 1.29 1.55 1.54 2.05 1.06 10.98 ,
- n. .,
- g its t t la ,
I?et f em te i I
, l,',',7 Q j ',',,', 0.807 0.614 0.394 0.361 0.173 1.02 0.217 11.8 0.328 0.395 0.307 0.350 16.77 ~ r.. .
e ttat a la j 6.38
" * ' " a 5 *'
r.y . t e. (.., i l'c50 2710 202 32.6 3.31 3.75 .1460 648 1400 3280 70.4 11066 t i t
, m e.... .
11.6 8.53 8.75 10.0 12.6 6.18 12.8 9.51 7.39 3.06 4.76 2.19 97.37 ; L
'"'^' 1263 2/20 211.7 43.3 16.6 11.4 20.06 1483 657 1405 3287 74.0 11192 1
(1) Conservative estimate by TSV laboratories. Obtained . in many cases by itDA result X volume. Y l P F
,m -. .v.-,, . - , - . _
.,.m .. , ,, .n. . . . , . , - - . , - . . , -
. . . - , ..-..,,c . . -
- 3. Concentrations of Gamma-rav Emittina Radionuclides in Ambient Air Tables II.B.Sa-5d list the concentrations of I-131 in air as measured- by activated charcoal sampling and Ge(Li) gamma-ray spectrum analysis during 1991. Each sample from the seven air sampling stations is counted within 96 hours after collection. A 100-minuto count and a sample volume of 800 m' is required to achieve an MDC of 33 f ci/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 superior resolution of Go(Li) spectrometry systems. Any 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 an" 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 in the case whether the I-131 source term would be a nuclear accident elsewhere, weapons testing fallout or reactor stack effluent. There were only occasional positive values very near the MDC value and all are assumed to be false positives. When a gamma-ray from natural background activity interferes'with the region o'f interest of a measured radionuclido, e.g., Cs-134, Ba-La 140, the number of falso positives is higher, implying
~
a systematic . error. I-131 concentrations due to reactor i f 28
- _- _ _ _ - . - - - - . .-_ - - ..~ - .. . - _ . . . - = . _ . -
1 offluent have never been detected in any sample type in the fort St. Vrain environs. There is essentially no fission product I-131 remaining in any of the fuel elements and, therefore, no possible source term. Table II.B.6 lists measured ambient air concentrations of Cs-134 and Cs-137. These values are from gamma-ray spectrum analyses on weekly air filters composited quarterly from each of the seven air sampling stations. The occasional positive values are either measurement system f also positives or Cs-137 concentrations possibly dos to resuspension of surface soil. The Cs-137 activity is due to Chernobyl or previous fallout which is bound by clay mineralt 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 gemma-ray spectrum is scanned for evidence cf 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. [ 29
-1 Table IT.B.5 lodine-131 Coicentrations in Air. (fti/m 3) a) First Quarter, 1991 Facility Sites Reference Sites Collection-Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 1/02/91 '< 20.0 < 24.0 < 19.0 < 19.0 < 20.0 e 23.0 < 29.0 1/09/91 < 30.0 < 25.0 < 21.0 < 22.0 < 35.0 < 24.0 < 34.0 1/16/91 < 34.0 < 12.0 < 16.0 < 17.0 < 26.0 < 33.0 < 24.0 1/23/91 < 7.9 < 21.0 < 35.0 < 34.0 < 20.0 < 32.0 < 33.0 1/30/91 < 26.0 < 18.0 < 25.0 < 20.0 < 19.0 < 33.0 < 22.0 2/06/91 < 11.0 < 13.0 < 16.0 < 17.0 < 26.0 < 19.0 < 34.0 E$ 2/13/91 '46.0 (33.0)* < 30.0 < 13.0 < 16.0 < 17.0 < 35.0 < 32.0 2/20/91 < 14.0 < 23.0 < 21.0 < 26.0 < 30.0 < 21.0 < 8.9 2/27/91 < 31.0 < 11.0 < 15.0 20.0 (22.0) < 19.0 < 21.0 < 21.0 3/06/91 < 32.0 < 16.0 < 18.0 < 23.0 < 18.0 < 26.0 < 23.0 3/13/91 < 20.0 ' < 21.0 < 23.0 < 17.0 < 35.0. 37.0 (38.0) < 26.0 3/20/91 < 32.0 < 32.0 < 24.0 < 26.0 <.28.0 < 28.0 < 14.0 3/27/91 < 34.0 < 21.0 < 28.0 < 19.0 39.0 (26.0) < 27.0 < 28 0
*L1.96o (Due to Counting Statistics) t
.y , , , _ , v w. , --. - -v., -
. r , , - - -, , -
3 Table 11.8.5. Iodine-131' Concentrations'in Air. (fCf/m ) b) Second Quarter,1991 - Facility Sites Reference Sites Collection } Date. F-7 F-9 F-16 A-19 R-3 R-4 R-11 4/03/91 < 15.0 < 19.0 < 29.0 < 14.0 < 17.0 < 27.0 < 15.0
- 4/10/91 < 23.0 < 22.0 < 26.0 h < 24.0 < 14.0 < 19.0 4/17/91 < 7.0 < 9.4 < 32.0 < 14.0 < 12.0 < 32.0 < 26.0 4/24/91 < 25.0 < 24.0' < 28.0 < 27.0 < 18.0 < 14.0 < 15.0 5/01/91 < 23.0 < 24.0 < 31.0 < 16.0 < 20.0 < 23.0 < 19.0 5/08/91 < 16.0 < 7.7 < 16.0 < 13.0 23.0 (22.0) < 25.0 < 5.8
. O 5/15/91 < 26.0 < 16.0 < 25.0 < 27.0 < 17.0 < 17.0 < 23.0 5/22/91 < 33.0 < 15.0 < 29.0 < 22.0 < 19.0 < 27.0 < 21.0 5/29/91 < 18_0 41.0 (35.0) < 23.0 < 12.0 < 17.0 < 16.0 38.0 (40.0) - l 1 6/05/91 < 24.0 < 16.0 < 15.0 < 18.0 < 20.0 < 20.0 < 19.0 6/11/91 < 21.0 < 28.0 < 20.0 < 26.0 < 35.0 < 21.0 < 12.0 6/;8/91 < 24.0 < 30.0 < 32.0 < 15.0 < 27.0 < 18.0 < 12.0 ; 6/25/91 < 30.0 < 34.0 29.0 (36.0)'< 20.0 < 22.0 < 14.0 < 11.0
- 1.96o'(Oue.to Counting Statistics) ,
h - sanple not collected (pump not functioning) ,
e Table II.B.5 lodine-131 Concentrations in Air. (fCi/m ) d) Third Quarter, 1991 Facility Sites Reference Sites Collection e. Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 7/02/91 < 17.0 < 15.0 < 24.0 32.0(35.0[ < 13.0 < 25.0 < 33.0 7/09/91 < 29.0 < 18.0 < 33.0 < 30.0 < 16.0 < 14.0 < 16.0 7/16/91 < 29.0 < 13.0 < 11.0 < 17.0 < 30.0 < 13.0 < 23.0 7/23/91 < 18.0 < 20.0 < 15.0 < 13.0 < 25.0 < 17.0 < 11.0 7/30/91 < 15.0 < 22.0 < 17.0 27.0 (25.0) < 28.0 < 14.0 < 18.0 g; 8/06/91 < 35.0 < 23.0 < 22.0 < 17.0 < 14.0 < 18.0 < 13.0 8/13/91 < 32.0 < 24.0 < 18.0 < 19.0 < 19.0 < 33.0 < 24.0 8/20/91 < 31.0 < 21.0 < 24.0 < 26.0 < 34.0 < 29.0 < 22.0 8/28/9? < 17.0 < 14.0 < 26.0 < 22.0 < 35.0 < 22.0 < 12.0 9/04/91 < 23.0 < 26.0 < 25.0 < 25.0 < 11.0 < 20.0 < 17.0 9/11/91 < 29.0 < 19.0 < 16.0 < 21.0 < 21.0 < 13.0 < 18.0 9/18/91 < 31.0 < 33.0 < 15.0 < 18.0 < 23.0 < 21.0 < 16.0 9/25/91 < 26.0 < 23.0 < 28.0 < 33.0 < 35.0 < 25.0 < 13.0
- 1.96o (Due to Counting Statistics)
O _
'I Table II.B.5 Iodine-131 Concer.trations in Air. (fCi/m3 ) d) Fourth- Quarter, 1991 Facility Sites Reference Sites Collection Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 , 10/02/91 < 25.0 < 28.0 < 33.0 < 15.0 < 11.0 < 29.0 < 18.0
- 10/09/91 < 23.0 < 18.0 < 15.0 32.0(30.0} < 35.0 < 22.0 < 12.0 10/16/91 < 17.0 < 30.0 < 33.0 < 26.0' < 19.0 < 20.0 < 34.0 10/23/91 < 10.0 < 9.0 < 14.0 < 19.0 < 29.0 < 23.0 < 9.5 l 10/30/91 < 21.0 < 25.0 < 18.0 < 22.0 < 18.0 < 13.0 < 12.0
{ 11/06/91 < 20.0 < 19.0 < 12.0 < 26.0 17.0 (19.0) < 11.0 < 13.0 , 11/13/91 < 18.0 < 31.0 < 20.0 < 15.0 < 25.0 < 23.0 -25.0 (23.0) . 11/20/91 < 23.0 < 16.0 <-15.0 19.0 (24.0) < 9.8 < 17.0 < 19.0 11/27/91 < 13.0 < 14.0
< 34.0 < 15.0 < 16.0 < 20.0 < 18.0 i
12/04/91 < 35.0 < 9.1 < 14.0 < 23.0 < 1.8 < 18.0 < 17.0 12/11/91 < 25.0 < 35.0 < 35.0 < 26.0 < 17.0 < 13.0 < 23.0 ' 12/18/91 < 20.0 < 18.0 < 18.0 < 32.0 < 14.0 < 22.0 34.0 (41.0) 12/25/91 < 32.0 < 22.0 < 24.0 < 22.0 < 28.0 '< 32.0 < 35.0
- 1.96o (Due to Counting Statistics) l .
t r w 1 s
! Table II.B.6 Radiocesium Concentrations in Ambient Air. (fCi/m )
l 1991 Facility Sites Reference Sites Collection Radio-Date nuclide F-7 F-9 F-16 A-19 R-3 R-4 R-11 4 1st Cs-134 < 1.6 < 1.3 < 1.8 < 1.9 3.2 (3.2) < 2.4 < 3.5 Quarter Cs-137 < 1.6 1:6 (1.8)* < 1.9 < 2.0 < 2.8 < 2.9 < 3.3 5 2nd Cs-134 < 1.5 < 1.1 < 1.6 < I .1 < 1.2 2.4 (1.6) < 1.5 Quarter Cs-137 < 1.5 < 1.2 < 1.6 < 1.2 < 1.3 1.7 (1.7) 1.5 (1.9) 3rd Cs-134 < 1.0 < 1.1 < 1.3 < 0.57 < 0.69 < 0.72 < 0.74 Quarter Cs-137 < 1.1 < 1.1 < 1.3 < 0.57 1.2 (.84) < 0.71 < 0.77
-4th Cs-134 < 2.3 < 2.4 < 1.2 < 1.7 < 3.4 2.3 (2.5) < 2.8 Quarter Cs-137 < 2.4 < 2.3 < 1.3 < 1.8 < 3.2 < 1.6 < 2.2
- 1.96o (Due to Counting Statistics)
Y . -
II.C. Radionuclide Concentration in Water
- 1. Drinkina WatigI Drinking water i.s sampled weekly and composited biweekly at two location.. Location R-6 is the well used for drinking water by the town of Gilcrest, Colorado, and R-3 is a water 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. Water treatment systems for the two water supplies are very different. .
