ML20154C126
| ML20154C126 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 12/31/1987 |
| From: | Borst F, Jerrica Johnson, Miller D COLORADO STATE UNIV., FORT COLLINS, CO |
| To: | |
| Shared Package | |
| ML20154C130 | List: |
| References | |
| NUDOCS 8805180057 | |
| Download: ML20154C126 (137) | |
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REPORT l 1987 8905100057 880510 PDR ADOCK 05000267 O a COLORADO STATE UNIVERSITY FORT COLLINS, COLORADO 80523 L - - - - . - - - -
lO' RADIOLOGICAL ENVIRONMENTAL PONITORING PROGRAM Summary Report for the Period January 1, 1987 - December 31, 1987 s ( , Prepared by: [' i a s E. John' son, Professor Date j rado StateN niversity Reviewed by: '_ m,.b_\k.\hhllbs 4//P 9/ // Radiochemistry Mupervisor ' ' D a tef l Approved by: [ 2/ b g M + C 27 lupport Se ces Manager Dat6 4 lI I 1 O :
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Acknowledgements Many persons have contributed to this project during 1987, and it is important to acknowledge their effort. We also wish to thank the citizens from whose farms, homes, and ranches we collect the environmental samples. Without their cooperation the project would not be possible. The persons working directly on the project have been: Sheri Chambers Laboratory Technician Mark Chapin Graduate Research Assistant Sharon Clow Chemist and Laboratory Coordinator Roger Gerdes Undergraduate Student s Laura Gonsalves Research Associate (J Art Rood Graduate Research Assistant Charles Sampier Chief Electronic Technician Janice Sipos Laboratory Assistant David Thorne , Graduate Research Assistant 0 Sh
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n Pro or and Project Director
@JamesE.Joh i
,,. . TABLE OF CONTENTS L,I Page No.
Acknowledgments i List of Tables 111 List of Figures v I. INTRODUCTION 1 II. SURVEILLANCE DATA FOR 1987 AND INTERPRETATION OF RESULTS A. External Gamma Exposure Rates 6 B. Air Sampling Data 9 C. Water Sampling Data 34 D. Milk Data 69 E. Food Products 78 F. Aquatic Pathways 80
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. G. Sample Cross-check Data 83 H. Summary and Conclusions 93 III. ENVIRONMENTAL PADIATION SURVEILLANCE PROGRAM AND SCHEDULE A. Collection and Analysis Schedule 111 B. Sampling Locations 117 C. Land-use Census 128 1
I J V l ii
7 LIST OF TABLES Page No. II.A.1 Gamma Exposure Rates. 8 II.B.1 Concentrations of Long-lived Gross Beta Activity in Airborne Particles.
- a. First Quarter, 11
- b. Second Quarter, 12
- c. Third Quarter, 13
- d. Fourth Quarter, 14 II.B.2 Tritium Concentrations in Atmospheric Water Vapor, pC1/L.
- a. First Quarter, 18
- b. Second Quarter, 19
- c. Third Quarter, 20
- d. Fourth Quarter, 21 II.B.3 Tritium Concentrations in Air, pC1/m 3, f%
k a. First Quarter, 22
- b. Second Quarter, 23
- c. Third Quarter, 24
- d. Fourth Quarter, 25 II . B.4 Tritium Released in Reactor Effluents. 26 II . B.5 I-131 Concentrations in Air.
- a. First Quarter, 29
- b. Second Quarter, 30
- c. Third Quarter, 31
- d. Fourth Quarter. 32 II . B.6 Radiocesium Concentrations in Ambient Air. 33 II.C.1 Gross Beta Concentrations in Bi-weekly Composites of Drinking Water. 36 II.C.2 Tritium Concentrations in Bi-weekly Composites of Drinking Water. 38 II.C.3 Radionuclide Concentrations in Bi-weekly Composites of Drinking Water. 41 iii
Io ') LIST OF TABLES (Continued) Page flo. II.C.4 Tritium Concentrations in Surface Water. 52 II.C.5 Radionuclide Concentrations in Surface Water. 53 II.C.6 Radionuclide Concentrations in Effluent Water. 65 II.C.7 Radionuclide Concentrations in Ground Water. 67 II.C.8 Maximum Permissible Concentrations in Water. 68 II.D.I. Radionuclide Concentrations in Milk. 71 II . E.1 Radionuclide Concentrations in Food Products. 79 II.F.1 Radionuclide Concentrations in Fish. 81 II.F.2 Radionuclide Concentrations in Sediment. 82 II.G.1 EPA Cross-check Data. 86 t' II.G.2 Tritium Concentrations in Cross-check Data,
\-}- CSU-Colorado Dept. of Health-PSC. 88 II.G.3 Gross Beta Concentrations in Water Cross-check Data, CSU-Colorado Dept. of Health-PSC. 90 II.G.4 Intralaboratory Cross-check Results. 92 II.H.1 Data Summary. 100 II.H.2 Geometric Means of Selected Sample Types 1984-1987. 108 III.A.1 Radiological Environmental Monitoring Program. 113 III.A.2 Detection Capabilities for Environmental Sample j Analysis, LLD. 115 l
, III.A.3 Reporting Levels. 116 l i III.B.1 Sampling Locations for Environmental Samples 117 III.C.1 Land-use Census,1987, 128 l l 1 i O iv
i _ LIST OF FIGURES V i Page No. Figure II.B.1 Gross Beta Concentrations in Air 15 Figure II.C.1 Tritium Concentrations in Water 1974-1987 40 Figure II.D.1 I-131 Concentrations in Milk at Site A-22 77 Figure III. B.1 Close-in Samplind LScations 126 Figure III.B.2 Adjacent and Reference Sampling Locations 127 Figure III.C.1 Land Use Census, 1987 129 I t i 4 I < i b i 1 V i , 8
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- f. Introduction to Radiological Environmental Monitoring Data for n
