ML20042E904
| ML20042E904 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 12/31/1989 |
| From: | Crawford A PUBLIC SERVICE CO. OF COLORADO |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| P-90139, NUDOCS 9005040059 | |
| Download: ML20042E904 (150) | |
Text
7 - r m h Public Service' ::"J.**!a* L .
P.O. Box 840 -
Denver CO . 80201 0640 A. Clegg Crawford Vice President Nuclear Operations i
' ~ April 23, 1990 Fort St. Vrain Unit No. 1 P-90139 U. S. Nuclear Regulatory Commission-ATTN: Document Control Desk Washington, D.C. 20555 Docket No, 50-267
SUBJECT:
Annual Radiological-Environmental Monitoring Report
.q Gentlemen: j-Enclosed please find a copy of the Fort St. Vrain Nucle'ar Generating .
4 Station Radiological Environmental Monitoring Program-Annual Summary j Report for 1989. The report is submitted in accordance with Section :!
7.5.1d of the Fort St..Vrain Technical Specifications and: 10CFR50.4. !
, Please contact Mr. M. H. Holmes at (303) 480-6960'if you have any questions regarding the report.
Sincerely, h-
.A. Clegg Crawford ,
-Vice President Nuclear Operations ACC:DDM/bw Enclosure 1
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P-90139- '- 2-2 LApril 23,-1990 <
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, fcc: Regional' Administrator,.-Region?IV!
l'} < s Attention:7 Md J. B A; Baird -
Technical? Assistant:-
LDivisionLof Reactor l Projects? >
- Mr..R. E..Far'rell) ..
e Senior 1Re'sident Inspector' ~
Fort-St'. Vrainc '
-Mr. Robert M. Quillen, Directors Radiation: Control. Division n ColoradotDepartment'of Healthi
-4210 East'11th Avenue- ^
l . Denver, CO 80220:
Dr. Jim' Johnson
. Colorado State University .
Radiation'and Radiation Biology Fort Collins,;C0 '80521 '
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FORT 'ST. VRAIN Q ,' ,7 NUCLEAR. , l V' ,/
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SUMMARY
REPORT.
1989 COLORADO STATE UNIVERSITY-FORT COLLINS, COLORADO 80523 .
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RADIOIDCICAL ENVIRONIENTAL MONITORING PROGRAM l
For the Fort St. Vrain Nuclear Generating Station Operated by the Public Service Co..of Colorado- ,
Summary Report ;
for the Period, January 1. 1989 - December - 31. 1989. ,
y Prepared by: / OO J ma s E. John (onj Professor . 'Dat4 C 1'rado State University Reviewed by: '\'.W kIVs u YA c, 0- d2V /%
Superintendent of Chemistry Date and Radiation Protection L Reviewed by: b b L\ tk.TAA h m J 96 Radiochemistry' supervisor. -Date Approved by: I N !9a Nuclear Support Services Manager Date 9
1
Acknowledaements 1 Many persons have contributed to this project during 1989,~ and
'it is important to acknowledge-their effort. We also wish to thank
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the citizens from whose farms, homes, and ranches we collect the i
environmental samples. Without their cooperation the project would i
not be-possible. )
We also wish to acknowledge and thank the Colorado' Division of i
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Wildlife, Fort Collins regional office for assisting with the fish-collection. Without their cooperation, equipment and-expertise the l collection would not be possible.
The persons working directly on the~ project have been: l1 Joseph Bianconi Graduate Research Assistant !
Deborah Blunt Graduate Research Assistant !
Michael Hammerstrom Student Employee Julie Mileham Student Employee '!
Grant T. Reid Programmer- l Charles Sampier Chief Electronic Technician Paul J. Valentinelli Graduate Student Employee ;
Laura Walker Graduate Student Employee- I M -
James E hnson Pro or and Project Director i
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Sharon J. low l
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Laboratory Coordinator 11
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, TABLE OF CONTENTS.
Page No.
Acknowledgments 11 List of Tables - iv . '
List'of Figures ' vi-I. INTRODUCTION = 1'
'II. SURVEILLANCE DATA'FOR'1989 1 AND INTERPRETATION OF RESULTS - !
A .- External Gamma Exposure Rates 7-B. Air' Sampling Data. -10 't C. ' Water Sampling Data 36-D. Milk Data .69
.i E. Food Products- 81' F. Aquatic. Pathways 83 G. Sample Cross-check Data H. ' Summary and Conclusions 94 1 III. ENVIRONMENTAL RADIATION SURVEILLANCE PROGRAM AND SCHEDULE 115-l L ,
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9 LIST OF TABLES Page No.
II . A , l' Gamma Exposure Rates. =9 II.B.1 Concentrations of Long-lived Gross Beta Activity in Airborne Particles,
- a. First.l Quarter, 12 b ', Second Quarter l 13 '-
- c. Third Quarter,- 14
'd. Fourth Quarter, 15-II.B.2 Tritium ConcentrationsLin Atmospheric Water-Vapor, pCi/L. .t
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- a. First Quarter,- 20'
- b. Second Quarter,- 21'
- c. Third Quarter, 22
- d. Fourth Quarter, 23 -
II.B.3 Tritium Concentrations in Air, pCi/m .
8
- a. First Quarter, 24
- b. Second Quarter, , 25-
- c. Third Quarter, 26 --
1 l d. Fourth Quarter, 27 I
II.B.4 Tritium Released in' Reactor Effluents. 28 II.B.5 I 131 Concentrations in Air. i
- a. First Quarter, -31 j
- b. Second Quarter, 32 Q l
- c. Third Quarter, .' 3 3
- d. Fourth-Quarter, 34
')
II.B.6 Radiocesium Concentrations in Ambient Air. 35 l II.C.1 Gross Beta Concentrations in Bi-weekly Composites
! of Drinking Water. 38 iv l
1 ,. .,
l' LIST'0F TABLES _(Continued).
Page No.
-l II.C.2 Tritium Concentrations'in Bi weekly _ Composites l of Drinking ~ Water. 39- 1 II.C.3 Radionuclide Concentrations in Bi-weekly Composites .
of . Drinking Water. . 14 0 II.C.4 Tritium Concentrations-in Surface Water. ~S1 II.C.S. Radionuclide Concentrations in Surface ~and Effluent Water 53-II.C.6 Radionuclideboncentrationsin' Ground-Water. 66 4 II.C.7 Tritium concentrations in Ground Water._ 67:
l II.C.B Maximum Permissible Concentrations-in Water. 68
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II.D.1 Radionuclide Concentrations in Milk. 73' II.D 2 Tritium Concentrations in Milk.. 80' l
-1 II.E.1 Radionuclide~ Concentrations in Food Products. 82' l II.F.1 Radionuclide Concentrations in-Fish, 84 !
II.F.2 Radionuclide Concentrations in Sediment. 85 i f)y II.G.1 EPA Cross-check Data. 89 j II.G.2 Tritium Concentrations in' Cross-check Data, )
CSU-Colorado Dept. of Health-PSC. -91 _!
II.G.3 Gross Beta Concentrations in Water Cross-check Data,
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1 CSU-Colorado Dept. of Health-PSC. .92. ;
i II.G 4 Intralaboratory Cross-check Results. 93 i
II.H.1 Data Summary.- 103 ~I II.H.2 Geometric Means of Selected Sample Types. _112;
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III.A.1 Radiological Environmental Monitoring Program. 1118 III.A.2 Detection Capabilities for Environmental Sample Analysis, LLD. 120 4 i
III.A.3 Reporting Levels. 121 III.B.1 Sampling Locations for Environmental Samples, 122 III.C.1 Land-use Census, 1989, 132.
V 4
LIST OF FIGURES Page No.
Figure II.B.1 Gross Beta Concentrations in' Air- '16
- Figure II. Col Tritium Concentrations in Water 1974-1989 52 Figure II.D.1 I-131 Concentrations in' Milk at Site A 22' Figure II.D.2 I-131. Concentrations in S. Platte River' 79 Figure'III.B.11 Close-in Sampling Locations 1130 i
~ Adjacent and Reference Sampling Locations -
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Figure III.B.2 131'
-t Figure III,C.1 Land Use Census, 1989 133: .
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- COLORADO STATE UNIVERSITY
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i For the Fort St.=Vrain Nuclear Generating Station i 1-Operated by the- Public= Service Co. of Colorado - ;
Summary Report 4 !
for the Period t Janumev 1. 1989 - Deca =her 31. 1989 L '
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Prepared by: /
J un s E. John Professor--
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Reviewed by: ' \ k bA.kIO l!u iA dla V /0 o -
Superintendent of Chemistry Date ,
and Radiation Protection- ' -
Reviewed by: k m . \ \' d . \A b k 4-24 90 Radiochemistry ' supervisor Date Approved by: Il
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Nuclear Support Services Manager- Date l:
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h Acknowledaements Many persons have contributed to this project during 1989, and !
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it is important to' acknowledge their ' effort. We also wish to thank
.the. citizens from whose farms, homes, and ranches we collect the environmental samples. -Without their cooperation the project would .
not be-possible.
h We also wish to acknowledge and thank the Colorado Division of Wildlife, Fort Collins regional; office for assisting with the fish-4 collection. Without their cooperation, equipment and expertise the collection would not~be possible.
The persons working directly on the project have'been: ;
Joseph Bianconi Graduate Research Assistant- I Deborah Blunt Graduate Research Assistant ;
Michael Hammerstrom Student' Employee Julia Mileham Student Employee ~
Grant T. Reid Programmer -
Charles Sampier Chief Electronic Technician Paul J. Valentinelli Graduate Student Employee Laura Walker Graduate Student Employee h
James Eb Johnson Pro or and Project Director
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Sharon J. Clow Laboratory Coordinator i
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TABLE OF CONTENTS Page 'No. ;
Acknowledgments' .ii List of Tables iv-List of Figures vi I. INTRODUCTION .
1 I II. SURVEILIANCE DATA FOR 1989 AND INTERPRETATION OF RESULTS-t A. . External Gamma' Exposure Rates 7 B. Air Sampling Data- 10 C. Water Sampling Data 36 D.. Milk-Data 69 E. Food Products 81 i
1 F. Aquatic Pathways 83 l G. Sample Cross-check Data 86 H. Summary and Conclusions 94 III. ENVIRONMENTAL RADIATION SURVEILIANCE PROGRAM AND SCHEDULE 115 i
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LIST OF TABLES Page No.
II.A.1 Gamma Exposure Rates.- 9 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 -
II.B.2 Tritium Concentrations in Atmospheric Water- ,
Vapor, pCi/L.
- a. First Quarter, -20
- b. Second Quarter, 21 -. ;
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- c. Third Quarter, 22 i
- d. Fourth Quarter, 23 II.B.3 Tritium Concentrations in Air, pCi/m 3. .i
- a. First Quarter, 24'
- b. Second Quarter, 25 '
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- c. Third Quarter, 26
- d. Fourth Quarter,- 27 II.B.4 Tritium Released in Reactor Effluents. 28 II.B.5 I-131 Concentrations in Air,
- a. First Quarter, 31
- b. Second Quarter, 32
- c. Third Quarter, 33
- d. Fourth Quarter, 34 <
II.B.6 Radiocesium Concentrations in Ambient Air. 35 II.C.1 Gross Beta Concentrations in Bi-weekly Composites of Drinking Water. 38 iv I
, __ _ ._..______.._..t
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i LIST OF TABLES (Continued)
- Page No.
II.C.2 Tritium Concentrations in Bi weekly _ Composites -
of Drinking Water. .. 39. ,
II.C.3 Radionuclide Concentrations in Bi weekly Composites of Drinking Water. 40 II.C.4 Tritium Concentrations in Surface Water. 51
.II.C.5 Radionuclide Concentrations in-Surface and Effluend Water. 53-II.C.6 Radionuclide Concentrations in Ground Water. '66 ;
+
II.C.7 Tritium Concentrations in Ground Water. 67 II.C.8 Maximum Permissible Concentrations in Water. 68-II.D.1 Radionuclide Concentrations in Milk. 73 II.D.2 Tritium Concentrations in Milk. 80 II.E.1 Radionuclide; Concentrations in Food Products. 82 1
II.F.1 Radionuclide Concentrations in Fish, 84 -
II.F.2 Radionuclide Concentrations in Sediment. 85 II.G.1 EPA Cross-check Data. 89 II.G.2 Tritium-Concentrations-in Cross-check Data, CSU-Colorado Dept. of Health-PSC. 91 II.G.3 Cross Beta Concentrations in. Water cross-check' Data, CSU Colorado Dept. of Health-PSC. 92 II.G.4 Intralaboratory Cross check Results. 93 II.H.1 Data Summary, 103 II.H.2 Geometric Means of Selected Sample Types. 112 III.A.1 Radiological Environmental Monitoring Program. 118
-III.A.2 Detection Capabilities for Environmental Sample '
. Analysis. LLD. 120 III.A.3 Reporting Levels. 121 III.B.1 Sampling Locations for Environmental Samples. 122 III.C.1 Land-use Census, 1989. 132 ,
V
t LIST OF FIGURES Page No. >
Figure II.B.1 Cross Beta Concentrations in. Air- 16 ;
L Figure II.C.1 Tritium Concentrations in Water 1974 1989~ 52 .;
Figure I:.4.1 I 131 Concentrations'in Milk at Site A-22 72 Figure II.D.2' I.131 Concentrations in S.'Platte River 791
' Figure III.B.1. Close in Sampling Locations-
130 Figure III.B.2 Adjacent and Reference Sampling Locations - 131 -
Figure III.C.1 Land Use Census,.1939 133 i
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I-I. Introduction to Radiological = Environmental Monitoring l Data for the Period January 1, 1989 - December 31, 1989.
^
During 1989 the Fort St. Vrain Nuclear Generating Station produced thermal energy as follows: - ,
i Dates with Thermal Gross Thermal Month Energy Generation Energy.-
Production (MWH)
Jan. 5-13 '187.2 '
Feb. .0 0
. Mar. 26-31 4935.1 Apr. 1-28 110,281.2; May. 6-31 295,085.6 June 1-30 391,039.6 July ' l-31. 488,537.3 Aug. 1-18 272,845.1 .:
Sep.-Dec. 0 0 J Total for 1989 1,562,941.1 i A complete and detailed listing of radioactivity released by all effluent routes may be found in' the Public Service '
Company of Colorado Semi-annual Effluent Release Reports for-l 1989 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 1989 on project samples. These l values are given for typical sample sizes, counting times and i decay times. The LLD is, therefore, an a oriori parameter to '
i indicate the capability of the detection system used. The LLD l l:
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t values in Table III. A.2 were calculated as suggested in NUREG-i 0472.
Throughout the report, however, when a sample result is {
listed- as -- less than a specified value, that value is the i calculated- MDC' (minimum detectable concentration).
'This approach is analogous to that of Currie (NUREG/CR-4007)': the
- MDC -is the ~same ' as S,, - the critical signal, and.theILLD is l' equal to So , the detectable signal. The MDC value applies-to the actual sample- size,- counting _ time -and- decay time applicable to that individual sample. It.is calculated as:
MDC = 2. 3 3 _ a,/E Y V e*1' l
Where. o, = Standard deviation of background count rate l E = Counting efficiency,'c s d pCi d Y = Chemical yield l V = Sample volume (or mass) 1~= 0.693/ Half-life t= Decay time between sample _ collection and' analysis This calculation method assumes that E and Y'are constants and makes no allowance for systematic error.
It should be noted that we have not used the notation < '
MDC for values less than MDC. Rather, we report the result as less than the actual MDC value. Because the MDC is dependent upon variables such as the background count time and sample size, the value ,ill be different for each sample type and ;
even within sample type.
Essentially all radioactivity values measured on this 2
project are near background levels and, more importantly, near the MDC values for each radionuclide and sample type. It has l been well-documented that environmental radioactivity values !
y exhibit great inherent' variability. This is partly - due to 1
sampling and analytical variability, but most importantly due 1 i
to true environmental or biological variability. As a result,-
the overall variability of the surveillance - data is quite-large, and it-is necessary to use-mean values from a rather large sample population size to make any conclusions about thes l.
absolute radioactivity concentrations in any environmental.
pathway..
Environmental radiation surveillance data also commonly ,
exhibit non-normal frequency distributions. Usually the data can be satisfactorily treated using log-normal statistics.
However, when the number of observations is small, i.e., less I than 10, log-normal treatment is tentative. The geometric ,
means and geometric standard- deviations are calculated for selected sample sets. IfIany data point measured resulted in a negative value, the corresponding MDC is used ~ in the calculation of the log-normal statistics. (Negative values are.possible due to the statistical nature of radioactivity counting.) In Section II.H. Conclusions and Summary, the geometric means and geometric standard deviations for the reporting period of 1989 are listed in Table II.H.2. .
The arithmetic mean for each sample set is also listed in Table II.H.2. All measured values, both positive and negative, are used in the calculations of the arithmetic mean.
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1 This-is the suggested practice by. Gilbert (Health Physics.
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Many sets of data' were - compared in ~ this report. The .;
- statistical test used was either a "t"-test or a paired "t"-
L test. If data sets are noted to be significantly different or not significantly.different, the confidence for the statement is'at the 95% level ( or = ' O .' 0 5 ) ..
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In this report we have-footnoted appropriate tables with the maximum permissible concentration . applicable to each l radionuclide. We have chosen to list the' maximum permissible j 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 l produce the maximum permissible radiation ' dose . rate to a-specified individual member of the general public. That value I is 500 mren/ year, but must include the dose from all possible sources, and, therefore, cannot be . solely due to reactor -)
effluent. As stated in 10CFR20 these are the maximum '
concentrations above natural background that a licensee may 1 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 '
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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 used for comparison purposes.
A limitL. that does apply is the. -independent maximum .-
permissible dose commitment rate set by the E.P. A. (4dCFR190) i for any.specified member of the general public from.any.part ,
of the nuclear fuel cycle. This:valueeis 25 mram/ year, the ;t l- dose rate to 'the whole body. from all- ' contributing 1
radionuclides excluding background 'and medical radiation dose rate. ,
Dose commitments are calculated for- hypothetical ;
individuals .for mean concentrations noted in' unrestricted areas.that are significantly above control mean. values.- !
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The following'is the footnote system used in this report La.- Sample'1ost prior to analysis.
.b. Sample missing at site.
c.. Instrument malfunction, d.
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-Sample lost during analysis, l q
- e. -Insufficient weight or volume for analysis.=- '
- f. Sample. unavailable.
- g. Analysis lLn progress. 3
- h. Sample not collected (actual reason.given).-
- 1. Analytical error (actual reason-given).
.i N.A. Not. applicable. i I
6'
II. ' Surveillance Data for January Through December-1989 and Interpretation of-Results l
A. External Gamma-ray Exposure-Rates l .
i
[ The average measured: gamma-ray' exposure rates expressed' '
h in mR/ day are given -in Table . II . A.1. - .The values were- i 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-the number of days that elapsed between pre-exposure and post- i
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exposure annealing to obtain the average daily exposure rate.
- l. The TLD devices are -changed quarterly at each _ location.
i Fading during fiald exposure 'is minimized ; by- the . post-annealing readout procedure.
The-TLD data indicate that'the arithmetic-mean measured' exposure rate-in the facility area for all of 1989 was 0.38 i mR/ day. The mean exposure rate was 0.38. mR/ day for -- the ,
adjacent area and 0.35 mR/ day for.the reference area. These j mean values were not significantly different from each other.
1
-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 fallout. The variation in measured values is due to true
-variation of the above sources plus the variation due to the measurement method. The purpose of the two TLD rings around the reactor is not to measure gamma-rays generated from the
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ll reactor ' facility itself, but to document the presence- or- /
-absence of' gamma-ray emitters deposited upon the ground from-the' reactor effluent. Since the inception of power production by the reactor, there has:been no detectable increase.in the l external exposure- rate dueLto reactor releases. Fallout L
L deposition,'both from.the Chinese nuclear weapon tests, and
/ .
I from-the Chernobyl accident,;was detected in the past. -
The TLD system was' calibrat'ed by exposing chips to a-scattered. gamma-ray flux produced in a cavity surrounded by :
uranium mill Ltailings.. This produces - a gamma-ray spectrum nearly identical to that from natural-background measured in the reactor environs. lThe quality control program includes calibration before readout of.each quarterly batch of TLD devices.
l l For comparison purposes, the EPA in EPA 520/5-89-034 Report #58 lists 0.37 0.27 mR/ day for the background external exposure rate in Denver during the period April to June 1989.
~
This is excellent agreement with the results from this program.
)
l Table II. A.1 Gansnma Exposure Rates. (mR/ day) 1989 l
i Facility Area 1st Quarter 2nd Quarter- 3rd Quarter 4th Quarter ,
F 0.38 0.36 0.38 0.36 i
F-2 0.39 0.33 0.41 0.38 F-3 0.42 0.32 0.39 0.34- ,,
l 0.45 0.35 F-4 0.40 0.34.
F-5 0.38 0.34 0.45 0.38 F-6 0.36 0.34 0.39. 0.42 F-7 0.39 0.38 0.37 0.40 F-8 0.38 0.43 0.44 0.40 F-9 0.36 0.38 0.41- 0.36-F-10 0.33 0.35 0.37 Ot35-F-11 0.41- 0.40 0.42 0.38 F-12 0.39 0.38 0.41 0.38
~F-13 0.35 0.30 0.37 0.32 F-14 0.35 0.35 0.36- 0.35 F-15 0.36 '0.35 0.42 0.38 F-16 0.37 0.33 0.37 0.35 F-17 0.41 0.36 0.38 0.38 F-18 0.42- 0.37 0.43 0.36 i (1.96o) 0.38(0.051) 0.36(0.060) 0.40(0.058) 0.36(0.048)
' Adjacent Area A-1 0.31 0.38 0.42 0.42 A-2 0.37 0.44 0.40 0.39 '
A-3 0.37 0.35 0.41 0.38 A-4 0.42 0.32 0.38 0.39 A-5 0.34 0.32 0.37 0.40-A-6 0.36 0.35 0.37 0.37 .
A-7 0.41 0.34- 0.36- 0.40' A-8 0.41 0.35 0.40 0.42 A-9 0.40 0.36 0.44 0.43 A-10 0.43 0.49 ~0.46 0.43 A-11 0.39 0.33 0.38 0.34 A-12 0.38 0.33 0.38 0.40 A-13 0.39 0.30 0.35 0.35 A-14 0.39 0.36 0.34 0.34 A-15 0.37 0.33 0.36 0.32 A-16 0.39 0.36 0.38 0.37 A-17 0.38 0.36 0.39 0.38 A-20 0.36 0.36 0.42 0.38
, 0.38(0.057) 0.36(0.087) 0.39(0.061) 0.38(0.063) l Reference Area R-2 0.39 0.35 0.33 0.37 R-3 0.36 0.34 0.41 0.37 R-4 0.34 0.28 0.36 0.32 R-5 0.38 0.33 0.36 0.38 I R-7 0.35 0.30 0.34 0.38
. 0.0 W 0.32(0.05H 0;36(0.060) 0.36(0.052) i (l .96 o)
l' a L II.B. Ambient-Air Concentrations I
. 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 i
1989. A-19, while~ technically in the adjacent zone, is only a few meters from the facility boundary and logically should -
I be considered a facility site. It has been termedia facility site since. the . inception of the - monitoring ' program. The reference sites R-3, R-4,- and R-11 are all new locations as of January 1, '
1984 and aufficiently distant- to , be considered reference (control) locations.- (See Table =III.B.1). /
The reported concentrations are -listed in-' units of j
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. A11 E filters, however, are saved' indefinitely for later alpha activity-analysis if needed.
The mean gross beta concentration in air for all facility '
stations for all of 1989 was 26 fCi/m 3. For 1988 the mean value was 26 fCi/m3 also. The mean concentration for all reference stations was 24 fCi/m3 . This slight difference was- !
not statistically significant at 95% confidence level. There was no evidence of fission product or activation product debris in surface air from the reentry of COSMOS 1900. The 10 ,
.:l L
U.S.S.R.. satellite was predicted to reenter the earth's >
atmosphere between mid September'and early October 1988.
L The gross, beta data-for 1989 have been added to the plot- i of air concentrations observed since 1973 (Figure II.B.1) .. In >
3' 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.
ce.n be observed that overall mean values are not significantly >
different and that world-wide fallout, ' principally- due to Chinese atmospheric nuclear weapon tests, is the predominant.
contributor to-the measured values over the period-shown.