. Table II.C.1 shows gross beta concentrations measured in 1991 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 practices;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 y;2an 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. Concentrations above MDC were detected after the major reactor releases. The yearly arithmetic mean value for the Gilcrest location was 620 2 e 35
pCi/L. Assuming this was the only drinking water intak for Gilcrest residents the resultant dose commitment calculation is as follows: Assuming 2 L/ day intake of drinking water, water from milk of a family milk cow and vegetables from a local garden irrigated with the well water, the yearly intake is 1250 L/ year. The adult committed effectivo dose equivalent is: 121QL x 620 DC.i x 6.3 x 10 4 mrea = 0.049 mrom. year L pCi This is an insignificant dose commitment. The EPA limit for community drinking whter systems is currently 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 Ge(Li) spectrometry for I-131. A three liter aliquot of the original sample is counted directly for the other gamma-ray emitters. - Inspection of Table II-C.3 reveals occasional positive i values of radionuclide concentration, but with the exception of Cs-137, these are interpreted to be random variations about the detection limit. The Cs-137 is the residue from the 1986 Chernobyl accident fallout as well as from past world-wide fallout from nuclear weapon testing. 36
Table 11.C.1 Gross Beta Concentrations in Biweekly Composites of Drinking Water. (pCi/L) Collection Gilcrest City R-6 Fort Collins City R-3 Date 1991 (Reference) 12/29 01/05 6.3 (2.5)* .84 (0.56) 01/12 01/19 5.1 (2.4) .67 (0.55) 01/26 02/02 S.1 (2.4) 1.4 (0.59) 02/09 02/16 6.8 (2.5) 1.6 (0.60) 02/23 03/02 5.6 (2.4) 1.5 (0.59) 03/09 03/16 5.1 (2.4) 1.4 (0.59) 03/23 03/30 5.6 (2.4) 1.0 (0.57) 04/06 04/13 4.4 (2.3) .90 (0.56)
-04/20 04/27 4.' (2.3) .89 (0.56) 05/04 05/11 8.3 (2.6) 1.0 (0.57) 05/18 05/25 3.3 (2.2) 1.3 (0.58) 06/01 06/07 4.0 (2.3) .90 (0.57) 06/14 06/21 3.3 (2.3) .53 (0.55) -
06/28 07/12 5.5 (2.4) .53 (0.55) 07/12 07/19 3.7 (2.3) .44 (0.54) 07/26 08/02 4.2 (2.3) .71 (0.56) 08/09 08/16 3.4 (2.3) .53 (0.54) 08/23 08/30 9.4 (2.7) .64 (0.55) 09/07 09/14 3.1 (2.3) .67 (0.56) 09/21 09/28 10 (2.7) .90 (0.57) 10/07 10/14 -5.3 (2.4) 1.4 (0.56) 10/21 10/28 8.7 (2.5) 1.5 (0.60) 11/02 11/09 13 (2.8) .92 (0.56) 11/16 11/23 6.6 (2.5) .63 (0.55) 11/30-12/07 5.8 (2.4) 1.1 (0.58) 12/14 12/21 4.6 (2.3) .91 (0.57)
*1.96o (Due to Counting Statistics) i l
I 37
. I Table !!.C.2 Tritium Concentrations in Biweekly Composites of Drinking Water. (pCi/L)
Collection Gilcrest City R-6 Fort Collins City R-3 Date 1991 (Reference) 12/29 01/05 < 400 < 400 01/12 01/19 < 400 < 400 01/26 02/02 < 400 < 400 02/09 02/16 < 400 < 400 02/23 03/02 < 400 < 400 03/09 03/16 < 400 < 400 03/23 03/30 < 400 < 400 04/06 04/13 < 400 < 400 04/20 04/27 < 400 < 400 05/04 05/11 < 390 < 390 05/18 05/25 < 390 < 390 06/01 06/07 < 390 < 390 06/15 06/22 < 390 < 390 06/29 07/06 < 380 < 380 07/13 07/20 < 390 < 390 07/27 68/03 < 390 < 390 08/10 08/17 < 390 < 390 08/24 09/31 < 400 < 400 09/07 09/14 490 (360)* < 350 09/21 09/28 640 (420) < 400 10/05 10/12 < 400 < 400 10/19 10/26 < 400 < 400 11/02 11/09 560 (420) < 400 11/16 11/23 760 (420) 410 (410) 11/30 12/07 600 (420) < 400 12/14 12/21 660 (420) 730 (420) i
*1.960 (Due ta Counting Statistics)
L l
Table II.C.3 Radionuclide Concentrations in Bi-wakly Composite of Drinking Water. (pCi/L) Collection for two weeks ending for two weeks cading for tvn weeks ending
; Date 02JAN91 16JAN91 30JANQ1 Radionuclide Gilcrest Ft Collins Gilcrest Ft Collins GilcrNs1 Ft Col' lins R R-3 R-6 R-3 R-6 R-3 I
I-131 < 0.39 < 0.37 < 0.28 < 0.12 < 0.33 < 0.47 Cs-134 < 2.0 < 3.0 e < 2.1 < 2.0 < 1.6 < 2.S Cs-137 < 2.5 < 3.7 5.4 (3.0)* < 2.5 < 1.9 < 3.1 i lg Zr-95 < 4.5 < 6.7 < 4.5 < 4.3 < 3.7 < 5.8 Nb-95 < 1.9 < 3.0 < 1.9 < 1.9 < 1.5 < 2.3 Co-58 < 2.0 < 2.9 < 1.9 < 1.8
. < 1.4 < 2.3 ;
Mn-54 < 2.1 < 3.0 < 2.1 3.3 (2.4) < 1.5 < 2.5 2n-65 < 5.9 < 7.6 < 5.8 < 5.5 < 4.9 < 6.9 Fe-59 < 4.7 < 7.8 < 4.7 < 4.7 < 4.2 < 6.1 Co-60 < 2.1 < 2.9 < 2.0 < 2.0 < 1.5 3.3 (3.2) Ba-140 < 5.0 < 4.9 < 3.2 < 3.1 < 4.3 < 4.0 La-140 < 5.7 < 5.6 < 3.7 < 3.6 < 4.9 < 4.6 l
- 1.96 o (Due to Counting Statistics) ,
l
.- - -- , _ _ _ - _ _ - _ _ _ _ - _ - _ _ _ - _ - ._ - ]
Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drieking Water. (pCi/L) Collection for two weeks ending for two weeks ending for t weeks ending Date 13FEB91 27FEB91 13 MAR 91 Radionuclide Gilcrest Ft Callins Gficrest Ft Collins uficrest Ft Collins R-6 R-3 R-6 R-3 R-6 R-3 I-131 < 0.3 < 0.19 < 0.28 < 0.18 < 0.41 < 0.5 Ij Cs-134 < 2.1 < 2.4 < 2.1 < 2.2 < 2.4 < 2.0 Cs-137 3.3 (3.0)* 4.2 (3.5) < 2.5 < 2.5 i 2.9 (3.5) < 2.3
$ Zr-95 < 4.8 < 5.6 < 5.3 < 4.7 < 6.2 < 4.6 Mb-95 < 1.9 < 2.3 < 1.9 < 2.0 < 2.2 < 1.8 Co-58 < 2.0 < 2.2 < 1.9 < 2.0 < 2.2 < 1.8 Mn-54 < 2.1 < 2.4 < 2.1 < 2.1 < 2.4 < 2.0 Zn-65 < 5.8 < 6.7 < 5.P- < 6.0 < 6.7 < 5.8 Fe-59 9.2 (6.2) < 6.1 < 5.7 < 4.9 _ < 6.6 < 4.5
< Co-60 < 2.2 < 2.C < 2.2 < 2.1 < 2.6 < 1.9 Ba-140 < 3.3 < 4.0 < 6.4 < 3.4 < 3.9 < 5.5 La-140 < 3.8 < 4.6 < 7.4 < 3.9 < 4.4 < 6.4
- 1.96 o (Due to Counting Statistics)
x Table .II.C,3 Radionuclide Concentrations in Bi-weekly Co@osite of Drinking nfater. (pC1/L) Collection for two weeks ending
~
for two weeks ending for two weeks ending Date- 27 MAR 91 10APR91 24APR91 4 Radionuclide Gilcrest Ft Collins Gilcrest Ft Collins Gilcrest Ft Collins Ro R-3 R-6 R-3 R-6 R-3 1-131 < 0.35 < 0.32 < 0.33 < 0.35 < 0.40 < 0.32 I
-Cs-134 < 2.5 < 2.2 < 1.6 < 1.5 < 2.3 < 1.8 Cs-137 < 3.0 < 2.6 : 4.4 (2.4)* < 1.9 < 2.8 < 2.2 i Zr-95 < 5.6 < 5.0 - < 3.8 < 3.6 < 5.3 < 4.0 Nb-95 < 2.2 < 2.0 < 1.5 < 1.4 < 2.0 < 1.7 Co-58 < 2.3 < 2.0 < 1.5 < 1.5 < 2.1 < 1.7 Mn-54 < 2.5 < 2.1 < 1.6 < 1. 5 2.4 (2.7) < 1.8 l Zn-65 < 7.0 < 6.4 < 4.5. < 4.6 < 6.2 < 5.6 Fe-59 < 5.7 < 4.9 < 4,4 < 3.5 < 5.8 < 4.2 Co-60 < 2.6 < 2.1 < 1.8 < 1.5 < 2.5 < 1.8 Ba-140 < 6.1 < 3.4 < 2.6 < 2.4 < 3.7 < 4.1 La-140 < 7.1 < 3.9 < 3.0 < 2.8 < 4.2 < 4.7
- 1.96o (Due to Counting Statistics)
O L___ _
Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L) Collection for two weeks ending- for two weeks ending for two weeks ending , Date 08MAY91 22MAY91 05JUN91 Radionuclide Gilcrest Ft Collins Gilcrest Ft Collins Gilcrest Ft Collins R-6 R-3 R-6 R-3 R-6 R-3 I-131 < 0.35 < 0.49 < 0.37 < 0.39
. < 0.24 0.52 (0.5)*
Cs-134 < 2.1 < 1.9 < 3.1 < 2.1 3.4 (2.7) < 2.4 Cs-137 3.8 (3.2) < 2.3 < 3.6 < 2.5 < 2.7 < 2.9 0 Zr-95 < 5.1 4.5 (5.3) < 6.6 < 4.4 < 5.0 < 5.6 Nb-95 < 2.0 < 1.7 < 2.8 < 1.8 < 2.1 < 2.1 Co-58 < 2.1 < 1.9 < 2.8 < 1.9 < 2.2 < 2.2 Mn-54 < 2.2 2.7 (2.3) < 3.0 < 2.0 < 2.2 < 2.4 Zn-65 < 5.9 < 5.1 < 8.2 < 5.9 < 6.4 < 6.6 i Fe-59 < 5.1 < 4.5 < 6.9 < 5.0 < 5.2 < 5.7 Co-60 < 2.3 < 1.9 < 3.1 < 2.0 < 2.3 < 2.6 t Ba-140 < 3.5 < 4.6 < 4.8 < 4.9 < 6.3 < 6.4 La-140 < 4.1 < 5.3 < 5.5 < 5.6 < 7.2 < 7.4 i
- 1.96o (Due' to Counting Statistics)
~
5 h
4 Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L) Collection for two weeks ending for two weeks ending for two weeks ending Date 18JUN91 03 jut.91 16JUL91 Radionuclide Gilcrest Ft Collins Gilcrest' Ft Collins Gilcrest Ft Collins R-6 R-3 R-6 R-3 R-6 R-3 1-131 < 0.19 < 0.3 < 0.37 < 0.33 < 0.48 < 0.38 Cs-134 < 1.2 < 2.1 4.0 (4.2) 2.1 (2.4) < 1.2 < 0.96 Cs-137 1.7 (1.7)* < 2.5 4.9 (5.0) 3.8 (2.9) < 1.4 2.2 (1.4)
, Zr-95' < 2.6 < 4.5 < 8.2 < 5.0 < 2.7 < 2.1 Nb-95 < 1.1 < 1.9 < 3.2 < 1.8 < 1.0 < 0.89 Co-58 < 1.2 < 1.9 < 3.1 < 1.8 < 1.1 < 0.97 Mn-54 < 1.2 < 2.0 < 3.4 < 2.0 < 1.2 < 0.96 Zn-65 < 3.3 < .5.5 < 9.1 < 5.4 < 3.1 < 2.6 Fe-59 < 2.8 < 4.8 < 8.8 < 5.0 < 2.6 < 2.2 Co-60 < 1.2 < 2.1 < 3.6 < 2.2 < !.2 < 0.93 I
Ba-140 < 3.4 < 5.5
~
< 7.9 < 4.6 < 1.9 < 1.5 La-140 < 3.9 < 6.3 < 9.1 < 5.3 < 2.1 < 1.7
- 1.96o (Due to Counting Statistics) ,
_________________.____...-.-m -_m
Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCf/L) Collection for two weeks ending for two weeks ending for two weeks ending Date- 26JUL91 13AUG91 '23AUG91 Radionuclide Gilcrest ' Ft Collins Gilcrest Ft Collins Gilcrest Ft Collins R-6 R-3 R-6 R-3 R-6 R-3 I-131 ~< 0.25 < 0.31 < 0.19 < 0.32 < 0.38 < 0.41 Cs-134 a < 1.7 < 2.9 < 1.2 2.8 (2.0) < 2.1 Cs-137 a 3.8 (2.5)* < 3.4 2.4 (1.7) < 2.0 3.0 (3.0) Zr-95 a < 4.3 < 6.3 < 2.8 < 3.5 < 4.7 g Nb-95 a < 1.7 < 2.7 < 1.1 < 1. 5 < 1.9 Co-58 a < 1.6 - 2.9 < 1.1 1.7 (2.0) < 1.9 Mn-54 a < 1.7 < 2.8 < 1.2 < 1.7 < 2.0 In-65 a < 4.8 < 7.9 < 3.2 < 4.6 < 5.4 Fe-59 a < 3.9 < 6.7 < 2.7 < 4.3 < 4.8 Co-60 a < 1.7 < 2.9 < 1.1 < 1.6 2.3 (2.4) Ba-140 a- < 2.7 < 4.6 < Z.1 < 2.6 < 5.0 i La-140 a < 3.1 < 5.3 < 3.6 < 3.0 < 5. 7
- 1.96o (Due to Counting Statistics) a - sample lost prior to analysis ,
~ - . _ _ _ - - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _
Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L) Collection for two weeks ending for two weeks endin9 for two weeks ending Oate- 11SEP91 25SEP91 090CT91 Radionuclide Gilcrest Ft Collins Gilcrest Ft Collins Gilcrest Ft Collins R-6 R-3 R-6 R-3 R-6 R' I-131 < 0.25 < 0.21 < 0.37 < 0.3 < 0.34 < 0.38 Cs-134 < 1.8 < 1.6 < 1.5 < 2.0 < 1.7 < 1.9 Cs-137 2.4 (2.5)* < 1.9 < 1.8 < 2.5 < 2.1 3.5 (2.9) an m Zr-95 < 4.4 < 3.6 < 3.6 < 4.4 < 3.7 < 5.2 Nb-95 < 1.6 < 1.4 < 1.4 < 2.0 < 1. 5 < 1.9 Co-58 < 1.6 < 1.4 < 1.4 < 1.8 < 1.7 < 1.8 Mn-54 1.9 (2.1) < 1.5 < 1.5 < 2.0 < 1.7 2.7 (2.4) Zn-65 < 4.9 < 4.2 < 4.2 < 5.6 < 4.6 < 5.5 Fe-59 < 4.0 < 3.6 < 3.5 < 5.6 < 4.5 < 4.7 j Co-60 < 1.7 < 1. 7 < 1.6 < 2.0 < 1.7 < 2.2 Ba-140 < 5.9 3.4 (3.2) < 5.2 < 6.5 < 2.6 < 3.3 La-140 < 6.8 3.9 (3.6) < 6.0 < 7.5 < 3.0 < 3.8
- 1.96o (Due to Counting Statistics) 6
Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L) Collection for two weeks ending for two weeks ending for two weeks ending Date 230CT91 05NOV91 20NOV91 Radionuclide Gilcrest Ft Collins Gilcrest Ft Collins Gilcrest Ft Collins R-6 R-3 R-6 R-3 R-6 R-3 I-131 < 0.21 < 0.37 < 0.46 < 0.39 < 0.4 < 0.36 Cs-134 < 3.3 < 2.1 < 2.1 < 1.7 < 2.2 < 1.8 Cs-137 < 4.1 < 2.5 < 2.5 < 2.1 < 2.6 < 2.2 -
$ Zr-95 < 7.2 < 4.4 <.6 < 3.7 < 5.1 < 4.0 Nb-95 < 2.8 < 1.9 < 2.0 < 1.6 < 2.0 < 1.6 Co-58 < 3.3 < 1.9 < 1.9 < 1.7 < 2.0 < 1.6 Mn-54 < 3.1 < ?.0 < 2.1 < 1.7 < 2.1 < 1.8 Zn.65 < 9.0 < 5.9 < 5.7 < 4.6 < 6.3 < 5.1 Fe-59 < 7.2 < 5.3 < 4.8 < 4.4 5.3 (6.3)* < 4.1 Co-60 < 3.0 < 2.0 3.8 (2.6) < 1.7 < 2.3 < 1.7 Ba-140 < 5.1 < 4.9 < 3.2 < 4.8 < 3.5 < 2.8 La-140 < 5.9 < 5.6 < 3.7 < 5.5 < 4.0 < 3.2 i
- 1.96o (Due to Counting Statistics) .
4 Table II.C.3 Ra'ionuclide Concentrations'in Bi eekly w Composite of Drinking Water. (pC1/L) Collection for two weeks ending for two weeks ending Date 04DEC91 18DEC91 Radionuclide Gilcrest Ft Collins G1frrest Ft Collins R-6 R-3 i-6 R-3 I-131 < 0.24 < 0.34 < 0.35 < 0.50 Cs-134 < 2.3 < 2.6 < 2.3 < 2.4 Cs-137 < 2.8 < 3.2 6.0 (3.3)* < 2.9 3 Zr-95 < 6.0 < 6.3 < 5.3 < 7.5 Hb-95 < 2.1 < 2.4 < 2.0 < 2.2 Co-58 < 2.3 < 2.4 < 2.0 < 2.8 Mn-54 3.8 (2.8) < 2.6 < 2.4 < 2.5 Zn-65 < 6.3 < 7.2 < 6.1 < 6.5 Fe-59 < 5.3 < 6.2 < 5.3 < 5.8 Co-60 < 2.5 < 2.8 < 2.4 < 2.6 t Ba-140 < 3.6 < 4.3 < 7.5 < 3.9 La-140 < 4.1 < 4.9 1 < 7.5 < 4.4
~~_ .
- 1.96 o (Due t1 Counting Stet.istics) -
- w r ~ ,--
'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 anF downstream sampling locations on both river courses. Table II.C.4 shows tritium conce.itrations measured during 1991 at the four surface water sites and the effluent route site. The arithmetic mean value for the downstream locations in 1991 was not, however, significantly dif ferent from the two upstream locations (Table II.H.2).