(J the Period January 1, 1987 - December 31, 1987 During 1987 the Fort St. Vrain Nuclear Generating Station produced electrical energy as follows: Dates with Thermal Gross Thermal Energy Month Energy Generation Production (MWH) Jan.-March 0 0 April 17-30 15018.3 May 1-31 164842.3 June 1-12 68393.1 15-30 80085.6 July 1-29 248206.8 August 0 0 September 12 0.4 17 43.0 30 42.7 October 1-3 3860.9 November 0 0 December 11-25 63648.8 27-31 23793.9 Total for 1987 667934.8 O A complete and detailed listing of radioactivity released by all effluent routes may be found in th3 Public Service Company of Colorado Semi-annual Effluent Release Reports for 1987 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 1987 on project samples. These values are given for typical sample sizes, counting times and decay times. The LLO is, therefore, an a priori parameter to indicate the capability of the detoction system used. The LLO values in Table III. A.2 were calculated O as suggested in NUREG-0472. l l
2 Throughout the report, however, when a sample result is listed as less than a specified value, that value is the calculated MDC (minimum detectable concentration). This approach is analogous to that of Currie (NUREG/CR-4007): the MDC is the same as c S , the critical signal, and the LLD is equal to SD , 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 = 2.33 eB /E Y V E -At Where: o g = Standard deviation of background count rate E = Counting efficiency, c s-1 pCi-I Y = Chemical yield V = Sample mass or volume
,e3 A = 0.693/ Half-life V
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 i values less than HDC. 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 will be different for each sample type and even within sample type. Essentially all radioactivity values measured on this project are l l near background levels and, more importantly, near the MDC values for each radionuclide and sample type. It has been well-documented that environmental radioactivity values exhibit great inherent variability. This is partly due to sampling and analytical variability, but most Q l l l l L.
3 importantly due to true environmental or biological variability. As a
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s 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 the 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 than 10, log-normal I treatment is tentative. The geometric means and geometric standard deviations are calculated for each sample set. If any 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 1987 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. This is the suggested practice by Gilbert (Health Physics 40:377,1984) and the NRC (NUREG/CR-4007). Many sets of data were compared in this report. The statistical test used was either a "t"-test or a paired "t"-test. If data sets are noted to be significantly different or not significantly different, the confidence for the statement is at the 95% level (a = 0.05). In this report we have footnoted appropriate tables with the maximum permissible concentration applicable to each radionuclide. We
4 have chosen to list the maximum permissible concentrations as found in im U Appendix 8 Table II of 10CFR20. This is the concentration in water or air of each radionuclide which if ingested or inhaled continuously would singularly produce the maximum permissible radiation dose rate to a specified individual member of the general public. That value is 500 mrem / year, but must include the dose from all possible sources, and, therefore, cannot be solely due to reactor effluent. As stated in 10CFR20 these are the maximum concentrations above natural background that a licensee may release to an unrestricted area. It is assumed that no direct ingestion or inhalation of effluents can occur at the restricted area boundary and that dilution and dispersion decreases the concentration before it reaches nearby residents. This is certainly the case for the Fort St. Vrain environs. There is no specified maximum permissible dose rate or dose commitment for residents near the Fort St. Vrain reactor from the reactor effluents. Such limits for water cooled reactors are found in 10CFR50 Appendix I. These are judged as "As Low as Reasonably Achievable" dose rates from such reactor types and, although not directly applicable to the Fort St. Vrain gas cooled reactor, can be used for comparison purposes. A limit that does apply is the independent maximum permissible dose commitment rate set by the E.P.A. (40CFR190) for any specified member of the general public from any part of the nuclear fuel cycle. This value is 25 mrem / year, the dose rate to the whole body from all contributing radionuclides excluding background and medical radiation dose rate. O
{ 5 Dose commitments are calculated for hypothetical individuals for any mean concentrations noted in unrestricted areas that are significantly above control mean values. The following is the footnote system used in this report. ,
- a. Sample lost prior to analysis,
- b. Sample missing at site,
- c. Instrument malfunction.
- d. Sample lost during analysis. ,
- e. Insufficient weight or volume for analysis,
- f. Sample unavailable,
- g. Analysis in progress.