There has never been.a significant. difference observed between facility and reference sites.- Thus, it can be again' s concluded that. reactor air effluents of particulate fission products or activation : products are not . a source . of ' dose T l
L commitment for the Fort St. Vrain environs. population.
f 11
.- ----i
M-Table II.B.1 Concentrations of Long-lived Gross Beta Particulate Activity in Af r. (fCi/m3)-
a) First Quarter, 1989 r Facility Sites Reference Sites Collection Date F-7 F-9 F-16 A-19 R-3 R .. R-11 ;
JAN 7 29 (1.5)* 28 (1.9) 28 (1.7) 29 (2.5) 21 (1.4) 21 (1.3) 28 (1.7)
JAN 14 16 (1.1) 12 (1.2) 21 (2.1) 21 (1.4) 12 (1.1) 15 (1.2) 18 (1.6)
JAN 21 18 (1.2) 22 (1.5) 41 (3.2) 23 (2.2) 20 (1.4)- 21 (1.3) 36 (2.5)
JAN 28 51 (2.0) 30 (1.6) 41 (1.9) 39 (1.6) 31 (1.6) 33 (1.4)' 26 (1.2) t FEB 4 12 (0.84) 29 (1.7) 18 (1.2) 32 (2.3) 26 (1.5) 30 (1.4) 30 (1.7)
FEB 11 .30 (1.7) 28 (2.6) 48 (2.9) 46 (1.8) 24 (1.8) 32 (1.7) 40 (2.5):
FEB 18 28 (1.4) 51 (4.0) 34 (1.6) 51 (5.8) 42 (1.7) .32 (1.5)- 42 (2.0)
FEB 25 47 (1.6) 30 (1.8) 38 (1.8) 40 (1.5) 37 (1.8) 37 (1.4) 40 (2.0)
MAR 4 25 (1.1) 28 (1.6) 52-(2.6) 26 (2.2) 28 (1.4) 30 (1.4) 31 (1.8)-
g MAR 11 38 (1.8) 40 (1.9) 34 (1.7) 33 (1.3) 33 (1.7) 32 (1.3) 34 (1.9)
MAR 18 20 (1.3)- e :25-(1.6) 17 (1.7) 25 (1.6) 23 (1.4): 18(J.5)
MAR 25 e 20 (1.0) 28 (147)' 27 (1.3) 23 (1.5) 23 (1.2).
A . 29 29 34 32 27 .27 . 31 1.96o 25 20- 21 20 16 13 16-MAX: 52 ex: 42 .i MIN: . 12 x_ (1.96o):'31 (21). -
n: 46 MIN: 12 i (1.96 o): .28(15) n: 35
- 1.96o (Due .to-counting statistics) e Insufficient; weight.or volume for an~ a lysis ,
_ ~ _ , _ . . _ _ _ __ _ _._ _ __ ~: _ _ _ _ ._ . _ _ _ . _ . . . _ _ _ _ _ _ _ _ _ . _ _ . -
?
E Table II.B.1 Concentrations of Long-lived Gross Beta Particulate Activity in Air. (fCi/m3) b) Second Quarter,1989 Facility Sites Reference Sites
, Collection Date' F-7 F-9 F-16 A-19 R-3 R-4 R-11 APR 1 13 (1.1)* 18 (1.6) 17 (1.3) 11 (1.5) 12 (1.3) 15 (1.2) 16 (1.4) .
APR 8 14 (1.5) 11 (1.0) 14 (1.2) 16 (1.0) 6.9 (0.95) 13 (0.91) 13 (1.31 APR15 17 (6.2) 28 (1.5) 30 (1.5) 24 (2.3) 27 (1.3) 31 (1.6) 19 (1.5) '
i APR 22 39 (2.3) 23 (1.3) 26 (1.6) 26 (1.3) 22 (1.4) 24 (1.3) 26 (1.7)
APR 29 e 19 (1.5) 20 (1.3) 20 (2.3) 19 (1.3) 20 (1.2) 21 (1.5)
MAY 8 21 (1.1) 28 (2.1) 18 (1.3) 19 (1.1) 16 (1.1) 17 (1 S) 17 (1.4)
MAY 15 23 (1.3) 21 (1.8) 24 (1.4) 23 (2.3) 21 (1.2) 23 (1.3) 23 (1.5)
MAY 20 18 (1.1) 16 (2.1) 19 (1.3) 18 (1.4) 17 (1.2) 19 (1.1) 18 (1.4) g MAY 27 21 (1.4) 20 (1.6) 20 (1.3) 18 (2.4) 20 (1.3) 21 (1.3) 20 (1.6)
JUN 3 16 (1.2) 19 (1.1) 18 (1.3) 18'(1.1) 19 (1.3) 16 (0.99) 18-(1.4)
JUN 10 16 (1.1) 17 {1.3) 17 (1.2) 18 (2.0) ,17 (1.1) 17 (1.1) 18 (1.5)-
l JUN 17 20 (1.1) 32 (4.8) 19 (1.3) 20 (1.2) 19 (1.3) 21 (1.2) .19 (1.4) l JUN 24 16 (1.2) 18 (1.6) 20 (1.3) 18 (2.1) 19 (1.3) 18 (1.2) 19 (1.6) 1
$ 20 21 20 19 18 20 19 i
1.96o 13 11 8.3 7.4 9.5 91 6.2 nn: 39 MAX: 31 MIN: 11 i (1.96o): 20(10) , MIN: 6.9 i.(1.96o): 19(8.3 )
n: 51 , n: 39
- 1. 96 o (Due to c,oun ting s<ng
,.....-~,g,_,--- ta tis tig.y
Table II.B.1 Concentrations of Long-lived Grc;s Beta Particulate Activity in Air. (fCi/m3) c) Third Quarter, 1989 Facility Sites Reference Sites
, Collection Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 JUL 1 24 (1.4)* 32 (2.0) 29 (1.6) 26 (2.3) 28 (1.6) 27 (1.5) 30 (1.9)
JUL' 8 26 (1.5) 32 (2.0) 29 (1.6) 26 (2.3) 28 (1.6) 27 (1.5) 30 (1.9) i JUL 15 26 (1.4) 26 (1.5) 26 (1.6) 27 (1.6) 24 (1.6) 25 (1.3) 27 (1.9)
JUL 22 20 (1.1) 28 (1.8) 17 (0.94) 26 (2.3) 27 (1.5) 29 (1.5) 28 (1.9)
JUL 29 30 (1.6) 29 (1.7) 32 (1.8) 28 (1.7) 25 (1.5) 28 (1.3) 31 (2.2)
AUG 5 11 (1.1) 36 (2.3) 27 (1.7) 25 (1.2) 22 (1.31 17 (1.7) 20 (1.9) 4 AUG 12 23 (1.7) 88 (5.2) 27 (1.7) 25 (1.2) 24 (1.5) 24 (1.2) 26 (1.8)
AUG 19 23 (1.7) 14 (2.1) 27 (1.4) 18 (2.1) 25 (1.4) 24 (1.3) 26 (1.7)
AUG 26 25 (1.6) 14 (2.2) 26 (1.6) 15 (2.1) 23 (1.5) 26 (1.3) 24 (1.7) g; SEP 2 30 (1.8) 24 (1.5) 26 (1.5) 26 (1.2) 27 (1.5) 30 (1.6) 27 (1.8)
SEP 9 2.1 (1.6) 18 (1.1) 38 (1.9) 51'(2.6) 26 (1.5) 18 (1.1) 28 (1.7)
SEP 16 16 (1.3) 17 (1.3)' 18 (1.3) 17(0.93) 17 (1.2) 18 (1.3) 17 (1.51 SEP 23 25 (1.8) 24 (1.2) 24 (1.6) 23 (2.0) 24 (1.5) 13 (1.0) 25 (1.7)
SEP 30 44 (2.4) 39 (1.8) 44 (1.9) 43 (1.5) 40 (1.8) 41 (1.7) 17 (1.6) i 25 30 28 27 26 25 . 25
+
1.96o - 15 36 14 19 9.8 14 89 MAA: 83 MAK
- 41 MIN: 11 i (1.96o): 27(22). MIN: 13 i (1.96 o): 25(11) n: 56
- n: 42 l.96o (Due to counting statistics) 9 3 y , y -%
v -+e m. < - -+- y n -# , e- % 4, w i-+ e w3,.-25 , 'w--- +amw-eww y-w--
Table II.B.1 Concentrations of Long-lived Gross Beta Particulate Activity in Air. (fC1/m3 )
d) Fourth Quarter,1989 Facilfty Sites Reference Sites Collection Date F-7 F-9 F-16 A-19 R R-4 R-11 23 (1.2) 4.4 (1.1) 24 (1.5)
OCT 7 26 (2.0)* 22 (1.9) 24 (1.5) 24 (1.2)
OCT 14 36 (2.5) 34 (1.9) 36 (1.6) 33 (1.4) 32 (1.7) 39 (1.9) 34 (1.9)
OCT 21 24 (2.1) 22 (1.2) 23 (1.2) 20 (1.8) 22 (1.6) 20 (1.1) '23 (1.51 OCT 28 17 (1.1) 27 (1.7) 29 (1.5) 28 (1.3) 40 (1.8) 24 (1.5) 27 (1.7)
NOV 4 24 (1.2) 21 (1.3) 25 (1.6) 25 (2.0) 24 (1.7) 20 (1.1) 23 (1.5)
NOV 11 15 (1.0) 16 (1.5) 17 (1.3). 16 (1.0) 15 (1.3) 15 (1.3) 17 (1.4)
NOV 18 23 (1.3) 3.6 (0.88) 26 (1.8) 23 (1.9) 24 (1.7) 20 (1.1) 24 (1.6)
NOV 25 22 (1.3) 35 (2.4) 32 (1.7) 32 (1.5) 27 (1.6) 25 (1.5) 30 (1.8)
DEC 2 22 (1.2) 22 (1.4) 19 (1.6) 18 (1.8) 17 (1.5) 17 (1.3) 20 (1.4) g DEC 9 21 (1.1) 20 (2.0) 22 (1.4) 26 (1.4) 22 (1.5) 19 (1.3) 24 (1.6)
DEC 16 32 (1.3) 34 (1.6) 30 (1.8) 30 (2.2) 28 (1.8) 30 (1.3) 31 (1.7)
DEC 23 36 (1.5) 42 (2.4) c 51 (2.1) 38 (2.0) 33 (1.7) 42 (2.2)
DEC 30 34 (1.7) 32 (1.7) 29 (1.7) 29 (2.4) 25 (1.9) 18 (1.1) 29 (1.6) 1 i 26 27 26 27 26 23 27 1.96o 14 15 11 17 14 ' 14 - 13
, FIAA: 51 MAX: 40 MIN: 15 x_ (1.96o): 27(14) . MIN: 15 i (1.96 o): 25(13) :
n: 49 n: 39
- 1.96o (Due to counting statistics) c Pump malfunction
- .- . -. , . . . , - - - _ . - ~ _ . _ . . _ _ . . . - . . . . . - _ . _ ~ . _ _ _ . _ - -
-1
.. i l
l Figure II.B.1 l
i 1000 -
Gross Beta Concentrations in Air i 900 -
800 -
700 -
" " '" ' Y **E""U " "" "
600 - 0----o R = 53 l
~
. Reference Sampling Stations l r = 60 i 400 -
l l .
300 -
200 - '
I sl
\ ,
1
\ l
\
m \ t E \ 'l I N 100 -
\ 'f U 90 - \ l 'l 80 - l f l 70 l I g l
60 \ I
\ j I l
- g 50 E
\ l\ ,
\ l \
40 -
@\ lll , l -
\
! l , \
30 -
\
\i 20 -
g l $
I \
h)
\ /
\v Y \ ,
10 ' ' ' ' ' ' ' ' ' 'e ' ' ' ' ' ' -J 1973 '74 '75 '76 '77 '78 '79 '80 '81 '82 '83 '84 '85 '86 '87 '88 '89 '9C -.
Time (year) 16
)
1 i
- 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 1989 is listed >
in Tables II.B.2a-2d. The corresponding tritium concan'tration in air (pCi/m3 ) is calculated from the specific activity data using weekly mean temperatures and dew points measured at the i
FSV meteorological tower. The measuring point is at a height
~
of 2 m from the surface. The tritium air concentrations are
! shown in Table II.B.3a-3d.
l The principle release mode of tritium from the reactor is l
batch liquid releases from holding tanks (system 62). The tank water is first analyzed and then released with sufficient additional dilution, if necessary, to not exceed 10CFR20 concentration limits. The summary of tritium release by al1 modes is shown in Table II.B.4. The summary indicates that the total tritium released in 1989 was 70 percent of that l released in 1988 by all routes. (See 1987 annual report to the USNRC). This effluent release was detected principally at two of the air sampling sites (F-16 and A-19).
Sampling locations F-16 and A-19 are located.near the Goosequill Ditch, which is the common route for . liquid effluent tritium release. Tables II.B.2a-2d indicate a strong correlation of elevated atmospheric tritium concentrations corresponding to the batch release of tritium in water along 17
l
)
i the ditch. Due to evaporation while in transit, elevated l tritium concentrations in air have been observed for these two ;
r l
locations often in past years. The concentrations observed, j however, have always been below the limit of - regulatory concern. The occasional elevated values at the reference sites are assumed to be statistically false positive values. ,
The high values observed at R-3 during October are as'sumed to i be analytical error, probably cross contamination. Great effort in the laboratory is taken to minimize the chances for I
sample cross contamination, but on this occasion this was likely the source of the aberrant values. R-3 is at the CSU !
- dairy farm in Fort Collins and cannot be influenced by FSV I effluents. ,
The mean value for sites F-16 and A-19 were significantly greater (P<0.001) than for all other sites during the year.
When all four facility sites are averaged, however, the total
- mean value was only 400 pCi/L. The mean for the three l reference sites was less than the MDC value of 400 pCi/L. The mean for the facility stations was not significantly different than the mean for the adjacent stations. Inhalation is not a significant pathway for tritium dose to humans. The milk and food product pathway is the only significant source of .
radiation dose to humans from environmental tritium. See results for these pathways in sections II.D and II.E.
18
i i
l i
Since the same relative humidity is assumed for all sites, Table II.B.3 shows the same site dependence on reactor r effluent as Table II.B.2. only the units used to measure i tritium in surface air are different.
r 4 r P
9 i
6 l
19
l l
l- Table II.B.2 Tritium Specific Activity.in Atmospheric Water Vapor. (pCi/L) a) First Quarter,1989 l
Facility Sites Reference Sites Collection j Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 JAN 7 < 400 < 400 < 400 < 400 < 400 < 400 < 400 l
JAN 14 < 400 < 400 < 400 < 400 < ,400 < 400 < 400 JAN 21 < 400 < 400 < 400 560 (340)' ' < 400 < 400 < 400 JAN 28 < 390 < 390 < 390 < 390 < 390 < 390 < 390 ,
FEB 4 < 400 .< 400 < 400 < 400 < 400 < 400 < 400 FEB 11 < 400 < 400 < 400 < 400 < 400 < 400 < 400 FEB 18 < 400 < 400 < 400 < 400 < 400 < 400 < 400 I FEB 25 480 (400)* < 400 < 400 < 400 < 400 < 400 < 400 MAR 4 < 400 < 400 < 400 < 400 < 400 < 400 < 400 g MAR 11 < 400 < 400 < 400 e < 400 < 4GO < 400 MAR 18 < 400- < 400 < 400 < 400 < 400 < 400 < 400 MAR 25 < 400 .< 400 < 400 < 400 < 400 < 400 < 400 1
l
- l.96 o (Due to counting statistics) e Insufficient weight or volume for~ analysis
~
Table II.B.2 Tritium Specific. Activity in Atmospheric Water Vapor. (pCi/L) b) Second Quarter,1989 Facility Sites Reference Sites Collection Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 APR 1 < 400 < 400 < 400 < 400 < 400 < 400 < 400 APR 8 < 400 < 400 < 400 < 400 < 400 < 400 < 400 APR 15 < 400 < 400 < 400 < 400 < 400 <400 < 400 APR 22 < 390 < 390 560(410)* 1600(430) < 390 < 390 < 390 APR 29 < 390 < 390 < 390 < 390 d < 390 < 390 MAY 6 < 400 < 400 700 (420) 760 (420) < 400 < 400 < 400 MAY 13 < 400 < 400 < 400 < 400 < 400 < 400 < 400 MAY 20 < 400 < 400 < 400 < 400 < 400 < 400 < 400 MAY 27 < 390 < 390 < 390 < 390 < 390 < 390 < 390 m JUN 3 < 390 < 390 < 390 < 390 < 390 < 390 < 390 JUN 10 < 400 < 390 < 400 < 400 < 390 < 390 < 400 JUN 17 < 400 < 400 < 400 < 400 < 400 < 400 < 400 JUN 24 < 390 < 390 < 390 < 390 < 390 < 390 < 390
- 1.96 o (Due to coun ting s tatis tics)-
d Sample lost during analysis, .
Table II.B.2 Tritium Specific Activity in Atmospheric Water Vapor. (pCi/L) c) Third Quarter, 1989 Facility Sites Reference Sites Collection Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 JUL 1 < 390 < 390 830 (410)* 970 (420) < 390 < 390 < 390
. JUL 8 < 430 < 430 720 (450) 730 (450) < 430 < 430 < 430 4
JUL 15 < 430 < 430 810 (450) 770 (450) < 430 < 430 < 430 JUL 22 < 420 < 420 1200 (450) 1100 (450) < 430 < 430 470 (440)
JUL 29 < 420 < 430 790 (420) 1300 (460) < 430 < 430 < 420 AUG 5 640 (420) 750 (420) 760 (420) 1100 (430) 490 (420) 660 (420) < 400 AUG 12- 920 (420) 620 (410) 1300 (430) 840 (420) 760 (420) < 400 470 (410)
AUG 19 < 400 710 (420) 890 (420) 1100 (430) 400 (420) < 400 < 400 1
l AUG 26 450 (420) 600 (410) 1100 (430) 1400 (430) 560 (410) < 400 < 390 3--
SEP 2 < 390 < 390 440 (420) 720 (420) < 390 < 390
.< 390 SEP 9 < 390 e. < 390 410 (410) < 390 < 390 < 390 SEP 16 < 400 < 400 < 400 < 400 < 400 < 400 < 400 i
SEP 23 < 400 < 400 < 430 < 390 e < 400
, < 400 SEP 30 530 (420) < 400 680 (420) < 390 < 400 < 400 - < 400 l
- 1.96o (Due to counting statistic.s) e Insufficient weight or voluae for analysis :
_ _ , _, . ~, . . . . _ . . . _ _ _ _ _ _ _ _ _
Table II.B.2 Tri tiu:n Specific Activi ty in Atmospheric Water Vapor. (pCi/L) d) Fourth Quarter,1989 Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3' R-4 R-11 OCT 7 < 390 < 390 e 1100 (420)" < 390 < 390 - < 390 ,
j OCT 14 450 (410) < 430 e 3700 (460) 4400 (470) e 580 (450)
OCT 21 650 (410) < 430 e 1800 (430) 550 (410) < 390 460 (410)
OCT 28 720 (410) 540 (410) 690 (410) l 1900 (440) 1000 (410) 1100 (410) < 390 NOV 4 < 390 < 390 2000 (440) 1000 (430) < 390 < 390 < 390 NOV 11 < 390 < 390 < 390 530 (420) < 390 < 390 < 390 NOV 18 < 390 < 390 < 390 < 390 < 390 < 390 < 390 NOV 25- < 390 < 390 < 390 1300 (420) < 430 . < 390 < 390 DEC 2 < 420 < 420 e 440 (440) < 420 e < 420 DEC 9 < 420 < 420 < 420 < 420. < 420 < 420 e DEC 16 e 'e < 420
< 420 < 420 e < 420 DEC 23 < 420 < 420 e e < 420 < 420 e DEC 30 < 410 < 410 < 410 < 410 < 410 e < 410 L -
e *1.96o (Due toweight Insufficient countin9 statistic or or vol-ume [-) analysis . I 4
._w--- -
, , ., ,_ . , . , ,,.-e -, -
Table II.B.3 Tritium Concentrations in Atmospheric Water Vapor. (pCi/m3 )
a) First Quarter, 1989 Facility Sites Reference Sites ColleEtion A-19 R-3 R-4 R-Il Date F-7 F-9 F-16
< l .2 < 1.2 < l.2 < 1.2 < l.2 JAN 7 < 1.2 < l.2
< .98 < .98 < .98 < .98 < .98 JAN 14 < .98 < .98
< 1.3 1.8(1.1) < l.3 < l.3 < 1.3 JAN 21 < 1.3 < l .3
< 1.4 < l.4 < l.4 < 1.4 < l.4 JAH 28 < 1.4 < l.4
< .68 < .68 < .68 < .68 < .68 FEB 4 < .68 < .68
< .75 < .75 < .75 < .75 < .75 g FEB 11 < .75 < .75
< l.2 < l.2 < l.2 < l.2 < 1.2 < l.2 FEB 18 < l.2
< l.5 < l.5 < l.5 < l.5 <l1.5 FEB 25 1.8(1.5) < l.5
< l.6 < 1.6 < l .6 < l.6- < 1.6 MAR 4 < 1.6 < l.6
< 1.6 < 1.6 e < l.6 < l.6 < 1.6 MAR 11 < 1.6
< l.3 < 1.3 < l.3 < 1.3 MAR 18 < 1.3 < l.3 < l.3
< l.6 < 1.6 < 1.6 < 1.6 < 1.6 < l.6 < l.6 MAR 25
- 1.96o (Due.to counting statistics) e Insufficient weight or volume for analysis
~.-
Table II.B.3 Tritium Concentrations in Atmospheric Water Vapor. (pCi/m3) b) Second Quarter,1989 Facility Sites Reference Sites Collection Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 APR 1 < 1.7 < 1.7 < 1.7 < 1.7 < 1.7 < 1.7 < 1.7 APR 8 < 1.5 < 1.5 < 1.5 < 1.5 < 1.5 < 1.5 < 1.5 APR 15 < 1.5 < 1.5 < 1.5 < 1.5 < l.5 < 1.5 < 1.5
~
APR 22 < 1.9 < 1.9 2.8(2.0) 7.9(2.1) < 1.9 < 1.9 < 1.9 APR 29 < 2.0 < 2.0 < 2.0 < 2.0 d < 2.0 < 2.0 N MAY 6 < 2.0 < 2.0 3.5(2.1) 3.8(2.1) < 2.0 < 2.0 < 2.0 MAY 13 < 2.2 < 2.2 < 2.2 < 2.2 < 2.2 < 2.2 < 2.2 MAY 20 < 2.5 < 2.5 < 2.5 < 2.5 < 2.5 < 2.5 < 2.5 MAY 27 < 2.0 < 2.0 < 2.0 < 2.0 < 2.0 < 2.0 < 2.0 JUtl 3 < 2.6 < 2.6 < 2.6 < 2.6 < 2.6 < 2.0 < 2.6 JUtl 10 < 3.3 < 3.2 '< 3.3 < 3.3 < 3.2 < 3.2 ,< 3.3 JUtl 17 < 2.9 < 2.9 < 2.9 < 2.9 < 2.9 < 2.9 < 2.9
[2.5
~
JUll 24 < 2.5 < 2.5 < 2.5 < 2.5 < 2.5 < 2.5
- l.96 o (Due to. counting statistics) -
d Sample lost during analysis -
Table 11.8.3 Tritium Concentrations in Atmospheric Water Vapor. (pCi/m3) c) Third Quarter,1989 Facility Sites Reference Sites Collection -
Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 JUL I < 3.1 < 3.1 6.5(3.2) 7.6(3.3) < 3.1 < 3.1 < 3.1 JUL 8 < 3.3 < 3.3 5.5(3.4) 5.6(3.4) < 3.3 < 3.3 < 3.3 JUL 15 < 3.7 < 3.7 7.0(3.9) 6.7(3.9) < 3.7 < 3.7 < 3.7 JUL 22 < 3.6 < 3.6 10(3.9) 9.5(3.9) < 3.7 < 3.7 4.0(3.8)
JUL 29 < 3.8 < 3.9 7.1(3.8) 12(4.1) < 3.9 < 3.9 < 3.8 y AUG 5 6.6(4.3) 7.7(4.3) 7.8(4.3) 11(4.4). 5.0(4.3) 6.8(4.3) < 4.1 AUG 12 9.2(4.2) 6.2(4.1) 13(4.3) 8.4(4.2) 7.6(4.2) < 400 4.7(4.1)
- AUG 19 < 3.6 6.3(3.7) '7.9(3.7) 9.8(3.8) 3.6(3.7) < 3.6 < 3.6 AUG 26 3.5(3.2) 4.6(3.2) 8.5(3.3) 11(3.3)' 4.3(3.2) < 3.1 < 3.0
~
SEP 2 < 1.1 < 1.1 1.2(1.1) 2.0(1.1) < 1.1 < 1.1 < 1.1 SEP 9 < 2.3 'e < 2.3 2.4(2.4) < 2.3 < 2.3 '< 2.3 SEP 16 < 2.0 < 2.0 < 2.0 < 2.0 < 2.0 < 2.0 < 2.0 SEP 23 -
< 1.5 < 1.5 < 1.6 < 1. 5 e < 1.5
< 1.5 SEP 30 2.1(1.7) < 1.6 2.7(1.7) < 1.5 < 1.6 < 1.6 < 1.6
- 1.96o (Due to counting s ta tis tics")
e Insuf ficient weight or volume for analysis
Table II.B.3 Tritium Concentrations in Atmospheric Water Vapor. (pCi/m3) d) Fourth Quarter,1989 Facility 5.'es Reference Sites Collection Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 OCT 7 < 1.6 < 1.6 e 4.4(1.7) < 1. 6 < 1.6 < 1.6 OCT 14 1.6(1.5) < 1.5 e 13(1.0) 16(1.7) e 2.1(1.6)
OCT 21 3.4(2.1) < 2.2 e 9.3(2.2) 2.8(2.1) < 2.0 2.4(2.1)
OCT 28 3.7(2.1) 2.8(2.1) 3.5(2.1) 9.7(2.2) 5.5(2.1) 5.6(2.1) < 2.0 il0V 4 < 1.9 < 1.9 9.7(2.1) 4.8(2.1) < 1.9 < 1.9 < 1.9 110V 11 < 1.8 < 1.8 < 1.8 2.4(1.9) < 1.8 < 1.8 < 1.8
!!0V 18 < 1.5 < 1.5 < 1. 5 < 1.5 < 1.5 < 1.5 - < 1.5 110V 25 < 1.6 < 1.6 < 1.6 5.4(1.7) < 1.8 < 1.6 < 1.6 DEC 2 < 1.4 < 1.4 e 1.5(1.5) < 1.4 e < 1.4 DEC 9 < 1.7 < 1.7 < 1.7 < 1.7 < 1.7 < 1.7 e DEC 16 e e < 1.1 < 1.1 < 1.1 e < 1.1
~~
DEC 23 < .88 < .88 e e < .88 < . 88 ' e DEC 30 ,
< 1.4 < 1.4 < 1.4 < 1.4 . < 1.4 .e < 1.4
- 1.96 o (Due to counting statistics) e Insufficient weight or volume for analysis -
__ _A_._m.- _- _ . . _ _ ~ ,,g._
.,4,, , ,. , -._,,,,s _ , , ,. . _ _ ,
, y n.,4.n_y. , .r,
.n
Table ll.B.4 Tritium Released (Ci) in Reactor Effluents,1989 Tritium Released (Ci) in Reactor Effluents, 1989 MODE JAff FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC TOTAL mtinuous furbine .00753 .00330 .00394 .0940 .220 .332 .253 .205 .0868 .113 .0339 .0153 1.368 sildin9 unp) itch riease t:act:r .0251 .0400 .0962 .0258 .0798 .0844 .0801 .311 .257 .121 .07% .0363 1.242 silding .
sinp) ttch 21:ase 8.70 3.44 4.59 9.31 5.88 '6.56 10.5 14.4 10.1 23.8 11.8 .345 109.4 iystem 62) iseous .0407 .00678 .0178 .623 .160 .850 .0728 1.46 .334 .0990 .0532 . 00786' 3.725 ack ITAL 8.773 3.490 4.708 10.05 6.340' 7.826 10.91 16.38 ' 10.78 24.13 11.% 0.4045 115.74
. l
.+
.--.m. . - . . , _ - . _
l i
- 3. Concentrations of Gamma-rav Emittina Radionuclides in
~
A=hiant Air Tables II.B.5a-5d list the concentrations of I-131 in air' l as measured by activated charcoal sampling and Ge(Li) gamma-- [,
ray spectrum analysis. Each sample from the seven air f
sampling stations is counted within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after collection.