- l. ,
l Table II.C.5 shows measurements of fission product and activation product concentrations in surface water samples. collected monthly. There were occasional positive values, but the mean of the downstream sites was not significantly different from the mean of the upstream sites during 1991 for any of-the gamma-ray emitting radionuclides measured. This has been the case since the inception of reactor operations at the Fort St. Vrain site. The occasional positive values are either. fallout Cs-137_, which can be. expected, or values close s, to-the uncertainty-limits and assumed to be false positives. In_ addition-to the monthly sampling of the South Platte River and S t . --V r a i n Creek, a continuous _ water sample it collected at station A-25. An aliquot of the farm pond outlet is sampled every 80 minutes and the composite -collected weekly. The weekly composites are then combined and analyzed monthly. The results of these samples are also shown in-Tables II'. C . 4 and II.C.S. For January through April and t-l
-48
September and- through _ December there was evidence of measurable tritium release (see Table II.C.4). - Mean values r for the other radionuclides were less than MDC except for cc-137. The correlation of the tritium concentrations with the effluent release report is good. t 1 m / 49
Table II.C.4 (pCi/L) Tritium Concentrations in Surface Water. Downstream Sites Upstream Sites Ef fluent S. Platte St. Vrain S. Platte Goosequill Collection St. Vrain F- 19 A-25 Date F-20 R-10 A-21 January < 400 < 400 < 400 < 400 3500 (460)* - February < 410 < 410 < 410 < 410 2300 (450)
< 390 420 (400) < 390 < 390 1100 (420)
March April < 400 < 400 < 400 < 400 430 (420)
< 390 < 390 < 390 < 390 < 400 May
< 390 < 390 < 390 < 390 < 390
$ June
< 380 < 380 < 380 < 380 < 390 July
< 400 < 400 < 400 < 400 < 400 August September < 350 370 (360) 380 (360) 420 (360) 1300 (430)
October < 400 < 400 530 (420) < 400 1000 (430i November 560 (420) < 400 < 400 < 400 8300 (510) f 550 (420) 760 (420) 570 (420) 860 (420) 2000 (450) p December
- 1.96o (Due to Counting Statistics)
x. 2 t Table II.C.5 Radionuclide Concentrations In Surface Water. (pCi/L) Collection Date: 1/12/91 Downstream Sites Upstream Sites Effluent Radio St. Vrain 5. Platte St. Vrain S. Platte Goosequill
-nuclide F-20 R-10 A F-19 A-25 Cs-134 < 2.4 < 2.0 < 3.5 < 2.0 < 1.7 Cs-137 4.4 (3.5)* 3.1 (2.9) < 4.4 < 2.4 < 2.1 Zr-95 < 5.8 5.3 (5.5) < 8.0 < 4.7 < 4.4 Nb-95 < 2.1 < 1.9 3.6 (3.9) < 1.8 < 1.6 Co-58 < 2.3 < 1. 9 < 3.4 < 1.8 < 1. 5 Mn-54 < 2.4 < 2.0 < 3.6 < 2.0 < 1.7 $ Zn-65 < 6.5 < 5.6 < 10.0 < 5.3 < 4.7 Fe-59 < 5.5 < 4.3 < 8.4 < 4.6 < 5.0 Co-60 < 2.6 < 2.0 < 3.5 < 2.2 < 1.6 Ba-140 < 3.9 < 3.2 < 5.7 < 3.3 6.1 (7.3)
La-140 < 4.4 < 3.7 < 6.5 < 3.7 7.0 (8.4)
+1.960 (Due to Counting Statistics) e 4
_ _ . _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ __ - __ o_ _ __ _ _ _ _.._ _ _ _ ___ . _ _ _ _ _ _ . _ _ _ _ _ _
- 3 .
I l Table II.C.5 Radionuclide' Concentrations In Surface Water. (pCi/L) Collection Date: 2/09/91 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 < 1.5 < 3.0 < 2.1 < 2.0 < 1.0 Cs-137 3.1 (2.2)* < 3.6 < 2.6 4.1 (2.9) 2.6 (1.5)
Zr-95 < 3.3 < 6.6 < 4.6 < 4.6 < 2.5 Nb-95 < 1.4 < 2.8 < 1.9 < 1.9 < 0.90 Co-58 < 1.4 < 2.8 < 2.1 < 2.0 < 1.1 Mn-54 < 1.5 < 3.0 < 2.1 < 2.0 1.1 (1.2)
< 2.8 lm Zn-65 < 4.2 < 8.4 < 5.8 < 5.9 Fe-59 < 3.6 < 7.4 < 5.0 < 4.9 < 2.3 Co-60 < 1. 5 < 2.9 < 2.1 < 1.9- < 0.98 Ba-140 < 2.4 < 6.6 < 5.2 < 4.5 < 3.5 l < 4.1 La-140 < 2.8 < 7.6 < 6.0 < 5.1 l
l
*1.96c (Due to Counting Statistics)
j 7
~
Table II.C.5 Radionuclide Concentrations In Surface Water. (pCf/L) Collection Date:.3/09/91 1 Downstream Sites Upstream Sites Ef fluent Radio St. Vrain S. Platte St. Vrain S. Platte Goosequill
-nuclide F-20 R-10 A F-19 A-25 Cs-134 < 1. 2 < 2.2 < 2.6 < 1.3 < 3.3 Cs-137 < 1.5 < 2.7 5.3-(3.7)* < 1.6 6.6 (4.5)
Zr-95 < 2.9 < 4.8 < 5.5 < 2.8 < 8.3 Nb-95 < 1.1 < 2.2 < 2.5 < 1.2 < 3.0 m Co-58 < 1.1 < 2.2 < 2.5 < 1.2 < 3.0
" Mn-54 < 1.3 < 2.2 < 2.5 1.E (1.6) 4.1 (3.8)
Zn-65 < 3.4 < 7.7 < 8.7 < 3.8 < 8.9 Fe-59 < 2.8 ' < 5.1 8.6 (7.6) < 4.3 < 7.3 Co-60 < l.3 < 2.1 <-2.4 < 1.3 < 2.9 Da-140 7.8 (8.8) < 3.6_ < 6.4 < 2.0 < 4.8~ La-140- 9.0 (10) < 4.2 < 7.3 < 2.3 < 5.5
- 1.960 (Due to Counting Statistics) 4
= - ~ . . a. -uw-- - - - +~ -- -
- =.. -- -- - - - - . .- - _ . - - .
. . _ - - - - -_ -_ - - = - . - . -
. +
Table II.C.5 Radicia>011de Concentrations In Surface Water. (pCf/L) Collectim Date: 4/1V91 Downstream Sites Upstream Sites Ef fluent Radio .-St. Vrain S. Platte St. Yrain S. Platte Goosequill
-nuclide F-20 R-10 A-21 F-19 A-25 Cs-134 < 2.2 ' < 3.0 < 2.4 < 3.5 < 2.0 Cs-137 ' < 2.6 < 3.7 < 2.9 < 4.2 < 2.4 Zr-95 < 4.6 < 6.9 < 5.6 < 8.6 < 4.6 Nb-95 < 2.1 < 3.1 < 2.2 < 3.1 < 1.9 Co-58 < 2.0 4.3 (3.5)* < 2.2 < 3.2 < 1.8 Mn-54 < 2.1 < 3.0 < 2.4 < 3.5 < 2.0 Zn-65 < 6.5 < 9.3 < 6.7 < 9.6 < 5.7 Fe-59 < 5.3 < 7.5 < 5.6 < 8.5 < 4.6
$ Co-60 < 2.1 < 3.1 < 2.6 < 3.7 < 2.1 Ba-140 < 3.4 < 6.3 < 5.2 < 5.6 < 3.2 La-140 <-3.9 < 7.2 < 5.9 < 6.5 < 3.7
*l.96a (Due to Counting Sta tis tics)
.- .w..
e' Table II.C.5 Radionuclide' Concentrations In Surface' Water. (pC1/L) . Collection Date: .5/11/91-. Downstream Sites Upstream Sites Effluent ' Radio St. Vrain _S. Platte St. Vrain S. Platte Goosequill
-nuclide F-2C' 'R-10. ~A-21 F-19 A-25 Cs-134 <-2.0 < 1. 5 < 2.4- < 1.8 < 1.2 Cs-137- < 2.4 <-1.9 < 2.9 < 2.2 3.4 (1.7)
'Zr-95 5.5 (5.6)* < 3.3 < 5.6 < 4.2 < 2.5 Nb-95 < 1.8 < 1.4 < 2.0 < 1.6 < 1.0 Co-58 < 1.9 < 1.5 < 2.1- < 1.6 < 1.2 Mn-54 < 2.0 < 1.5 < 2.3 < 1.8 < 1.1 Zn <.5.4 < 4.1 < 6.3 < 4.9 < 3.1 Fe-59 < 4.6 < 3.5 < 6.2 < 4.6
< 3.3 FA Co-60 < 1.9 2.4 (1.8) < 2.5 < 1.9 < 1.1 Ba-140 < 4.8 < 3.5 < 3.8 < 2.9 5.5 (5.1)
La-140 < 5.5 < 4.0 < 4.4 < 3.4 6.3 (5.9)
*1.96o (Due to Counting Statistics)
_.___.______________._____m
iO
- 3. .
Table II.C.5 Radionuclide Contentrations In Sueface Water. (pC1/L) Collection Date: 6/07/91 Downstream Sites Upstream Sites Effluent
-Radio St. '! rain 5. Platte St. Vrain S. Platte Goosequill
-nuclide F-20 R-10 A F-19 A-25 Cs-134 < I .7 < 2.5 < 2.0 < 3.0 < 1.7 Cs-137 < 2.1 < 3.0 < 2.5 4.3 (4.4)* 2.6..(2.4)
'Zr-95 '< 3.7 < 5.4 < 4.7 < 7.0 < 3.0 Nb-95 < 1.6 < 2.3 < 1.8 < 2.7 < 1.5 m Co-58 .< 1.6 .< 2.3
* < 2.0 < 3.0 < 1.9 Mn-54 < 1. 7 < 2.4. < 2.0 < 3.0 < 1.7 Zn-65 < 4.6 < 6.9 < 5.6 < 7.9 < 4.3 Fe-59 < 3.8 c 6.3 8.5 (6.3) < 6.9 < 5.3 Co-60 < 1.7 < 2. 5 < 2.1 < 3.3 < 1.6 Ba-140 < 2.7 < 6.5 < 3.3 < 4.9 < 2.6 La-140 <.3.1 < 7.4 < 3.8 < 5.6 < 3.0
*1.96o (Due to Counting Statistics)
h= j Table II.C.5 Radionuclide Concentrations In Surface Water. (pCi/L) Collection Date: 7/12/91 Downstream Sites Upstream Sites l Effluent Radio St. Vrain. S. Platte St. Vrain S. Platte Goosequill
-nuclide F-20 R-10 A-21 F-19 A-25 Cs-134 < 2.0 < 2.0 < 2.3 < 1.7 < 2.2 Cs-137 < 2.4 < 2.4 < 2.9 2.8 (2.4)* < 2.6 Zr-95 < 4.6 < 4.3 < 5.3 < 3.7 < 5.0 Nb-95 < 1.8 < 1.7 < 2.1 < 1.5 < 1.9 Co-58 < 1.8 < 1.8 < 2.2 < 1.6 < 2.5:
u'
" Mn-54 < 2.0 < 1.9 < 2.3 < 1.7 < 2.2 Zn-65 < 5.4 < 5.4 < 6.3 < 4.5 < 5.7 Fe-59 < 4.6 < 4.6 < 5.3 < 3.9 < 4.9 Co-60 < 2.1 < 1.9 2.7 (2.9) < 1.6 . < 2.3 Ba-140 < 3.2 < 3.1 < 5.4 < 2.7 < 3.5 La-140 ..< 3.7 < 3.5 < 6.2 < 3.1 < 4.0
*1.960 (Due to Counting Statistics)
E
g
' r.
i Table II.C.5 Radionuclide Concentrations In Surface Water. (pCi/L) Collection Date: 8/09/91 I Downstream Sites Upstream Sites Effluent - Radio St. Vrain 5, Platte St. Vrain S. Platte Goosequill
-nuclide F-20 R-10 A F A-25 Cs-134 < 1. 9 < 2.0 < 2.3 < 2.3
< 2.4 Cs-137 3.0 (2.7) * '< 2.4 4.9 (3.3) < 2.9 < 2.9 Zr-95 < 4.1 < 4.2 < 5.2 < 5.3 < 6.6 Nb-95 < 1.7 < 1.8 < 2.0 < 2.1 < 2.2 (n-C0-58 < 1. 7 < 1.8 < 2.1 < 2.1 < 2.2 Mn-54 < 1.9 < 1.9 3.0 (2,5) < 2.3 < 2.4 Zn-65 < 5.2 < 5.6 < 5.9 < 6.4 < 6.3 Fe-59 < 4.3- < 4.6 < 5.3 < 5.5 < 5.6 C0-60 < 1. 9 < 1.9 < 2.4 < 2.5 < 2.6 Ba-140 < 3.0 < 3.1 < 3.8 5.3 (4.5) < 3.9 La-140 < 3.4 < 3.5 < 4.4 6.1 (5.2) < 4.4
*1.96o (Due to Countin9 Statistics)
g y T
~H , .
.u- .
f , Table II.C.5.RSdionuclide Concentrations 11nLSurface Water..(pC1'L)- . / . Collection Date:-9/14/91! - Downstream Sites . Upstream Sites' Ef fluent- , Radio- St. Vrain S. Platte? ' St.'Yrain S. Platte Goosequill
-nuclide F-20 R210 'A-21~ F-19' A-25 Cs-134 < 1.9 < 3.1- <- 2.0 : .< 2.1 < 1.2 Cs-137' '3.8 (2.7)* < 3.7 4.5 (2.9) < 2.5 < 1.4 Zr-95 -<:4.1
< 6.6- < 4.7 - < 4.5 <:2.5 Nb-95 < 1.7- .< 2.7 1. 8 .. < 2.0 < 1.0 -
' (n :
Co-58 ' < 1.7 < 2.8 - < 1. 9 ~ < 1.9 < 1.1 Mn-54 < 1.9 < 2.9
< 2.0- < 2.0- < 1.2 7n-65 < 5.0 < 7.'4 -< 5.4 < 6.0
< 3.1 Fe-59 (.4.3-
'< 6.9_ 7.3 (5.8) < 5. I ' < 2.7 Co-60. 6.8 (2.4) < 3.0- < 2.1. ' < 2.0 '< 1.1 Ba-140 < 4.9 <'4.6 < 4.2
'<'3.3- < 1.8-
.La-140 < 5 .'7 < 5.3 < 4.9' < 3.8' .< 2.0'
*1.96o (Due - to . Coun ti n9 'S ta ti s ti cs )'
1 < 1 e Y
Table II.C.5 Radionuclide Concentrations In Surface Water. (pCi/L) Collection Date: 10/12/91 Downstream Sites Upstream Sites Effluent , Radio St.'Vrain S. Platte St. Vrain. S. Platte Goosequill
-nuclide F-20 R-10 A-21 F A-25 Cs-134 2.2 (2.3)* < 2.0 < 2.4 < 2.2 < 1.1 Cs-137 4.0'(2.7) < 2.5 < 3.0 < 2.6 < 1.4 Zr-95 < 4.4 < 5.0 < 5.6 < 4.7 < 3.4 Nb-95 < 1.8 < 1.9 < 2.1 < 2.0 < 1.1 Co-58 < 1.8 < 2.0 < 2.4 < 2.0 < 1.3 cr- Mn-54 3.2 (2.3) < 2.1 < 2.4 < 2.1 1.6 (1.4)
Zn-65 < 5.3 < 5.4 < 6.6 < 5.9 < 3.1 Fe-59 < 4.3 < 4.6 < 5.6 < 5.3 < 3.8 Co-60 < 1.9 < 2.2 3.2 (3.1) < 2.1 5.0 (1.5)
-Ba-140 <'4.5 < 3.3 < 3.9 < 3.3 < 6.5 La-140 < 5.2 < 3.8 < 4.4 < 3.8 < 7.5
*1.96o (Due to Counting Statistics) r
,,- _ _ _- __ ______.__.__._m_ _ _ _ _ . . - . - _ _ . _ . _ _ _ . _ _ . . _ _ . _ _ _ _
t
. h-Table II.C.5 Radionuclide. Concentrations In Surface Water. (pCf /L)
Collection Date: 11/09/91' 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 <-1.9 < 2.3 < 2.1- < 2.0 < 2.1 Cs-137- 3.3 (2.7)* < 2.8 2.8'(3.0) 3.4 (2.9) < 2.6 Zr-95 < 4.4 < 5.8 < 4.6 < 4.7- < 4.9 Nb < 1.7 < 2.2 < 1.9 < 1.8 < 1.9 Co-58 < 1.9 < 2.3 < 2.1 < 1.9 < 1.9 O Mn-54 < 1.9 < 2.3 < 2.1 < 1.9 < 2.1 Zn-65 < 4.9 < 6.2 < 5.5 < 5.4 < 5.9 Fe-59 < 4.3 < 6.1 < 4.7 < 5.2 < 6.7 Co-60 4.0 (2.4) < 2.4 < 2.0 < 1.9 < 2.3 Ba-140 < 5.8 < 3.7 < 3.3 < 5.0 < 3.4 La-140 < 6.6 < 4.3 < 3.8 < 5.3 < 3.9
- 1.96c (Due to Counting Statistics) u.,.m. w_. - - - -
m e # Table II.C.5 Radionuclide Concentrations In' Surface Water. (pCi/L) Collection Dated 12/14/91 -
-Downstream Sttes Upstream' Sites- Effluent Radio St..Yrain S. Platte St. Vrain S. Platte Goosequill
-nuclide F-20 R-10 A-21 F-19 A-25:
Cs-134 < 2.3 < 2.2 < 2.5 < 2.1 < 2.2 Cs-137 2.9-(3.4)* 6.0 (3.1) < 3.0 < 2.6 < 2.7 Zr-95 < 5.5
' < 5.1 < 5.8 < 4.8 < 5.1 .