- h. Sample not collected (actual reason given),
- i. Analytical error (actual reason given). ,
N.A. Not applicable. O a l O
6 II. Surveillance Data for January Through December 1987 and Interpretation of Results i A. External Gama-ray Exposure Rates P The average measured gamma-ray exposure rates expressed in mR/ day are given in Table II.A.1. The values were determined by CaF2:Dy (TLD-200) dosimeters at each of 41 locations (see Table III.B.1). Two TLD chips per package are 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-exposure annealing to obtain the average daily exposure rate. The TLD devices are changed quarterly at each location. Fading during field exposure is minimized by the post-annealing readout procedure. The TLD data indicate that the arithmetic mean measured expos rate in the facility area for all of 1987 sas 0.44 mR/ day. The mean exposure rate was 0.44 mR/ day for the adjacent area and 0.43 mR/ day for the reference area. These mean values were not significantly different from each other. The exposure rate measured at all sites is due to a combination of exposure from cosmic rays, from natural gamma-ray emitters in the earth's crust and from ground surface deposition of fission products due to previous world-wide fa;'out. 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 i:.. to measure gama-rays generated from the reactor facility itself, but to document the presence or absence of gamma-ray emitters deposited upon the ground from the reactor effluents. Since the inception of O
7 power production by the reactor, there has been no detectable increase in the external exposure rate due to reactor releases. The TLD system was calibrated by exposing chips to a scattered gama-ray flux produced in a cavity surrounded by uranium mill tailings. This produces a gamma-ray spectrum nearly identical to that from natural background measured in the reactor environs. The quality control program includes calibration before readout of each quarterly batch of TLD devices. O l
8 Table II. A.1 Gamma-Ray Exposure Rates. (mR/ day) 1987. F3cility Area 1st Quarter 2nd Quarter j 3rd Quarter 4th Quarter (]) F-1 0.47 0.41 0.42 0.42 F-2 0.43 0.39 0.45 0.45 F-3 0.46 0.45 0.41 0.00 F-4 0.44 0.36 0.43 0.40 F-5 0.45 0.39 0.42 0.52 F-6 0.45 0.37 0.36 0.45 F-7 0.48 0.48 0.44 0.43 F-8 0.47 0.46 0.47 0.44 F-9 0.45 0.40 0.43 0.44 F-10 0.41 0.39 0.44 0.45 F-11 0.52 0.46 0.48 0.49 F-12 0.47 0.43 0.52 0.45 F-13 0.42 0.41 0.36 0.52 F-14 0.42 0.37 0.43 0.42 F-15 0.43 0.38 0.41 0.43 F-16 0.47 0.38 0.43 0.43 F-17 0.45 0.41 0.46 0.50 F-18 0.47 0.39 0.48 0.49 i (1.96c)- 0.45 (0.03) 0.41(0.04) 0.44(0.04) 0.46(0.04) Adjacent Area A-1 0.49 0.39 0.48 0.46 A-2 0.50 0.41 0.49 0.47 A-3 0.46 0.41 0.46 0.45 A-4 0.43 0.37 0.44 0.44 A-5 0.40 0.39 0.40 0.43 A-6 0.43 0.37 0.44 0.39 A-7 0.44 0.41 0.46 0.37 A-8 0.52 0.40 0.53 0.46 A-9 0.50 0.37 0.46 0.50 A-10 0.51 0.48 0.56 0.54 A-11 0.46 0.35 0.48 0.48 A-12 0.43 0.37 0.45 0.42 A-13 0.40 0.37 0.40 0.34 A-14 0.42 0.40 0.32 0.40 A-15 0.45 0.40 0.44 0.42 A-16 0.44 0.44 0.44 0.41 A-17 0.53 0.41 0.48 0.46 A-20 0.49 0.40 0.55 0.49 li(1.96c) 0.46 (0.04) 0.40(0.03) 0.46(0.06) 0.44(0.05) Reference Area R-1 0.44 0.40 0.43 0.39 R-2 0.46 0.37 0.48 0.44 R-3 0.41 0.37 0.40 0.47 O- R-4 0.47 0.44 0.46 0.49 R-7 0.40 0.34 0.44 0.41 i (1.96c) 0.44 (0.03) 0.38(0.04) 0.44(0.03) 0.44(0.04)
9 II.B. Ambient Air Ctacentrations O V 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 1987. A-19, while technically in the adjacent zone, is only a few meters from the facility boundary and logically should be considered a facility site. It has been termed a facility site since the inception of the monitoring program. The reference sites R-3, R-4, and R-11 are all new locations as of January 1,1984 and sufficiently distant to be considered reference (control) locations. (See Table III.B.1). The reported concentrations are listed in units of femtocuries per cubic meter of ambient air, although the measured activity is due to a mixture of radionuclides. It should