A 100 minute count and a sample volume of 800 m3 is required to achieve an MDC of 33 fCi/m3 . Radon daughters and Thoron [
daughters are trapped en 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- j 131 using the Ge(Li) high resolution spectrometry system. Any '
positive I-131 activity is corrected for radioactive decay back to the midpoint of the collection period. Decay correction to the midpoint of the sampling period is appropriate as any I-131 in air would not arrive at the sampling stations at a constant rate, but rather randomly-in pulses of short duration compared to the collection period. -
This is the case whether the I-131 source term would be weapons testing fallout or reactor stack effluent.
There were only occasional positive valuas very near the MDC value and all are assumed to be false positives. I-131 -
concentrations due to reactor effluent have never been #
detected in any sample type in the Fort St. Vrain environs.
Table II.B.6 lists measured ambient air concentrations of Cs-134 and Cs-137. These values are from gamma-ray spectrum analyses on weekly air filters composited quarterly from each 29-
P t
l t
t i 1 l t of the seven air sampling stations. The occasional positive
~
Cs-137 concentrations measured are likely due to resuspension of surface soil. The Cs-137 activity is due to Chernobyl or ,
l l previous world-wide fallout which is bound by clay minerals on v
the surface of undisturbed soil. For the entire year, the !
mean of the facility stations was not different from the mean j of the reference stations. ,
Although only Cs-134 and Cs-137 are reported, each gamma- i ray spectrum is scanned for evidence of peaks from- other fission products and activation products. only gam" my activity due to the naturally occurring' backynond 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.
l l e 4
30-
Table II.B.5 Iodine-131 Concentrations in Air. (fCi/m3) a) First Quarter,1989
- Facility Sites Reference Sites Collection Midpoint F-7 F-9 F-16 A-19 R-3 R-4 , R-11 .
- 1/04/89 < 16.0 < 14.0 < 21.0 < 31.0 < 20.0 < 19.0 < 19.0
! 1/11/89 < 18.0 < 18.0 < 16.0 < 9.1 < 9.2 < 15.0 < 24.0 1/18/89 < 12.0 < 20.0 < 25.0 < 15.0 < 26.0 < 20.0 < 21.0 1/25/89 < 11.0 < 13.0 < 18.0 < 7.5 < 19.0 < 11.0 < 12.0 2/01/89 < 11.0 < 13.0 < 22.0 < 32.0 < 12.0 < 24.0 < 13.0 2/08/89 < 7.5 < 17.0 20 (24)* < 25.0 15 (16) < 27.0 < 20.0 2/15/89 < 11.0 33 (38) < 16.0 < 31 < 14.0 . < 15.0 < 28.0 i
2/22/89 < 7.9 < 9.9 < 1.1 < 5.3 < 12.0 < 4.3 < 6.6 i
, 3/01/89 < 16.0 20.0 (20.0) < 23.0 < 20.0 < 7.5 < 16.0 < 22.0
~
3/08/89 < 9.7 < 15.0 < 14.0 21.0 (23.0) < 17.0 < 16.0 < 7.4 3/15/89 < 18.0 f < 23.0 < 17.0 23.0 (25.0) < 16.0 < 20.0 3/22/89 e < 21.0 < 27.0 < 27.0 < 13.0 < 19.0 < 21.0
- 1496o (Due to Counting Statistics) .
~
e Insuf ficient wieght or volume for analysis f Sample unavailable y e g _ , ,y .. -
4 .e . ., , + . . . . , ,-y-.-- .y~. . e,i ~ ., __.y.w+.,..~%,
Table II.B.5 lodine-131 Concentrations in Air. (fCi/m3) a) Second Quarter, 1989 Co l l ec tiori Facility Sites Reference Sites F.idpoint F-7 F-9 F-16 A-19 R-3 R-4 R-11 -
3/29/89 < 21.0 < 27.0 < 9.4 < 29.0 40 (30) < 12.0 < 13.0 4/5/89 < 27.0 < 6.4 < 14.0 < 11.0 < 16.0 < 3.1 < 27.0 4/12/89 31 (30) < 12.0 40.0 (30.0) < 16.0 < 23.0 < 20.0 <-14.0 4/19/89 < 26.0 < 22.0 < 16.0 < 13.0 < 10.0 < 18.0 < 19.0 4/26/89 e < 19.0 < 11.0 < 19.0 < 23.0 < 12.0 39.0 (36.0) 5/03/89 < l0.0 < 29.0 < 23.0 < 30.0 < 9.0 < 4.9 < 14.0 5/10/89 < 8.5 < 25.0 < 15.0 < 11.0 < 7.6 < 14.0 < 21.0 .
5/17/89 < 13.0 < 12.0 31.0 (30.0) < 15.0 < 8.1 < 26.0 < 23.0 5/24/89 < 11.0 < 14.0 < 7.2 < 14.0 < 16.0 < 32.0 < 18.0 Lm 5/31/89 < 7.2 < 12.0 < 15.0 < 20.0 < 14.0 < 15.0 < 14.0 6/07/89 < 5.6 < 7.4 < 18.0 < 20.0 < 9.7 < 6.7 d 6/14/89 < 22.0 < 26.0 < 24.0 < 9.3 < 12.0 < 8.9 < 22.0 6/21/89 < 20.0 < 10.0 < 10.0 < 18.0 < 29.0 < 14.0 < 14.0
- l.96o (Due to Counting Statistics) d Sample lost during evaluation :
e Insufficient weight or volume for analysis
l Table 11.B.5 lodine-131 Concentrations in Air.
c) Third Quarter 1989 I
Cci %n Facility Sites Reference Sites Hidpoint F-7 F-9 F-16 A-19 R-3 R-4 R-11 6/28/89 < 7.3 < 8.1 < 8.8 < 18.0 < 6.2 < 14.0 < 8.3 7/05/89 26.0 (31.0)*< 8.5 < 22.0 < 13.0 < 20.0 < 19.0 < 32.0 7/12/89 < 5.1 < 12.0 < 16.0 < 14.0 < 23.0 < 15.0 < 14.0 7/19/89 < 19.0 < 31.0 < 18.0 < 21.0 < 5.2 15.0 (16.0) < 18.0 7/26/89 < 6.2 32.0 (31.0) < 6.7 < 15.0 < 32.0 < 6.3 < 7.8 8/02/89 < 15.0 < 10.0 < 7.0 < 15.0 < 19.0 < 35.0 < 31.0 8/09/89 < 23.0 < 18.0 < 7.0 < 13.0 < 9.4 < 4.4 20.0 (24.0) 8/16/89 < 17.0 < 31.0 < 6.8 < 19.0 < 5.8 < 7.4 < 29.0 8/23/89 < 28.0 < 29.0 43.0 (43.0) < 34.0 < 13.0 < 21.0 < 8.0
, 8/30/89 < 10.0 < 24.0 < 30.0 < 26.0 < 17.0 < 11.0 < 13.0 U 9/06/89 < 9.6 < 9.4 < 25.0 < 15.0 < 8.5 < 7.2 < 7.3 9/13/89 < 13.0 < 12.0 < 28.0 < 11.0 < 13.0 < 10.0 < 17.0 9/20/89 45.0 (32.0) < 14.0 < 15.0 < 16.0 < 11.0 < 8.3 < 28.0 9/27/89 ,
< 9.2 < 6.3 < 24.0 < 5.4 < 11.0 < 14.0. < 21.0
- 1.96o (Due to Counting Statistics) e e
..-.i--.s_m _:. _ .m.. _
Table II.B.5 Iodine-131 Concentrations in Air. I d) Fourth Quarter,1989 ,
Facility Sites Reference Sites i, Collection . -
jMidpoint F-7 F-9 F-16 A-19 R-3 R-4 R-11 10/04/89 < 17.0 < 6.9 < 7.1 < 33.0 < 11.0 < 12.0 < 7.6 10/11/89 < 11.0 < 9.6 < 32.0 < 28.0 < 17.0 < 24.0 < 21.0 10/18/89 < 11.0 12 (14)* < 12.0 < 12.0 < 28.0 < 6.3 25.0 (27.0) 10/25/89 < 3.8 < 22.0 21.0 (14.0) < 7.9 < 18.0 < 36.0 < 26.0 11/01/89 < 6.4 < 5.4 < 20.0 < 16.0 < 17.0 < 7.8 < 17.0 11/08/89 < 14.0 < 35.0 < 34.0 < 11.0 < 15.0 < 19.0 < 9.5 11/15/89 < 16.0 < 4.3 < 6.4 < 9.0 < 10.0 < 12.0 < 7.6 11/22/89 < 25.0 < 10.0 < 30.0 < 18.0 < 33.0 < 35.0 < 21.0 11/29/89 < 4.8 < 12.0 < 6.8 < 15.0 < 29.0 < 11.0 < 11.0
- 12/06/89 < 9.4 < 20.0 < 13.0 < 9.6 < 18.0 < 12.0 < 16.0 12/13/89 < 13.0 < 19.0 < 22.0 < 21.0 < 14.0 < 18.0 < 17.0 12/20/89 < 29.0 < 9.8 ~c < 6.2 < 16.0 < 26.0 < 27.0 12/27/89 < 8.2 < 6.7 < 17.0 < 30.0 < 16.0 < 4.1 < 6.6
- 1.96o (Due to Counting Statistics) c Instrument malfunction ,
. n s , , ,. _ . =c.u -
+..m --v r., ,w. v-- w-a 2,= --
1 m _.i _ , . .
Table II.B.6 Radiocesium Concentrations in Ambient Air. ( f Ci/m3) 1989 Facility Sites Reference Sites Radio-nuclide F-7 F-9 F-16 A-19 R-3 R-4 R-11 1st Cs-134 < 0.49 < 1.9 < 1.6 < 1.7 < 1.1 < 1.1 < 2.0 Quarter Cs-137 < 0.49 < 2.1 2.4 (1.9)* < 1.7 < 1.1 < 1.2 < 2.1 2nd Cs-134 < 0.86 < 1.2 < 1.4 < 1.2 < 1.5 < 1.4 < 1.1 Quarter Cs-137 < 0.87 < 1.2 1.4 (1.6) < 1.2 1.5 (1.8) < 1.4 < 1.0
~
3rd Cs-134 < 1.4 < 0.49 < 1.0 < 0.87 < 0.79 s 0.94 1.3 (1.4)
M Quarter Cs-137 < 1.4 < 0.53 < 1.0 < 0.88 < 0.84 < 0.92 < 1.1 4th Cs-134 < 0.84 < 1.6 < 0.55 < 0.66 < 1.1 < 0.57 . < 1.9 -
Quarter Cs-137 < 0.80 < I.5 < 0.59 < 0.68 < 1.2 < 0.62 2.1 (2.3)
- 1.96o (Due to Counting Statistics) e
t t
! l II.C. Radionuclide Concentration in Water ,
- 1. Drinkina Water .
Drinking water is sampled weekly and composited biweek,1y l at two locations. 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 affluents. R-3 samples are from the Fort Collina drinking water supply and serve as a reference location since i
its source is run-off surface water from the Rocky Mountains i
to the West. However, water treatment systems ' for the two s
water supplies are very different.
1 Table II.C.1 shows gross beta concentrations measured in -
1989 from each water supply. The mean for the Gilcrest site was again significantly higher than the Reference site in Fort Collins. This is only due to the different water treatment -i practices. The city of Gilcrest does not filter its water and natural radionuclide concentrations due to the suspended solids are responsible for the higher measured concentrations.
As can be observed in Table II.H.2, the mean for the entire
~
year for the Gilcrest site was similar to that observed in previous years. i Table II.C.2 lists measured tritium concentrations in these same two drinking water sources. The yearly arithmetic .
mean value for the Gilcrest location was less than MDC. The mean yearly concentration measured in the Gilcrest supply was .
statistically the same as in the Fort Collins supply. The EPA 4
36
limit for community drinking water systems 'is 20,000 pC1/L for tritium. Figure II.C.1 shows tritium concentrations in the Gilcrest drinking (potable) water source. ,,
The two drinking water supplies are also analyzed for l fission product and activation product concentrations. A [
]
sample of 18 liters is passed through Dowax 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 l values of radionuclide concentration, but with the exception ;
of Cs-137, these are interpreted to be random variations. The Cs-137 is the residue from the 1986 Chernobyl accident f allout as well as from past world-wide f allout from nuclear weapon testing.
b
(
9 I
I 37
, e w w -v-e -wvyse as -w,w-w,y- wr-v= t+--
l I
l I i i Table !!.C.1 Gross Beta Concentrations in Biweekly Composites of Drinking Water. (pCi/L) !
l i l Collection Gilcrest City R-6 Fort Collins City R-3 !
Date 89 (Reference) .-
DEC 31 4 JAN 7 7.3 (2.5)* 1.5 (0.59) 3 JAN 14 4 21 6.3 (2.5) 1.3 (0.59) !
JAN 28 4 FEB 4 5.8 (2.4) 1.1 (0.57)
FE8 11 4 18 5.3 (2.4) 0.98 (0.57)
- 7.7 (2.5) 1.3 (0.69)
FE8 25 4 MAR 4
- MAR 11 4 18 7.8 (2.5) 0.82 (0.56)
MAR 25 4 APR 1 7.0 (2.6) 0.77 (0.56)
APR 8 8 15 6.8 (2.5) 0.70 (0.56)
APR 22 4 29 5.3 (2.4) 0.91 (0.57)
MAY 6 4 13 6.4 (2.5) 0.89 (0.57)
MAY 20 4 27 5.9 (2.5) 0.77 (0.56)
JUN 3 810 6.1 (2.5) 1.1 (0.57)
JUN 17 4 24 7.5 (2.5) 0.78 (0.56)
JUL 1 8 8 5.0 (2.4) 0.86 (0.56)
JUL 15 8 22 5.4 (2.4) 1.0 (0.57)
JUL 29 8 AUG S 6.2 (2.5) 0.67 (0.56)
AUG 12 4 19 5.3 (2.4) 1.3 (0.59) l AUG 26 4 SEP 2 6.0 (2.5) '0.82 (0.56)
SEP 9 8 16 5.2 (2.4) 1.5 (0.60) l SEP 23 8 30 4.9 (2.4) 1.0 (0.58) l OCT 7 8 14 6.0 (2.5) 1.0 (0.57)
OCT 21 8 28 4.1 (2.3) 0.76 (0.56)
NOV 4 8 11 4.8 (2.4) 0.56 (0.55)
NOV 18 4 25 6.4 (2.5) 0.99 (0.57) ,
DEC 2 8 9 3.8 (2.3) 0.87 (0.56) l DEC 16 8 23 3.7 (2.3) 1.1 (0.57)
- 1.96o (Due to Counting Statistics) 38
i i
Table !!.C.2-Tritium Concentrations in Biweekly Composites of Drinking Water. (pC1/L)
Collection Gilcrest City R-6 Fort Collins City R-3 Date 1989 (Reference) ,,
DEC 31 & JAN 7 550 (450)* < 430 JAN 14 4 21 < 460 < 460 l JAN 28 & FEB 4 < 400 < 400 FEB 11 & 18- < 400 < 400 :
FEB 25 & MAR 4 < 400 < 400 i MAR 11 & 18 < 400 s 400 MAR 25 & APR 1 < 400 < 400 APR 8 8 15 < 390 < 390 APR 22 & 29 < 400 < 400 MAY 6 & 13 < 400 < 400 MAY 20 & 27 < 390 < 390 JUN 3 & 10 < 390 < 390 l JUN 17 & 24 < 390 < 390 JUL 1 8 8 < 420 < 420 JUL 15 & 22 < 430 < 430 JUL 29 & AUG S < 400 < 400 AUG 12 & 19 < 390 450 (440)
AUG 26 3 SEP 2 < 390 < 390 SEP 9 8 16 < 410 < 410 SEP 23 & 30 < 410 < 410 OCT 7 & 14 < 430 < 420 OCT 21 & 28 < 390 < 390 NOV 4 & 11 < 420 < 420 NOV 18 8 25 < 420 < 420- '
i DEC 2 & 9 < 420 < 420
- DEC 16 8 23 < 430 < 430 i
- 1.96o (Due to counting statistics) l 1
39
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 JAN 7 JAN 21 FE8 4 Radionuclide Gilcrest Ft Collins Gilcrest Ft Collins Gilcrest Ft Collins R-6 R R-6 R-3' R-6 R-3 .
I-131 < 0.29 0.57 (0.60) < 0.50 < 0.38 < 0.099 < 0.33 Cs-134 < 1.6 < 1.9 < 3.2 < 2.2 < 0.76 1.1 (1.3)
Cs-137 < 1.9 < 2.7 5.0 (5.5) 2.7 (3.1) 1.9 (1.1) 1.9 (1.5)
Zr-95 < 3.6 < 4.8 < 7.2 < 4.9 < 1.7 < 2.3 Nb-95 < 1.6 < 2.2 < 3.0 < 2.0 < 0.79 < 1.2 Co-58 < 1.4 < 1.9 < 3.0 < 2.0 < 0.70 < 1.0 Mn-54 < 1.5 < 2.2 < 3.1 < 2.2 0.90 (0.90) 1.2 (1.3) ~ ~ "~~ -- -
Zn-65 9.0 (5.1)* < 5.7 < 7.7 < 5.1 < 2.2 < 3.1
< 3.9 < 5.2 < 7.1 < 5.0 < 1.8 < 2.7 h Fe-59 Co-60 < 1.5 < 2.2 < 3.0 < 2.4 < 0.71 < 1.0 Ba-140 < 2.6 < 5.3 < 6.2 < 5.1 2.3 (2.3) < 1.8 La-140 < 3.0 < 6.1 < 7.1 < 5.9 2.6 (2.6) -< 2.1
- l.96 o (Due to Counting Statistics) ,
~
w_,4 _
y v-p ~- w w e=- y 4 e y--w -,7 _
y p -
y -
m 1.e - ,y -g w ,s_sw_4 ---.y
i Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L)
Collection for two weeks ending for two weeks ending' for two weeks ending Date- FEB 18 MAR 4 MAR 18 Radionuclide 'Gilcrest Ft Collins Gilcrest Ft Collins - Gilcrest. Ft Collins -
R-6 R-3 R-6 R-3 R-6 R-3 I-131 < 0.19 < 0.36 < 0.24 < 0.44 < 0.25' ' O.50 (0.48)
Cs-134 < 1.2 < 1.7 < 3.3 < 3.1 < 2.2 < 1.4 Cs-137 1.5 (1.8)* < 2.6 8.0 (4.9) < 4.4 2.7 (3.2) < 1.7 Zr-95 < 2.8 4.6 (4.9) < 8.1 < 6.7 < 5.2 < 3.1 Nb-95 < 1.4 < 1.6 < 3.1 < 2.7 < 2.1 < 1.4 Co-58 < 1.2 < 1.6 3.7 (4.0) < 2.9 < 2.0 < 1.3 Mn-54 < 1.2 < 1.7 < 3.4 < 2.9 < 2.2 < 1.4 Zn-65 < 3.6 < 4.1 < 8.3 < 7.2 < 5.6 < 3.7 Fe-59 < 3.1 < 3.8 < 8.4 < 7.5 < 5.6 < 3.7 Co-60 < 1.1 < 1.8 < 3.6 < 3.0 < 2.3 < 1.4 1
< 3.6. < 3.5 Ba-140 < 2.0 5.9 (4.5)' < 5.5 < 6.6.-
1 La-140 < 2.3 6.8 (5.2)- < 6.3 < 7.5 -< 4.1 < 4.0 1
l.96 o (Due to Counting Statistics)
- ... _ _ _ . , - _ - . _ . , _ . _ ._ _ _ . _ . . _ _ _ , ~ _ _ ,
Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking ifater. (pCi/L).
Collection for two weeks ending for two weeks ending. for two weeks ending Date APR 1 APR 15- APR 29 Radionuclide Gilcrest Ft Collins Gilcrest .Ft Collins Gilcrest. Ft Collins R-6 R-3 R-6 R-3 .R-6 R-3 I-131 < 0.5 < 0.45 < 0.49 < 0.34 < 0.47 < 0.22 Cs-134 < 1.6 < 2.1 < 1.2 1 < 2.1 < 2.0 < 1.8 Cs-137 < 2.0 < 2.6 1.6 (1.7) < 2.5 < 2.4 < 2.6 Zr-95 < 3.8 < 5.1 < 2.7: < 5.0 < 4.7 < 3.9 Hb-95 < 1.6 4.4(2.7)* < 1. 3 - < 139 < 1 e8 ' < 1.6 Co-58 < 1.5 < 1.9 4 1.1 < 1.9 < 1.8 < 2.0 Mn-54 < 1.7 < 2.1 1.9 (1.5) - <. 2.1' < 2.1 < 1.8 Zn-65 < 4.3 < 5.5' 3.6 (4.1) 5.8 (5.9) < 5.0 ' < 4.3' A
Fe-59 < 4.0 < 5.4 < 3.0. < 4.9 < 4.7 < 4.0 Co-60 < 1.4 < 2.3 < 1.2 < 2.3 < 2.1 <.1.3 -
Ba-140 < 2.7 < 5.6 < 3.3 < 3.4 < 3.2 -< 2.6 La-140 <-3.1 < 6.4 < 3.7
< .3.9 < 3.7 .< 3.0
- .]
- l.96 o (Due to Counting Statistics)
Y 1-i . .._.... .- - , , . _ . . . , . . .. -
_m'-m-.~.l--.--.i_.m _,._-_.-__.___._.._.-.__..-..m_._ _ , _ _ _ . , _ _ _ _ _ _ _ _ _ _ _ _
Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L)
I Collection for two weeks ending for two weeks ending for two weeks ending .i Date MAY 13 MAY 27- utlN 10 Radionuclide Gilcrest Ft Collins Gilcrest Ft Collins Gilcrest Ft Collins R-6 R-3 R-6 R-3 R-6 R-3
~
1-131 < 0.18 < 0.44 < 0.18 < 0.42. < 0.18 < 0.16 Cs-134 < 1.6 < 1.1 < 2.0 < 1.1 <-2.4 < 0.97:
Cs-137 < 1.8 < 1.3 < 2.4 - 1.8 (1.5) < 3.5 2.4 (1.4)
~
Zr-95 < 3.6 < 2.6 < 4.6 < 2.5 < 5.9 < 2.2
< 1.8 Nb-95 < 1.6 < 1.1 < 1.1 < 2.2 < 0.94 Co-58 < 1.4 < 0.97 - < 2.0 < 1.1 , <-2.3 < 0.88 tin-54 < 1.5 < 1.0 < 2.0 < 1.1 < 2.3 1.3 (1.2) 2n-65 5.5(5.2)* < 2.8 < 4.8 < 2.9 < 5.8 < 2.6 O Fe-59 < 3.6 < 3.0 < 5.2 < 3.1- < 6.1 < 2.4 Co-60 < 1.5 ' < 0.97 < 2.2 < 1. 0 < 2.5 < 0.91-Ba-140 < 2.6 4.5 (4.0) < 5.4 < 3.1 < 3.5 < 2.8 La-140 < 3.0 5.2 (4.6) < 6.2 < 3.6- < 4.0 < 3.2
- l.96 o (Due to Counting Statistics) a
\
_ . . . ._.-._,.2. ._. .-
-c_ _, . - , , . . . , , . - ~ . , _ _ _ .
Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L)
I Collection for two weeks ending for two weeks ending for two weeks ending Date JUN 24 JUL 1 JUL 8 Radionuclide Gilcrest Ft Collins Gilcrest Ft Collins - Gilcrest Ft Collins R-6 R-3 R-6 R-3 R-6 R-3 I-131 0.54 (0.50)* < 0.33 < 0.4 < 0.34 < 0.39 < 0.33 -
Cs-134 < 2.4- < 1.5 < 2.7 < 2.1 < 1.0 < 2.4 Cs-137 < 2.9 2.2 (2.1) 4.6 (3.8)- < 3.1 1.3 (1.5) 5.4 (4.0)
Zr-95 < 6.2 < 3.1 < 6.3 < 4.7 < 2.3 < 5.1' Nb-95 < 2.2 < 1.3 < 2.3 < 1.9 < 0.99 < 2.2 C0-58 < 2.4 < 1.3 < 2.4 < 2.1 < 1.0 < 2.2 Mn-54 < 2.5 < 1.5 < 2.7 < 2.1 < 1.0 < 2.3 ,
Zn-65 < 5.8 < 3.4 < 6.5 < 5.1 < 2.6- < 5.6 2
< 5.6 < 3.7 < 6.4 < 4.9 < 2.6
~
Fe-59 < 5.3 Co-60 < 2.7 < 1.3 < 2.9 2.1 (2.5) < 0.94 2.8.(2.7)
Ba-140 < 6.1 4.7-(4.0) '6.0 (7.2) . < 3.1 "< 1.7 < 3.5 La-140 < 7.1 5.4 (4.6) 6.9 (8.3) < 3.6 < 1.9 :< 4.0
- 1.96 o (Due to Counting Statistics) ,
.,,,m . -,1
- -. +m- m .. -
. . . 3 ie-- cc,, y . . . . . . , , . , , . , . . - p%., -,,w, ,. ., _ __e. . _ __-_m.
1 Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L)
I Collection for two weeks ending for two weeks ending for two weeks ending Date AUG 5 AUG 19 SEP 2 -
Radionuclide Gilcrest Ft Collins Gilcrest Ft Collins Gilcrest Ft Collins-R-6 R-3 R-6 R-3 R-6 R-3 I-131 < 0.54 < 0.35 < 0.3 < 0.52 < 0.5 < 0.45 Cs-134 < 1.5 < 1.1 < 2.1 < 2.0 < 1.3 < 1.5 Cs-137 < 1.9 2.0 (1.6)* < 2.7 < 3.0 < 1.9 < 1.7 Zr-95 < 3.5 < 2.5 5.5 (6.6) < 4.4 < 3.0 < 3.3 tJb-95 < 1.7 < 1.0 < 1.9 < 1.7 < 1.2 < 1.3 Co-58 < 1.4 < 1.0 < 2.1 < 1.9 < 1.3 < 1.3 Mn-54 < 1.6 < 1.1 2.5 (2.6) < 2.0 < 1.3 1.5 (1.7)
' Zn-65 < 4.6 < 2.9 < 5.2 < 4.6 < .3.2 < 3.4 Fe-59 < 3.7 < 2.8 < 5.1 <-4.3 < 2.9 < 3.3 Co-60 < 1.5 < 0.99 < 2.4 < 2.0 < -1.3 2.0 (1.9)
Ba-140 < 3.6 < 1.8 < 5.5 < 2.9 < 3.5 < 2.3 La-140 < 4.1 < 2.1 < 6.3 < 3.3 < 4.0 < 2.7
~
- 1.96o (Du'e to. Counting Statistics) b
,.,,m _6-_, .,,, _
ma
.- -se..a,-,+wa A.u-. ri =,,_:.mze'.-_-.e+%
-u-a-a.*m.s.aav--+--m.,ws.aAar,,e -ma =
72 M*m-- a-a-..n- .#.En-r'a. -ar.al--
-. .6+.-5a .ag .,-t .
.q.
Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L)~
l Collection for two weeks ending for two weeks ending for two weeks ending Date SEP 16 SEP 30 OCT 14 Radionuclide Gilcrest Ft Collins Gilcrest Ft Collins Gilcrest Ft Collins
'R-6 R-3 R-6 R-3 R-6 R-3 1-131 < 0.38 < 0.34 < 0.15 < 0.15 0.71 (0.61)' < 0.42 Cs-134 < 2.5 < 1.9 < 2.0 < 1.2 1.4 (1.4) < 1.0 Cs-137 < 3.0 2.7 (2.8)* 3.3 (3.0) 2.8 (1.7) 2.2 (1.8) ' 3.4 (1.8)
Zr-95 < 5.5 < 4.2 < 4.7 < 2.9 < 2.6 .< 2.3 fib-95 < 2.7 < 2.2 < 1.8 < 1.2 ' < 1.3 < 0.95 Co-58 < 2.3 < 1.8 < 2.0 < 1.2 < 1.1 < 1.1 Mn-54 < 2.5 < 1.9 < 2.1 < 1. 3 ' < 1.2
~
< 1.0-Zn-65 < 7.4 < 4.9 < 5.0 8.7 (3.7) 8.3 (4.1) < 2.6 lN Fe-59 < 6.9 < 5.6 < 5.5 < 3.4 3.2'(3.6) < 2. 7 .
Co-60 < 2.4 < 1.9 < 2.2 < 1.1 < 1.1- < 1.0 '
Ba-140 < 6.4 < 3.4 < 5.7 < 2.0~ < - 2.0 < 1.5 La-140 < 7.4 < 3.9 < 6.5 < 2.3 < 2.3 < 1.8
- 1.96'o (Due to Counting Statistics) 4
-a ~
m s- , -m -- --+c p-
- e -
w r'
Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. . (pC1/L)
I Collection for two weeks ending for two weeks ending for two weeks ending' Date OCT 28 NOV 11 NOV 25 Radionuclide Gilcrest Ft Collins Gilcrest Ft Collins Gilcrest Ft Collins R-6 R-3 R-6 R-3 .R-6 R-3 4
I-131 < 0.13 < 0.13 < 0.48 < 0.41 < 0.46 < 0.39 -
Cs-134 < 1.2 < 0.83 < 2.4 < 2.2- < 1.5- < 1.9 Cs-137 < 1.4 1.3 (1.2) 5.4 (3.5) 6.2 (3.8) 2.9 (2.3) < 2.4-Zr-95 < 2.7 < 1.8 < 5.6 < 5.1 < 3.6 < 4.6 Nb-95 < 1.3 < 0.74 < 2.2 < 2.0 < 1.7 < 1.8' Co-58 < 1.2 < 0.76 < 2.3 < 2.2 < 1.5 < 1.9 ,
Mn-54 < 1.2 < 0.84 < 2.4- <'2.1 < 1.6 < 2.0 1
Zn-65 6.7 (3.9)* 4.6 (2.4) < 6.0 <.5.3 10.0 (5.7) < 4.7
~
Fe-59 < 3.1 < 2.1 < 5.5 < 5.0 < 4.1 < 4.6 Co-60 < 1.1 < 0.79 ' < 2.6 < 2.2 < 1.4 < 2.1..
Ba-140 < 3.1 -< 1.9 < 5.7 < 3.2 < 3.8 < 5.0 La-140 < 3.5 < 2.2 < 6.5 < 3.7 < 4.3 < 5.8
- l.96 o (Due to Counting Statistics)
, r ,, s.. s~< nn .a. ..
-e a... m.n ,m a u.s,- ~^ m- 'sn-(.,n.,,_-w.->
- a,w. ,, ,4,+.~ .m,,,,,
y_4 ,_ __ _,g_
Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water.. (pCf/L)
Collection for' two weeks ending for two weeks ending Date DEC 9 DEC 23 Radionuclide 'Gilcrest Ft Collins Gilcrest Ft Collint R-6 R-3 R-6 R-3 i I-131 < 0.33- < 0.2 < 0.32- < 0.35 Cs-134 < 0.85 < 1.2 < 1.4 2.8 (2.8)
Cs-137 1.5 (1.3)* < 1.4 3.3 (2.2) < 2.9 Zr-95 < 1.9 < 2.6 4.1 (4.1) < 5.7 fib-95 < 0.86 < 1.1 < 1. 7 < 2.1 Co-58 1.1 (1.0) .< 1.2 < 1.4 < 2.2 Mn-54 < 0.88 1.2 (1.4) < 1.5 < 2.3-Zn-65 < 2.5: < 2.8 < 4.5 < 5.7 Fe-59 < 2.4 3.6 (3.9) < 3.5 .
, $ .< 5.9 -
Co-60 < 0.81 1.0'(1.2) < 1.4 < 2.5.
Ba-140 < 1.5 < 3.0 < 2.6 < 5.3 La-140 < 1.7 < 3.4 < 2.9 < 6.1 o__
'l.96o (Due to Counting Statistics) ,.
7 I
l Z
. _ _ . . . . . . . . . __._..y . . . . ,. . .._, . ._ - .- -..
j;
- 2. Surface Water-Surface . water is collected monthly from four - sites.
Since .the- reactor water effluent' can be directed to either i k river course, .there are ' upstream and downstream - sampling locations on both the St. Vrain Creek and on the South Platte-
. River. 4 Table II.C.4 shows tritium concentrations measureB during ~
1989 at the -four surface water sites. Most of the values were
~
less than MDC. The arithmetic.mean value for the-downstream-locations in 1989 was not significantly different from the two 'l upstream locations (Table II.H.2). In fact the mean' values !"
were identical. The EPA lists 380 1.(1,650) pCi/L.for tritium .
measured in surface = water samples measured over the entire '
United States during April to June of 1989.. -l Table II.C.5 shows measurements of fission product and activation product concentrations. in surface water' .samp1'es 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 1989 for l any of the gamma-ray emitting radionuclides measured. This-a has been the case since the inception of reactor operations at .
the Fort St. Vrain site. The occasional positive values are ,
either fallout Cs-137, which can be expected, or values close to the uncertainty limits and' assumed to be false poqitives.
In addition to the monthly sampling of-the South Platte River and St. Vrain Creek, a continuous water sample is collected at station A-25.
i An aliquot of the farm pond outlet
. 49 1
-l - i 4 ;
j '!
.z 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.5.- For every month _there was evidence of measurable tritium release -(see Table II.C.4) . Mean values -
for the other radionuclides were less than.MDC except for.Cs-- I 1
137.- The correlation of the tritium. concentrations Mith the l
^
offluent' release report'is high. -
-l r
I
. l 4
i i
50 t
Table II.C.4 Tritium Concentrations in Surface Water. (pCf/L)
Downstream Sites Upstream Sites- Effluent Collection St. Vrain S. Platte St. Vrain S. Platte Goosequill . .i Date F-20 R-10 A-21 F-19 A-25'
~
January < 460 < 460 < 460: < 460. 37000f790)*
February < 400 < 400 < 400 < 400 23000-(670)
March < 400 < 400 < 400 < 400 24000 (680)
April < 400 < 400 1500 (430) < 400 .19000 (620) [
< 400 < 400 < 400 < 400-May 24000 (660)
June < 400 < 400 < 400 < 400- =9900 (530)-
. July < 430 < 420 < 420 <-420 11000 (540)- ..
August < 390 < 390 -< 390~ -< 390 21000 (650) .
September < 410 < 410 ' < 410 < 410 26000 (690)
October < 420 880.(420) < 410 400 (410) 52000 (890)
November < 420 <~420 < 420 < 420 71000 (1000)
December < 410 < 410 < 410 < 410 27000 (720)
I
-i I '
i I
l.
i I Figure II.C.1 Tritium Concentrations in Water 1974-1989 l e--e Surface Upstream a-- Surface Downstream }
00f o ~o Potable (Gilcrest) r,
< ss 1300 -
gg.
A -* 8 '
1200 -
..o I t
< 1100 -
i ,\- [ il it I .I s . , :s g 1 1000 -
s is g .t-k: ' [ g -
i g n
- 8 900 - o # f kI i I- - :I *1 l 1 mO 800 -
g [" if ig s- i a' na . - g
'8 !
~
~
700 - . .
f i'$
- -1
- .i ip- !I I
600 - ~f : i .! .3.
4 500 -
- .$ # p' 3 -
.i4 31, 3 ..
!:g .
i-3
!. 3~
1
- t , : -
A S' 1
i 400 - g g' i j g. o . g 3 '
j 300 -
j !
. -f f" . . .,
i* 200 -
i
~'! i* '*
I- 'o n
- D
\ ' ,/ .*. ' /
AN-.-
4-5100 - -
I I I I I s a 's A $ a 4 I I I e I I 1973 '74 '75 '76 '7 7. '78 '79 '80 '81 ' '82 '83 '84 - -'85 '86 '87 ' . '88 ' '89
'90 Time (year) 1
, ,. - * . - y *.w. .,ys . ...w=- - *. yn., >=v. _+ % .w..
~ v a m. ,-. 3 , , , , .,%,.--,, , . , - _ _ , _ _ _ _ __ , ,
a Table II.C.5 Radionuclide Concentrations In Surface Water. (pCi/L)
Collection Date: 1/14/89 Downstream Sites Upstream Sites Effluent
~ ~ ~ ~ ~ ' ' ' ' '
Radio St. Vrain S. Platte St. Vrain S. Platte Goosequill-
-nucli& F-20 R-10 A-21 F-19 A-25 Cs-134 < 2.0 < 2.4 < 1.5 < 2.2 < 2.5 Cs-137 < 2.5 < 2.9 < 1.8 -4.9 (3.9) < 3.0 --
Zr-95 7.5 (5.9)* < 5.8 < 3.4 -< 4.9 < 6.7 Nb-95 < 2.4 < 2.2 1.6 (1.7) < 2.0 < 2.3 Co-58 < 1.9 < 2.2 < 1.4 < 2.1 <12.6
< 2.2 < 2.4 < 1.4 : < 2.1 < 2.6-Mn-54 Zn-65 < 6.0 < 5.7. 8.4 (4.8): < 5.3 . < 6.4 Fe-59 < 5.4 < 5.9 < 4.0 < 5.0 < 7.2:
Co-60 < 1.9 < 2.6- 2.5 (1.8) < 2.2 < 2.8 Ba-140 < 3.5 < 3.9 < 2.6 < 4.1 < 4.0 La-140 -< 4.0 < 4.5 c 3.0 < 4.7 < 4.6 B
- l.96o (Due-to Counting Statistics)
I
_ _ _ _ _ _ _ _ _ _ .. -. _ ._ _L__.. .._ . _ . . _
_ . w _.- __
Table II.C.5 Radionuclide Concentrations In. Surface Water. (pCi/L)
Collection Date: 2/11/89 q
Downstream Sites Upstream Sites Effluent Radio St. Vrain S. Platte St. Vrain S. Platte . Goosequill
-nuclide F-20
, R-10 A-21 F-19 A-25 Cs-134 < 2.2 3.8 (3.0)* 2.3 (1.9) <:3.2- 3.3 (2.2)-
Cs-137 < 2.7 < 3.0 2.1.(2.2) < 4.7 4.3 (3.3) '
Zr-95 < 5.2 < 5.2 < 3.5 < 7.5 < 4.0 .
Nb-95 < 2.0 < 2.5 < 1.9 < 2.9 < 1.7 Co-58 < 2.0 < 2.1 <-1.4 < 3.0 2.7 (2.3)-
Mn-54 < 2.1 < 2.7' 2.I'(1.9) < 3.2 < 1.8 2n-65 < 5.3 < 7.3 < 5.0 :< 7.8 . < 4.4 Fe-59 < 4.9 < 6.0 < 4.0 < 7.5- < 4.2 Co-60 < 2.3 < 2.4- < 1.5 < 3.4 < 1.8 Ba-140 < 3.5 < 4.7 < 3.3 5.9 (7.1) < 6.1 La-140 < 4.0 < 5.4 . < 3.8 6.8 (8.2) < 7.0
?
l.960 (Due to Counting Statistics) 1 i
e l :
na. .,- .w w . +i. My rwc s - *M- r s<m-a-mu- @g ywh-* w** -. -r m, g :p +.sA w mcg_ .wA1
- s. .
Table li C.5 Radionuclide-Concentrations In Surface Water. (pCi/L)-
Collection Date: 3/11/89 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 < 4.3 < 4.2 < 2.4 < 1.6
< 1.8 Cs-137 < 5.0 < 6.0 3.0 (3.5) 2.9 (2.1) 5.7 (3.2)- -
Zr-95 < 10 < 9.2 < 5.6 <-3.4 < 4.0 Nb-95 < 4.0 < 3.5 < 2.4 < 1.5 . <11.7 Co-58 < 4.1 < 3.9
< 2.2 < 1.5 < 1.7 -
Mn-54 < 4.2 < 4.0 < 2.4 < 1.4 2.7 (2.2)
Zn-65 '11 (12)* < 8.9 < 5.8 5.7 (4.7) < 4.4 Fe-59 < 10' < 8.6 < 5.6 < 3.3 5.9 (6.1)
Co-60 < 4.6 < 3.9 < 2.3 < 1.5 < 1. 8 Ba-140 14 (11) < 5.8 '< 4.2 < 2.4 < 5.8 La-140 16 (13) < 6.7 < 4.8 < 2.8 <-6.7 81 __
i *l.96c (Due to Counting Statistics) e r
.e 1
'~ .
_. -~ , ._, _. _ ._ - ., . ,; _ . . ~ , ;. , . - . _.
. . = . . . _ . , ,
J l Table II.C.5 Radionuclide Concentrations In Surface Water. (pCi/L) :
Collection Date: 4/08/89 Downstream hites Upstream Sites Effluent . -
Radio 'St. Vrain S. Platte St. Vrain S. Platte Goosequill i
-nucli de F-20 R-10 A-21 F-19 A-25.
l .
Cs-134 < 1.4 < 1.2 < 1.9 < 1.6 < 2.0 i Cs-137 2.6 (2.5)* 2.9 (1.8) < 2.3 < 1.9 ' < 2.4 '
Zr-95 < '3.1 < 2.8 < 4.4 < 3.7
< 4.6 Nb-95 < 1.3 2.1 (1.4) < 1.8 < 1.4 < 1.8 C0-58 < 1.3 < 1.1 < 1.8 <:1.4 < 2.2
- Mn-54 < 1.4 < 1.2 < 1.9 < 1.6 < 2.1-2n-65 < 3.4 5.6 (3.9) < 4.5 < 3.7 < 4.9 Fe-59 < 3.5 < 3.2 <-4.5 < 3.7 < 6.2 Co-60 < 1.4 < 1.3 < 2.1 < 1.7- < 2.1 Ba-140 < 2.0 < 2.8 < 3.7 < 3.9 < 3.2 La-140 < 2.3 < 3.2 < 4.2 < 4.4 < 3.7 m
- 1.960 (Due'to Counting Statistics) 4 I
1
- m. .- ..a., --....w.-,... .-.,.a.-.. em - _ . ~ . - - - . . . - .
i Table II.C.5 Radionuclide Concentrations In Surface Water. (pCi/L)
Collection Date: 5/13/89 Downstream Sites Upstream Sites Effluent Radio St. Vrain S. Platte St. Vrain S. Platte Goosequill
-nuclide F-20 R-10 A-21 F-19 A-25 Cs-134 < 2.2 < 3.0 < 2.4 < 3.4 < 1.2 Cs-137 4.7 (3.9)* 6.5 (5.4) < 3.0 < 4.1 < 1.4 -
Zr-95 < 4.8' < 6.9 < 5.8 < 8.0 < 2.9 Nb-95 < 2.0 < 2.9 < 2.2 < 3.1 < 1.1 Co-58 < 2.1 < 2.9 < 2.3 < 3.1 < 1.1.
Mn-54 < 2.2 < 3.0 < 2.5 .
< 3.4 < 1.2 ' .
Zn-65 < 5.4 < 7.7- 6.4 (6.8) < 7.9 11'(3.8)
Fe-59 < 5.2 < 7.2 < 5.9 ' < 7.8 5.3 (4.1)-
Co-60 < 2.2 < 3.0 < 2.7 < 3.6 < 1.1 Ba-140 < 4.2 < 4.6 < 4.1' < 5.4 < 4.1 La-140 < 4.8 < 5.3 < 4.7 < 6.3 < 4.7
- l.96o (Due to Counting Statistics)
- j
- 6 5
e
. ,n , . . , _ , _ . . . _ _ , . . _ , . . _ . . . . , _ . , ,, , .z. s,.___.,. . _ . . . . . __ _ _ _ . _ _ , . - .-
a.
Table II.C.5 Radionuclide Concentrations In Surface Water.-(pCf/L)
Collection Date: 6/10/89 .
Downstream Sites Upstream Sites. . Effluent
'l Radio St. ' train S. Platte St. Vrain S. Platte Goosequill
-nuclide F-20 R-10 .A-21 F-19 'A-25 Cs-134 < 2.1 < 1.4 < 2~4 . < 2.3 < 1.4 Cs-137 3.7 (3.7)* 3.2 (2.1) 4.2 (3.4) < 2.8 < 1.7 -
- Zr-95 < 4.7 < 3.2 < 5.5 < 5.5 ' < 3.0-Nb-95 < 1.8 < 1.6 < 2.2 < 2.1 < 1.3 Co-58 < 2.0 < 1.3 .< 2.2 < 2.2 '< 1.2 Mn-54 < 2.1 < 1.5 2.8 (2.8) < 2.3. < 1.4 Zn-65 < 5.1 < 4.0 < 5.4 < 5.7 < 3.9 "'
Fe-59 < 4.7 < 3.6 < 5.5 < 5.6 < 3.5 Co-60 < 2.2 < 1.4 < 2.6 < 2.5 -< 1.3 Ba-140 < 3.1 < 2.8 < 3.8 < 3.8 < 6.4 ,
La-140 < 3.5 < 3.2 < 4.3 < 4.4 <.7.3
~
E
- l.960 (Due to Counting Statistics)
~
b O
4 l .
_~ _. . _ _ - , _ _. ,. _ . . . - . .
2-Table II.C.5 Radionuclide Concentrations In Surface Water. (pC1/L)
Collection Date: 7/08/89 Downstream Sites Upstream Sites Effluent Radio St. Vrain S. Platte St. Vrain S. Platte - Goosequill
-nucli de F-20 R-10 A-21 F-19 A-25.
Cs-134 < 2.4 < 3.9 < 2.2 < 1.5 .
< 1.1 Cs-137 < 2.7 < 4.8 < 3.2 3.6 (2.3) < 1.3 -
Zr-95 < 5.0 < 9.1 < 5.0 < 3.3 < 2.5-Nb-95 < 2.2 < 3.5 .< 1.9 < 1.6 - < 1.3 Co-58 < 2.3 -< 3.6 < 2.1 <1.4 . < 1. 0 Mn-54 < 2.4 < 3.9 < 2.2 < 1.5 < 1.1 2n-65 < 6.5 < 9.? < 5.3 - <4.2 < 2.8-Fe-59 < 5.7 <n9 < 5.2 < 3.9 3.7 (4.4)
- Co-60 < 2.3 - < 4.2 < 2.2 < 1.5 - < 1.1 =
Ba-140 7.9 (6.0)* < 6.2. < 3.3 < 2.6 < '1.9.
La-140 9.0 (6.9) < 7.1 < 3.8 - < 3.0 < 2.1
- l.960 (Due to Counting Statistics)-
,e, 9,, # *Wr
., % 6--.J. y ---m'- e- - 'rur ___g-rm _, .
_ , _ . . -s__._y- ___ rw
s.