Nb-95 < 2.2 < 2.0 < 2.2
< 1.9 < 2.0 cn
'" Co-58 < 2.6 < 2.4 < 2.3 < 1.9 < 2.0 2.7 (2.9) Mn-54 < 2.2' 3.6 (3.1) 2.7-(2.6) < 2.2 I Zn-65 < 6.4 < 5.9- <-6.8 < 5.7 < 6.0 i Fe-59 < 5.4 < 6.8 < 5.7 < 4.8 < 4.9 Co-60 < 2.5 < 2.3 < 2.6 < 2.3 < 2.4 Ba-140 <-3.8 < 3.5 < 4.0
< 3.3 < 3.5 La-140 -< 4.4 < 4.1 < 4.6 <-3.8 < 4.1 *1.'96o (Due to Counting Statistics)
__ ,__m.__ . . _- __ . _ _ . _ _ _ _ _ - . - - -- . _ - - ---
- 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 well at a_ personal residence in the town of Milliken. Table II.C.6 lists the measured concentrations of fission products and activation products in ground water. The Cs-137 results are not surprising due to residue of Chernobyl fallout, and the other results above MDC are assumed to be statistically false positive values. Table II.C.7 shows tritium concentrationis in the same well water samples. The results indicate short-lived cor.tamination of the aquifer supplying F-16 well. This well is not used for drinking water purposes and therefore dose commitment calculations are not ' warranted. Figure II.C.1 shows' measured 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 beginning early in 1991. The mean lifetime of tritium in the F-16 aquifer appears to be very short. See Figure _II.C.2. For comparison purposes:we include Table II.C.8 which lists the Maximum Permissible Concentrations in drinking water from 10CFR20. 1 63
4 Table II.C.6 Radionuclide Concentrations in Ground Water. (pCf/L) 2nd 3rd 4th ist-Quarter 11 MAY 91 Quarter 09 AUG 91 Quarter 09 NOV 91 Quarter 16 FEB 91 Radio- F-16 R-5 R-5 F-16 R-5 F-16 R-5 nuclide F-16
< 2.2 < 1.8 < 2.1 < 2.1 < 2.0 < 2.2 < 2.1 Cs-134 < 3.4
< 2.2 4.1 (3.1) 3.7 (3.1) < 2.4 < 2.7 < 2.6 Cs-137 7.7 (4.6)* 6.5 (3.2)
< 4.2 < 4.8 < 4.7 < 4.7 < 5. 7 < 4.5 Zr-95 < 6.9 < 4.9
< 2.1 < 1.7 < 2.0 < 2.1 < 1.9 < 2.2 < 2.0 Nb-95 < 3.1
$ < 2.0 < 1. 7 < 1.9 < 2.0 < 1.9 < 2.2 < 2.1 Co-58 < 3.1
< 3.1 < 2.2 < 1.8 < 2.1 4.0 (2.6) < 2.0 < 2.2 < 2.1 Mn-54
< 7.5 < 5.1 < 6.5 < 6.3 < 5.6 < 5.8 < 5.8 Zn-65 < 10.0
< 5.2 <43 < 5.0 < 5.1 < 4.6 < 5.0 < 4.8 Fe-59 < 7.8
< 2.2 < 1.7 < 2.2 2.7 (2.4) < 2.1 3.1 (2.7) < 2.1 Co-60 < 3.0
< 4.4 < 2.8 < 3.4 < 3.7 < 3.3 < 6.4 < 3.3 Ed-140 < 6.5
< 5.0 < 3.3 < 3.9 < 4.2 < 3.7 < 7.4 < 3.8 La-140 < 7.5 l
*1.960 (Due to Cour, ting S ta tistics)
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R_ a Figure !!.C.1 ' [ Tritium Concentrations at Location F-16 For 1984-1991 j 10000 'p l l
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Tahir II.C.8 Maximum Permissible Concentrations in Drinking Water. '
'(10CFR20, . Aprendix B, ~ Table ~ II) 11 - 3 . 3 x 106'pCi/L.'
2 I-131 3.x.10 pCi/L 3 Cs-134 9 x 10 pCf/L 4 Cs-137 2 x 10 pCi/L 4 g Zr-95 6 x 10 pC1/L Hb-95 1 x 10 pC1/L 5 Co-58 1 x 10 pCi/L l 5 Mn-54 1 x 10 pCi/L 5 Zn-65 1 x 10 pCi/L l Fe-59' 6 x 10 pCi/L 4 Co-60 5 x 10 pCi/L Ba-140 3 x 104 'pCf/L
.La-140 2 x 10* pCi/L t
l'
'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 infant consuming milk produced from cows grazing local pastures. Milk is the critical pathway E 3r possible dose commitment to humans from environmental contamination of H-3. I-131, Cs-137- and Sr-90. For this reason milk is sampled extensively to document the presence or absence of radioactivity due to reactor operations. A three liter milk sample is counted for determination of- Cs-137, Cs-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 Mellor, Health Physics 38: 203-213, 1980.
There - are no dairies (or personal milk cows) in the
; facility' 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 (refer- to updated FSAR). The description of these locations can be found in Table 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 o n ' p ". a t u r e - b u t under dry-lot management typical of EatTcern Colorado.
69
-- = . -
r Table II.D.1 lists the concentrations of all radionuclides that-are investigated in milk samples. During 1991, elevated concentrations of I-131 were again consistently ' observed only at site A-22. The source of this I-131 is from nuclear medicine thyroid therapy practice in the Denver 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 (Independence) 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 t l describing this observation and the magnitude of the I-131 l concentrations has been submitted for publication in the Health Physics Journal. Note that A-22 drops out of the sampling program each year in order to meet milk collection Y 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 controlled and independent of K intake. K-nat is measured -in - all milk samples as a quality control measure for the other radionuclides determined . l-in the same sample by gamma-ray spectrometry, but K-nat concentrations are no longer reported in Table II.D.1. t Table II.D.2 lists measured tritium concentrations in milk. Significant elevated tritium concentrations in milk due L to reactor effluents have never been observed during the oper.ational or defueling phase of the reactor. This implies 7 d
the. tritium from_ reactor effluents is not contributing any radiation dose to huinans via the milk pathway. Tritium conce'ntrations 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
- ' t ; 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 effluents has never been observed during the operational or defueling phases of Fort St. Vrain.
!~ t-l 71
v Table II.D.1 Radionuclide Concentrations In Milk. (pCf/L). A-23 A-24 A-26 R-8 LOCATIDH A-6 A-18 A-22 h 1/05/91 1/12/91 1/12/91 1/12/91 Collection Date 1/12/91 1/05/91
< 0.33 < 0.43 < 0.21 < 0.5 1-131 < 0.49 < 0.29 h l
< 2.7 < 3.5 < 1.7 < 2.3 Cs-134 < 2.1 < 2.1 h
< 3.2 < 5.1 4.1 (2.9)* < 3.5 Cs-137 < 2.6 < 2.5 h
< 4.3 h < 4.2 < 5.1 < 3.3 < 3.5 Ba-140 < 3.4
< 4.9 h < 4.8 < 5.9 < 3.8 < 4.0 ld-140 < 3.9 2/09/91 h 2/02/91 2/09/91 2/09/91 2/02/91 Collection Date 2/09/91
< 0.4 h < 0.25 < 0.44 < 0.23 < 0.17 M I-131 < 0.35
< 2.5 < 3.4 < 2. 3 < 3.7 < 2.4 Cs-134 3.0 (2.8) h
< 3.5 < 3.1 h < 4.9 < 3.3 < 4.4 4.2 (4.1)
Cs-137
< 3.4 < 5.1 h < 4.7 < 4.2 < 5.9 < 4.2 Ba-140
< 5.9 < 5.5 < 4.9 < 6.8 < 4.8 ta < 3.9 h
___. -140 3/09/91 3/02/91 3/02/91 3/09/91 3/09/91 3/02/91 Collection Date 3/02/91
< 0.46 < 0.27 < 0.4 < 0. 5 < 0.41 < 0.48 1-131 < 0.31 2.5 (2.8) < 2.5 < 2.4 < 4.0 < 2.3 < 2.7 Cs-134 < l.5 2.3 (2.3) < 3.4 < 3.6 < 3.5 < 5.9 3.6 (4.0) 4.4 (3.9)
Cs-137
< 2.5 < 3.4 < 3.5 9.4 (5.3) < 5.9 < 4.6 < 4.3 Ba-140
< 3.9 < 4.1 11.0 (6.1) < 6.8 < 5.3 < 5.0 La-140 < 2.8 h - sample not collected (at dairy owner's request)
- 1.96c (Due to Counting Statistics) t_ _ _ _ _ _ _ _
u Table II.D.1LRadionuclide Concentrations In' Milk.- (pCi/L). .- LOCATION 'A-6 A A-22' 'A-23 .A-24 .A-26 R-8 Collection Date. 4/06/91: :4/13/91- ~ 4/06/91' 4/06/91 4/13/91- 4/13/91: ;4/06/91 1-131 < 0.31' < 0.45 < 0.37 < 0.45'- .< 0.5 < 0.35 <'0.37-Cs-134 < 2.3 < 2.4: < 2.3~ < 2.5L < 2.6i ~< 2.3- J< ' 2.4' Cs-137 < 3.5 < 3.71 5.9 (4.0) < 3.1 < 3 . 2 .- < 3.5- ,< 3.5 -
~Ba-140 4.0(417)* < 4.3 < 4.3 .< 4.0 < 4.9 < 4.3- < 4.4 La-140 4.5 (5.4) ' < 4.9 < 5.0 < 4.6' < 5.6' < 4.9. < 5.0 Collection Date 5/04/91- 5/11/91 -5/04/91 5/04/91- 5/11/91 5/18/91- 5/04/91 1-131 0.48 (0.53) < 0.28 2.3 (0.65) ,< 0.41 < 0.48, < 0.19- < 0.34 U Cs 134 < 2.5 < 2.3 2.8-(3.1) < 2.6 < 2.5 < 2.7 < 2.3 Cs-137 ^< 3.1 < 3.4 < 3.1 4.2 (3.7) < 3.1 < 3.2 < 3.5 i Ba-140 < 4.1 <.4.2 < 5.3 < 4.1 < 4.0 < 4.3 4.6 (5.3)
La-140 < 4.7 <.4.8 < 6.1 < 4.7 < 4.6 < 4.9 5.3 (6.1) Collection Date 5/18/91 5/25/91 5/18/91 5/18/91 5/25/91 5/25/91 5/18/91 ! I-131 < 0.'32 < 0.35 < 0.47 < 0.29 < 0.43 < 0.43 < 0.5 Cs-134 < 2.2 < 2.2 2.4 (2.3) 2.2 (2.6) < 2.4 < 2.4 < 1.8 Cs-137 < 3.2 < 3.2 3.1 (2.7) <.3.2 e 3.0 < 2.8 2.6 (3.1) q
< 4.4 < 3.1 < 3.1 < 3.1 < 4.0 < 3.7 < 3.7 Ba-140 La-140- < 5.0 < 3.6 < 3.5 < 3.6 < 4.5 < 4.3 < 4.2 4
- l.96o (Due. to Counting Statistics.)
Table II.D.1 Radionuclide Concentrations In Milk. (pCi/L). LOCATION A-6 A-18 A A-23 A A-26 R-8
~
Collection Date 6/01/91 6/07/91 6/01/91 6/01/91 6/07/91 6/07/91 6/08/91 1-131 < 0.3 < 0.3 2.1 (.62)* .< 0.3 < 0.4 < 0.5 0.4 (.43) Cs-134 < 2.2- < 2.3 < 3.6 < 2.3 < 2.8 < 3.1 < 2.3 Cs-137 < 3.3 < 3.4 < 5.1 < 3.3 5.6 (5.0) < 3.9 < 3.4 Ba-140 < 3.2' < 4.4 < 6.4 < 3.3 < 4.t < 5.1 < 4.2 La-140 < 3.6 < 5.0 < 7.4
. < 3.8 < 4.8 < 5.9 < 4.8
" Collection Date 6/14/91 6/21/91 h 6/14/91 6/21/91 6/21/91 6/21/91 I-131 < 0.35 < 0.49 h < 0.45 < 0.33 < 0.18 < 0.36
% Cs-134 < 2.5 < 2.0 h < 2.5 < 2.0. < 2.0 < 1.5 Cs-137 < 3.0 c 2.4 h < 3.0 < 2.9 < 2.9 < 1.8 Ba-140 < 4.1 < 3.1 h < 5.0 < 6.5 < 2.8 < 3.6 La-140 < 4.8 .< 3.6 h < 5.7 < 7.5 < 3.2 < 4.1 Collection Date 7/12/91 7/12/91 h 7/12/a1 7/12/91 7/19/91 7/12/91 1-131 < 0.49 < 0.34 h < 0.27 < 0.19 < 0.2 < 0.34 Cs-134 < 2.4 < 1.9 h < 2.1 < 2.5 < 2.5 < 2.7 Cs-137 < 3.6 < 2.8 h 4.9 (3.0) < 3.1 < 2.9 <-3.3 Ba-140 < 3.5 < 2.7 h < 3.3 < 4.1 < 3.9 < 4.8
-140 < 4.1 < 3.2 h < 3.8 < 4.7 < 4.5 < 5.6
- 1.96o (Due to Counting Statistics) h - sample not collected (at dairy owner's request) 1 ?
u _ _ -- . - - -
. 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 7/19/91 '7/26/91 h 7/19/91 7/26/91 7/26/91 7/26/91 1-131 < 0.36 - .< 0.4 h < 0.42 < 0.44 < 0.2 '< 0.5 Cs-134 y2.4 < 2.4 h < 2.3 < 2.3 < 2.3 3.1 (2.7) Cs-137 4.1 (3.6)* 4.2 (3.5) h < 3.3 < 3. 3 < 3.4 3.7 (3.8) Ba-140 ' < 4.8 < 5.0 < 3.7 < 4.5 < 3.4 < 3.2 h La-140 < 5.5 < 5.7 h < 4.2 < 5.2 < 3.9
. < 3.6 Collection Date 8/09/91 8/02/91 h 8/09/91 8/09/91 8/09/91 8/02/91 y 1-131 .< 0.47 < 0.41 h < 0.43 < 0.2 < 0.44 < 0.22 Cs-134 < 2.3 < 2.0 h < 1.9 < 2.0 < 2.6 < 3.3 Cs-137 3.5 (4.1)- 3.7 (2.9) h 4.1 (3.3) 3.5 (2.9) < 3.1 5.3 (5.9)
Ba-140- < 3.3 < 3.9 h < 3.5 < 3.2 < 4.2 < 4.9
< 3.8 La-140 < 4.5 h < 4.0 < 3.6 < 4.8- < 5.6 Collection Date 8/16/91 8/23/91 h 8/16/91 8/23/91 8/31/91 8/16/91 1-131 < 0.2 < 0.48 h < 0.29 < 0.22 < 0.16 < 0.18 Cs-134 < 2.0 < 2.3 h < 2.3 < 2.5 < 2.2 < 2.1 Cs-137 < 2.9 5.6 (4.0) h 6.4 (4.1) < 3.1 3.6 (3.2) < 2. 7 Ba-140 < 2.8 < 3.7 h < 3.4 < 4.4 < 3.5 < 3.6 La-140 < 3.2 < 4.2 h < 4:0 < 5.1 < 4.0 < 4.2
- 1.96o (Due to Caunting Statistics.) .
h - sample not collected (at dairy owner's request) .