also be noted that the current Q technical specifications no longer require measurement of gross alpha activity. All filt?rs, however, are saved indefinitely for later alpha particle analysis if needed. No statistically significant difference was found in the arithmetic mean values between the facility and reference sites during any quarter of 1987 There was also no difference between quarters as was observed during 1986 due to the Chernobyl f allout. l The gross beta data for 1987 have been added to the plot of air concentrations observed since 1973 (Figure II.B.2). In this figure the i half-yearly mean values for the facility sites are plotted with the values from the reference sites. The contribution from Chernobyl is clearly evident in 1986. It can be observed that overall mean values - are not significantly different and that world-wide fallout principally lQ l l i I t
10 due to Chinese atmospheric nuclear weapon tests is the predominant contributor to the measured values. There has never been a significant difference observed between facility and reference sites. Thus, it can be again concluded that reactor air effluents of particulate fission products or activation products are not a source of dose commitment for the Fort St. Vrain environs population. 4 O 1 l l l 9 O
O O O Table II.B.1 Concentrations of Long-lived Gross Beta Particulate Activity in Air. (fCi/m3 ) a.) Collection Period: First Quarter, 1987. Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 Jan 3 26 (1.6)* 29 (2.4) 32 (2.1) 26 (2.0) 31 (2.1) 11 (1.1) 24 (1.8) Jan 10 32 (1.6) 33 (2.1) 30 (2.1) 30 (1.9) 26 (1.9) 29 (1.7) 28 (2.1) Jan 16 27 (1.8) 27 (2.4) 21 (2.0) 25 (2.4) 24 (2.0) 28 (1.9) 34 (2.4) Jan 24 39 (2.4) 13 (1.0) 31 (2.3) c1 17 (1.6) 18 (1.4) 6.9 (1.3) Jan 31 28 (2.1) 9.8 (1.2) 6.3 (1.3) 35 (4.0) 32 (2.8) 19 (1.5) 18 (1.7) Feb 7 27 (1.4) 27 (2.0) 26 (1.8) 24 (1.9) 27 (2.1) 24 (1.6) 27 (2.3) Feb 14 35 (1.8) 35 (2.7) 31 (1.9) 35 (2.8) 38 (2.4) 29 (1.7) 36 (2.8) Feb 20 18 (1.1) 23 (2.2) 14 (1.5) 16 (2.2) 15 (1.5) 17 (1.2) 16 (2.1) Feb 28 24 (1.2) 32 (2.3) 31 (1.7) c2 34 (1.9) 36 (1.6) 20 (1.8) :: Mar 6 41 (1.8) 37 (2.4) 33 (2.2) c2 36 (2.6) 38 (2.1) 41 (2.6) Mar 14 22 (1.3) 21 (1.8) 21 (1.9) 8.6 (1.1) 27 (1.8) c3 33 (1.9) Mar 21 14 (0.90) 16 (1.6) 15 (1.4) 13 (0.91) 15 (1.3) 18 (1.4) 19 (1.5) Mar 28 13 (1.0) 15 (1.9) 16 (1.4) 10 (1.1) 20 (1.4) 19 (1.1) 22 (1.6) 3I: 27 24 24 22 26 24 25 n: 13 13 13 10 13 12 13 1.96o: 17 17 17 19 15 16 20 MAX: 41 X: 24 MAX: 47. . X: 25 MIN: 6.3 n: 49 MIN: 6.9 n: 38 1.960 : 17 1.96 c: 17 l
- 1.96o (due to counting statistics.)
c1 Insufficient deposit on filter. c2 Pump inoperative. No replacement pump available. I c3 Pump inoperative for major fraction of sampling period.
O O O Table II.B.1 Concentrations of Long-lived Gross Beta Particulate Activity in Air. (fCi/m ) b.) Collection Perioo: Second Quarter, 1987. Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 Apr 4 16 (1.1)* 19 (1.8) 16 (1.3) 18 (1.1) 19 (1.3) 18 (1.5) 21 (1.5) Apr 11 20 (1.3) 4.0 (1.5) 20 (1.6) 19 (1.6) 19 (1.5) 15 (1.0) 17 (1.2) Apr 18 19 (1.2) 21 (1.5) c1 21 (1.4) 19 (1.7) 18 (1.2) 21 (1.6) Apr 24 17 (1.4) 20 (1.5) 22 (3.6) 26 (1.9) 22 (1.5) 14 (1.2) 38 (7.6) May 1 39 (2.0) 27 (1.5) 30 (1.6) 35 (1.9) 29 (2.0) 39 (1.9) 32 (1.8) May 9 38 (1.7) 29 (1.6) 38 (2.0) 44 (2.3) 28 (1.6) 22 (1.1) 18 (1.1) May 16 14 (1.1) 19 (1.3) 15 (1.3) 19 (1.3) 20 (1.5) 20 (1.2) 34 (1.8) May 23 14 (1.2) 15 (1.3) 11 (1.3) 13 (1.5) 13 (1.2) 13 (1.1) 10 (0.87) .-. May 29 18 (1.2) 17 (1.2) 17 (1.4) 21 (1.7) 17 (1.4) 28 (2.0) 21 (1.5) Jun 6 22 (1.4) 21 (1.5) 20 (1.6) 19 (1.4) 21 (1.4) 10 (0.87) 21 (1.2) Jun 12 20 (1.3) 22 (1.5) 21 (1.5) 19 (1.4) 20 (1.6) 19 (1.2) 27 (3.3) Jun 19 26 (1.7) 26 (1.7) 24 (1.8) 24 (2.0) 24 (1.7) 15 (1.2) 9.1 (1.2) Jun 26 28 (1.3) 30 (1.7) 33 (1.8) 29 (1.5) 26 (1.9) 25 (1.2) 25 (1.3) X: 22 21 22 24 21 20 23 n: 13 13 12 13 13 13 13 1.960: 16 13 15 16 8.8 15 17 MAX: 44 X: 22 MAX: 39 X: 21 MIN: 4.0 n: 51 MIN: 9.1 n: 39 1.96c: 15 1.96a: 14
- 1.96 o(Due to counting statistics.)