Table II.C.5 Radionuclide Concentrations In Surface Water. (pC1/L)
Collection Date: 8/12/89 - :
Downstream Sites Upstream Sites Effluent
- Radio St. Vrain S. Platte St. Vrain S. Platte Goosequill
-nuclide F-20 R-10 A-21 F-19 A-25 Cs-134 < 2.5 < 1.1 < 3.3 < 2.4 < 2.7 Cs-137 < 3.1 1.9 (1.6) < 4.1 < 3.7 < 2.5 --
Zr-95 < 6.4 < 2.5 < 8.7 6.8 (6.9)~ < 3.1 Nb-95 < 2.4 1.9 (1.4) < 3.0 < 2.3 < 5.9 C0-58 3.4 (3.0)* 1.4 (1.3) < 3.0 < 2.5 < 2.3 Mn-54 < 2.6 < 1.1 < 3.5 < 2.4 <.2.6 Zn-65 < 5.9 3.8 (3.3) < 8.0 < 5.6- .< 6.0 Fe-59 < 6.1 3.6 (4.0) < 7.9 7.3 (7.1) < 5.9 -
Co-60 < 2.8 < 0.98 < 3.4 . < 2.4- < 2.7 Ba-140 < 6.5 < 1.9 '20 (10) < 5.6 < 4.1 La-140 < 7.5 < 2.2 23 (12) < 6.4. < 4.7 g
- l.960 (Due to Counting Statistics) t e b 2._:_._ _ _._._____r__ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ 'u__ w--- - - - ~ " ~ ' *N'-r% N---*-C f T- -
ac *'W-,~%e '
w, --*Wam-- -4 e- -e,+ c ew- _- er- =
s Table II.C.5 Radionuclide Concentrations In Surface' Water. (pCi/L)
Collection Date: 9/09/89 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 < 1.3 < 0.84
< 1.3 < 1.4 < 1.2 Cs-137 3.3 (2.3)* < 1.0 < 1.6 1.7 (2.1) 1.8 (1.8) -
Zr-95 < 2.9 < 2.0 < 3.1 < 3.3
< 3.4 Nb-95 < 1.2
< 0.79 < 1.2 < 1.3 < 1.2 Co-58 < 1.2 .< 0.75 < 1.3 < 1.3 < 1.1 Mn-54 1.7 (1.5) 1.3'(1.0) 1.5 (1.5) < 1.4 < 1.3.
Zn-65: < 3.1 < 2.2 < 3.6 < 3.3 8.0 (4.2)
Fe-59 < 3.2 < '2.3 < 3.5 < 3.7 < '4.4 Co-60 < 1.3 < 0.79 < 1.3. < 1.5 :< 1.2 Ba-140 < 1.9 < 1.4 < 2.1 < 2.3 < 2.0 La-140. < 2.2 < 1.6 < 2.4- < 2.6 < 2.3 l.96o (Due to Counting Statistics) i' 3y=-1. ,,_m...
, s.
.) y --..-.r' .
.ip,, _ . . .= vy.n,, y g- 4 , pg ~y 3 y.q- ' r - .g,. ~m, y*-g, _ ,,, , __g._u_ _, ,
Table II.C.5 Radionuclide Concentrations In Surface Water. (pCi/L)
Collection Date: 10/14/89 Downstream Sites Upstream Sites Effluent Radio St. Vrain S. Platte- St. Vrain - S. Platte Goosequill
-nuclide F-20 R-10 A-21 F-19 A-25 Cs-134 < 2.2 < 2.5 < 2.0 < 1.8 < 2.1 Cs-137 4.0'(4.0)* < 3.0 < 2.4 3.8-(3.2) . 4.1 (3.0) .
Zr-95 < 5.1- < 5.8 < 4.8 < 4.1 < 5.3 Hb-95 < 2.1 < 2.3 < 1.8 < 1.6 .< 1.9 _
Co-58 < 2.2 < 2.3 < 1.8 < 1.8 < 2.1 Mn-54 < 2.3 < 2.5 < 2.0 < 1.8' < 2.1~-
2n-65 < 5.7 < 5.8 < 4.8: < 4.6 < 4.9 Fe-59 ' < 5.2 < 5.7 < 4.9 < 4.4- <~ 4.8 Co-60 < 2.2 . < 2.6' < 2.2. < 1.8 < 23 . ,
4.4 (4.8)
Ba-140 . 7.1 (5.6) < 3.2 < 3.3 < 3.4' La-140 5.0 (5.6) 8.2 (6.4) < 3.7 <-3.8 1< 3.9 lC
- 1.960 (Due to Counting Statistics)
Nh,
. .E e
,,-.p. i.
t p 41 -pe *
.Ne y"* ' Yl ee9t-# "'.y p W n" %. -+ y h4 pav h-g, 7 (4 -3r-g 1 4.31- tr > r'W4-rew w 's
Table II.C.5 Radionuclide Concentrations ~In Surface Water. (pCf/L) d Collection Date: 11/11/89 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 Cs-134 < 2.1 < 1.9 < 1.4 < 1.2 < 1.3 Cs-137 5.3~(3.7)* < 2.3 3.2 (2.0)- 2.4 (1.7) 1.5 {1.8) -
Zr-95 < 4.8 < 4.6 < 3.3 < 2.6 < 2 . 7-Nb-95 < 2.0 < 1.8 < 1.3 < 1.2 1.4 (1.5)
Co-58 < 2.0 3.1 (2.2) < 1.4 < 1.1 < 1.1 Mn-54 < 2.0 < 1.9 < 1.4- < 1.2 -< 1.3 Zn-65 < 5.1 < 4.8 < 3.4 , 9.7-(3.7)' 4.2:(3.8)
Fe-59 < 4.8 < 4.5 < 3.7 3.5 (3.5)~ r< 3.1 Co-60 < 2.1 < 2.1 < 1.5 < 1.1 < 1.2 Ba-140 < 3.1 < 3.1 6.4 (4.4)' < 2.2 < 4.0 La-140 < 3.5 < 3.6 7.4-(5.0). ..< 2.5 < 4.6 -
B
- 1.960 (Due to' Counting Statistics) ~
. e I
_ , - - - _ _ , - s-e-+- ._v g ., #-*w 'b-
- W
%_ , 9- w<*en=t-- - -7- * *
-1 --*e*9# s' d- C & *W" f --' -"+-'t-+y--+- (r'r>v **e4@yy -
=Tt 'e. , e g my-%-gi F
Table II.C.5 Radionuclide Concentrations In Surface Water. (pCi/L)
Collection Date: 12/09/89 Downstream Sites Upstream: Sites Effluent Radio St. Vrain S. Platte- St. Vrain 15. Platte' Goosequill.
-nuclide F-20 R A-21' F-19 JA-25' Cs-134 < 2.3 < 1.4 < 3.8 2.5 (2.9) < 2.0
~
Cs-137 < 2.5 2.9 (2.1)* < 4.5 < 3.0 < 2.5 Zr-95 < 4.9 < 3.3 < 8.7- < 5.7 ~< 4.8 Nb-95 < 1.9 < 1.4 <~3.5 < 2.2 < 1.8 -
Co-58 < 2.1 < 1.3 < 3.5 < 2.2 < 2.2' 14n-54 < 2.1 < 1.4 < 3.8 ~ < 2.4 < 2.0 Zn-65 < 5.4 < 4.0 < 9.2 < 5.8 ' < 4.8 Fe-59 < 5.3 < 3.9 1< 8.9 < S.7 < 4.7
< 2.0 Co-60 < 1.4 < 4.1- -< 2.6 ~ < 2.2 - - ~~-+-
Ba-140 < 4.1 < 2.5 < 6.0 < 4.3- < 3.4 La-140 < 4.7 < 2.9 < 6.9 <~5.0- < 3.9 i
- 32 ,
-*l.96o (Due to Counting _ Statistics) r m ,.. .g,y- -
4 ._ g -w -
+m%-.ms*- M .* Eawr-i-y. gw +- w= ape.f.9 f C T 'N" __ m- n_-.__'.__C_r.- 'fs_%-r.
. . . .- . . . , ~ . . . _ . . . . m. .
i v
- 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 t the reactor down the hydrological gradient,- and at R-5, the Ehrlich feedlot. . Table II.C.6 lists the measured concentrations of fission products and - activation - products- in ground water. The 'Cs-137 j results are not surprising due to residue of Chernobyl fallout, and the other results above MDC are assumed to be statistically false positive values. f Table II.C.7 show tritium concentrations -in the' same Well-water samples.- The results' indicate short-lived contamination of the aquifer supplying F-16 well . This well is not used for l
drinking water purposes and therafore dose' commitment calculations.
are not warranted.
It should be noted that location R-5 at the Ehrlich ' feed 1'ot .;
became unavailable in. December of 1989. A new well R-5Ilocation I was found in early January at a personal residence in;the town of Milliken. The new location is less _than' 1 mile west of the previous well site, j 4-
)
l 1
i 65 s
Table II.C.6 Radionuclide Concentrations in Ground Water. (pCf/L) l l
1st 2nd 3rd 4th Quarter 3-25-89 Quarter 5-20-89 Quarter 8-19-89 Quarter 11-18-89**
Radio-nuclide F-16 R-5 F-16 R-5 F-16 R-5 F-16~ R-5 Cs-134 < 1.9 < 2.2 < 2.0 <.1.3 <-1.6- < 1.2 1.7'(1.8) < 2.5 Cs-137 7.2 (3.3)* 4.2 (3.2) 5.0 (3.5) < 1.5 2.5 (2.5) 3.2-(1.9) 11.(2.7))
3.6 (3.7)
Zr-95 < 4.2 < 5.0 < 4.4 3.4 (3.5) < 3.6 < 2.8 .< 3.5 < 5.5 Hb-95 < 1.8 < 2.1 < 2.0 1.5 (1.6) 3.6 (2.2) < 1.3 < 1.7
< 3.3
, Co-58 < 1.8 < 2.0 < 1.9 < 1.2 < 1.5 < 1.2 < 1.4 < 2.3 1
Mn-54 < 1.8 < 2.2 2.0 (2.4) < 1.3 < l.7 < 1.3 < 1.5 < 2.6 Zn-65 < 5.1 < 5.6 < 5.8 14 (4.2) 41 (6.3) 11 (4.1) < 5.1 < 9.4 '
< 4.4 < 5.3 < 4.8-Fe-59 3.4 (4.1) < 4.1- < 3.5 < 3.4 < 6.3
$ Co-60 < 1.8 5.0 (2.8) < 2.0 1.2 (1.A) 1.5 (1.9) < 1.1- < 1.5 2.9 (2.8)
Ba-140 < 3.5 < 3.5 < 3.0 <-2.8 < 4.0 - < 2.1 < 2.4. .< 4.5 . .
La-140 < 4.0 <.4.1 < 3.4 < 3.2 < 4.6 < 2.4 < 2.7 < 5.2 -
- 1.96o (Due to Counting Statistics)
- R-5 was collected on 1-2-90 a f ter ' a new loca tion. was found .in Milliken..
i
- m. _ .. y a . . ~ , . _ .,
y c -+ - - - . , i.-
% - % _..M- g. -,y , gh r .- , .E. p y7 ...w,. c. c. , . . ymn,...,,, .
, ,,v.
Table II.C.7 Tritium Concentrations in Ground Water. 1989-(pC1/L)
Ist 2nd 3rd 4th~
Quarter 3-25-89 Quarter 5-20-89 . Quarter 8-19-89 - Quarter .11-18-89**
l F-16 R-5 F-16 R-5 F-16 R-5 F-16 R-5 950 (420)* < 390 < 390 < 390 4500 (470) 750_(420) -< 420 < 430
- 1.96o (Due to counting statistics)
- R-5 was collected 1-2-90 after a well was located in Milliken.
1 4
e , O I
-7,.'a ....e _ wa-r. .-w+_'u * -%- --u- , et -
MWm-- ' f- " "P,-, e -5.e- --e%, r# M> r+ c-p.e- g- ' ,. , -P y &,.h
- - F A - -% '
_ $ W
- m Table II.C.8 Maximum Pemissible Concentrations in Drinking Water. ;
(10CFR20, Appendix B, Table II) p H-3 6 3 x'10 pCi/L I-131 2 3 x 10 pCi/L Cs-134 3 9 x 10 pCi/L Cs-137 4 2 x 10 .pCi/L.
Zr-95 6 x'104 pCi/L Hb-95 1 x 10 pCi/L Co-58 . 1 x'10 pCi/L-Hn-54 ' lLx'.10 pCi/L -
m Zn-55 1 x 10 pCi/L 4
Fe-59 6 x 10 pCi/L
.Co-60 5 x l'04 pCi/L Ba-140 3 x 10 pCi/L
' ~
La-140 . 2 x 10 pCi/L e
a
.--.-.:-.----=-=-- - --- --,
i i
l i
i II.D. Milk The dairy food chain is the critical pathway for possible radiation dose commitment around any nuclear facility. The 5 critical individual would be an infant consuming milk produced ;
from cows grazing local pastures. Milk is the critical pathway for possible dose commitment to humans from environmental contamination of H-3, I-131, Cs-137 and'Sr-90. I 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, l
1980.
There are no dairies (or personal milk cows) in the l :
facility area, 1.6 km radius from the reactor. The six dairies in the adjacent area, 1.6-8 km radius, were selected i as they are located in the highest X/Q areas (refer to updated l FSAR). The description of these locations can be found in i-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 l are virtually identical at all dairy locations. The cows in.
the milking herd are never on pasture but under dry-lot management typical of Eastern Colorado.
I L
69 i
\
i Table II.D.1 lists the concentrations of all radionuclides that are investigated-in milk samples. During ,
i 1989, elevated concentrations of I-131 were again consistently !
ebserved only at site A-22. The source of this I-131 is from nuclear medicine thyroid therapy practice in the Denver i 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 ' rather than well water. The ditch (Independence) receives S. Platte water upstream of TSV. This observation was first made in 1985 and discussed at length in the 1985 REMP summary report.
Figure II.D.1 shows the frequency and magnitude of the I-131 concentrations observed at the A-22 dairy in recent years.
The large peak observed in May knd June of 1986 is of course due to Chernobyl fallout, but all other peaks are due to hospital release in Denver. The concentrations in 1989 were greater thun in previous years. Figure II.D. 2 shows the measured I-131 concentrations in the S. Platte River.for only October through December of 1989. Samples were collected at the output of the Denver sewage treatment plant at the north site of the city and also at A-22. There is considerable decay and dilution in transport between the two sampling sites. The A-22 average is 47% of the Denver output average. I 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. 4 concentrations are homeostatically controlled and independent of K intake. K-nat is measured in all milk samples as a 70
+
- _ - , --_,.._m.-, -
~ - , - - , - - . - . . . . . - . ~ . .
t l
I quality control measure for the other radionuclides determined i i
in the some sample by gamma-ray spectrometry, but X-nat !
concentrations are no longer reported in Table II.D.1.
,, l Table II.D.2 lists measured tritium concentrations in milk. significant elevated tritium concentrations in milk due to reactor effluents have never been observed in the a operational period of the reactor. This implies the tritium l f
from reactor affluents is not contributing any radiation dose to humans via the milk pathway. Tritium concentrations in ,
milk should respond rapidly to changes in tritium concentrations of the forage water intake or drinking water intake to the cow. This is due to the short biological half-life for water in the cow (about three days for the lactating cow). As noted in previous reports, the reported tritium ,
concentration in milk is the tritium in water extracted from the milk. contamination of milk samples by any radionuclide ,
due to reactor effluents has never been observed during the operational periods of Fort St. Vrain.
For comparison purposes, the EPA lists a measured Cs-137 concentration in milk from Denver as 5 ! 8 pC1/L on 6/30/89.
The *I in the same milk sample was 4 9 pCi/L.
1 l
I 71
Figure II.D.1 300 -
g8 : I-131 Concentrations in Milk at Site A-22 .
70 -
so -
so -
l 40 - [
30 -
20 -
10 -
90 -
80 -
7.0 -
60 -
50 -
3 40 -
h O 30 -
S
. 2.0 -
M 1.0 - f f.
09 -
08 -
07 -
06 -
05 -
l-- i u R
a
,1DC O4 - -
O.3 - . .
02 -
...........t...........t.......... t g)........... ...........
J M M J S N J M M J S N J M -M J S N 'J M M J S N J M M J S N 1985 1986 1987 1988 1989
. . _ . ._ ~ _ 2. , . . ..~ _. . . . _ . . _ - . . _ . _ . . _ . . . _ . .
Table II.D.1 Radionuclide Concentrations In Milk. (pCi/L).
InrATinN A-6 A-18 A-22 A-23 A-24 A-26 R-8 Collection Date 1/14/89 1/07/89 1/21/89 1/14/89 1/28/89 1/24/89 I-131 < 0.31 < 0.30 f < 0.25 < 0.27 < 0.20 < 0.25 Cs-134 < 3.3 < 2.4 f < 2.4 1.9 (2.1) < 1.9 < 2.9 Cs-137 8.3 (5.8)* 2.8 (3.4) f < 2.9 < 2.2 5.5 (2.7) < 3.5 Ba-140 < 4.7 < 4.0 f < 3.7 < 4.0 < 3.2 < 4.8 La-140 < 5.5 < 4.6 f < 4.2 < 4.6 < 3.6 < 5.5
~
Collection Date 2/25/89 2/04/89 2/11/89 2/11/89 2/25/89 2/25/89 2/04/89 I-131 < 0.35 < 0.41 < 0.4 0.37 (0.38) < 0.26 < 0.23 < 0.31 Cs-134 < 2.7 < 2.4 < 1.4 < 2.5 < 1.5 < 2.1 < 3.1 Cs-137 < 3.3 < 2.8 < 1.6 < 3.1 < 1.9 < 2.5 < 4.0 Ba-140 < 4.6 < 3.7 < 2.2 < 4.1 < 3.0 < 4.4 < 5.3 ,
O La-140 < 5.3 < 4.3 < 2.6 < 4.7 < 3.4 < 5.0 < 6.1 Collection Date 3/18/89 3/11/89 3/04/89 3/04/89 3/25/89 3/25/89 3/11/89 131 c 0.50 < 0.31 < 0.21 < 0.22 < 0.25 < 0.34 0.50 (0.53)
Cs-134 < 1.4 < 1.4 < 2.9 < 1. 4 < 2.5 ,< 2.7 < 2.3 Cs-137 3.2 (2.0) < 1.6 < 3.3 < 1. 7 < 3.8 < 3.2 < 3.4 Ba-140 < 2.2 < 2.5 <.4.4 < 3.7
< 2.7 < 4.3 44.5 La-140 < 2.5 < 2.9 . < 5.0 < 3.2 < 4.3 < 4.9 < 5.2
- 1.96o (Due to Counting Statistics) f samnio unavailable
Table II.D.1 Radionuclide Concentrations In Milk. (pCi/L).
LOCATION A-6 A-18 A-22 A-23 A-24 A-26 R-8 Collection Date 4/22/89 4/15/89 4/01/89 4/01/89 4/08/89 4/08/89 4/08/89 I-131 < 0.17 < 0.13 1.5 (0.46)* < 0.31 < 0.21 < 0.24 < 0.31 Cs-134 < 2.3 < 1.5 < 2.7 < 1.6 < 1.9 < 2.0 < 1.9 Cs-137 < 2.8 < 1.9 < 3.3 < 2.0 2.6 (2.7) 4.8 (2.9) 3.3 (3.2)
Ba-140 < 3.7 < 2.5 < 4.6 < 3.1 < 3.8 < 3.2 < 2.6 La-140 < 4.2 < 2.8 < 5.3 < 3.6 < 4.4 < 3.7 < 3.0 Collection Date 5/20/89 5/06/89 5/06/89 5/06/89 5/13/89 5/13/89 5/13/89 I-131 < 0.3 0.51 (0.61) 0.58 (0.37) < 0.41 < 0.34 < 0.37 < 0.33 Cs-134 < 4.0 < 2.2 < 1.7 < 2.7 < 2.5 < 1.8 < 2.6 Cs-137 < 4.6 < 2.7 2.4 (2.5) < 3.0 < 2.9 < 2.1 3.7 (3.9)
Ba-140 < 6.1 < 3.7 < 3.2 < 4.1 < 5.4 < 3.8 < 5.3 La-140 < 7.1 < 4.2 < 3.7 < 4.7 < 6.2 < 4.3 < 6.1 Collection Date 5/27/89 5/13/89 5120/89 5/20/89 5/27/89 5/27/89 5/27789 I-131 < 0.39 < 0.33 2.8 (0.53) < 0.5 0.34 (0.39) < 0.15 < 0.38 Cs-134 < 2.9 < 2.6 < 3.0 < 2.5 < 2.2 < 2.0 < 1.4 Cs-137 - < 3.1 3.7 (3.9) 3.6 (4.2) < 3.1 3.1 (3.1) + 2.9 < 1.8 Ba-140 < 4.9 < 5.3 < 6.1 < 4.2 < 3.4 < 2.8 < 2.3 La-140 < 5.7 < 6.1 ~ < 7.0 < 4.9 < 3.9 < 3.3 < 2.7
- I.96o (Due to Counting Statistics)
_. _ . _ _ _ _ _ _ _ _ .~ . . __. . . . . _ . . . ._, __ _ ._ ._ ..
Table II.D.1 Radionuclide Concentrations In Milk. (pCi/L).
InraTTnu A6 A 1R A 77 A-74 A-23 A-26 R-8 Collection Date 6/10/89 6/03/89 6/03/89 6/03/89 6/10/89 6/10/89 6/10/89 I-131 <.0.37 < 0.3 0.45 (0.41) < 0.18 < 0.31 < 0.39 < 0.36
~
Cs-134 < 3.7 < 2.9 < 1.5 2.7 (2.1) < 2.2 , < 4.2 < 2.4 Cs-137 7.8 (6.7)* 3.6 (4.1) < 1.8 < 2.1 3.9 (3.9) < 4.9 < 2.7 Ba-140 < 5.9 < 5.8 < 3.1 < 3.5 < 3.2 < 6.3 < 3.6 La-140 < 6.8 < 6.7 < 3.5 -< 4.0 < 3.7 < 7.3 < 4.1 Collection Date 6/17/89 6/24/89 6/17/89 6/17/89 6/24/89 6/24/89 6/17/89 I-131 c 0.32 < 0.45 6.4 (0.28) < 0.20 0.52 (0.55) < 0.19 0.56 (0.59)
Cs-134 < 1.5 < 2.5 < 2.5 < 1.5 < 2.5 < 0.86 < 2.5 Cs-137 1.9 (2.2) < 2.7 < 3.0 < 1.8 < 3.1 2.3 (1.2) < 3.1 Ba-140 4.6 (4.9) < 5.2 < 4.1 4.0 (3.7) < S.2 < 1.4 < 6.3 La-140 5.2 (5.7) < 6.0 < 4.7 4.6 (4.2) < 6.0 u,
< 1.6 < 7.2 Collection Date 7/01/89 7/08/89 7/01/89 7/01/89 7/08/89 7/08/89 7/8/89 I-131 < 0.38 < 0.3 2.7 (0.53) < 0.5 < 0.47 < 0.47 < 0.26 Cs-134 4.9 (4.0) < 1.7 < 2.5 < 1.3 < 3.3 < 2.5 < 2.6 Cs-137 < 4.2 3.7 (2.4) 4.6 (3.5) < 1.5
< 3.9 < 3.0 3.0 (3.7)
Ba-140 < 5.4 < 3.1 < 4.1 < 2.0 < 4.8 < 3.7
< 4.5 La-140
< 6.2 < 3.5 - < 4.7 < 2.3 < 5.5 < 4.3 < 5.2
- 1.960 (Due to Countin9 Statistics)
Table II.D.1 Radionuclide Concentrations In Milk. (pCi/L).
LOCATION A-6 A-18 A-22 A-23 A-24 A-26 R-8 Collection Date 7/22/89 7/29/89 7/29/89 7/29/89 7/22/89 7/22/89 7/22/89 I-131 < 0.45 < 0.23 6.9 (0.46)* < 0.2 < 0.29 < 0.23 < 0.24 Cs-134 < 2.2 < 2.4 < 3.5 < 2.6 < I.8 < 1.5~ < 2.7 Cs-137 < 2.6 < 2.6 < 4.2 < 3.2 2.8 (2.7) 3.9 (2.2) < 3.2 Ba-140 < 3.5 < 3.7 < 5.5 < 4.2 < 3.5 < 2.5 < 4.8 La-140 < 4.1 < 4.3 < 6.4 < 4.9 < 4.0 < 2.8 < 5.6 Collection Date 8/05/89 8/12/89 8/12/89 8/12/89 8/12/89 8/12/89 8/05/89 I-131 < 0.2 < 0.48 0.62 (0.45) < 0.3 < 0.22 < 0.32 < 0.28 Cs-134 < 1.4 < 1.8 < 2.2 < 1.4 < 1.7 5.0 (3.4) < 2.0 Cs-137 4.8 (1.9) < 2.2 < 2.4 2.0 (2.1) 2.4 (2.4) < 3.3 < 2.5 Ba-140 < 2.3 < 3.1 < 4.9 < 3.3 < 3.7 < 6.0 < 3.2 La-140 < 2.6 < 3.5 < 5.7 < 3.8 < 4.2 < 6.9 < 3.7 coIIection Date 8/19/89 8/26/89 8/26/89 8/26/89 8/25/89 8/25/89 8/19/89 I-131 < 0.25 < 0.34 15.0 (0.6) < 0.33 < 0.27 < 0.22 < 0.18 Cs-134 < 1.7 < 3.6 < 2.2 < 1.7 < 2.4- < I.7 < I.8 Cs-137 - < 2.0 < 4.2 < 2.8 2.1 (2.5) 3.1 (3.5)
< 2.0 < 2.1 Ba-140 < 2.7 < 6.5 < 4.7 < 2.7 < 4.0 < 2.6 < 2.9 La-140 < 3.1 < 7.5- < 5.4 < 3.1 < 4.5 < 3.0 < 3.3 1
1.96o (Due to Counting Statistics)
. . .. . ~ . . . _ . . . - . __ .. . _ _ . , . _ _ _ _ -
"/
Table II.D.1 Radionuclide Concentrations In Milk. (pCi/L).