& ~.
h[ ?DX &% ~ ' ' V2 ,r Q= s , Table 11,0.1 Radionuclide concentrations la Milk. iptfit). A-23 A-2A A-2E R-8 LOCATION A-6 A $8 A-22 h 9/07/91 9/21/91 9/14/91 9/14/91 l Collection DMe : 9/n7bl 9/14/91
< 0.4 < 0.5 h < 0.3 < 0.3 < 0.2 0.5 (.49)
I-131
< 2.0 < l.1 < 2.3 < 2.3 Cs-134 < 2.3 < 2.5 h
< 3.0 h < 2.9 1.6 (1.9) < 3.4 < 3.3 Cs-137 < 2.9
< 4.0 h < 3.7 2.2 (2.5) < 3.4 < 3.4 Ba-140 < 3.7'
< 4.3 < 4.6 h < 4.3 2.5 (2.9) < 3.9 < 3.9 La-140 h 9/21/91 9/28/91 9/28/91 9/28/91 Collection Date 9/21/91 9/28/91
< 0.22 h < 0.44 < C.5 < 0.48 < 0.48 1-131 < 0.32
< 2.4 h 1.2 (1.4) < 2.4 < 2.6 < 2.4 5 Cs-134 < 2.4
< 3.5 < 3.5 h 1.9 (1.7) 5.6 (4.1) < 3.1 3.5 (3.4)
Cs-137
< 3.4 < 2.6 < 3.4 < 4.2 < 4.5 Ba-140 < 4.5 h
< 3.9 h < 3.0 < 3.9 < 4.8 < 5.1 La-140 < 5.2 10/05/91 h 10/09/91 10/12/91 10/12/91 10/19/91 Collection Date 10/05/91 h < 0.44 < 0.49 < 0.39 < 0.31 1-131 < 0.26 < 0.'
<z0 h < 2.5 < 2.6 < 2.7 < 2.0 Cs-134 < 2.7
< 3.2 < 3.0 h < 3.0 < 3.6 < 3.2 2.9 (3.0)
Cs-137
< 4.3 7.5 (5.3) h < 3.9 < 3.7 < 4.2 < 3.3 Ba-140 8.5 (6.1) h < 4.5 < 4.3 < 4.8 < 3.8 J, La-140 < 5.0
- 1.96o (Due to Counting Statistics) h - sample not coll:cted ;' dairy owner's request)
I
- Table II.D.1 Radionuclide Concentrations 'In Miik. (pCi/L). ,
LOCATION A-6 A *8 A-22 'A-23 A-24 A-26 R-8 : Collection Date 11/02/91- 11/02/91- 11/02/91' 11/02/91- 11/09/91 11/09/91 '11/09/91
.-131 0.47 (0.53)* < 0.39' h < 0.5 < 0.3 < 0.2 < 0.32 Cs-134- < 2.4 < 2.5 h < 2.2 - < 1.8 < 4.1 < 3.4 Cs-137' < 3.4 < 3.0 h < 3.3 3.6 (3.1) < 5.8 < 4.9 Ba-140' < 4.2 < 3.9 h < 3.2 < 2.6 < 6.0 < 4.9 La-140 < 4.8 < 4.5 h < 3.7 - < 2.9 < 6.9 < 5.7 ;
i Collection Date 12/14/91- 12/07/91 12/07/91 12/07/91 12/14/91 12/21/91 12/14/91 ' 1-131 < 0.33 < 0.34 h < 0.34- .< 0.46 < 0.44 < 0.33 Cs-134 < 2.5 < 2.4 h < 2.9 < 2.5 3.1 (3.2) < 1.5 ! Cs-137 -< 3.0 < 2.9 h < 3.4 < 3.0 < 3.2 3.2 {2.2) Ba-140 < 3.9 < 3.9 h < 4.6 < 4.1 < 4.3 '< 2.5 - La 'A0 < 4.5 < 4.5 h < 5.3 < 4.7 < 4.9 < 2.8 ' t
- 1.96o (Due to Counting Statistics) -
h - sample not collected (at dairy owner * , request) .
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T < < < < < < < < < < < < < < t t o 2 eu n D. n D e o Y R R ( l I i E E p _ I t Y R B B o m c R A - T T M M 6 a . l e e l e A U U R H C L I E E Y Y S U S U E T E T 9 s b l t N B R R Y Y N N L L G G P P 1 - _ a oa A E A P A A U U U U U U E E T CD J F M A M M J J J J A A S S
- h u
y Table II.D.2 Tritium Concentrations in Milk. (pC1/L) 1991 Adjacent Sites Refererce Collection Date A-6 - A-18. A-22 A A-24 A-26 R-8~ OCTOBER 500 (410)* 830 (420) h 600 (410) < 400 '< 400 < 400 fl0VEMBER '< 400 < 400 'h 570 (420) < 400 < 400 < 400 DECEMBER- 570 (420) < 400 -h < 400 540-(420) 490 (420) 790 (420) I! i i
- 1.96. (Due to Counting Statistics) * !
h - sample not. collected (at dairy owner's request)- , i %. , , '-~6- v--* - _ 4- - . _ _ _ _ _ _ _ _ _ _ - _ _ - - - - - - - - - - - - - . . - - - - - - - - - . - - - - - - - - _ --- --
II.E. Food Products , Food sampling -locations were selected from areas possibly irrigated by surface 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. Locatjons and available ; produce of ten change due to owner steeds, harvest time, harvest l 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 1991 harvest. Two of the food samples showed detectable Cs-137 from past Chernobyl fallout i deposition and the one result with positive I-131 is assumed to be a false 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. 1-131 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 observed, presumably due to surface L
soil deposits. 80
- f
1 : :! # ! ;;[ t! I! ;ir a 5 > L'
)
) )
g 7 0 6 _ k 3 0 0 0 0 0 -
/ 1 8 9 2 8 -
f - 4 ( 7 0 ( 0 C s 1 7 1 1 8 1 _ p C 0 0 ( < < < < < < 2 1 s 1 3 t c u _ d _ _ o ) r 0 P 4
- 3 0 4 0 d 1 5 5 1 9 3 9 .
o - 2 ( 2 o s 1 6 5 6 1 7 6 F C 0 i n 7 1 s n - i o *
) .
t 0 ) a s r 1 0 0 6 0 0 0 c k 3 1 8 8 i n 1 1 2 7 ( 2 1 1 t e 9 - 1 1 1 6 1 2 6 s c / I 0 i n 4 < < < < < <
< t o 2 7 a .
_ C / 1 t 9 S e . _ d e S g i t R n l a N E i c D E O P t u P L P n , n n e U S S L E u . o o p O E E E P S o i i y L O 0 M R S C d t T A T 1 R I E N a c T A A E L N P O o - R e d N T M T I R P I t l o A O D A H O E N 1 l o C P T W C C P O e o F u C D E. ( _ I n I i o o 6 e t 9 a J l b a c o 8 9 7
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2- .. 29 8 0 3 1 3 2 1 1 A A A A A _ T L A A R + r
... ... - . - - . - - - - . . ~ - . - -..-.- - - --..--~.-.~ ~ . - . _ -
-+
l l II . F . - Aquatic Pathways Table II.F.1 shows radionuclido concentrations measured ' in fish samples collected at F-19, A-25 and R-10 on two dates ! in 1991. The fish were collected by shocking and netting and l the composite sample was homogenized without cleaning and analy*ed on a wet weight basis. The positive values of co-137 l were assumed to be due to fallout. l Table II.F.2 shows the measured concentrations of both { Ce-137 and Cs-134 in surface sediment collected at R-10, the i downstream location. There was measurable activity of Cs-137 clearly due to the Chernobyl fallout. The cesium ions are beund nearly irreversibly by the clay mineral matrix in the , sediment. The concentrations observed in 1991 were statjstically the same as observed in 1990. observation -for p.m hirala fluminna, 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 ! 1 Asia.- The freshwater clams are now found in large river systems in 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 hava indicated no evidence of Corbicula at any ; L of the sampling sites of the reactor surface water coursos, i 1 j1 L:- I j; 82 l V M- W 'TT --PV-54 V,17wWm se M-y ~ 41 WP--.wr - if e- g- qyry, -rr'-NY'W'S-J
^ - Table II.F.1 Radionuclide Concentrations in Fish. (pC f /kg) Collection Date First Half Second Half Upstream E f fluent Downstream Upstream Ef fit:ent Downstream Radionuclide F-19 A-25 R-10 F-19 A-25 R-10 Cs-134
- < 5.6 < 4.3 < S.7 < 5.5 < 6.0 < 6.3 Cs-137
< 6.6 < 5.2 < 6.7 < 6.2 7.2 (8.4)* 16.0 (8.2) i
- Co-58
!- < 5.8 < 4.5 < 5.8 < 5.0 < 5.4 < 6.3 Mn-54
< 5.6 < 4.3 < 5.7 < 5.2 < S.8 < 6.0
$ In-65
< 16.0 < 12.0 < 16.0 < 15.0 < 17.0 < 21.0 {
Fe-59
< 8.8 < 8.4 < 9.1 < 8.8 < 15.0 < 10.0 Co-60
- < 6.1 < 4.4 < 6.0 < 5.7 < 6.2 < 6.9
- 1.96o (Due to Counting Statistics)
I b e,- _ _ -r - e . - - ,mm _ _ . - - - _ - _ . - - - - _ - - - - - - - _ - - - - . - - _ . _ _ . . _ _ . . _ - . - - - . _ . . . - . . - - -
- o; 1 i
l II.F.2 l RadionJclide Concentrations in -Sediment from location R10. (pCi/kg) Radionuclide Collection Date 6/28/91 Cs-134 < 10.0 Cs-137 54.0 (12.0)
- j Radionuclide Collection Date 10/19/91
.. Cs-134 < 11.0 Cs-137 83.0 (13.0)-
1.96o (Due to Counting Statistics) 4 F F I l. i 84 i L 1 J
, . . .. . - ~ - . - - - - . - . - . _ - - - . . - _ . . . . - . . . - . - . _ . .
l 4 j i
.T.I.G. Samplo 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 studioc program is the principal crosscheck. This involves the analysis of a variety of environmental media containing various leveln of radionuclides. The media, type of analysis and frequency of analysis for the EPA program are summarized below. .- lipJillun Analysis (radionuclide) Freauency Water 11 - 3 Triannually Water Gross beta, gross alpha Semiannually Water Co-60, Zn~65, Cs-13 4, Co-13 7 Triannually Water I-131 Somiannually , Air partic- Cs-137, gross beta, Stmiannually 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 noted that during 1989, our laboratory became certitied by the EPA for drinking water analysis. Table II.G.1 gives the EPA crosscheck data for 1991. The EPA uses the parameter, Estimated Laboratory Precision (ELP), calculated as one standard deviation for one datermination. 85
i l 1 l The normalized deviation of our mean from the known is calculated as: CSU mean value - EPA knpyn valva o/n Wheret o = standard deviation of the mean of all participating laboratory results n = number of analyses by our .aboratory, normally n=3 , The control limit is determined by the mean range of all results and three standard deviations of the range. If any result exceeds two standard deviations from the mean (warning level), the result is unacceptable. Whenever our mean value falls outside this limit, the calculations are rechecked and the sample reanalyzed if possible. During 1991 all results except 13 were within the warning level. The resulte exceeding the warning level have the notation (n) in Table II.G.I. Table II.G.2 lists independent results for H-3 in water samples split between this laboratory and the laboratory at the Fort St. Vrain Generating Station. The comparison between - laboratories in general was acceptable. ,
' Table II.G.3 lists the results of gross beta analyses of the split water samples. The procedural differences between ,
l 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 i' crosscheck program. Replicate samples are independently analyzed. The- replicate results are- not statistically l 1 l' 86
+
.x different and imply that the precision of the methods is acceptable. During 1991 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 often recalculated by hand and those done during 1991 were all verified to be correct. , I b v 9 h 9 87
Tablo ll.G.1 EPA Cecus* Check Dato $umesry. 1991. Radio- CSU EFA 1 E.L.P.* Wormalized Deviation Date suclide Value Value f rcn kno.sn** WA1EP TRIT 1DM spCl/L) Feb 22 M3 4367 4418 442 0.20 Jun 21 H3 12000 124B0 1248 0.67 Oct 18 M3 2700 2454 352 1.21 WATER, Alpha /Jeta (pci/L) Jan 25 alpha 10.33 5.0 $.0 1.83 beta 5.67 5.0 5.0 0.23 May 17 alpha 11.67 24.0 6.0 3.56 (1) beta 29.00 46.0 5.0 5.89 (2) Sep 20 alpha 14.00 10 3 5.0 1.39 beta 15.00 20 3 5.0 1. 73 WATER, 1 131 (pCl/L) Feb 15 1 131 77.67 75.0 8.0 0.58 Aug 09 I 131 18.67 20.0 6.0 0.34 WATER, Perfornance (pci/L) Apr 16 alpha 23.67 54.0 14.0 3. 75 (3) beta 102.00 115.0 17.0 1.32 Cs 134 43.33 24.0 5.0 6.70 (4) Cs 137 48.33 25.0 5.0 8.La (5) Oct 22 alpha 81.00 82.0 21.0 -0.D8 bets 45.00 65.0 10.0 3.46 (6) Cs 134 10.67 10.0 5.0 0.23 Cs 137 15.67 11.0 5.0 1.62 WATER, Gamma (pcl/L) Feb 8 Co 60 38.33 40.0 5.0 0.58 Zn 65 133.00 149.0 15.0 1.85 Cs 134 4.67 8.0 5.0 i.15 Cs 137 10.67 8.0 5.0 0.9i Ba 133 16.33 75.0 8.0 12.70 (7) Jun 07 Co 60 9.00 10.0 5.0 0.35 2n 65 83.00 108.0 11.0 3.94 (8) Cs 134 11.67 15.0 5.0 1.15 Cs 137 15.33 14.0 5.0 0.46 Ba 133 16.33 62.0 6.0 -13.io (9) Oct & Co 60 21.33 29.0 5.0 2.66 2n 65 42.67 73.0 7.0 7.51 (10) Cs 134 7.67 10.0 5.0 0.61 Cs 137 10.00 10.0 5.0 0.G0 Ba 133 83.67 98.0 10.0 2.48 i I
- E.L.P. = Expected laboratory precision.
** Wormalized deviation s (CSU mean EPA known)/(dn); if this value falls between upper & lower warning levels, the accuracy is acceptacle.