c1 Insufficient deposit on filter. E-- ,
f) v /~) ( (') v Table II.B.1 Concentrations of Long-lived Gross Beta Particulate Activity in Air. (fCi/m ) c.) Collection period: Third Quarter, 1987. Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 Jul 3 24 (1.7)* 22 (1.8) 24 (2.0) 25 (2.0) 27 (2.0) 29 (1.5) 22 (1.5) Jul 11 31 (1.5) 29 (1.5) 31 (1.6) 29 (1.5) 27 (1.7) 26 (1.3) 27 (1.4) Jul 17 24 (1.7) 26 (1.7) 22 (1.8) 23 (1.6) 23 (1.8) 40 (2.0) 21 (1.2) Jul 25 26 (2.7) 18 (1.4) 21 (1.3) 20 (1.2) 16 (1.8) 17 (1.1) 9.7 (1.2) Aug 1 21 (2.0) 22 (1.9) 13 (1.4) 25 (2.5) 20 (1.7) 18 (1.0) 59 (5.6) Aug 8 33 (2.1) 30 (2.2) 27 (1.4) 28 (1.6) 20 (2.0) 24 (1.2) 11 (0.88) Aug 15 20 (2.0) 26 (2.0) 24 (1.7) 23 (1.8) 22 (1.8) 23 (1.2) 21 (1.2) Aug 22 33 (2.3) 23 (1.6) 23 (1.3) 11 (1.0) 24 (2.2) 23 (1.4) 22 (1.4) -. Aug 29 18 (1.9) 17 (1.9) 17 (1.5) 15 (2.0) 23 (1.9) 19 (1.1) 19 (1.1) '" Sept 5 32 (2.1) 32 (2.2) 29 (1.5) 33 (2.4) 28 (2.3) 23 (1.2) 20 (1.7) Sept 12 28 (2.1) 27 (2.1) 25 (1.8) 30 (2.4) 31 (2.3) 13 (1.0) 23 (1.8) Sept 19 22 (1.9) 25 (2.1) 24 (1.5) 24 (1.9) 28 (2.5) 35 (2.1) 24 (1.5) Sept 26 44 (2.5) 43 (2.7) 39 (2.2) 49 (3.0) 41 (2.8) 38 (1.6) 35 (2.6) X: 27 26 25 26 25 25 24 n: 13 13 13 13 13 13 13 1.960: 14 13 13 18 12 16 24 MAX: 49 X: 26 FmX: 59 X: 25 MIN: 11 n: 52 MIN: 9.7 n: 39 1.96o: 14 1.960: 18
- 1.960(Due to counting statistics.)
9
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O O Table II.B.1 Concentrations of Long-lived Gross Beta Particulate Activity in Air. (fCi/m') d.) Collection period: Fourth Quarter 1987. Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 Oct 3 36 (2.2', * < 2.4 33 (1.6) 36 (2.3) 35 (2.8) 30 (1.5) 32 (1.8) Oct 10 34 (2.2) 30 (1.5) 33 (1.9) 34 (2.40 37 (2.5) 26 (1.30) 25 (1.3) Oct 17 33 (2.0) 36 (1.8) 34 (1.7) 37 (2.4) 30 (2.6) 33 (1.6) c2 Oct 24 34 (2.1) 30 (1.5) 43 (2.2) 34 (2.5) 28 (2.7) 31 (1.4) 27 (1.2) Cct 31 35 (2.0) 32 (1.6) 33 (1.6) 56 (5.1) c1 50 (1.5) 35 (1.7) Nov 7 28 (1.8) 35 (4.5) 27 (1.8) 24 (1.4) 24 (2.9) 27 (1.4) 27 (1.6) Nov 14 52 (2.2) c4 51 (2.1) 62 (0.68) 39 (3.5) 39 (1.7) 40 (1.8) Nov 21 38 (2.0) 33 (1.4) c3 31 (1.6) 32 (2.2) 25 (1.3) 28 (1.2) Nov 28 51 (2.1) 27 (1.4) 49 (2.1) 45 (1.7) 45 (1.2) 39 (1.7) 39 (1.7) Dec 5 42 (2.2) 37 (1.6) 38 (2.1) 24 (1.6) 37 (2.5) 27 (1.4) 35 (1.4) 3; Dec 12 19 (1.3) 20 (1.4) 18 (1.3) 19 (1.10 14 (1.6) 17 (1.2) 17 (1.2) Dec 19 27 (1.7) 26 (1.5) 37 (2.1) 30 (1.7) c2 25 (1.4) 20 (1.1) Dec 28 23 (1 3) 20 (1.2) 21 (1.3) 25 (1.2) 23 (1.8) 22 (1.2) 18 (1.1) X: 35 26 35 35 31 29 29 1.96 c: 19 27 20 25 17 12 15 MAX: 62 X: 33 MAX: 85 X: 29 MIN: < 2.4 n: 50 MIN: 14 n: 36 1.96a: 23 1.96 r. 14
- 1.96 c (Due to counting statistics.)
c1 Cartridge broken, air filter and charcoal are not representative of the air flow. 3 c2 Volume was less than 300 m . c3 Pump malfunction.
I ! 15 l r Figure II.B.1 { 10* 900 Gross Beta Concentrations in Air , 800 - 700 - e o Facility Sampliag Stations 600 - X=59 e = 59 500 - Reference Sampling Stations 400 - X = 60 e = 59 300 - l ? l
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O ,e , , , , , , , , , >. , , , , , 1973 '74 '75 '76 '77 '78 '79 '80 '81 '82 '83 '84 '85 '86 '87 '88 Time (year)
I 16
- 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 1987 is listed in Tables II.B.2a-2d. The corresponding tritium concentration in air (pCi/m3) is calculated from the specific activity data using weekly mean temperatures and dew points measured at the FSV meteorological tower. The measuring point is at a height of 2 m from the surface. The tritium air concentrations are shown in Table II.B.3a-3d.
The principle release mode of tritium from the reactor is batch t' liquid releases from holding tanks. The tank water is first analyzed and then released with sufficient additional dilution, if necessary, in order not to exceed 10CFR20 concentration limits. The summary of tritium release by all modes is shown in Table II.B.4. The summary indicates that tritium released in 1987 was less than in 1986 for all routes. (See 1986 anr.ual report to the USNRC). Sampling locations F-16 and A-19 are located near the Goosequill Ditch, which is the principal route for effluent tritium release. l Tables II.B.2a-2d indicate a strong correlation of elevated atmospheric l l tritium concentrations corresponding to the batch release of tritium in j water along the ditch. Due to evaporation while in transit, elevated ! tritium concentrations in air have been observed for these two locations often in past years. The concentrations observed, however, have always been below the limit of regulatory concern. The occasional elevated O .