LOCATION A-6 A-18 A-22 A-23 A-24 A-26 R-8 Collection Date 9/09/89 9/02/89 9/02/89 9/02/89 9/09/89 9/09/89 9/09/89 I-131 < 0.34 < 0.38 9.2 (0.42)* < 0.23 < 0.35 < 0.3 < 0.21 Cs-134 < 2.6 < 1.8 < 2.8 < 1.8 < 2.5 < 2.3 < 3.7 ~ ~~
Cs-137 < 3.1 4.2 (2.6) < 3.2 < 2.1 < 3.0 4.6 (3.9) < 5.4 Ba-140 < 4.9 < 2.9 < 4.1 < 2.9 < 4.0 < 3.3 < 5.3 La-140 < 5.6 < 3.4 < 4.7 < 3.3 < 4.6 < 3.8 < 6.1 Collection Date 9/30/89 9/23/89 9/23/89 9/23/89 9/30/89 9/30/89 9/23/69 I-131 < 0.33 < 0.41 1.5 (0.64) 0.28 (0.27) < 0.15 < 0.33 < 0.3 Cs-134 < 1.5 < 2.3 3.7 (3.0) < 1.7 < 3.6 < 2.0 < 2.6 Cs-137 < 1.8 6.3 (4.0) < 3.0 < 2.0 < 5.4 < 2.4 < 2.9 Ba-140 < 2.9 < 3.3 < 5.2 < 2.8 < 5.3 < 3.3 < 4.4 La-140 < 3.4 < 3.8 < 6.0 < 3.2 < 6.1 < 3.7 < 5.0 Collection Date 10/21/89 10/07/89 10/14/89 10/07/89 10/28/89 10/27/89
~~
10/21/89 I-131 < 0.19 < 0.23 4.6 (0.56) < 0.45 < 0.24 < 0.29 < 0.36 Cs-134 < 2.6 < 1.9 < 3.4 < 3.5 < 1.9 3.5 (2.4) < 2.7 Cs-137 < 3.1 3.1 (3.4) < 4.0 < 4.5 3.2 (3.3)
- 2.5 t < 2.9 Ba-140 < 4.2 < 2.8 < 5.3 < 5.9
.< 3.1 < 3.3 < 3.7 La-140 < 4.8 < 3.2 ~ < 6.0 < 6.8 < 3.5 < 3.8 4.3 i
)
- 1.96o (Due to Counting Statistics)
._ _ _ ~ - -. . - . _ _ - _ ._ __ - _ . , - _, _._. -_.-.. ~-. _ _ _
.A- ,
lable II.D.1 Radionuclide Concentrations In Milk. (pCi/L).
LOCATION A-6 A-18 A-22 A-23 A-24 A-26 R-8 Coilection Date 11/18/89 11/04/89 11/04/89 11/04/89 11/25/89- 11/25/89 11/18/89 I-131 < 0.25 < 0.21 3.1 (0.38) < 0.24 < 0.16 < 0.22 < 0.31 Cs-134 < 1.9 < 2.2 < 2.1 < 1.3 < 2.2 < 1.4 < 2.5 Cs-137 < 2.1 < 3.3 < 2.5 < 1. 6 < 2.6 < 1.8 4.9 (4.4)
Ba-140 < 2.9 3.7 (4.4)* < 3.3 < 2.1 4.6 (4.4) < 2.5 < 3.7 La-140 < 3.4 4.3 (5.1) < 3.7 < 2.4 5.2 (5.0) < 2.9 < 4.2 Collection Date 12/16/89 12/09/89 12/9/89 12/09/89 12/16/89 12/23/89 12/16/89 I-131 < 0.29 < 0.38 < 0.27 < 0.33 < 0.16 < 0.35 < 0.35 Cs-134 < 2.5 < 3.0 < 2.5 < 1.9 < 3.6 < 1.4 < 2.3 Cs-137 < 2.9 < 3.4 < 3.0 2.9 (2.5) < 5.0 1.9 (2.0) 5.5 (4.0)
Ba-140 < 4.4 < 4.7 < 4.0 < 2.7 < 4.8 < 2.9 < 3.8 la-140 < 5.1 < 5.4 < 4.6 < 3.1 < 5.5
~
< 3.3 < 4.3-
, a>
- 1<96o (Due to Counting Statistics)
+ %e yag- e.- g e-. y w w- ,gr g-- y .w- .%m4-ye. > rp .-.w< >. g.7m- ,#
1 I-131 Concentrations at Two Sites on the l S. Platte-River Upstream of F.S.V.,1989 1 1
1000 - _
", Figure II.D.2 l
- J l
i , , Denver Metro District .
l
' Sewage Plant .
- --
- AI22 i
l 100 - s l
1 - ,
D -
b -
\ l h \ Y O -
e I \ f I -
O.
I l\ / \ \\ I
- I \./
\
\ l I \r .
, I i \ l \
l \
l
\
I l \l 1
\ \
10 -
\ l \
l
- \1
\l e
1 i
4
~
i .
1 -
4 J
i t 1 1 l 1 1.0 360
- 280 300 320 340 -
t-79 E .lullan Dav No. _ . _ . _ . _ . . - . _ _ . ,
Table II.D.2 Tritium Concentrations in Milk. (pC1/L)
Adjacent Sites Reference Collection Date A-6 A-18 A-22 A-23 A-24 A-26 R-8 JAN 7-28 < 400 < 460 f < 400 < 400 < 400 < 400 FEB 4-25 < 390 < 400 < 400 < 400 < 390 < 400 < 390 s '
MAR 4-25 < 390 < 390 < 390 < 390 < 390 < 390 < 390 APR 1-23 < 390 < 390 < 400 < 400 < 400 < 400 < 400 MAY 6 & 13 < 400 < 400 < 400 < 400 < 400 < 400 < 400 MAY 20 & 27 < 400 < 400 < 390 < 390 < 400 < 390 < 400 JUN 3 4.10 < 400 < 390 < 390 < 390 < 400 < 400 < 400-JUN 17 & 24 < 390 < 390 < 390 < 390 < 390 < 390 < 390 JUL 1 & 8 < 390 < 390 < 390 < 390 < 390 < 390 < 390
. JUL 15-29 < 400 < 400 490 (410)* 490 (410) 460 (420) 870 (420) < 400 8
AUG 5 & 12 < 400 440 (410) 480 (420) 500 (420) < 400 510 (440) < 400
-AUG 19 & 26 480 (420) 460 (410) 430 (440) 650 (420) 690 (420) 470 (410) 570 (420)
SEP 2-16 < 400 < 410 640 (450) < 410 < 400 < 400 < 400 SEP 23 & 30 < 390 < 400 < 390 < 390 < 390 < 410 < 400 OCT 7-28 < 390 < 390 .< 390 <350 < 390 < 390 < 390 NOV 4-25 < 430 < 390 < 390 < 390 < 420 < 3,90 < 390 DEC 2-30 < 420 < 410 < 420 < 410 < 410 < 410 < 410 1 .
i
- . , _ , . _ _ _ -- -- ~ -~ - ' ' ~ ~ ~~~
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 seepage from the farm pond. The locations of these food product collection sites are described in Table III.B.l. One sample of each principal' class ~of food products was collected from these locations. Locations and available produce of ten change due to owner needs, harvest time, harvest size, etc. ;
Each sample is homogenized without drying immediately l 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 1989 harvest. Three of the food samples I showed detectable Cs-137 from past Chernobyl fallout ;
depos Ltion but no I-131 or Cs-134 was detected above MDC. The gamma-ray spectra were scanned for other radionuclides, btit only the raturally occurring were observed, presumably due to surface soil deposits.
i
. 81 i 1 '
I l
i
.. j f
Table II.E.1 Radionuclide Concentrations in Food Products (Pci/kg) ,
Collection Date 9/21/89 Location Food Type I-131 Cs-134 Cs-137 .
F A-28 BEANS <15 <15 23 (26)*
A-27 CUCUMBERS <7.4 <7.2 14 (10) -
i R-6 CABBAGE <10 <6.6 <7.9 R-6 MELON <5.0 <3.3 <4.9 R-6 POTATOES <12 <7.2 <8.7 R-6 TOMATOES <3.8 <3.5 8.0 (6.1) ,
A-27 PEPPERS <18 <7.6 <11 -
A-27 ONIONS <6.2 <6.0 <7.2 R-6 TOMATILLOS <7.2 <7.5 <11 )
- 1.96o (Due to Counting Statistics) t t
82
I i
l II.F. Aquatic Pathways 8
l Table II.F.1 shows radionuclide concentrations measured 1
1 in fish samples collected at F-19, A-25 and R-10 on two dates ;
t .. l l in 1989. The fish were collected by shocking and netting and j
' i the composite sample was homogenized without cleaning and-analyzed on a wet weight basis.- The positive values of Cs-137 l Were assumed to be due to fallout. The other values above MDC .
l were assumed to be false positive. [
Table II.F.2 shows the measured concentrations of both ,
Cs-137 and Cs-134 in surface sediment collected at R-10, the downstream location. There was measurable activity of Cs-137 l
clearly- due to the Chernobyl fallout. The cesium ions are bound nearly irreversibly by the clay mineral matrix in the sediment.
Monitoring for corbicula fluminen, a species of 1
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 '.
Asia. The freshwater clams are now found in large river !
systems in the U.S. from coast to coast. The Colorado l l
Division of Wildlife has stated that Corbicula have been found l
in Northern Colorado at Boyd Lake, some 30 miles from the Fort St. Vrain Nuclear Generating Station. However, to this date, our samplings have indicated no evidence of Corbicula in any of the sampling sites of the reactor surface water courses.
i r
83
Table II.F.1 Radionuclide Concentrations in Fish. (pC1/kg)
Collection Dat e First Half Second Half upstream trrivent Downstream Ef fluent
$ stream Downstream Radionuclide F-19 A-25 R-10 F-19 A-25 R-10 Cs-134
< 8.3 < 10 < 15 < 4.7 < 2.7 12 (15)
Cs-137 12 (12)* 15 (13) < 18 < 5.6 6.3 (3.9) < 15 C0-58
< 7.8 < 17 < 24 4.8 (5.2) < 2.5 < 11 Mn-54
< 8.0 < 11 34 (20) < 4.8 3.8 (3.4) < 12 Zn-65
< 20 < 28 < 44 < 13 < 8.7 < 31 Fe-59
< 100 < 43 < 25 < 7.9 < 5.2 < 20 SE Co-60
< 8.8 < 10 < 15 < 5.1 < 3.8 < 13
- 1.96o (Due to counting stctistics.)
E g -- g = p,+w w kwwa g- y- p - _ _ - .--_n u3mw__,,___._; ,s_m ,o,-w ._
r.
II.F.2 ~
Radionuclide Concentrations in Sediment from downstream Iccation RIO. ( pC f / kg )..
Radionuclide Collection Date 3/25/89 Cs-134 < 34 Cs-137 110 (37)*
Radionuclide Collection Date 8/5/89 Cs-134 < 12 Cs-137 130 (13)
- 1.96o (Due to Counting' Statistics)
- g ..
4 6 -
I 1
II.G. Sample Crosscheck Program
,- To assure 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 j assurance programs.
intralaboratory quality The U.S.
Environmental Protection Agency . (EPA) sponsored laboratory intercomparison studies program is the principal crosscheck.
This involves the analysis of a variety of environmental media containing various levels of radionuclides. The media, type of analysis and frequency of analysis for the EPA program are summarized below.
Medium Analysis (radionuclide) Frecuency Water H-3 Triannually Water Gross beta, gross alpha semiannually Water co-60, 2n-65, Cs-134, Cs-137 Triannually ,
Water I-131 Semiannually l Air partic- Cs-137, gross beta, Semiannually L ulate filter gross alpha I
l Milk I-131, Cs-137 Annually For each radionuclide analysis of a particular medium, three I
independent measurements are performed and all results are reported to the EPA. It should be noted that during the year, l
L our laboratory became certified by the EPA for drinking water analysis.
Table II.G.1 gives the EPA crosscheck data for 1989. The EPA uses the term, Estimated Laboratory Precision (ELP),
calculated as one standard deviation for one determination.
86 l
?
i ,
t 1 I
4 I
The normalized deviation of our mean from the known is [
- calculated ast
]
l CSU mean value EPA known value e4B ..
{
i i !
l Where: a = standard deviation of' the mean of all participating f
l laboratory resulta [
l n - number of analyses by our laboratory, normally n=3 The control limit is determined by the mean range of all '
results and three standard deviations of the range. If any result exceeds 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 1989 all results except 14 were within the warning level. The resulto '
exceeding the warning level have the notation (n) _in Table II.G.I. If possible, the corrected values are shown in the '
table. The recheck process and conclusion are given below for each of these samples.
1.
L The laboratory was changing building on campus during this period and the alpha gas-flow system was inoperative.
- 2. No apparent reason for aberrant result.
- 3. No apparent reason for aberrant result.
- 4. "K count yield was incorrect. New calibration produced correct result.
Table II.G.2 lists independent results for H-3 in. water ,
samples split between this laboratory and the Colorado 87 i
i i
l Department of Health, Radiation Control Division 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 i the split water samples. The procedural differences between the laboratories were previously investigated and minimized.
l It is concluded that the differences can be attributed *only to total analytical uncertainty.
Table II al. 4 shows results of an intralaboratory crosscheck program. Replicate samples are independently [
t i
analyzed. The replicate results are not statistically different and imply that the precision of the methods is acceptable.
During 1989 approximately 30% 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 l computer calculated and listed. '
computer calculations are often recalculated by hand and those done during 1989 were all verified to be correct.
l 4
l i
^
88
V .
Table !!.G.I EPA Cross-Check Data Summary. 1989.
n Radio CSU EPA' 1 E.L.P.* ' Normalized Deviation-Date. nuclide Value Value- from known**
WATER. TRITIUM (pCi/L)
Feb 24 -H-3 No value reported due to calibration changes Jun 23 H 4012 4503. 450 -1.89 Oct 20 H-3 3327 3493. .364 -0.80 .
' WATER. Alpha / Beta (pCi/L)
Jan 20 alpha 7.3' 8.0 5.0 ' 0.23-beta 5.0 4.0 '5.0- 0.35 May 12 alpha 25 30: 8.0 -1.01 beta 58 50 5.0 2.66 Sep 22 alpha (1) 4.0 5.0 beta 8.7 6.0 .5.0 0.92-WATER.-I-131 (pCi/L)
Feb 17 1-131 139 106 11 (2)
WATER, Performance:(pC1/L)
Apr 18 alpha 25 29' 7.0. 1.07- ,-
beta 51 57 5.0' -1.96-
- Cs-134 18 20. 5.0 -0.69' Cs-137 24 20 5.0 - 1.39 Oct 31 beta 33 32 5.0 0.23 Cs-134 5 5.0 5.0 0.00 Cs-137 7.3 5.0 5.0 0.81
- E.L.P. = Expected laboratory-precision. '
- Normalized deviation = -(CSU mean - EPA known)/.('o/fii).. if this value' falls between upper & lower warnin9. levels, the accuracy is acceptable 89 l
) '
> l Table !!.G.I' EPA Cross-Check Data Sumary. 1989. (continued) ;
j Radio CSU EPA. 1 E.L.P.* Normalized Deviation )
Date- nuclide Value Value .from known j WATER. Gamma (pCi/L) q Feb 10 .00-60' 8.0 10 5.0 -0.69 i e
Zn-65 137 159 16 -2.54 '
.Cs-134 7.0' 10 5.0 -1.04 ;
Cs-137 13 10 5.0 0.92 'l Jun 9 Ba-133- 44 49 5.0 . -1.73
- i Co-60 31 31 5.0 -O Zn-65 156 165 17 -0.95 "
Cs-134 34 39 5.0- -1.85 Cs-137 20 -
20 5.0 0.12 t
Oct Ba-133 45 59 6.0 -3.95 (3)' !
Co-60 22 30 5.0 -2.89 Zn-65 123 129 13 -0.75 Cs-134 25 29 5.0 -1250 '
i Cs-137 58 59 5.0 -0.35 MILK (pCi/L)
Apr 28 Cs-137' 48 50 5.0 -0.81 K-40 1450 1600 80- -3.3 (4) 1 AIRFILTERS(pCi/L) v
~
Mar 31 alpha 19 -21 5.0- -0.81 l beta 62 62 5.0 -0.12 .
Cs-137 22 20 5.0 0.81 +
Aug 25 alpha 1.0 6.0 5.0 -1.73 Cs-137 9.7 10 5.0 -0.12
- E.L.P. = Expected laboratory precision.
- Normalized deviation = (CSU mean - EPA known)/(c/fii), if this i value falls between upper & lower warning levels, the a.ccuracy :
l is acceptable t
'$' f I
- ]
l' ;
- r
Table II.G.2 Tritium Crosscheck Analyses on Split Water Samples Determined By Colorado State University. Colorado Department of Health, and Public' Service Company.
] '
Collection Sample Tritium Concentrations pCi/L .i Date Location CSU CDH PSC l Jan 14 A-25 16000(520) 28152 (300) 29200(752.)
Jan 14 A 440 145 <349 Jan 4 E 310 134 '349 Feb 11 A-25 21000(640) 24549 (278) 2640(737)
Feb 11 A <280 124 (90) <361 Feb 8 E-41 <280- 80 (90) <361 Mar 11 A-25 33000(750) '28268 (283) 31500(7$1).
tiar 11 A-21 <280' 21- 641 (438)
Mar 8 E-41 <280 68 <357 Apr 8 A-25' 24000 (660)' 18837(238) 19800(664)
Apr 8 A-21 1800(430) 24 (86) <348 Apr 5 E-41 <270 200-(89)- 102 (87.40)
May 13 A-25 25000(670) 20834 (247) 23500L(703)
May 13 A-21 <280 -4 (85) <346 May 3 E-41 <280 111-(87) 1700(420)
Jun 10 A-25 5600 (490) 5028 (142) 13700(816)
Jun 10 A-21 '270
< -37(85) <344 Jun 14 E-41 <250 <344 Jul' 8 A-25 16000(610)' 13722 (206) 14500(601)
Jul 8 A-21 560(430). 10(84) 4339 Jul E-41 Not collected Aug 12 A-25 23000 (670) 18016 (232). 19200(647)
Aug 12 A 21 <270 89(87)- <333 Aug 23 E-41 520(430) -34 (85) <555 Sep 9 A-25 16000 (610) 16433(227) 17700 (636)
Sep 9 A-21 530(430) 48(91) <339 Sep 6 E-41 370 (420) 89 (92) 555 (416)
Oct 14 A-25 45000 (850) 43012 (353) 45000(882)
Oct 14 A-21 390(420) 27~(93) <338 Oct 5 E-41 8000 (520)- 6529 (162) 7010 (505).
Nov 11 A-25 75000 (1000) 73046 (451) 75900 (1100)
Nov 11 A-21 290 (420) 14. (94') <344 Nov 18 E-41 1200(440) 1194 (110) 1420(435)
Dec 9 A-25 '36000(780) .32604 (308) 32600(788)
Dec 9 -A-21 420 (420) 19 (91 <354 Dec 6 E-41 530(440) -1 (90 <354 1
h 91
[:
p-i' Table II.G.3 -
. Gross Beta Crosscheck Analyses on Spitt Water Samples Determined by Colorado State University. Colorado Department 'of Health, and Public Service Company of Colorado.
Collection Sample Gross Be'ta Concentrations pCi/L Date Location CSU CDH pSC
.Jan 14 A-25 2.7(1.3) 21 5) 11.6 6.91 ..
Jan 14 A-21 2.1(1.3) 14 4)- 6.55 6.49 Jan 4 E-41. 11(5.7) 15 4) 7.76. 6.56 Feb 11 A-25 13(2.7) :18 5.68(6.71).
Feb:11 A-21 7.9(2.5) 17 <5.34 Feb 8- E-41 13(5.9) 11 <5.33 Mar 11 Mar 11 Mar 8 A-25 A-21 E-41 11.
10 11
.'.)
.}
16-16 15-13.70 (6.77 9.79(6.60))
10.40.(6.62)
Apr 8 A-25 15(6.0) 18 ?2.80 (6.62)
Apr 8 A-21 8.6(5.7) 13' 17.60 (6.38 Apr 5 E-41 9.9(5.7) 14 9.07(6.70) )
May 13 A-25 17(6.1) 20(5) .8.00(7.00)
May 13 A-21 12-(5.8) 7(4) <5.00 May 3 E-41 12(5.9) 12(4) 8.00(6.00)
Jun 10 A-25 16(6.0) 20 (5) 13.10 (6.94)
Jun 10 A-21 8.6(5.7) <5.00-Jun 14 E-41 21(6.3). 13.20(7.58)
Jul 8 A-25 13(5.9) 13(4) 9.43(6.62)
Jul 8 A-21 11(5.8) .
13 (4) 6.06 (6.46)
Jul E-41 Not Collected .
Aug 12 A-25 15(6.0) 13(4) 10.90 (6.76)
Aug 12 A-21 7.6(5.7) 13 (4)
Aug 23 6.06(6.66)
E-41 8.6 (5.7) 7(4) 11.00(6.52) i Sep 20 A-25 13 .
17 4) 14.60 6.67)
Sep 20 A-21 17 . 36 5 21.50 7.09 Sep 20 E-41 12 . 12 4 12.20 6.85 Oct 23 A-25 11 5.8) 18(4) 9.92 (6.48)
Oct 23 A-21 12 5.9) 17 (4) 15.10 (6.77)
Oct 23 E-41 12 5.9) 13 (4) 9.57(6.37)
Nov A-25 11 (5.8)
Nov 18 4) 6.68(5.84)
A-21 11(5.8) 23 4) <4.48 Nov E-41 14 (5.9) 16'4) 16.30(6/44)
Dec A-25 11(5.8) 14 (4) 7.36'(6.96).
Dec A-21 0.34 (5.3) 15 (4) 8.79 (6.78)
Dec E-41 11 (5.8) 27 (5) 11.70 (6.98).
92
1 Tcble:II.G.4' Intr:laborat:ry Crosscheck Results, (pCi/L)
(Replicate Analysis of Same Sample)
Water Radio- 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter
'Nuclide A B A B A B A B Cs-134 cl.7 <3.3 <1.5 <0.85 <2.5 <l.5 <1.2 <l.3 Cs-137 2.8(2.3)* 8.0(4.9) 2.2(2.1) 1.2(1.2) <3.0 2.0(2.2) <l.4 2.2(1.9)
Zr-45 <3.7 <8.1 <3.1 <2.1 <5.5 <3.2 <2.7 <2.6 Nb-95 <2.1 <3.1 <l.3 <0.93 <2.7 <1.7 1.9(1.3) <1.1 00-58 <1.6 3.7(4.0) <l.3 <0.87 <2.3 <l.4 <l.1 <l.2 Mn-54 <l.6 <3.4 <1.5 <0.84 <2.5 <1.5 <l.2- 1.8(1.6)
Zn-65 <5.6 <8.3 <3.4 <2.3 <7.4 <4.4 5.2(3.7) <3.4 Fe-59 <4.4 <8.4 <3.7 <2.1 <6.9 <4.1 <3.0 <3.2 Co-60 <I.S <3.6 <l.3 <0.83 <2.4 <1.4 <1.2 <l.2 Ba-140 <2.8 <5.5 4.7(4.0) <2.8 <6.4 <3.7 <2.3 '< 2.l La-140 <3.3 <6.3 5.4(4.6) <3.2 <7.4 <4.3 <2.6 <2.4 Gross Beta 7.7(2.5) 4.1(2.3) 0.78(0.56) 0.94(0.57) 2.8(2.4) 5.2(2.4) 3.7(2.3) 4.6(2.4) 11- 3 <400- <400 <410 500(410) <410 <410 45000 44000 u, Milk w
lst Quarter 2nd Quarter 3rd Quarter 4th Quarter A B A B A B A B Cs-134 <l.4 <l.5 <2.5 <l.3 4.9(4.0) <2.9 <2.5 <l.6 Cs-137 <l.7 <l.7 <3.1 2.0(1.8) <4.2 3.9(4.1) <3.0 <2.0 Ba-140 <2.7 <3.0 <5.2 <2.0 <5.4 <4.6 <4.0 <2.6 La-140 <3.2 <3.5 <6.0 <2.3~ <6.2 <5.3 <4.6 <C.9 H-3 <390 <390 <390 ' <390 <400 <420 <390 <390
- 1.96o (Due to counting statistics) -
u_ . _
1 1
1 I
II.H. Summary and Conclusions Table II.H.1 summarizes the radiation and environmental l
radioactivity measurements conducted during 1989 in the j environs of - the Fort St. Vrain Nuclear Generating Station, owned and operated by Public Service Company of Colorado. The )
values for each sample type-may be compared to pre-operational .
and operational periods for this reactor, as well as' to the ,
values from other U.S. environmental monitoring programs. ;
(e.g., EPA 520) . It must be emphasized, however, that the mean values in Table II.H.1 are only the means of the values t
greater than MDu, the statistically minimum detectable :
concentration. The range also is given only for detectable measurements. The mean and range values, therefore, are not the true means or ranges if.any of the values in the sample ,
popula, tion were less than MDC. The format of Table II.H.1 is a requirement of the NRC. '
l Inspection of Table II.H.1 reveals that (except for I-151 at site A-22) there were no individual measurements that "
l
- exceeded the Reporting Level (RL) (see Table III.A.3). The Chernobyl fallout was still observable in several sample types. 5 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. '
This difference cannot be due to reactor effluent activity for the following reasons:
- a. None of the individual- fission product or ,
94
l [
i activation product radionuclides measured were significantly higher in the Gilcrest drinking weter.