88 l
Table II.G.1 EPA Cross Check Data Summary, 1991. (contiroed) Radio
- CSU EPA 1 E.L.P.* Wormalized Deviation Date ruclida Value Value f rorn known**
MILK (pCf/L) Apr 26 l 131 73.33 60.0 6.0 3.85 (ii) ca.137 52.33 49.0 5.0 1.15 K 40 1521.67 1650.0 83.0 2.68 (12) AIR FILTERS (pC1/L) Mar 29 alpha 22.67 25.0 6.0 0.67 beta 124.00 124.0 6.0 0.00 Ct 137 99.00 40.0 5.0 20.44 (13) Aug 30 alpha 22.67 25.0 5.0 0.67 bets 90.33 92.0 10.0 0.29 C4 137 30.67 30.0 5.0 0.23 I i
- l
- E.L.P. = fapeeted Laboratory precision.
" NormelIZed A. ' ation a (CSU mean EPA known)/(a[n), if th{s value f aits between upper & tower warning levels, the accuracy la acceptable. 89
.. _ h l 1
' Tame II .G.2 ,
Tritium Crosscheck Analyses on Split Water samplen Determined by Colorado state University and P4Lic SeryIce Company. 1991 , Collection Sanple Tritita Concentrations pct /L t Date Location CSU PSC 4 Jan 12 A 25 3500 (460)* 3970 (506) Jan 12 A 21 <400 <366 Jan 2 E 41 <400 <366 f Feb 09 A-25 2300 (450) 2620 (476)
.Feb 09 A 21 <410 <355 ,
Feb 13 E 41 <400 <358 Mar 09 A 25- 1100 (400) 1620 (456) Mar 09 A 21 <390 <355 Mar 13 E 41 <390 <355-Apr-13 A 25 690 (400) 1400 (448) Apr 13 A 21 <400 <352 Apr 03 E 41 <400 523 (432) ,
'May 11 A 25 <400 <352
. May 11 A 21 <390 <352 May 08 E 41 <400 <352 Jun 07 A 25 <390 <361 Jun 07 A 21 <390 <361 Jun 05 E 41 <390 <361 Jul 12 A 25 - < 390 <347 Jul.12 A 21 < 380 358 Jul 03 E-41 < 380 <347 Aug 09 A 25 < 400 <3f7 Aug 09 A 21 < 400 <35/-
Aug 07 E 41 < 400 <357 Sep 14 A 25 1500 (380) 911-(457) Sep 14 A 21 3A0 (360) <368 Sep 04 E 41- < 400 <368 Oct 12 A 25 1400 (430) 838 (446) Oct 12 A 21 530 (420) 586 (442) Oct 02 E-41 < 400 - 392 (438) Nov 09 A 25 5700 (480)- 5900 (525)- Nov 09 A 21 -< 400 <357-Nov 06 E 41 450 (410) <357
'Dec 14 A 25 2300 (450) 1730 s459)
Dec-14 A 21 570 (420) <357 Dec 04 E 41 < 400 <357 l l
- 1.960 (Due to C unting Statistics.)
-90' .
. . _ . _ . _ _ _ _ _ . _ _._m_ _ _ . . .._ _
Table !!.G.3 Gross Beta Crosscheck Analyses an Split Water Samples Determined by colorado State university and Public Service Company of Colorado. 1991 Collection Sanple Gross Beta Concentrations pCl/L Date Location CSU PSC Jan 12 A 25 14 (5.9)* 24.00 (8.00) Jan 12. A 21 9.2 (5.7) 14.00 (7.00) Jan 2 E 41 11 (5.7) 15.00 (8.00) Feb 09 A 25 19 (6.2) 11.70 (6.96) Feb 09 A 21 16 (6.0) 8.16 (6.70) Feb 20 E 41 15 (5.9)- 12.00 (6.89) Mar 09. A 25 18 (6.1) 8.45 (6.61) Mar 09 A 21 19 (6.2) 12.40 (6.92) Mar 13 E 41 18 (6.0) 7.49 (6.58)
-Apr-13 A 25 22 (6.4) 20.30 (7.15)
Apr 13 A 21 13 (5.9) 12.50 (6.79). ! Apr 03 E 41 13 (5.9) 12.10 (6.63) e May 11 A 25 20 (6.2) 16.80 (6.82) May 11 A 21 12 (5.9) 13.30 (6.75) May 08 E 41 11 (5.8) 15.30 (6.79) Jun 07 A 25 11 (5.8) < 5.46 Jun 07 A 21 9.7 (5.7) 9.09 (7.06) Jun 05 .E 41 5.3 (5.5). 5.13 (6.89)- Jul 12 A 25 19 (6.1) 16.70 Jul 12 A 21 14 (5.9) 7.94 Jul 03 E 41- 2.8 (5.4)- 11.20 Aug 09 A 25 -14 (5.9) -9.36 Aug 09 A 21 12-(5.9) 12.90 Aug 07 E 41 7.9 (5.6) 10.60 Sep 14 A 25 10 (5.8) 19.30 (7.12) Sep 14 A 21 13 (6.0) 15.50 (7.03) Sep 04 E 41 9.9 (5.8) 14.50 (6.87) oct 12 A 25 10 (5.8) 9.19 (7.30) oct 12 A 21 9.6 (5.8) <5.82 oct 62 E 41. 10 (5.8) 11.00 (7.52) l Nov 09 A 25 17 (6.1) <5.40 l Nov 09 A 21 9.5 (5.8) 8.91 (7.04) ) Nov 06 E 41 12 (5.8) 13.70 (7.26) Dee:14 A 25 9.1.(5,7) 9.85 (6.64) Dec 14. A 21 9.8 (5.8) 11.90 (6.81)
'Dec 04 E 41 11 (5.8) 11.60 (6.71)
- 1.960 (Due to Counting Statistics.)
i b 91 _. -- .
c
'lable II.C.4 Int rainteratory Cross-Check Result s. (pCf /1.) .
(Rep 1Icate .%alysis of Sa tw* Sa sple) - lit inkin g Water i'ad to- _Ist Quarter 2nd Quarter 3rd Quarter 4th Quarter nuctIde A B' A B A B A D Cs-134 <2.I <2.2 3.4,(2.7) <2.7 <2.9 <2.1 <l.9 <2.2 Cs-137 .<2.5 5.6 (3.1)* <2.7 <3.3 <3.4 3.7 (2.9) 3.5 (2.9) <2.7 Zr-95 <5.3 <4.7 <5.0 <7.0 <6.3 <4.4 <5 2 . <5.3 Hb-95 <l.9 <2.1 <2.1 <2.4 <2.7 <1.8 <l.9 <2.1 ' Co-58 <l.9 <2.3 <2.2- <2.8 <2.9 <2.1 <l.8 -:2.2
!!n-54 <2.1 <2.3 <E.2 <2.8 <2.8 <2.1 2.7 (2.4) 2.5 (2.7)
Zn-65 <5.8 <6.5. <6.4 <7.2 <7.9 <5.5 <5.5 <5.9 - Te-59 <5.7 <5.0 <5.2 <7.3 <6.7 <4.7 <4.7 <5.3 l g Co-60 <2.2 <2.1 <2.3- <2.9 <2.9 <2.0 <2.2
<3.3
<2.4
<3.7 Ba-140 <6.4- <3.5 <6.3 <4.4 <4.6.. <3.1 La-140 <7.4 <4.1 <7.2 <5.1 <5.3 <3.6 3.8 <4.2 i Gross Beta 5.6 (2.4) 6.0 (2.4) 4.0 (2.3) 5.6 (2.5) 3.4 (2.3) 3.1 (2.3) 13 G.8) 11 (2.7) 11 - 3 <400 <400' <400 <400 <390 <390 <400 < @)
i tiLik i nadio- 1st Quarter 2nd quarter 3rd Quarter 4th Quarter nue1ide _A _ B A B A B A _b_
.I Cs-134 <2.3 <2.4 <2.5 <2.3- <2.3 <2.3 <2.0 <2.2 Cs-137 5.9 (4.0) <2.9 <3.0 <3.3 3.5 (4.1) 5.2 (3.3) 2.9 (3.0) <3.2 Ba-140 <4.3 <3.8 <4.1 <4.2 <3.3 <3.7 <3.3 <3.1 ;
La-140 <5.0 <4.4 <4.8 <4.9 <3.8 <4.3 <3.8 <3.6 11- 3 <400 <400 <400 <400 <390 <390 <400 <400 g.gr..es .c we wmeaM+ m.-m ew
- 1.960 (1?oe 1o Cotintin g S tat istics.) - l
. m 'y ,~ ~ , , , . . , , , , w-~ w ,, - . , - - - _~+e-n.,-.~-- , .,-...._-c -
--~c__ . - _ _ . _ _ _
. l i
1 1 . 11 . Summary and conclusions ' Table 11.H.1 summarizes the radiation and environmental i radioactivity measurements conducted during 1991 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 nay 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 I1.11.1 are only the means of the values [ greater than MDC , . the statistically minimum detectable I concentration. The range also-is given only for-detectable measurements. The mean and range values, therefore, are not the true means or ranges if any of the values in the sample population were less than MDC. The format of Table II.H.1 is a requirement of the NRC. Inspection of Table II.H.1 reveals that (except for I-131 i , at site '
-22) there were no individual measurements that exceeded the Reporting Level (RL) (see Table III.A.3). The i
Chernobyl fallout was still observable in several sample ; types. For the category of gross beta concentrations in drinking
. water, the mean for the Gilcrest well was again significantly greater than for the reference supply located in Fort Collins.
The-following conclusions seem valid,
- a. None of the ' individual fission product or activation product. radionuclides measured were 93
1
)
signifienntly higher in the Gilcrest drinking water.
- b. Tritium concentrations measured at Gilcrest were.
however, statistically greater than those in Fort Collins. This is due to FSV tritium release. 1 However, the resultant dose commitment is insignificant,
- c. The city of Gilcrest does not filter and treat its l water to the same degree as Fort Collins. This has been verified and evidenced by the f act that the ;
gamma-ray spectra of the cuspended 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 lOJs filtration C' the water.
For the category of tritium in surface water, as has been the case since reactor operation, elevated concentrations were noted at station A-25, the outlet of the (Goosequill) farm l- pond. A-25 is directly in~the principal effluent route and i elevated' concentrations should be expected, to correlate with release schedules. Downstream surf ace water concentrations of tritium have occasionally been elevated, but there is l l
significant dilution before any human use of this water, f During 1991 elevated tritium concentrations were not obrarved downstream and the mean values for the first and second half s of 1991 were not significantly different. l i I *.31 was observed again in milk samples, but again only l i f rom Dairy A-22. Because the reactor did not release any { significant fission products during 1991, the source of the I-131 concentrations in milk could not be reactor effluent. It . was documented in the 1985 annual report that the source of l the I-131 concentrations during that year was not due to the 1 reactor but due to nuclear medicine use and release upstream of the reactor. This was an important observation as I-131 id certainly a critical radionuclide in human dose commitment possibilities, a fact of which 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 source of the I-131 observed again in milk samples during 1991. Irrigation water samples confirmed this conclusion.
(' Cs-137 was also observed in many environmental' samples [ due to the Chernobyl fallout. Tritium concentrations from well water site F-16 do appear to be increasing with time. This could be due to ll l 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 in not used for drinking water purposes and elevated tritium concentrations have not been observed in any food chain sample. Table 11.11.2 presents an additional summary of mean values for selected sample types. The sample types and radionuclides were chosen on the basis of their importance in documenting possible radiation dose to humans. Air and surf ace water would be the predominant environmental transport _ routes ano drinking water and milk would be the predominant sources of radiation dose if significant radioactivity release from FSV occurred. Table II.H.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 s presented in the body of this report contain only positive calculated values above the minimum detectable concontration (MDC) levels. Any calculated values loss than zero or less than the minimum detectable concentration (MDC) are listed as less than the actual MDC for that sample analysis, llowever, the actual result in all cases was used in the calculation f or the arithmetic mean values for the period. Therefore, all 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 I 1 . 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 96
r, l contain less than zero radioactivity, due to the random nature of radioactive decay, it is statistically possible to obtain sample count rates-less than background and hence a negative result. It is equally true that many sample types do in fact have zero concentrations of certain radionuclides. Therefore, f to obtain the correct mean value from the distribution of analytical results, all positive results must be averaged with all negative results. If the negative results were omitted, the resulting arithmetic mean would be falsely biased high. From the values presented in Tables II.H.1 and II.H.2 and the tabular data of the report, the following observations and conclusions may be drawn: *
- 1. Tritium was again the only radionuclide that was detected in significant concentrations _in - any of .
the. effluent pathways that could be attributeo to the reactor. Since the tritium is released as tritiated water, the dilution by the surrounding hydrosphere is_ great. Although in 1991, tritium could be detected in the effluent pathway, the mean values of downstream surface water were not l statistically greater than upstream concentrations. l 4 Aotin-every previous report, it was again apparent that for most sample types the variability observed around the mean values was great. This variability l is due to counting statistics and methodological variation, but principally due to true t 1 'ironmental variation (often termed sampling L 97 E . - - . _ . . _ _ . , - _ . . _ . . -
crror). It must be recognized and accounted for in i analysis of z.ny set of environmental data before meaningful conclusions can be drawn.
- 3. Thr "hernobyl accident f allout 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 sample types because the fallout deposition was considerably greater during the pre-operational period.
- 4. The prompt and sensitive 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 decommissioning.
It can be concluded from the deta collected by the 98
7[! environnental monitoring program that the radiation dose commitments calculated for the closest inhabitants or other parts of the nearby ecosystems due to current reactor effluents are negligible. Natural background radiation and the dose commitment from atmospheric fallout are the only known significant sources of radiation dose to the , residents of the area. During the current 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. - l t t-l 1' l 99
, . - _ _ _.___ _. __ _ . _ . . . _ _ - ._. _.-.. _ u:
Table II.H.1 Environmental Radiological Monitoring Program Annual sistmary Fort St. Vrain Nuclear Generating Facility, Platteville, Colorado Locations with Highest Reference Nuniper of Medium or Pathway Type and Facility Adjacent location Annual Mean Location Nonroutine Sarrples (Unit of Total Nunber Location Mean(f)g Reported of Analyses Mean(f)g Mean(f)g Name Mean (f) measurement) Range Measurements Performed Range Range Distance & Range Direction 0.46 (4/4) G. ,(18/18) 0 Direct Radiation TLD (158) 0.3 72/72) 0.39 (68/68) A2 uCR42 (0.20-0.53) (0.25-0.58) & WCR255 (0.40-0.57) (0.31-0.53) (r*/ day) 6.8 km 25 (207/207) F-7 Farm 25 (52/52) 24 (156/156) O Air, Gross # (363) (12-69) (0.60-69) CR21 & CR34 (4.9-69) Particgtetes 1.5 km 145* (fCi/m ) Gansna spectrometry Cs-134 (28) < 2.4 R-3 Csu 3.2 (1/4) 2.6 (3/12) 0 Vet Hosp. (2.3-3.2) 45 km 330-Cs-137 (28) 1.6 (1/16) R-4 US 66 1.7 (1/4) 1.5 (3/12) 0
& US 287 (1.2-1.7) 21 km F-7 Farra 46 (1/52) 30 (7/156) 0 31 (8/207)
Air,Cgarcoat I-131 (363) (17-39) (19-46) CR21 & CR34 (pCi/m ) 1.5 km 145* F-7 Farm 636 (7/52) 583 (24/156) 0 Air, Atmospheric H-3 (364) 621 (37/208) (430-960) CRES 8, CR34 (540-780) (350-870) Watergapor 1.5 km 145-(pCi/m ) beenandrarsebasedupondetectablemeasurementsonly. Fraction (f) of detectable measurements at specified locations is indicated in parentheses. t-
Table II.H.1 Envirorvnental Radiologicat 'tonitoring Program Annual Sunenary Fort St. Vrain Nuclear Generating Facility, Plattevitte, Colorado Meditse or Pathway - Type and Facility Adjacent Locations with Highest Reference Ntsnber of Sarples (Unit of Total Nunber Location Location Annual Mean L cation Nonroutine measurement) of Analyses Mean(f)g Mean(f)g Name Mean (f)b Mean(f)g Reported Performed Range Range Distance & Range Range Measurements Direction Drinking Water Gross # (52) 5.8 (26/26) R-6 Gilcrest 5.8 (26/26) 0.95 (26/26) 0 (pci/t.) (3.1-13) City Water (3.1-13) (0.44-1.6) ' 9.3 km 60* H-3 (52) 618 (6/26) R-6 Gilcrest. 618 (6/26) 570 (2/26) 0 (490-760) City Water (490-760) (410-730) 9.3 km 60* Gama spectrometry _ I-131 (52) < 0.46 R-3 ft. Col 1 ins 0.52 (1/26) 0.52 (1/26) 0 o
~ City Water 45 km 330*
Cs-134 (52) 3.4 (3/26) R-6 Gilerest 3.4 (3/26) 2.1 (1/26) 0 (2.8-4.0) City Water (2.8-4.0) 9.3 km 60* Cs-137 (52) 3.9 (9/26) R-6 Giterest 3.9 (9/26) 3.3 (7/26) 0 (1.7-6.0) City water (1.7-6.0) (2.2-4.2) 9.3 km 60* Zr-95 (52) < 7.2 R-3 Ft. Collins 4.5 (1/26) 4.5 (1/26) O City Water 45 km 330' Nb-95 (52) < 2.8 --- ---
< 2.0 0 beenandrangebasedupondetectablemeasurementsonly.