.,, - ~ - - - . - - , ,__r , - .. _ _ , . . .
17 values at the reference sites are assumed to be statistically false positive values. The mean value for sites F-16 and A-19 were significantly greater than for all other sites during the year. When all four facility sites are averaged, however, the total mean value is less than the HDC value of 250 pCi/L. Radiation dose commitment estimates sre not warranted on the basis of elevated air concentration values alone. Inhalation is not a significant pathway for dose to humans. The milk and food product pathway is the only significant source of radiation dose to humans from environmental tritium. Since the same relative humidity is assumed for all sites, Table II.B.3 shows the same site dependence on reactor effluent as Table 11.8.2. O O
O O Q Table II.B.2 Tritium Concentrations in Atmospheric Water Vapor. (pCi/L) a.) Collection Period: First Quarter,1987. Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 Jan 3 < 230 < 230 < 230 < 230 < 230 < 230 < 230 Jan 10 < 240 < 240 < 240 < 240 < 240 < 240 < 240 Jan 17 < 240 < 240 < 240 < 240 290 (280)* < 240 290 (280) Jan 24 < 230 < 230 < 230 < 230 < 230 < 230 < 230 Jan 31 < 230 < 230 < 230 < 230 < 230 < 230 < 230 5; Feb 7 < 230 < 230 < 230 < 230 < 230 < 230 < 230 Feb 14 < 230 < 230 < 230 < 230 < 230 < 230 < 230 ' Feb 21 < 240 < 240 < 240 < 240 < 240 < 240 < 240 Feb 28 370 (290) 300 (280) < 240 < 240 < 240 < 240 < 240 Mar 6 < 240 < 240 < 240 < 240 < 240 < 240 < 240 Mar 14 < 240 < 240 < 240 < 240 < 240 < 240 < 240 Mar 21 < 230 < 230 < 230 < 230 < 230 < 230 < 230 Mar 28 e < 230 < 230 < 230 < 230 e < 230
- 1.96 o (Due to counting statistics.)
e Insufficient sample volume for analysis. l
q Q O
.) LJ LJ Table II.B.2 Tritium Concentrations in Atmospheric Water Vapor. (pCi/L) b.) Collection Period: Second Quarter, 1987.
Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 Apr 4 < 240 < 240 < 240 < 240 < 240 < 240 370 (280)* Apr 11 < 230 < 230 < 230 < 230 < 230 < 230 < 230 Apr 18 < 230 < 230 < 230 < 230 < 230 < 230 < 230 Apr 25 < 240 < 240 < 240 < 240 < 240 < 240 < 240 May 1 < 230 < 230 < 230 < 230 < 230 < 230 < 230 U5 i May 9 < 230 < 230 < 230 < 230 < 230 < 230 < 230 May 16 < 230 < 230 250 (270) < 230 < 230 < 230 230 (270) May 23 < 230 < 230 870 (280) < 230 < 230 < 230 < 230 May 29 < 230 < 230 710 (280) 510 (280) < 230 < 230 < 230 Jun 6 < 230 < 230 580 (290) 620 (290) < 230 < 230 < 230 Jun 12 < 230 < 230 < 230 < 230 < 230 < 230 < 230 Jun 19 < 230 < 230 e e < 230 < 230 < 230 Jun 26 < 230 < 230 < 230 1000 (290) < 230 < 230 < 230
- 1.96 c(Due to counting statistics.)
e Insufficient sample volume for analysis.
O O O Table II.B.2 Tritium Concentrations in Atmospheric Water Vapor. (pCi/L) c.) Collection Period: Third Quarter, 1987. Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 Jul 3 < 230 < 230 310 (280)* 360 (280) < 230 < 230 < 230 Jul 10 < 230 < 230 460 (280) 620 (280) < 230 < 230 230 (280) Jul 17 < 230 < 230 250 (280) < 230 < 230 < 230 < 230 Jul 25 < 230 < 230 440 (280) < 230 < 230 < 230 < 230 Aug 1 < 230 < 230 480 (280) 270 (280) < 230 < 230 < 230 E$ Aug 8 < 230 < 230 < 230 290 (280) < 230 < 230 < 230 < Aug 15 < 230 < 230 < 230 < 230 < 230 < 230 e I l .Aug 22 < 230 < 230 < 230 280 (270) < 230 360 (270) < 230 I , Aug 29 < 230 < 230 < 230 400 (270) < 230 < 230 < 230 Sept 5 < 230 < 230 < 230 < 230 < 230 < 230. < 230 Sept 12 < 230 < 230 < 230 < 230 < 230 < 230 < 230 l Sept 19 < 230 < 230 < 230 < 230 580 (260) < 230 < 230 l Sept 26 < 230 < 230 < 230 < 230 < 230 < 230 < 230 i j
- 1.96o (Due to counting statistics.)
j e Insufficient sample volume for analysis.
,m ._, . . _ _ ,,_ _ , , , , . . _ . _ . . . . - _ _ - - . . . , . . . _ . . - - , .
, . - - - . - - , , ,- . , . . , ,. ,.m . - ., . , u_m ,.-_m .