- b. Tritium concentrations measured at Gilcrest were statistically the same as than- those in Fort Collins.
- 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 is supported by the fact that the l gamma-ray spectra of the suspended solids from .
Gilcrest water samples show only elevated concentrations of the natural radionuclides. It has been concluded in previous reports that the elevated gross beta concentra:.f ons in Gilcrest ,
L water are due to elevated concentrations of the naturally occurring U-238, and Th-232 decay ,
products. The suspended solids are higher in Gilcrest water samples due to less filtration of the water.
For the category of tritium in surface water, as has been -
the case since reactor operation, elevated concentrations were noted at station A-25, the outlet of the (Goosequill) farm pond. A-25 is directly in the principal effluent route and elevated concentrations should be expected, to correlate with release schedules. Elevated concentrations of tritium have never been observed, however, in any human food source in-direct or indirect contact with the f.wrm pond ' water.
95
i i
1
)
Downstream surface water concentrations of tritium have ;
i occasionally been elevate,d, but there is significant dilution .l before any human use of this water. During 1989 elevated #
tritium concentrations were observed downstream on several ;
occasions but the mean values for the first and second half of ,
1989 were not significantly greater than in upstream surface I i water. An historical summary of tritium concentra' tion in upstream, downstream and potable surface water for six month periods from 1974 to 1989 is depicted in Figure II.C.1. The i potable water concentrations plotted are those for the Gilcrest city water well. 5 I-131 was observed again in milk samples, but again only from Dairy A-22. Because the reactor did not release any ,
significant fission products during 1989, the source of the I-131 concentrations in milk could not be reactor affluent. It was documented in the 1985 annual report that the source of ,
the I-131 concentrations during that year was not due to the reactor but due to nuclear medicine use and release upstream of the reactor. This was an important observation as I-131 is ;
certainly a critical radionuclide in human dose commitment
- possibilities, a fact of 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 1989. Irrigation water samples confirmed this conclusion. An additional continuous water sampler on the I 4 1.
Platte River outlet of the Denver Metro Sewage District plant 96 .
l
- l I
revealed-the same variation in I-131 concentrations observed J J
at A-22. This further confirms that the Denver hospitals are j the source of the I-131.
Cs-137 was also observed in many environmental sampi s due to the Chernobyl fallout.
~
Table II.H.2 presents an - additional summary of mean- !
. values for selected sample _ types. The sample. tybes ' and
. i radionuclides were chosen on- the-basis of their importance in L
i u documenting' possible' radiation dose to humans. Air and .;
surface water would be the predominant environmental transport -l routes and drinking water and milk would be the predominant i
sources of radiation dose it .significant radioactivity release from FSV occurred. Table II.H.2 also-allows comparison to the I
three most recent years of operation.
- r l The arithmetic means in Table.II.H.2 were calculated for '
l l
all sample results. It should be noted that the tabu'lar d'ata presented in the body of this report contain only positive calculated values above the minimum detectable concentration (MDC) levels. Any calculated values less than zero or less l-l than the minimum detectable concentration MDC are listed as 4 less than the actual MDC for that sample analysis. However, the actual result in all' cases was used in the calculation for.
E the arithmetic mean values for the period. Therefore, all l
values, negative as well as positive, were included, This procedure is now generally accepted and gives a proper I
estimate of the true mean value. Because of this procedure, -i t
however, the values listed in Table II.H.2 cannot be i
97 e t
calculated directly from the-tabular values-in the report. It must be emphasized that while-it is true that-no sample can contain less than-zero radioactivity, due to the random nature.
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. Thefrefore,
, q a
to - obtain the correct mean.value from the distribution of l analytical results, all positive results must be averaged with.
all. negative results. .If the negative results were omitted, ,
i the resulting' arithmetic mean would be falsely biased high- l l
From log-normal analysis of each data set for each 12-month period, the geometric - mean - 'and geometric standard j deviations are also presented in Table II.H.2. The log-normal 'I probability treatment is to plot all data for each sample type !
over the year on . log-probit coordinates. The samples ,are ranked by ine.:reasing activity concentration and the cumulativ'e percentage of rankings are plotted 1on the probit abscissa versus the activity concentration of the log ordinate. The ,
geometric mean value, X,, is determined directly from the 50th percentile point. The geometric standard deviation is simply-the slope of the 1ine which can be calculated from the ratio between 84.1 percentile point and the 50th percentile. In a normal distribution, the arithmetic standard deviatio,n is an additive parameter to the arithmetic mean, i.e. (X o);
whereas, in the log-normal distribution the geometric standard deviation, o g, is a multiplicative parameter to the geometric 98
' me a n - ( X, L + . 0,) . The area- between X, multiplied by a, and X, e
divided - by a, should contain 68% of ' the frequency - values.
- t With . the log-normal - ' analysis , no bias results' from using 1 either actual values or less than MDC values in estimating the ,
geometric mean. The geometric mean is identical to the median. , i r
From the values presented in Tables II.H.12;nd '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 l the effluent pathways that could;be' attributed-to reactor operation.- Since the tritium- is' released as tritiated water, the dilutionL b'y the surrounding ;
hydrosphere is great.- Although in' 1989 a few elevated levels of- tritiated water could be detected in downstream. surface water samples, the 'I mean values of downstream surface water was not +
- . statistically greater than upstream concentrations.
The tritium concentrations measured-
?
- I i
.?
e I
i l
99 l
l
2~ .
- o j j l
in milk produced by.the nearest dairy herd were also all less than MDC.
]
2 ~. Figure II.C.'l is a plot of' tritium ' measured in-f surface water ' samples over the period 1974-1989. (
During the period' the predominant source term is f that of; fallout deposition. There'is some delay
. period in the peaks'due to the mean residence. time' ,
of tritium in thel hydrosphere and input from other areas. . Beginning i in 1981, an -increase can - be -
observed in the downstream locations- relative to upstream. This amall increase is statistically- i si'gnificant,i e- the radiation dose commitment.
that can be ca. .ced as a . result .of possible ingestion of this as drinking water 'was found to be lI negligible as. compared 'to. natural background radiation dose . rates. This was' discussed in'the 1986 annual report. [
t
- 3. As in every previous report, it was again apparent '
that for most sample types the variability observed around the mean values was great. This variability is due to counting statistics and methodological j
, variation, but principally due to true environmental variation' (often termed sampling error). It must be recognized and accounted for in analysis of any set of environmental data before meaningful conclusions.can be drawn.
- 4. The Chernobyl accident fallout has totally obscured T
100
p, k i n ,
f what fission product debris has remained in the FSV $
l environs from the October 1980 Chinese atmospheric-
~
U nuclear weapon. test. The biosphere will contain: !
the Chernobyl fallout, particularly Cs-137, for.Sn equally-long period.
Nuclear' weapon' test' fallout ,
has'since the inception of the project been noted s
to be the 'only = predominant source. tard above l natural background. It is the variation in fallout j deposition, in addition to- the variation in ;
naturally occurring -radionuclides, that man' dates l
the large number of environmental samples-to detect' ,
- any- possible radioactivity due to reactor effluents. A' simple comparison of pre-operational-d and operational values is of little value for most j sample types because the fallout ' deposition was considerably . greater during the pre-operatio'nal period.
- 5. 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 1
accidental releases from the FSV reactor operation..
It can be concluded from the data collected by the environmental monitoring program that the radiation <
i dose commitments calculated for the closest inhabitants or other parts of the nearby ecosystems
. due to current reactor effluents are -negligible. l 101
l i
Natural. - background ~ radiation-- and the dose
. commitment from atmospheric fallout are - the only.
known-significant sources of radiation-dose to the I
residents of.the area.
l 4 f I e 4
' i 4
i t
t I
l~
102.
L
-e w. ,,
Table ' 11.11.1 Environmental Radiological Monitoring Program Annual Summary Fort St. Vrain Nuclear Generating' Facility, Platteville, Colorado
. Medium or Pathway. Type and Facility Adj acent Locations with liighest Reference' Number of Samples (Unit of Total Number Location Mean (f)g Location Nah"""*1M**" Mean (f)b .Lcationg Nonroutine measurement) of Analysis Mean (f)$ Mean (f) Reported Performed. range range Distance & Range Range Measurements Direction-Direct Radiation TLD (164) -0.38 (72/72) 0.38 (72/72) A-10 WCR26b 0.45 (4/4) 0.35 (20/20) 0 (mR/ day) (0.30-0.45) (0.30-0.49) & WCR 15 (0.43-0.49) 0.28-0.41 7.8 km, 214*
Air, Gross (357) 26 (202/202) F-16 3-Bar 20 (51/51) 24 (155/155) O Particulates (11-88) Ranch (4.4-52) (6.9-42)
( fCi/m') 1.2 km,'0*
c3 Gamma Spectrometry
. u>
Cs-134 (28) ----
R-11 1.3-(1/12) 1.3 (1/12) 0 Johnstown (1.3) (1.3) 10.5 km 349*
Cs-137 (28) 1.9 (2/16) F-16 3-Bar 1.9 2/16 1.8 (2/12) 0 (1.4-2.4) Ranch (1.4-2.4) (1.5-2.1) 1.2 km 0*
Air, Charcoal 1-131 (359) 29 (13/204) F-7 UCR21 34 3/50 25 (7/155) 0 (pCi/m') (12-45) & WCR34 (26-45) (15-40) 1.5 km 146*
Air, Atmospheric 11-3 (346) 930 (50/198) .R-3 Ft. Co111ns 1200 (7/50) 920 (13/148) 0 Uater vapor (410-3700) . City Water (400-4400):
~
'(400-4400)
. (pci/m') -
33.5 km 335*
4
'Mean and range based upon detectable measurements on1'y. ' Fraction (f) of detectable measurements at specified locations is indicated in parentheses.
___m.__ _ - ~ . . - _- - . _ .- -
~.__ .. .. , _ - _ . -_ ~ _ _ _ _ _ _:
-; Table 1 1 .11. 1 Environmental Radiological Monitoring Program Annual Summary Fort-St. Vrain Nuclear Generating Facility, Platteville, Colorado Medium or Pathway Type and Facility Adj acent Locations with Highest Reference Number of Samples (Unit of Total Number Location Location NagnnualMean Location Nonroutine Mean (f)g Mea (fib Mean (f)g measurement) of Analysis Mean (f)E Reported Performed range range Distance & Range Range Measurements Direction Drinking Water Grossp (52) 5.8 (26/26)' R-6 Gilcrest '5.8 (26/26) 0.98 (26/26) O.
(pCi/L) (3.7-7.8) City Water' (3.7-7.8) (0.56-1.5) 9.3 km 60* .
11 - 3 ( 5 2 ) 550 (1/26) R-6 Gilcrest 550 (1/26)- 450 (1/26) 0 (550) City Water (550) (450) 9.3 km 60*
Gamma Spectrometry I-131 (52) 0.63 (2/26) R-6 Gilcrest 0.63 (2/26) 0.54 (2/26). 0 (0.54-0.71) City Water (0.54-0.71) (0.50-0.57) 9.3 km 60*
Cs-134 (52) 1.4 (1/26) R-3 Ft. Collins 2.0 (2/26) 2.0 (2/26) 0 (1.4) City Water (1.1-2.8) (1.1-2.8).
33.5 km 335*
Cs-137 (52) 3.2 (14/26) R-6 Gilcrest. 3.2 (14/26)' 2.9 (12/26) O.
(1.3-8.0) City Water (1.3-8.0). (1.3-5.2)-
9.3 km 60*
Zr-95 (52) 4.8 (2/26). R-6 Gilcrest 4.8 (2/26) 4.6 (1/26) 0 (4.1-5.5) City Water (4.1-5.5) (4.6) 9.3 km 60*
Nb-95 (52) ----
R-3 Ft. Collins 4.4 (1/26) 4.4 (1/26) O (4.4) (4.4)
City Water.
- 33.5.km 335* .
. *Mean 7.<' : a.re based upon detectable measurements only. Fraction '(f) of detectable measurements at _specified locations is indicteed in parentheses. -
.,.mm__- +e%,- 4 e m --,h- --m- ,, T4---di+ ,Twp- -a e &b*
- e% "- % -MWy'
- y '*P"*m P ,M'*'.- 'iq9 a -
=q r C # N ** uh- 4
Table 11 '. H .1 Environmental. Radiological Monitoring Program Annual Summary Fort St. Vrain Nuclear Generating Facility. Platteville, Colorado Medium or Pathway Type and Facility Adj acent Locations with Highest Reference Number of Samples (Unit of Total Number- ~ Location Location **" ### ' " " " '"*
Hean (f)g NamE""* Mean (fib measucement) of Analysis Mean (f)$ Nean (f)E 1 Reported Performed range range Distance & Range Range Measurements Direction Drinking Water Co-58 (52) 2.4 (2/26) R-6 Cilcrest 2.4 (2/26) ----
0 (pCi/L) (1.1-3.7) City Water (1.1-3.7) 9.3 km 60*
Mn-54 (52) 1.8 (3/26) R-6 Gilcrest 1.8 (3/26) 1.3 (4/26) 0 (0.90-2.5) City Water (0.9-2.5) (1.2-1.5) 9.3 km 60*
Zn-65 (52) 7.2 (6/26) R-6 Gilcrest 7.2 (6/26) 6.4'(3/26) O.
(3.6-10) City Water (3.6-10) (4.6-8.7) 9.3 km 60*
Fe-59 (52) 3.2 (1/26) R-3 Ft. Collins 3.6 (1/26) 3.6-(1/26) 0 (3.2) City Water' (3.6)' (3.6) 33.5 km 335*
Co-60 (52) ----
R-3.Ft. Collins 2.0 (4/26) 2.0 (4/26)' O City Water (1.0-2.8) (1.0-2.8) 33.5 ka"335*
Ba-140 (52) 4.2 (2/26) R-3 Ft. Collins. 5.0 (3/26)L 5.0 (3/26) 0 (2.3-6.0) City Water (4.5-5.9) (4.5-5.9)
- 33.5 km 335*
La-140 (52)' 4.8 (2/26) R-6 Ft. Collins. 5.8-(3/26) 5.8 (3/26) 0
. (2.6-6.9) City Water (5.2-6.8). (5.2-6.8) 33.5 km 335*
'Mean and range based upon detectable measurements only. Fraction (f) of detectable . measurements. at specJfied locations is
' indicated in parentheses.
4 e-__m....m. . _ - ,-.s..-..#I.-_~. o..'--- w.m=.-~ >--.--~.1-.- -- a-u,---- m.- im--- -
% , , . .y_ .- ..! =.w......, - .- .- . .- .
Table 1 1 . 11 . 1 Environmental Radiological Monitoring Program Annual Summary Fort St. Vrain Nuclear Generating Facility, Platteville, Colorado Medium or Pathway Type and Facility Adj acent Locations with Highest Reference Number of Sanples (Unit of Total Number Location Location ### " "E "' "*
Mean (f)g Nak"""*1M**" Mean (fib Mean (f)E Reported weasurement) of Analysis Mean (f)E Performed range range Distance & Range Range Measurements Direction Surface Water 11 - 3 ( 6 0 ) 27000 (13/36) A-25 Goosequill 29000 (12/12) 950 (2/24)' O (pci/L) (880-71000) Pond (9900-71000) (400-1500) 2.2 km 8*-
Gamma Spectrometry
_../
Cs-134 (60) 3.6 (2/36) R-10 S. Platte 3.8 (1/12) 2.4 (2/24) 0 (3.3-3.8) at CO 60 (3.8) (2.3-2.5)
, 10 km 290*
Cs-137 (60) 3.7 (16/36) F-20 St. Vrain '3.9 (6/12) 3.2 (10/24) 0 (1.5-6.5) at'WCR 19 1/2 (2.6-5.3), (1.7-4.9) 1.5 km 354*
Zr-95 (60) 7.5 (1/36) F-20 St. Vrain 7.5 (1/12) 6.8 (1/24); 0
, (7.5) at UCR lo 1/2. (7.5) (6.8) 1.5 km 354* .
Nb-95 (60) 1.8 (3/36) R-10 S. Platte 2.0 (2/12) 1.6 (1/24) -O (1.9-2.1) at CO 60 (1.9-2.1) (1.6) 10 km 290*
Co-58 (60) 2.7 (4/36) F-20 St. Vrain 3.4 (1/12) ----
0 (1.4-3.4) at;WCR 19 1/2 (3.4) 1.5 km 354*
Mn-54 (60) 1.9 (3/36) A-25 Goosequill 2.7 (1/12) 2.1(3/24) 0 (1.3-2.7) PondL .
(2.7) *
(1.5-2.8) 2.2 km B*
Zn-65 (60) 7.3 (3/36) F-20 St. Vrain' 11 (1/12) 7.6 (4/24) 0 (3.8-11) at WCR.19.1/2 (11). (5.7-8.4)L
- 1.5 km 354*
"Mean and range based upon detectable measurements only. Fraction (f) of detectable measurements at specified locations is indicated in parentheses.
. - . _ _ . . _ - - _ _ . . ,,- - -.-.m. _ .._._ _ _ _ . .-m.
Table II.H.1 Environmental Radiological Monitoring Program Annual Summary Fort St. Vrain Nucleat Generating Facility Platteville, Colorado
, Medium or Pathway ' Type and Facility Adj acent Locations with Highest Reference . Number of Samples (Unit of Total Number Location Location Location Nonroutine measurement) of Analysis Mean (f)g Mean (f)g. Nak"""*lN**" Mean (f)b Mean (f)g Reported Performed range range Distance & Range . Range Measurements Direction Surface Water Gamma Spectrometry (pCi/L) Fe-59 (60) 3.6 (1/24) R-10 S. Platte 3.6 (1/12) ~ 4.6 (2/24) 0
- (3.6) at CO 60 . (3.6) (3.5-5.7) 10 km 290*
Co-60 (60) 2.5 (1/24) 0 (2.5)
Ba-140 (60) 14 (1/24) F-20 St. Vrain 14 (1/24) 20 (1/24) 0-(16) at WCR 19 1/2 (14) (20) 1.5 km 354' La-140 (60) 16 (1/24) F-20 St..Vrain 16 (1/24) 23 (1/24) 0 (16) ~ at WCR 19 1/2- (16) (23)'
- 1.5 km 354*
4
' E3
! Ground Water H-3 2700 (?/4)~ F-16 3 Bar Ranch 2700 (2/4) ' 750 (1/4) 0
' (pci/L) (950-4500) 1.2 km 0* -950-4500' camma Spectrometry Cs-134 (8) . 1.8-(1/4)' F-16 3 Bar Ranch 1.8 (1/4) 0 (1.8) 1.2 km O' Cs-137'(8) 6.4 (4/4) F-16 3 Bar Ranch 6.4 (4/4) . .3.7 (3/4)- 0 (2.5-11.0) 1.2 km 0* . (2.5-11.0) (3.2-4.2)
Zr-95 (8) .R-5 Miliken 3.4 (1/4) 3.4.(1/41 ' '
.0 (3.4) ( 3.'4 )
fMeen and range based upon detectable measurements only. Fraction (f) of detectable measurements at specified locations is indicated in parentheses.
_a
., ., -i.a-~, u y .s. ..w v -_sm._s .4.%.. .*..er _-- g % u 9,~ ,-*,
4 + , _ . , , . , + ,__5.___.__,. __
,,1, g
Table II.H.1 Environmental Radiological Monitoring Program Annual Summary Fort St. Vrain Nuclear Generating Facility, Platteville, Colorado
' Medium or Pathway Type and Facility Adj acent Locations with Highest
- Reference Number ofL Samples (Unit of Total Number Location Location * " "' " '"*
Mean'(f)g Nak"""*1M**" Mean (f)b mzasurement) of Analysis Mean (f)5 Mean-(f)5 Reported Performed range range Distance & Range Range' Measurements Direction Ground Water Gamma Spectrometry (PCi/L)
Nb-95 (8) 3.6 (1/4) F-16 3 Bar Ranch 3.6 (1/4) 1.5 (1/4) 0 ~
(3.6)$- >
1.2 km 0* 'h '*48.6)
(1.5) s -. . *..n i o- p .ua.s .
O' Co-58 (8) ---- ----
Mn-54 (8) 2.0 (1/4). F-16 3 Bar 2.0 (1/4) ----
0-2.0 Ranch 2.0 1.2 km 0*
Zn-65 (8) 41 (1/4) F-16 3 Bar Ranch 41-(1/4) 13 (2/4) 0 (41) 1.2'km 0* (41). .(11-14)
Fe-59 (8) ----
R-5 Miliken 3.4 (1/4) 3.4-(1/4) 'O' 9.5 km 11*' (3.4) (3.4)
Co-60 (8) 1.5 (1/4) 'R-5 Miliken 3.0 (3/4) ~ ' 3.0 (3/4) 0 (1.5) 9.5 km 11* .1.2-5.0 (1.2-5.0)
Ba-140 (8) ---- ---- ---- ----
O t
- s ., s .
0 La-140
. i . i (8))
rls
.O faD '4 / ' # f. i. 8 4as ns-g.,,
~
~*Mean and range based upon detectable measurements only. Fraction J(f) of detectable measurements at specified locations . i.s-indicated in parentheses.
v - -
. . . . - - .,: - , - - .. - -~ ; .a - , -, - , ; , ,. -- . . . . . - ,
Table'II.ll.1 Environmental Radiological Monitoring Program Annual Summary Fort St.-Vrain Nuclear Generating Facility, Platteville, Colorado (Medium or Pathway Type and Facility Adj acent Locations with Highest- Reference Number of
-Samples (Unit of Total Number Location Location NagnnualMean Location Nonroutine Mean (f)g Mea (f)b Mean (f)g Eeasurement) of Analysis Mean (f)$ Reported Performed range range Distance & Range Range Measurements Direction
. Sediment Gamma Spectrometry (pCi/kg. dry)
Cs-134 (2) ---- ---- ---- ---- ----
0 Cs-137 (2) 120 (2/2) R-10-S. Platte 120 (2/2) ----
0 (110-130) at Co 60 -(110-130) 10 km 290*
e Milk H-3 (111) 540 (15/101) A 6165 '620 (3/17) 570'(1/17) 0 (pCi/L) (430-870) WCR 32 (470-870)
J7.8 km 242*
gamma Spectrometry I-131 (114) 3.2 (18/101) 'A 11733 4.3 (13/16) 0.53 (2/17) 0 (0.28-15) .WCR 36 _
(b.45-15)' (0.50-0.56) 3.2 km 85*
Cs-134 (114) 3.6 (6/101) A-6'- 13278 4.9 (1/17) ----
0 (1.9-5.0) WCR 32 (4.9)
~7.1'km 113*
Cs-137 (114) 3.7 (31/101) A 13278 .5.2-(5/17). 4.1'(5/17) 0 .
. (1.9'8.3) WCR 32 (1.9-8.'3). (3.0-5.5) 7.1 km 113*
?Mean and range based upon detectable measurements only. Fraction (f) of detectable measurements at specified locations is indicated in parentheses. .
-_w .. : _ ~-- .~ ..
.- - - - - . . --__.-.._z_ w :-- - - - z. .,
' Table . II .11.1 Environmental Radiological Monitoring Program Annual Summary
-Fort St. Vrain Nuclear Generating Facility, Platteville, Colorado Medium or Pathway Type and Facility Adj acent Iecations with liighest Reference ' Number of Srmples (Unit of Total Number Location location p,A nual'Mean Iscation Nonroutine measurement) of Analysis Mean (f)g Mean (f)g (f)b Mean (f)g Reported Performed range range Distance & Range Range Measurements Direction Milk Gamma Spectrometry (PCi/L)
Ba-140 (114) 4.2 (4/101) A-6 --13278 4.6 (1/17) ----
0 (3.7-4.6) WCR 32 (4.6) 7.1 km 113*
A 20718 WCR 17-6.9 km 338' La-140 (114) 4.8 (4/101) A 13278 5.2 (1/17) ----
0 (4.3-5.2) WCR 32 (5.2) 7.1 km 113*
A-24'- 20718.
.UCR 17 6.9 km 338' Food Products. Gamma ~ Spectrometry (pCi/kg, wet)
I-131 (10) ---- ---- ---- ----
0 Cs-134 (10) ---- ---- :--- ----
0 Cs-137 (10)- 15 (3/7) A 11399' 23 (1/1) '
0 (8.G-23) . WCR 40b. '23 5.3 km 34*
- Mean and range based upon detectable measurements on1'y; Fraction (f) of detectable measurements at specified locations is
~
indicated in parentheses.