Fraction (f) of detectal;,le measurements at specified locations is indicated in parentheses.
Table II.H.1 Environmental Radiological Monitoring Program Amual Strmary 4 Fort St. Vrain Hoclear Generating Facility, Platteville, Colorado Mediun or Pathway Type and Facility Adjacent Locations with Highest Reference Munber of Sanples (Unit of Tota! Pamber Locati Locaticg Annual Mean Locatiog Nonroutine measurement) of Analyses Mean(g)f Mean (f) Name Mean (f) Mean (f) Reported Perfornied Range , Range Distance & Range Range Measurementt Direction .i i Drinking water Co-58 (52) 1.7(1/26) R-6 Gilcrest 1.7 (1/2o) < 2.8 0 City Water , 9.3 km 60* Mn-54 (52) 2.7 (3/26) R-3 Ft. Coliins 2.9 (3/2oi 2.9 (3/26) 0 (1.9-3.8) City uater (2.7-3.3) (2.7-3.3) 45 km 330* , Zn-65 (52) < 9.0 --- --- --- 0 h Fe-59 (52) 7.3 (2/26) R-6 Gilcrest 7.6 (2/26) < 6.2 0 (5.3-9.2) City Water (5.3-9.2) 9.3 km 60* Co-60 (52) 3.8 (1/26) R-6 Gilcrest 3.8 (1/26) 2.87 (2/26) O City water (2.31-3.23) T 9.3 km 60* Ba-140 (52) < 7.5 R-3 Ft. Collins 3.4 (1/26) 3.4 (1/26) O City Water 45 km 330* ; La-140 (52) < 7.5 R-3 Ft. Collins 3.9 (1/26) 3.9 (1/26) 0 (4.6-7.3' City water 45 km 330* beanandrangebasedupondetectablemeasurementsonly. Traction (f) of detectable measurements at specified locations is indicated in parentheses. I
- w. _ . _ _ _ - _ - -
Table II.H.1 Envirorinental Radiological Monitoring Program Annual suonary ^ Fort St..Vrain Nuclear Generating Facility, Plattevitte, Colorado Medius or Pathway Type and Facility Adjacent. - Locations with Highest Reference Nuiber of sanples (Unit of Total Nunber Location Location Annual Mean Location Nonroutine measurement) of Ana1yses Mean(f)g Kean(f)g Name Mean (f) Mean(f)g Reported Performed Range Range Distance & Range Range Measurements Direction surface Water H-3 (60) 1747 (12/36) A-25 Goosequill 2786 (7/12) 552 (5/24) 0 (pCi/L) 070-8300) 2.2 km 2r (1000-8300) (380-860) Gama spectrometry Cs-134 (60) 2.2 (1/36) F-20 St. Vrain 2.2 (1/12) < 3.5 0 1.5 km 345* Cs-137 (60) 3.8 (13/36) R-10 s. Platte 4.6 (2/12) 4.0 (8/24) 0 (2.6-6.6) at CO 6G (3.1-6.0) (2.8-5.3) 5 w 10 km 290* Zr-95 (60) 5.4 (2/36) F-20 st. Vrain 5.5 (1/12) < 8.6 0 ' (5.3-5.5) 1.5 km 345* Nb-95 (60) < 3.1 A-21 St. Vrain 3.6 (1/12) 3.6 (1/24) O Bridge 2.4 km 220' Co-58 (60) 4.3 (1/36) R-10 s. Plaite 4.3 (1/12) < 3.4 e at CO 60 10 km 290* Mn-54 (60) 3.0 (6/36) A-21 St. Vrain 3.3 (2/12) 2.3(2/24) 0 (1.6-4.1) Bridge 2.4 km (3.0-3.6) (1.5-3.0) 220* Zn-65 (60) < 9.6 --- ---
< 10 0 beanandrangebasedtpondetectablemeasurementsonly.
- Fraction (f) of detectable measurements at specified locations is indicated in parentheses.
____.-____.m___ _ . _ _ _ . _ __ _ _ _ _ _ _ _ _ _ m
r
~
-Table II.H.1 ' Environmental' Radiological Monitoring Program Annual Summary
-Fort St. Vrain Nuclear Generating Facility,.'Platteville, Colorado ,
Medium or Pathway Type and: Facility- Adjacent; Locations with HigHst Reference- Nund)er of.
' Sanples (Unit of Total Ntatier Locationg Locat f org _ Annual Mean- Locatior Nonroutine-measuremerit) of Analyses Mean (f) .Mean (f)
Name Me f,@ Mean(f)g Reported Performed: -Range Distance & Measurements Range: ' nge- Range Direction-Surface Water Ganens Spectrometry
"(pci/L)
Fe-59-(60) < 7.5, A-21 St. Vrain 8.1 (3/24) 8.1 (3/24) 0 Bridge 2.4 km (7.3-8.6) (7.3-8.6) 220-Co-60 (66; 4.6'(4/36) F-20 St. Vrain 5.4'(2/12) 3.0 (2/24)' 0 (2.4-5.8) 1.5 km 345* (4.0-6.8) (2.7-3.2) _- Ba *40 (6u) 6.2-(4/36) 'F-20 St. Vrain 7.8 (1/12) < 6.4 0 g (5.3-7.8) 1.5 km 345* La-140 (60) 7.1 (4/36) F-20 St. Vrain 9.0 (1/12) < 7.5 0
-(6.1-9.0) 1.5 km 345' Ground Water H-3 (8) 1950 (2/4) F-16 3-Bar 1950 (?!6) < 400 0 (pci/L) .(1600-2300) . Ranch (1600-2500);
'1.2 km 0*
Gamma Spectrometry Cs-134 (8) < 3.4 --- ---
< 2.2 0 Cs-137 (8)' 5.7 (2/4) F-16 3-Bar 5.7-(2/4) 5.3 (2/4) 0 (3.7-7.7) Ranch (3.7-7.7) (4.1-6.5)
'1.2 km 0*
Zr-95 (8) < 6.9 --- ---
< 4.9 0 Mb-95 (8) < 3.1 --- ---
< 2.1 .0
., y beanandrangebasedtpondetectablemeasurementsonly.
Fraction (f) of detectable' measurements at specified locations is indicated in parentheses.
j; Table II.H.1 Environmental Radiological Monitoring vrogram Annual Stannary Fort St. Vrain Nuclear Generating Facility, Platteville, Colorado Medium or Pathway Type arvj Facility M t -ceo Locations with Highest Reference' 4taber of Samples (Urtit of Total Ntaber Locat ; p- . 24 g Annual Mean . Locati Nonroutine measurement) of Analyses Mean ~2)g' He - .f) Name Mean (f)" Mean(g)- f Reported , Performed Range m .ge Distance & Range Range Measurements Direction Ground Water Game Spectrometry (pci/L) Co-58 (8) < 3.1 --- ---
< 2.1 0 Mn-54 (8) 4.0 (1/4) F-16 3-Bar- 4.0 (1/4) < 2.2 0 Ranch 1.2 km O' Zn-65 (8) < 10 --- ---
< 7.5 0 h Fe-59 (8) < 7.8 --- ---
< 5.2 0 Co-60 (8) 2.9 (2/4) F *6 3-Bar 2.9 (2/4) < 2.2 0 (2.7-3.1) Ranch (2.7-3.1) 1.2 km 0*
Ba-140 (8) < 6.5 --- ---
< 4.4 0 La-140 (M < 7.5 --- ---
< 5.0 0 keanandrangebasedupondetectablemeasurementsonly.
Fraction (f) of detectable measurements at specified locations is indicated in parentheses. 6
r < p y
~ '
' Table;II.H.1' Environmental Radictogical' Monitoring Program' Annual Staunary Fort St. Vrain Nuclear Generating Facility, Platteville, Colorado ^
. Meditas or Pathways -Type and' . Facility ' Adjacent- Locations with' Highest " Reference? Number of -
'.Se@tes (Unit of ' riotal - Nuuber .
Locatlon Location . Annual'Mean . Location measurement). 'of Analyses - Mean(f)g' Mean(f)g .
- tlame Mean (f) iMean(f)g' - Nonroutine' Reported--
' Performed' Range Range.
Distance & Range. LRange
- Measurements Direction Sediment ~ . Gamune spectrometry .
.(pci/kg. dry)
Cs-134"(2) . < 11
--- --- .--- -'O-g- Cs-137.'(2) 69 (2/2) R-10 S. Platte 69 (2/2) ---
O (54-83) at'to 60 (54-83) - 10 km 290*
. Milk H-3 (108) 587 (9/91) A-18 Boos 830 (1/1/) 563 (3/16) O' I5 (pCi/L) (410-830) Dairy (440-790)-
4.7 km-Gansna spectrometry 1-131 (108)' 1.6.(3/91) A-22 Percy 2.2 (2/17) 0.45 (2/17) 'O (0.47-2.3) odenbaugh Dairy (2.1-2.3). (0.39-0.51). 5 km 90* Cs-134~(108) '2.5 (7/91) A-26 Dochef f 3.1 (1/17) 3.1 (1/17) 0 (1.2-3.1) Dairy 6.8 km Cs-137 (108)- 4 1 (21/91) A-22 Percy 4.5 (2/17). 3.7 (8/17) 0 (1.6-6.4) Odenbaugh Dairy (3.1'5.9) (2.6-5.3) 5 km 90* ' han'andrangebasedupondetectablemeasurementsonly. Fraction (f) of detectable measurements at.specified locations is' indicated ir. parentheses.
}- i y 3 ,, "v i g-- y .-- w ,.iy.-
.Tabte II.H.1- 'EnvironmentaliRadiotogical Monitoring' Program Annual Sunnary' -
Fort $ti Vrain Nuclear Generating Facility,'Platteville, Colorado _
~
' Medits or Pathway Type and . Fac!1ity. . Adjacent - Locations with Highest Reference' Number o'f.
Sanptes -(Unit of ' - Total Ntaber- Locati Annual-Mean L catlon Nonroutine measurement)- of. Analyses- Mean(g).'.. f -Locatlog) Mean (f - Name Mean (f)b Mean (f)g' ~ Reported-Performed -Rangen Range. Distance & Range Range: Measurements Direction Milk Gagna Spectrometry (pCi/L) . . Ba-140'(108) 5.8 (4/91) A-23 Leroy- 9.4 (1/17) 4.6 (1/17) 0 (2.2-9.4) odenbaugh Dalry 4.1 km 83* La-140 (108) 6.7 (4/91) A-23 Leroy 11 (1/17) 5.3 (1/17) 0 (2.5-11) Odenbaugh Dairy 4.1 km 83* g" - Food Products Ganna Spectrometry (pCi/kg, wet) . . 1-131.(8) 17 (1/8) R-6 Hernandez. 17 (1/6) --- 0 Gilcrest
- 9.6 km 60*
Cs-134 (9) 17.(1/8) R-6 Hernandez 17 (1/6) --- 0 Gilcrest 9.6 km 60* Cs-137 (9) 31 (1/8) A-27 WCR25 31 (1/7' --- 0
& WCR38 .
4.3 km beanandrangebasedupondetectablemeasurementsonly. Fraction (f) of detectable measurements at specified locations is indicrited in parentheses.
.- 1
. . - . _ . - _ - - - - - - - - - _ _ . _ _ _ - - - . - _ _ _ _ w , . , , -
Table II.H.1 Environmental Radiological Monitoring Program Annual Strvnary Fort St. Vrain Nuclear Generating Facility, Platteville, Colorado Medium or Pathway Type and Facility Adjacent Locations with Highest Reference Nunber of samples (Unit of Total Nunber Location Location Annual Mean L cati Wonroutine measurement) of Analyses Mean (f)g Mean(f)g Nane Mean (f)b Mean (f g) Reported Performed Range Rante Distance & Range Range Measurements Direction Fish Ganma Spectrometry (pci/kg, wet) Cs-134 (6) < 6.0 --- ---
< 6.3 0 cs-137 (6) 7.? (1/4) R-10 S. Platte 16 (1/2) 16 (1/2) O at CO 60 10 km 290*
Co-58 (6) < 5.8 --- ---
< 6.3 0 5
on Mn-54 (6) < 5.8 --- ---
< 6.0 0 Zn-65 (6) < 17 --- ---
< 21 0
[ Fe-59 (6) < 15 --- ---
< 10 0 Co-60 (6) < 6.2 --- ---
< 6.9 0 bean and rcnge based upon detectable sensurements only.
Fraction (f) of detectable measurements at specified locations is indicated in parentheses. l
9 Table 11.11.2 Summary Table of Arithmetic. Means and S' t andard Deviations for Selected Sample Types. 1988' 1989 1990 1991-R. R R a R o Atmospheric Water Vapor (pci/L) 11 - 3 Facility 470 43 <256 285 <9.4 395 Reference 172 <420 <299 288 <80 395 $ Air (fCi/m 3) Gross Beta Facility 26 26 23 12 29 31 Reference 24 24 23 12 25 23 I-131 Facility 1.9 2.2 1.5 3 1.6 13 Reference <4.5 2.2 1.4. 9 0.52 14 Cs-137 Facility 0.73 0.32 0.55 0.92 0.12 0.69 Reference 1.0 0.46 0.22 0.66 0.911 1.3 a e
o Table II.31.2 Summary Table of Arithmetic Means'and Standard Deviations for Selected sample Types. 1988 1989 1990 1991 R R R o R o Drinking Water (pC1/L) 11 - 3 Gilcrest 370 <390 <238 317 32 4G5 Ft. Col 1 ins 120 <390 <215 288 <48 345 Gross Beta Gilcrest 6.8 5.8 4.5 1.8 5.8 2.4 .{ Ft. Collins 1.1 0.98 0.86 0.39 0.95 0.35 I-131 Gilcrest 0.099 0.068 0.017 0.19 <0.0028 0.16 Ft. Collins 0.083 0.14 0.046 0.24 <0.022 0.20 Cs-137 Gilcrest 1.7 2.2 1.3 1.4 2.2 1.6 Ft. Collins 1.4 1.8 2.4 1.8 1.7 1.2 0
- - - . ~ __
~
s p'
- Table II.II.2 : : Summary: Table'of Arithmetic'Means and Standard! Deviations foriselected Sample Types.
1988: .1989 1990 1991-
"R R 'R' o R. .o.