O O O Table II.B.2 Tritium Concentrations in Atmospheric Water Vapor. (pCf/L) c.) Collection Period: Fourth Quarter, 1987. Collection Facility Sites Date F-7 F-9 Reference Sites F-16 A-19 R-3 R-4 R-11 Oct 3 < 240 < 240 < 240 < 240 < 240 < 240 < 240 Oct 10 < 230 < 230 < 230 < 230 < 230 < 230 < 230 Oct 17 < 230 < 230 < 230 540 (280T < 230 < 230 340 (270) Oct 24 < 230 < 230 < 230 < 230 < 230 < 230 350 (280) Oct 31 < 230 < 230 250 (280) 300 (280) < 230 < 230 < 230 Nov 7 < 230 < 230 410 (280) 340 (280) < 230 < 230 440 (280) Nov 14 < 230 < 230 < 230 < 230 e < 230 < 230 Nov 21 < 230 < 230 < 230 ,
< 230 < 230 < 230 < 230 t
Nov 28 < 250 < 230 < 230 ' < 230 < 230 < 230 < 230 i Dec 5 < 250 < 250 < 230 < 230 < 250 < 250 < 230 Dec 12 < 230 < 230 < 230 < 230 310 (280) < 230 < 230 Dec 19 < 290 < 290 400 (280) 530 (290) < 290 < 290 < 290 Dec 28 e < 290 < 290 < 290 e < 290 < 290
- 1.96 c(Due to counting statistics.)
e Insufficient volume for analysis.
O O O Table II.B.3 Tritium Concentrations in Atmospheric Water Vapor. (pCi/m3 ) a.) Collection Period: First Quarter,1987. Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 Jan 3 < 0.64 < 0.64 < 0.64 < 0.64 < 0.64 < 0.64 < 0.64 Jan 10 < 0.75 < 0.75 < 0.75 < 0.75 < 0.75 < 0.75 < 0.75 Jan 17 < 0.61 < 0.61 < 0.61 < 0.61 0.74 (0.71)* < 0.61 0.74 (0.71) Jar,24 < 0.48 < 0.48 < 0.48 < 0.48 < 0.48 < 0.48 < 0.48 Jan 31 < 0.76 < 0.76 < 0.76 < 0.76 < 0.76 < 0.76 < 0.76 % Feb 7 < 0.80 < 0.80 < 0.80 < 0.80 < 0.80 < 0.80 < 0.80 Feb 14 < 0.74 < 0.74 < 0.74 < 0.74 < 0.74 < 0.74 < 0.74 Feb 21 < 0.77 < 0.77 < 0.77 < 0.77 < 0.77 < 0.77 < 0.77 Feb 28 1.1 (0.83) 0.89 (0.83) < 0.71 < 0.71 < 0.71 < 0.71 < 0.71 Mar 7 < 0.99 < 0.99 < 0.99 < 0.99 < 0.99 < 0.99 < 0.99 Mar 14 < 0.89 < 0.89 < 0.89 < 0.89 < 0.89 < 0.89 < 0.89 Mar 21 < 0.96 < 0.96 < 0.% < 0.96 < 0.96 < 0.% < 0.% ; I Mar 28 e < 0.67 .< 0.67 < 0.67 < 0.67 e < 0.67
- 1.96 o (Due to counting statistics.). '
e Insufficient sample volume. 3 0 H MPC = 2x10 pCi/m3 (10CFR20 Appendix B, Column II). air
O O O Table II.B.3 Tritiur Concentrations in Atmospheric Water Vapor. (pCi/m3) a.) Collection Period: Second Quarter,1987. Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 Apr 4 < 0.75 < 0.75 < 0.75 < 0.75 < 0.75 < 0.75 1.2 (0.87)* Apr 11 < 0.78 < 0.78 < 0.78 < 0.78 < 0.78 < 0.78 < 0.78 Apr 18 < 0.99 < 0.99 < 0.99 < 0.99 < 0.99 < 0.99 < 0.99 Apr 25 < 1.1 < 1.1 < 1.1 < 1.1 < 1.1 < 1.1 < 1.1 May 2 < 1.6 < 1.6 < 1.6 - 1. 6 < 1.6 < 1.6 < 1.6 U May 9 < 1.5 < 1. 5 < 1.5 < 1.5 < 1. 5 < 1.5 < 1.5 May 16 < 1.8 < 1.8 1.9 (2.1) < 1.8 < 1.8 < 1.8 1.8 (2.1) May 23 < 1.9 < 1.9 7.4 (2.4) < 1.9 < 1.9 < 1.9 < 1.9 May 29 < 1.6 < 1.6 4.9 (1.9) 3.5 (1.9) < 1.6 < 1.6 < 1.6 Jun 6 < 1.5 < 1.5 3.8 (1.9) 4.0 (1.9) < 1. 5 < 1. 5 < 1.5 Jun 12 < 2.0 < 2.0 < 2.0 < 2.0 < 2.0 < 2.0 < 2.0 Jun 19 < 2.0 < 2.0 e e < 2.0 < 2.0 < 2.0 9 Jun 26 < 1.9 < 1.9 < 1.9 8.2 (2.4) < 1.9 < 1.9 < 1.9
- 1.96 o (Due to counting statistics.)
e Insufficient sample volume for analysis. 3 5 H MPC,jp = 2x10 Ci/m (10CFR20 Appendix B, Column II).