Table 1 1 . 11 . 1 Environmental Radiological Monitoring Program Annual Summary Fort St. Vrain Nuclear Generating Facility, Platteville, Colorado
-Medium or Pathway Type and Facility Adj acent Locations with Highest Reference Number of Samples.(Unit of Total Number Location Location L cation Nonroutine Mean (f)g Nah"""*1N**" Mean (fib Mean (f)g measurement) of Analysis Mean (f)5 Reported Performed range range Distance & Range Range Measurements Direction Fish Gamma Spectrometry (pCi/kg, wet)
Cs-134 (6) 12 (1/4) ----
R-10 S. Platte 12 (1/2) ----
0
-(12) at Co 60 (12) 10 Km 290*
Cs-137 (6) 11 (2/4) A-25 Goosequil1~ .11 (2/2) 12 (1/2) 0 (6.3-15) Pond (6.3-15) (12)
(( 212 km 8*
Co-58 (6) ----
F-19 S. Platte 4.8 (1/2) 4.8 (1/2) 0 1.2 Km 90* (4.8) (4,8)
Mn-54 (6) 19 (2/4) R-10 S. Platte 34 (1/2) --+- 0 (3.8-34) at Co 60 (34) 10 Km 2900 .
Zn-65 (6) ---- ---- ---- ---- ----
0 Fe-59 (6) ---- ---- ' ---- : ---- ----
0 4
Co-60-(6) ---- ---- ---- ---- ----
0 9'
?Mean -and range based upon detectable measurements only. - Fraction (f) of detectable measurements at specified ' locations is indicated in parentheses.
. - - - = v -.- y - - - y,,.
y , , ,-,.s. ~ r ..% .y... ,, ,_ yw ,,,
~
Table II.H.2 Summary Table of Geometric Means, Geometric' Standard Deviations and Arithmetic Means for Selected Sample Types.
_ 1986 1987 1988 1989 X o X X o X .X o X X o X 9 9 9. 9 9 9 9 9 ,
Atmospheric Water Vapor (pCi/L)
H-3 .
Facility 220 2.1 <240 190 2.2 <230 400 2.6 470. 410' '2.1 43 Raforence 180 2.4 <240 190 1.9 <230 250 2.7 172 560' 2.2 <420 Air (fCi/m 3)
Gross Beta Facility 29 2.0 44 24- 1. 5 ' 26 25 1.4 26 25 1.4 26' ,
Reference 31 2.0 51 24 1.4~ 25 23 1.4 24 23 7.0 24 i
~I-131 CFacility 18 2.5 14 12 2.9 1.1 10 5.5 1.9 8.5 2.7 2.2
! " Reference 16 5.5 19 12 2.9 1.2 10 .5.8 .<4.5 8.0 -2.4 2. 2.
+
- Facility 2.5 3.3 4.1 1.3' 2.6 0.33. 1.6 1.9- 0.73. 0.78 2.4 0.32-Reference 2.0 4.7 4.5 1.1 2.6 0.44 1.4 5.8 1.0 0.85 2.0~ 0.46 i
6
- 4 l
. ,- - . a. .- . ,, m . . -..n - . - - . . . . _ . - - _ _ - _ .- __- -.
t' Table II.H.2 Summary Table of Geometric Means, Geometric Standard Deviations and Arithmetic Means for Selected Sample Types.
1986 1987 1988 1989 X o X X o X X o X. Y 'l 9 9 9 9 9 9 9 .%
Drinking Water (pCi/L) -
H--3 Gilcrest 130 2.9 <240 150 2.6 75 - 310 3.1 '370 240 3.1 <390-Ft.. Collins 210 1.4 <240 210 1.7 <230 260- .2.0 120 320 1.6 <390 Gross Beta Gilcrest 3.8 1.4 4.0 4.7 1.5 5.1 - 6.7 1.3 6.8 '5.7 1.2 5.8 Ft. Collins 1.3 1.9 1.6 0.7 1.5 .79 - 1.0 1.4 1.1 0.95- 1.3 0.98 I-131 .
! Gilcrest 0.2 2.4 0.14 0.2. 2.1 .052' O.17 2.0 0.099 l0.18 2.4 0.068 Ft. Collins 0.2 1.7 <0.49 0.2 3.5 - .071 0.18 2.5 0.083 0.19 2.9 0.14 C'
-Gilcrest 2.6 2.1 1.4 1.8 - 2.1 2.1 1.7 2.9. 1.7 1.8 3.3. 2.2 ;
Ft. ' Collins 2.0 3.3 1.3 1.9 3.1 1.1 1. 7, 2.1 1.4 11.6 2.1 1.8
- e i
- 'i
~
-i.
.- g a .% .+vi,.wi g e.8.. d v=iv e iW.4 -r "' F * '-
4t- '*'3' "
'T#F
h#"- *'".'Y'
T" D" '*'# N" 'N-
""Y** $W*F 4 'Y' 'Y " ' ' ' #
i- Table II.H.2 Summary Table of Geometric Means, Geometric Standard Deviations and 4
Arithmetic Means for Selected Sample Types.
_ 1986 _ _
1987 _ _
1988 _
1989 _
X o X X o X X o _X X o X 9 9 9 9 9 9 9 9' Surface Water (pCi/L). ,
~
H-3' !
Effluent 7800 4.3 15000 4200 3.5 7700 30000 1.6 31000 25000 1.7 29000 Downstream 180 3.3 72 170 2.3 21 370 2.3 430 260 2.6 <390 Upstream 230 1.4 <240 160 2.3 <230 300 2.7 430 300 2.5 <390 Cs-137
' Effluent 2.8 1.6 2.8 1.5 4.5 1.7 . 2.5 1.4 1.9 1.7 2.6 -1.3 i Downstream 1.8 2.5 1.7 2.2 2.7 0.01' ' 2.4 2.9 2.5 2.6' 2.4 1.8
- Upstream 1.9 3.1 1.5 2.3 3.0 0.32 1.7 2.6 1.4 2.4 2.0 2.0
~!
Milk (pC1/L)-
Ji-3 gAdjacent 190 1.8 <240 200 1.6 <230 230 2.1 70 300 12.3 <390
'Raferencs 140 3.6 <240 160 . 2.5 <230 180 2.8 <220 -250 3.1 <390 I-131 'I Adjacent 0.46 12 3.9 0.22 3.1 0.15' O.20 ' 2.8 0.046 0.24 3.9 0.57 Reference 0.68 5.9 3.8 0.14 5.2 0.02 0.17 2.1 :<0.17 0.18 3.0 <0.50 '
Cs-137 Adjacent 5.8 3.4 11 '3 .1 2.3 3.2 2 ." O 3.4 2.7 1.8 2.5 1.5 Reference 7.6 4.2 13 2.7 3.2 3.6 2.4 3.5 3.3 2.0 2.5 1.5
.________._______._______N. ' ' ' _ _ _ 'T*T'I " ""'
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i I
III. Radiological Environmental Monitoring Program ;
A. Sample Collection and Analysis Schedule ;
Table III.A.1 outlines the - sampling design, .the J collection frequency and the type of analysis for all environmental samples. It should be= repeated that' this i schedule was only adopted January 1,1984, and while different l
in - certain aspects from the previous schedule, has as its intent the same objective. That' objective is to document the radiation and radioactivity -levels in the critical pathways of f
dose to humans.- Such data is necessary to prove that reactor.. ,
radioactivity effluents produce. environmental concentrations. ;
-(
i that are within appropriate environmental.~ protection limits i and at the same time'are as low as reasonably achievable.
During 1989, there were the following changes in the sampling program: '
l
- 1. R-8 dairy (Johnston 5535 E. Highway 402, Loveland) ,
went out of business and the-new-R-8 location during 1989 was the Gorzeman dairy,.directly_ 4 l- south of the Johnston dairy'. The Gorzeman
- l. address was 2056 S. County. Road 7, Loveland,-
CO.
- 2. R-5 at Ehrlich feed lot was changed to=a personal-l- residence well in Milliken, Co. The new address is 108 S. Grace Street,_Milliken,-Co.-
l Table III.B.1 gives the description of each sampling l- location by number, sector and distance from the reactor.
l These descriptions were expanded somewhat in this report.
J15 4 n a v -
m - v ,
V
'h
.f
- )
Each of these. sampling locations (except ~ certain reference locations) can be' identified on scale mapse(Figures'~III.B.1
, and III.B.2)., Topographical maps showing greater detail, as well as photographs of principal sampling sites are on file in the CSU laboratory.
During July of 1989 the land-use census was conducted to' l
= determine the locations of the nearest residence, the' nearest milk animal, and. the nearest - garden producing broad leaf vegetation in each of the 16 meteorological sectors around the :
reactor. These locations by address are shown in Table i
III.C.1' Figure III.C.1 shows these locations in each sector.
At the time of the . 1989 census it was verified
- that the closest permanent residence in Sector 16 (17250 CR' 19 1/2 ) was the critical receptor with .regards to mean annual dose -
- commitment. However,.that residence was> abandoned early in U the fall. The closest resident now is at the Russell = farm'F- '!
16.
l A few residents in the sampling sectors up to a distance of 8 km from the plant have cows or goats that could be used for personal , milk consumption. 'However, from direct ;
discussion with these persons, this is not'a common practice and all 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 I-131 in' milk from A-22 would never be detected in the composited milk supply. 2 Table III. A.2 lists the LLD concentration values for each 4
i.
116
, _ . - , . - , _ , .. , . _ . . . .m
?
6 sample type and radionuclide= measured in this report. These.
LLD values - are the actual values- pertinent to the sample sizes,. counting yields, and counting times used .in the '
i- 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 USNRC reporting level' .for each ' I sample type and-radionuclide.
l l
l l
t I
i l'
117
- , . - - --. .. - .- - ..e
Table III.A.1 Operational Radiological Environmental Monitoring Program i
letsmisor or Seopiee Sempiing Iype end Irequency f sepo a u ro'l's t hvay Collection fregisency of Analysis oriU/or sospio end Locations A 1 f t ttuttfit Samplos from seven locations: Continuous sempler operation Iledlelodino Centstori .
Irltlin oxido '
with semple collection weekly. Analyze weekly for I-8 31 F aillo t nif f rio end or es required t>y duet toeding, lleeuld scintiteetinn retticulatos foser semplos from erf-site locations
. cotenting for tritina on
, (in silf ferent sectors) of tits folghost viilchever is more frequent.
vetel veper extracted calculated annical svarege ground Free silles gel-on earh level D/Q and altborne M/Q. sesople collected..
One semple from the vicinity or e '
community havlog the highest coleteleted ferticesloto Semplor:
ennual overego ground level D/Q. Gross beto radioactivity following filter change, two semples frote control location compoelte (by location) for gemme I 15 to 30 kilomotors (to to 20 miles) quarterly.gotopic distent and in the least prevalent wind direction, Quarterly exposure. Gemme dose quarterly.
as sit (cf itAnt Aliott forty stet tons witte two or more dosimotors or one Instrument for mossuring and recore*Ing dose rate continuously to Iso placed as follows:
- 1) en annor ring of stations in the genere t eres or tise site botendary and on nester ring in also se te 5 mile rerigo from the site witi; e stetton in each .
t sector of oech ring (16 sectore x 2 '
l risigs = 32 stations). the belonce of the stations, eight,:shall be piect'd in special interest eroes such an population centers, noorby residences,
~
schools, and in two or throo eroes c) to servo es control stations.
unli nn0FNs one semple upstroom, escl! stroom, one semples collected monthly. Comme isotopic enelysis surrece and tritterm monthly.
snappio downstream. .
Ono samplo in Immodleto eroe of Composite semple over one Comme isotopic enelysis Surrace week period. 1ho weekly and composite for t rit ium (Insm Pon1) dischargo. monthly.
composites wift be combined For the montlily semple, 4
a . .
If gross liota activity in air or water le grooter then ten tipos the yearly poen of control semple for esty medlues, gamme lautopic i
neelysis slinield Iso performed on (lio indivsdual semplos.
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Table III.A.2 Detection Capabilities for Environmental' Sample Analysis .
Lower Limit of Octcction (LLD)*
Analysis Water Airborne Particulate Fish Hlik Food Products- Sediment (pCi/L) or Gas (fC1/m 3 ) (pC1/kg, wet) (pCf/L) (pCl/kg, wet) (pCl/kg. dry)
Cross Beta 3.06 3. 7.5 11- 1 494 I-131 0.89 66.4 ._ 0.89. '56.8 ci-134 5.50 0.06 19.5 4.98 44.4 90.6 Cs-137 6.60 7.86 18.5 6.14' 44.6' 100 Zr-95 10.12 lib-95 4.12 Co-50 4.60 12.8
- lin-54 -4.68 12.7 7:i-65 10.94 23 6 fe-59 0.40 31.4 Co-60 4.40 14.5 na-140 6.66 -
- 8.00 _
La-140 7.66 . 9.16
.
- As suggested'in ilUREG-0472 All values.are at or below values ilsted in Table 8.2-2 of '
g technical specifications. - .
o . _ .
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- renew. w"" **
, y % q m- .-
e.M9-wy n>W. .-%e6. y$=was-a--a y.+ma--e*-.J,, , awc--g-.i.a3,_-3 y-g nw_ f.w_w-
Taole IIT.A.3 Rrporting Levels for Nonroutine Operating Reports MPORTING LF'/ELS FOR NONROUTINE OPERATING REPORTS
.. REPORTING IEVEL fRL)
Water Airborne Partinulate or ces Fish Hilk Brood t.eef vegetation Analysis (pCl/ f) (pCl/m 3) - + -(pCl/kg. wet) (pCl/f) (pCI,hg, wet) 4(s) it- 3 2 x to 3 4 the-Sta 1x 10 3 x 10 2 4 Fe-59 in x 10 1 x 10 i 3 4 Co-58 1 x 10- 3 x 10 2 .
k co-60 3x to . 1 x 10 2 ' %
Zn-65 3x to ' 2 x 10 2
r>b-95, Z r-9 5 4x 10 s-133 2 2 0.9 3. t x 10
~
3 3 C s- 13 ts 30 10 1 x 10 60 t x 10 3 3 cs-137 50 20 ' 2 x 10 70 2 x 10-
. c-. 2 2
.N On-It0,La-140 3 2x to -
3 x 10 for drinking water semples. This Is 40CFR Part'141 value.
4 e
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4 i Radiological Environmental Monitoring Program'(continued)-
Table III.B.1 '
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.
l ~
F-2 21st pole N of ditch on-dirt extension of CR 21 just 2 .1.1 before road drops down to' river bottom.
~
i F-3 17th pole N of ditch on dirt extension--of'CR 21 or 3 0.7 q
. first pole N of-E-W road.
, F-4 15th pole N of ditch on dirt extension of CR 21, S of 4. 0.7 pump road,. midway between F-3'and F-5. ,,
F-5 ~11th pole N of. ditch on' dirt extension of CR 21, near 5 0.6 _
E drive to pump house.
l" _
F-6 8th pole N of ditch on: dirt extension of CR 21, - 6- O.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 housecon N side of road 0.4 km E 8 1.3 of-CR'19).-. ..
i~
F-9 Pole E of first shed at intersection of CR 19): 9. 1.5 and CR 34. '
F-10 Pole on NW corner of intersection of dirt extension 10' l.5 j of CR 19 and 34. .
l
~ . -.
Table III.B.1 Radiological Environmental Monitoring Program (continued)
Sampling Site Descriptions (F: Facility Area 0-1.6 km. A: Adjacent Area 1.6-8 km. R: Reference Area)
Exposure Site No.. Location Description (see map) Sector Distance, Pathway km t
Direct Radiation F-11 7th pole N of intersection of~ dirt extension of CR 19 11 1.2 I with CR 34. .f
.: k 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. 1 4
F-13 Take first-dirt road.S of Visitor Center. Go W across 13 0.5 railroad tracks, follow dirt road to metal staircase going down off dike. 'TLD is taped to railing.
g F-14 2nd pole 0.1'km S-intersection CR 36)L& Rd 19. 14 1.5-w F-15 2nd. pole 0.7 km S of intersection of CR 38 on CR 19. 15 1.5 F-16 Pole at NE corner of potato cellar at 3 Bar Ranch 1 1.2 (Russell's). ,
F-17 Visitor Center, on N end of cross' beam over' entrance. 13. 0.2 F-18 Pole closest to house on'SW corner, 17250 CR 19). 16 0.8 i -
The address of 17250 is taped to.the Mountain Bell *
underground cable warning post.
l l-l l:
_. - _. - _ _ _ _ _. _ . , _ _. .. _u . . _ ,
._; . d _. ._. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
- i Table III.B.1 Radiological Environmental Monitoring Program (continued)
Samplir.g Site Descriptions (F: Facility Area 0-1.6 km. A: Adjacent Area 1.6-8 km. ' R: Reference Area) l Exposure Site No. 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' .l A-2 Pole on NE corner intersection of CR'42 and CR 256. 2- 6.8 A-3 Pole on NE corner of intersection of CR 42 and CO 60. '3 7.5
- .i A-4 1st pole NE of intersection of CR 29 and CR 38, take 4 7.4 ]
- CR 29 E out of Gilcrest to CR'38. -l
.i
, A-5 SE corner of.CR 34 and CR 29. Taped to road sign'on 5 7.2
- SW corner of intersection..
I l A-6 Pole on S side'of CR 32 near. drive to dairy-13278 CR 6 7.1 g 32.
A-7 Niles Miller dairy. 0.4 km E of US 85 on:12854 CR 30.
TLD is located on pole at NE corner of house. 7 7.3
, A-8 On CO 66 (CR30) farm on S side of road (address 9476) 8 4.7 I Pole in front'of house. '!
- A-9 Corner of CO 66 (CR' 30)' and CR 19,; Miller produce 9 4.6 stand. Second pole S on CR 19, . on E side of road.
A-10 Pole on SE corner at intersection CR 261 & CR 15. 10 7.8-
'A-11 At intersection of CO 66 and CR 13, 2nd pole N of lf 7.2 intersectica on E side-of CR13. .
P i ~,~.----vri -
,ww-,-.+ . . - - . - - - . - e.
3
~- e +uar."- -
y f - -* g. r ew -ee4-*P-- _ =-----+t--<-n- _c'__c* _ua-.___2 .x>w-e .+ m e-
l Table III.B.1 Radiological Environmental Monitoring Program (continued)
! Sampling Site Descriptions 1
(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 A-12 On CR 34, pole E of house N of Lake Thomas 2 km from 12 7.2 I-25.
13 A-13 Pole opposite lake, N of silage pits E side of CR 13 5.8 2.9 km N of CR 34.
A-14 Intersection of CR 13 and CR 40, NW corner. 14 6.9 4
A-15 Intersection of CR 42 and CR 15, NW corner. 15 6.7 A-16 Intersection of CR 44 and CR 19, SW corner. 16 6.8 -
A-17 Platteville school (S edge of town on Nain St.) 6 5.9 g pole on NW corner just outside school intramural
!- m field.
A-20 1st pole N of white picket fence and driveway 9 2.5 into turkey farm on S end of building that is parallel with CR 19.
.._ - _ - . . , . - - , ., _.. . . . , , _. _ . = _ , _ , . , . , , , _ - . _ _ _ . _ _ . . . . _ _ _ _ . . _ . , _ . _ _ .
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 R-1 Milliken School, on CR 21'. s TLD is located on pole 9.3 which is located at SE corner of Iola park, across the street from school.
R-2 Johnstown School (Letford Elementary), turn left 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 to'cchool'on W side of town. -~ ~-- ~ -
h R-3 CSU dairy farm on W Drake, N of Vet Hospital, Ft.
Collins, CO. Pole is E of hay barn next to 45.1 railroad tracks.
R-4 Air sampler corner US 287 and CO 66, Longzont 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
- - - - - w-m_.a-mm------ , - - - - - ----e---- - - - - - - - - - -
I-l l
l i
Table III.B.1 Radiological Environmental Monitoring Program sampling Site Descriptions ,
! (F: Facility Area 0-1.6 km. A: Adjacent Area 1.6-8 km. R: Reference Area)
Exposure Site No. Location Description (see map) Sector Distance, ;
Pathway . km l
Airborne F-7 Farm at intersection of CR 21 and CR 34. Air 7 1.5 sampler is located on west side of shop. Silica e
gel inside building on N end of workbench.
F-9 First shed along 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 '
4 gel in mailbox on tree to S of pump.
A-19 Hunting cabin between Goosequill ditch and Platte 1 1.7 i River.. Air sampler is on W side of. cabin, silica j gel is in bar on tree north of air sample.r. ;
R-3 Colorado State University Dairy, W. Drake Rd., Ft. 45.1 Collins, CO. W side of shed directly N of main
- dairy building. Silica gel inside mailbox. .
R-4 Intersection of US 66 and US 287, E side of dairy 20.5 i store, north edge of Iongmont. Silica gel is in mailbox attached to utility pole.
l R-11 Air sampler.is located in alley behind PSC office, 10.5 next to garage. Silica gel is located next to air * '
l sampler in mailbox and on top of post, 13 1/2 Parish
- St., Johnston, CO.
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) Stctor Distance, Pathway km Waterborne Surface F-19 S. Platte at dan located on dirt road E of pump 4 1.2 house #3 directly E of reactor.
F-20 St. Vrain creek on Rd. 19) 0.3 km from discharge 16 1.5 into St. Vrain creek. Directly N of reactor. ,
A-21 St. Vrain creek at bridge on 3d. 34, E of Rd. 19. 11 2.4-A-25 Goosequill Pond outlet. Continuous sampler located 1 2.2 4
in green box adjacent to the green shed on the N end of the pond.
c-. R-10 S. Platte river at bridge on CO 60 where highway 10.1 O has just turned and headed South. .
Ground F-16 Well behind residence at 3 Bar Ranch (Russell's), 1 1.2 17578 WCR 19 1/2.
R-5 Well at 108 S. Grace, Milliken.
- 9.5 :
4
- Drinking R-3 CSU dairy W Drake Rd., Ft. Collins, CO, N of 45.1 Vet Hospital. Water sample is taken from hydrant -
inside the entrance to the milking parlor.. ,
i R-6 Gilcrest U.S. Post Office located on Birch St. and
~
- 9.3 Rd. 40 off of Hwy 85.. Water taken from utility sink inside Post Office.
i
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) 6 Exposure Site No. Location Description (see map) Sector Distance, Pathway km ,
'i Ingestion '
Milk A-6 Hendrickson Dairy, 13278 Rd. 32 (Grand Ave.) 6 7.1 1.6 km E of US 85.
A-18 Boos Dairy, 11258 W Rd. 40, W of US 85 behind 2 4.7 modular home. ,
s A-22 Percy Odenbaugh Dairy, S on dirt rd from "LeRoy & 5 3.2 Paul Odenbaugh Dairy" sign. Dairy sign on WCR 36, E of Rd 23. Dairy sign is located next to mailbox of Mike Thomas.
A-23 Ieroy Odenbaugh Dairy,11733 Rd 36, W of Rd 25. 4 4.1 A-24 Marostica Dairy, 20718 Rd 17, 4 miles S of CO 60. 16 6.9 1 A-26 L & F Dairy (Fiechtner), E of Rd 13 on Rd 32. 11 7.8 6165 WCR 32.
R-8 Gorzman Dairy, 2056 S. CR 17, located off exit $255 22.5 W of I-25 dirctly N of Johnson's Corner restaurant.
Fish .
t F-19 S. Platte at dan 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
Table III.B.1 Radiological Environmental Nonitoring 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 Food Products A-27 Fields on SE corner of intersection 4 4.3 of WCR 25 and NCR 38.
A-28 Residence 11399 WCR 40). 2 5.3
'- R-6 Hernandez Produce Stand, Highway 85, Gilcrest. 9.6 ,
i e
1
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I
. - - . ._ _- . . _ - _ . . . . _ . . . . _ . ~ . . - . _ _ _ , _ . . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _
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i I I I Figere III.B.1 ;
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4 130
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131
v Table III.C.1 1989 Land Use Census
- Sector Nearest Nearest Nearest Milk Residence Garden Animal ,,
1 17578 CR 191/2 *** ***
i 2 18311 CR 23 18311 CR 23** 11283 CR-40**
3 11100 CR 38** 11100 CR 38** 11165 CR 38 4 11247 CR 36 11777 CR 36** ***
I i 5 16541 CR 23 16134 CR 23 16134 CR 23 i i
l _
6 11056 CR 23** 11056 CR 23 13278 OR 32 7 9999 CR 34 10999 CR 23** ***
8 15883 CR 21** 14605 CR 21** 15152 CR 13**
9 9379 CR 34** 9379 CR 34** 9033 CR 26 10 9061 CR 34 15449 CR 19** 7388 CO 66 -
11 8745 CR 34 6769 CR 32** 15266 CR 13 i
12 Aristocrat 6519 CR 34** 5492 CR 34 l
Ranch **
13 17375 CR 17** 17038 CR 17 *** '
14 8896 CR 19** 8896 CR 19** ***
15 9115 CR 38** 8903 CR 38 8903 CR 38 16 9239 CR 30** 21445 CR 19** 18986 CR 19** ;
- Census Date: July 21, 1989 "
- New Location
- No milk animals i
132
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i Figure III.C.1 Land Use Census, 1989 ls
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9 Nearest Residence '
E Nearest Garden A Nearest Milk Animal 133
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