Surface ; Water ' (pci/L) . 11 - 3 Effluent. 31000~ 29000 303- 623' 1499 2496 Downstream 430 - <390 . <371 397 6.2 ,427-tJpstream- 430 - <390 <415 352 20- 419 Cs-137 Effluent 1.9 1.3- 1.4 1.9 1.7 2.0 t* Downstream 2.5 1.8' 2.1- 1.9: 2.3 1.7 Upstream 11.4 L2.0- 2.2 1.9 2.0 1.9 Milk (pci/L) 11 - 3 Adjacent 70' <390' <280 330 <133 362 Reference <
'220 <390 <290 340 '<110 398, I-131 Adjacent 'O.046 0.57 0.53. 2.0 0.070 0.39 Reference <0.17- <0.50 0.0060 0.33 <0.0028 0.24 Cs-137 Adjacent 2. 7 . - l '. 5 1.5- '2.0 1.9. 1.8 Reference '3.3 1.5 16 2.3 2.4 1.9-e
III.: Radiological Environmental Monitoring Program A. Sample. Collection and Analysis Schedule j l
-Table- III.A.1 outlines the sampling design, the i 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 f erent in certain aspects from the previous schedule, has as its l
' tent the same objective.
. That objective is to document the L radiation and radioactivity levels in the critical pathways of l-l possible dose to humans. Such data is necessary to prove that 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 1991, there were no changes in the sampling program. Table III.'B.1 gives the description of each sampling location by number, sector and distance from the reactor. Each of"these sampling locations. (except certain reference
. locations) can-be identified on scale maps (Figures III.B.1 and--III.B.2). Topographical maps chowing greater detail,.as well as photographs of princ.f pal sampling sites are on file in
!; the CSU laboratory. During September 1991 the land-use census was again i conducted to determine the locations of the nearest residence, l l. l L 112 n
the nearest milk animal, and the nearest garden producing broad leaf vegetation in each of the 16 meteorological sectors around 'the reactor.. Thesa locations are shown in Table . III.C.1. Figura III.C.1 shows these locations in each sector. At the- time of the 1991 census it was verified that the closest permanent residence in Sector 16 was the critical receptor with reaards to nean annual dose commitment and ir at the Russell farm F-16. A few residents in the sampling sectors up to a distance of 8 km from the plant have cows or goats that could be used l for personal milk consumption. However, from direct discussion with these persons, this is not a common practice l and all cow milk produced is transported to commercial processors. The milk produced locally is diluted by a large milk shed, processed and distributed over a large area for
. consumption. For this reason the elevated 1-131 in milk from A-22 would never be detected in the composited milk supply.
l Table III. A.2 lists the LLD concentration values for each j sample type and radionuclide measured in this repert. These LLD ~ values are the actual values- pertinent to the sample sizes, counting yields, and counting times used in the project. - . Typical decay periods were used in the calculations. It should be noted that the LLD values are in all cases equal <- to or less than those required by the technical l' specifications. [ Table III.A.3 lists the UCNRC reporting level for each l sample type and radionuclide. 113
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t 7 , gj _ .a 3 y , .7 i-Tatsle'Ill.A.2. Delectibn' CapabiliLies for Envtronmental: Sample. Analysis
-Lower Limit of Detection!(LtD)
Fish . Milk' . Ercod' Products- SedimentL Analysis; TWater- ! Airliorne Particulate. '(pC l/kg. .. dry)
- (pCl/L)._ forLGas-(IC1/m3) ~(pCi/kg, wet). (pCi/L). : (pCi/kg,' wet)
Gross lieta -3.86. l3.25 3 r494' 494 11 .i 1-131 0.890 : 66;. 4 0.890 .56.8 Cs-134 '5.58 -8.06 19,5 .5.53 44.4' .90.6 Cs-137 5.34 7.86. 18.5 5.3d 44.6 100-
/r-95 7.96 M tib-95 4.24:
.C0-58 3.66 12.8 Hn-54 .3.64 12.7 Zn-65 7.92 e
fe-59 B.30 31.4 Co-60 3.74 14.5 lla-140 8.87 8.07 , La-140 10.2 :10.2 i
- As suggested in 14UREG-0472. All values =are 'at or below values listed in Table 8.2-2. of . Technical Specifications.
.i s
M- ,. -
, _. __ __.__________._m. _ _ _ _ _ . _ _ _ _ _ . _ .
_J'w<-'. Table III .A. 3. Reporting Levels (RL)- for flonroutine Operating Reports Reporting Level (RL)
' Analysis Water Fish Milk Broad Leaf Vegetation :
(pC1/L) AirborneParg)iculateorGas.
~(ICl/m (pC1/kg, wet) (pCl/L) (pCf /.kg. wet) - fl-3 2 x 10 (*}
4 Mn-54 1 x 10 3 3 x 10 fe-59 4 x 10 1 x 10 1 x 10 3 4 Co-58 3 x 10
- h Co-60 3 x 10 1 x 10 Zn-65 3 x 10 2 x 10 4 x 10 2 fib-95, Zr-95 1 x 10 2-2 I-131 2 .9 x 10 3 J
Cs-134 30 1 x 10 4 1 x 10 60 1 x 10 3 Cs-137 50 2 x 10 4 2 x 10 3 70 2 x 10 3 2 Ba-140, 2 x 10 3 x 10 La-140
- a. For drinking water samples. -This is 40CfR Part 141 value.
4
4 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, Pathway km Direct Radiation F-1 Pole by gate to Goosequill road on dirt extension of 1 1.3 CR 21. F-2 21st pole N of ditch on dirt extension of CR 21 just 2 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. g; 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 11th 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 1st pole W of pump house or N side of road 0.4 km E 8 1.3 of CR 19h, F-9 Pole E of first shed at intersection of CR 19 9 1.5 and CR 34. F-10 Po3.e on NW corner of intersection of dirt extension 10 1.5 of-CR 19 and 34. ,
.s.
1
.i '
1 Table'.III.B.1 Radiological 2nvironmentcl Monitoring' Program'(continued)' sampling, Site Descriptions 1 (F:-Facility 1 Area.f0-l'.6 km. 'A:'. Adjacent Area'1.6-8 km. 'l: Reference-Area) Exposure Site No. ' Location' Description '(see map) Sector.' ' Distance, Pathway- km Direct Radiation F-11 7t.h pole N of intersection of dirt extension 'of CR '19 11' . 1.2 xwith 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 Aristocrat Brangus office.. , F-13 Tak'e 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.36h & 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 Centor, on N end of' cross beam over' entrance. 13 0.2 F-18 . Pole. closest to house on SW corner, 17250 CR'19k. 16 0.8 The address of'17250 is taped to the Mountain Bell underground cable warning post. t O
, -. , , . -r
N ' ?YS
?pty ,
r r 7 9 m - 7 TableiIII.B.1.; Radiological'EnvironmentalLNonitoring Program.,(continued) ' 1
*i
- sampling site' Descriptions-4
- (F:; Facility'AreacO-1.6'km..:A:: Adjacent Area-1.6-8/)ca. R:' Reference' Area)' g Exposure -Site No. 1 Location Description (see map); ' Sector Distance,:
- ' Pathway, 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 25%. 2 6.8-3 ~
A-3 : Pole on NE.. corner'of.. intersection'of CR.42 and CO 60.. 3 7.5 A 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 ]
3 SW' corner.of.. Intersection.
. 2 A-6 Pole =on.SLsidelof CR 32 near drive to dairy 13278 CR 6' .. 7 . '1 '
32.
~
, 'A-7 'Niles Miller dairy. 'O.4 km E of US 85 on 12854 CR 30. TLD'i'sTlocated.on pole at.NE corner of house. 7 7.3 : A-8, -OnL CO 66 '(CR30)' farm on S side of' road (address 9476) 8 '4.7: I Fole in frent'of house.
~
l A Corner.of CO.66 (CR 30) and CR 19, . Miller produce.
~
9 4.6 i
-stand. -:Second pole S on'CR 19, on E side of road.
A-10. Pole on SE. corner at intersection'CR 26 & CR 15. 10 7.8 A'-11 At intersection of.CO 66 and'CR 13,' 2nd pole N of 'll 7.2
~
j intersection on E side of CR13. l 4 i b s._ . . , _ _ _ _._ _ _ __ __
a g' - re Table III.B.1-l Radiological iEnvironmental. Monitoring Program-(continued).' sampling site' Descriptions A: .- Adj acent, Area l. 6-8 ! km. . R: Reference' Area).
~
i 1(F: . Facility-Area 0-1.6"km.- . Exposure' Site. 'No. - Location Description (see map). Sector. . Distance, 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-silage' pits E side of CR 13 13 '5.8-2'.9 km N of.CR.34. 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 N
A-16 -Intersection of CR 44'and CR 19,..SW corner. '16 6.8
,A-17 Platte"ille. school ~(S edge of town on Main St.) 6 5.9 pole on:NWicorner just outside school intramural field.
A-20 1st pole' N 'of'. white pi'.ket fence ~ and driveway 9 2.5
.into turkey farm on S end of building that is parallel with"CR 19.
9
- [ .
Table'III.B.2- 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)-
t
. Exposure. Site No. Location Description (see map) - Sector. Distance, Pathway .km Direct-Radiation R-1 Milliken School, on-CR121\. ' TLD.is located.on pole 9.3' whichl-is' located at SE. corner of Lola park, across the street from school.
R-2 Johnstown. School'(Letford Elementary), turnjleft at 10.8 school crossing on. Idaho St. onto Jay Ave. and proceed to school. TLD is located on pole at SE corner of main entrance 1to school on W side of town. ) R-3'- CSU dairy farm on'W' Drake, N o'f' Vet Hospital, Ft. 45.1-Collins, CO. ' Pole is E'of hay barn next to railroad tracks. R-4 Air sampler corner US 287 and CO 66, Longmont Dairy 20.5 Store. TLD is located on pole directly behind air-sampler. R-7 Behind Gilcrest School quonset auditorium, pole 9.3 on SW end of school property, just before garage. Waterborne Sediment from Shoreline R-10 Sediment from'S. Platte River-at bridge'on CO'60.- 10.1
.m ___. _ . _ _ _ _ -
- _ _ . _ . _ _ . _ _ _ _ _ _ _ _ __2 _ _ _ _ _ _ _ _ __ - _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ . . . _ . _ _ _ . . _ _ _ . . _ *
" ~
+
t-Table III.B'.1 Radiological-Environmental Monitoring-Program sampling Site Descriptions. (F: . Facility'AreaLO-1.6 km. . ~A: Adjacent: Area 1.6-8 km. R:: Reference Area)' Exposure Site'No. Location Description (see map)" Sector -Distance,.
- Pathway. ikm' Airborne F Farm at' intersection of CR'21 and CR 34.- Air 7 .1. 5 sampler'is located'on west 7 side of shop. . Silica gel.inside buildingfon N end.of workbench.
F-9 First:shed along1 drive ~at end of Rd 19 intersection 9. "1. 5 with Rd 34. Silica' gel is located in~shed. F-16 Potato cellar at 3 Bar Ranch.(Russell's). Silica 16 1.2'
-. . gel.in mailbox on tree toL6 of pump..
E$ A-19 Hunting cabin between Goosequill ditch and Platte 1 1.7' River. Air sampler is on W side of cabin, silica , gel'is in box on' tree north of air sampler. R-3 Colorado State University Dairy, W. Drake Rd., Ft. 45.1' Collins, CO..W' side of shed directly N of main dairyfbuilding. : Silica gel inside; mailbox. R-4' IntersectionLoffUS 66 and.US.287, E side of dairy 20.5 store, north edge of Longmont. . Silica. gel is in mailbox' attached to. utility pole. R-11 Air sampler.is located in alley bchind PSC office, 10.5' ., next to garage. ~ Silica 1 gel is-located next to air sampler in mailbox and on top of post, 13 1/2. Parish St., Johnston, CO. p . 2_.__ .--. a . . . ~ ~ . , ~ - + -
4 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) i Sector Distance, Exposure Site No. Location Description (see map) km Pathway Waterborne 4 1.2 Surface F-19 S. Platte at dam located on dirt road E of pump house #3 directly E of reactor. 16 1.5 F-20 St. Vrain creek on Rd. 19\ 0.3 km from discharge into St. Vrain creek. Directly N of reactor. 11 2.4 A-21 St. Vrain creek at bridge on Rd. 34, E of Rd. 19. Continuous sampler located 1 2.2 A-25 Goosequill Pond outlet. hk in green box adjacent to the green shed on the N end of the pond. Platte river at bridge on CO 60 where highway 10.1 R-10 S. has just turned and headed South. 1.2 Ground F-16 Well behind residence at 3 Bar Ranch (Russell's), 1 17578 WCR 19 1/2. 9.5 R-5 Well at 108 S. Grace, Milliken. 45.1 Drinking R-3 CSU dairy W Drake Rd., Ft. Collins, CO, N of Vet Hospital. Water sample is ta}'.en trok hydrant inside the entrance to the milking parlor. 9.3 R-6 Gilcrest U.S. Post Office located on Birch St. and Rd. 40 off of Hwy 85. Water taken from utility sink inside Post Office. .
A u. 4 Table:III.B.1 ' Radiological Environmental'.' Monitoring Program '(continued) sampling'eite Descriptions (F: Facil3ty 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 Ingestion ' Milk A-6 Hendrickson' Dairy, 13278 Rd. 32 (Grand Ave.) 6 7.1
'l.6:km E"of US 85.
A-18 Boos Dairy,.11258 W Rd. 40, W of US 85 behind 2 4.7-modular home. A-22 Percy-Odenbaugh Dairy, S on dirt rd from "LcRoy & 5' 3.2
. - Paul Odenbaugh' Dairy" sign. Dairy sign on WCR 36, s E of Rd 23.. Dairy sign is located next to mailbox of Mike Thomasi.
A-23 .Leroy Odenbaugh Dairy, 11733 Rd'3'6, 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 Jim Docheff l> airy, east of. Road 13 on R 32, at 11 9.4
-4513 WCR 32.
R-8 Borba Dairy, 2252'S. CR 7, take the Hwy. 402 exit for 22.5 Loveland from I-25, travel west 1.6 km to Cty. Rd. 7. Turn south and go to second dairy on left. 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
, , +
s b 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) Sector- Distance, Exposure Site No. Location Description (see map) km Pathway Food 4 4.3 Products A-27 Fields on SE corner of intersection of WCR 25 and WCR 38. 2 5.3 A-20 Residence 11399 WCR 40%. 9.6 R-6 Hernandez Produce Stand, Highway 85, Gilcrest. L% l l
F:gure lil L*1 1
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k Figure Ill.B.2 Adjacent and Ref erence Sampiing Locations hi l M- l -
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f,E $ 6 Table III.C.1 1991 Land Use Census
- n Sector Nearest Nearest Nearect Milk Residence Garden Animal 1 17578 CR 19\ 9626 CR 44 ***
2 18311 CR 23 18999 CR 23 11283 CR 40\ v' 3 11100 CR 38 11100 CR 38 11165 CR 38 4 11247 CR Tc 11777 CR 36 11777 CR 36 5~ 16543 CR 23 16134 CR 23 16134 CR 23 i l 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 21 9 9456 CR 34** 9456 CR 34** 9033 CR 26 10 9061 CR 34 15449 CR 19 7388 CO 66 11 8745 CR 34 G769 CR 32 4513 CR 32 12 Aristocrat 6519 CR 34 5492 CR 34 Ranch 13 17038 CR 17 17038 CR 17 *** 14 8896 CR 19 8896 CR 19 *** I 15 9115 CR 38 9115 CR 38 *** 16 9239 CR 30 9102 CR 44** 18986 CR 19
- Census Data: Sept. 24, 1991
** New Location
*** No milk animals
[ 120
e O Figure III.C.1 Land Use Census, 1991 f f')Ck . -{ :',/, ~f~' [ b ,),h . -t' h. .k;'p .3
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