O O O Table II.B.3 Tritium Concentrations in Atmospheric Water Vapor. (pCf/m3 ) c.) Collection Period: Third Quarter,1987. Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 Jul 3 < 2.3 < 2.3 3.1 (2.8)* 3.6 (2.8) < 2.3 < 2.3 < 2.3 Jul 10 < 2.1 < 2.1 4.2 (2.5) 5.6 (2.5) < 2.1 < 2.1 2.1 (2.5) Jul 17 < 2.1 < 2.1 2.2 (2.5) 2.1 (2.5) < 2.1 < 2.1 < 2.1 Jul 25 < 1.9 < 1.9 3.6 (2.3) < 1.9 < 1.9 < 1.9 < 1.9 Aug 1 < 2.5 < 2.5 5.2 (3.0) 3.0 (2.9) < 2.5 < 2.5 < 2.5 Aug 8 < 2.4 < 2.4 < 2.4 3.0 (2.9) < 2.4 < 2.4 < 2.4 Aug 15 < 2.3 < 2.3 < 2.3 < 2.3 < 2.3 < 2.3 < 2.3 Aug 22 < 1.9 < 1.9 < 1.9 2.3 (2.3) < 1.9 3.0 (2.2) < 1.9 Aug 29 < 2.1 < 2.1 < 2.1 3.7 (2.5) < 2.1 < 2.1 < 2.1 Sept 5 < 2.1 < 2.1 < 2.1 < 2.1 < 2.1 < 2.1 < 2.1 Sept 12 < 1.7 < 1.7 < 1.7 < 1.7 < 1.7 < 1.7 < 1.7 Sept 19 < 1.6 < 1.6 < 1.6 < 1.6 3.9 (1.8) < 1.6 < 1.6 Sept 26 < 1.4 < 1.4 < 1.4 < 1.4 < 1.4 < 1.4 < 1.4
- 1.96c(Due to counting statistics.)
3 5 H MPC,gg = 2x10 pCi/m3 (10CFR20 Appendix B, Column II).
O O O 3 Table II.B.3 Tritium Concentrations in Atmospheric Water Vapor. (pCf/m ) c.) Collection Period: Fourth Quarter,1987. Collection
- Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 Oct 3 < 1.2 < 1.2 < 1.2 < 1.2 < 1.2 < 1.2 < 1.2 3ct 10 < 1.0 < 1.0 < 1.0 < 1.0 < 1.0 < 1.0 < 1.0 Oct 17 < 1.0 < 1.0 < 1.0 2.4 (1.2)* < 1.0 < 1.0 1.5 (1.2)
Oct 24 < 0.97 < 0.97 < 0.97 < 0.97 < 0.97 < 0.97 1.3 (1.1) Oct 31 < 1.1 < 1.1 1.2 (1.3) 1.4 (1.3) < 1.1 < 1.1 < 1.1 g; Nov 7 < 1.4 < 1.4 2.5 (1.7) 2.1 (1.7) < 1.4 < 1.4 2.7 (1.7) Nov 14 < 1.0 < 1.0 < 1.0 < 1.0 < 1.0 < 1.0 < 1.0 Nov 21 < 0.78 < 0.78 < 0.78 < 0.78 < 0.78 < 0.78 < 0.78 Nov 28 < 0.77 < 0.77 < 0.77 < 0.77 < 0.77 < 0.77 < 0.77 Dec 5 < 0.91 < 0.91 < 0.91 < 0.91 < 0.91 < 0.91 < 0.91 Dec 12 < 0.69 < 0.69 < 0.69 < 0.69 0.93(0.84) < 0.69 < 0.69 Dec 19 < 0.58 < 0.58 0.80(0.56) 1.1 (0.58) < 0.58 < 0.58 < 0.58 Dec 28 < 0.58 < 0.58 < 0.58 < 0.58 < 0.58 < 0.58 < 0.58
- 1.96o(Due to counting statistics.)
e3 Insufficient vglume fgr analysis. H MPC,jp = 2x10 pCi/m (10CFR20 Appendix B, Column II).
m O O% U 1 l l Table 11.B.4 T ri t time Released (Cil in Reagfor Errtuents. 198L I I I TRI T IUM RELEASED (C E ) IN REACTOR EFFLUENTS, 1987 1 I I l t 1 ! I I I I i 1 1 1 1 I I I I I MODE l JAN I FEB i MAR I APR I MAY I JUN I JUL l AUG I SEP l OCT I NOV I DEC I TOTAL I I I I I I I I I I I I I I I I I I I I i 1 1 1 I I i 1 1 1 1 I continuous i I I I I I I I I I I I I I l (Turbine i .0290 I .0232 I .008621 .003861 .0420 I .0788 i .159 I .0242 I .007331 .002581 .0264 I .614 11.02 I l Building i l i l l I I I l l l 1 l l 1 sump) i I I I i 1 1 1 1 1 I I I I I I I I i e i 1 1 1 I I I I I l natch l I I I I I I I I I I i l I i Release i I i 1 1 I i l l l l 1 I I I (Reactor i .0166 I .0124 l .0124 l .003268 .0343 8 .0371 l .313 l .149 l .312 I .0384 I .0129 I .0455 l .987 l l liu i 4 d i ng I sump) i i i i i i I i 1 I i l l l 1 1 i I i I l I l I I i I 1 l l 1 1 I I I I I I i 1 l 1 _I I I I I I I I I I I I I I I I I I natch 1 1 c 1 I I I I I I I I I I I nelease 11.39 1 .921 l 2.27 I .443 122.6 16.01 17.13 12.64 l .767 I .400 11.10 18.34 154.0 l I is/ stem 62) l I I I I I I I I I I i 1 1 I I I i i l I i I i I i l i i I I i i i i i i i i i I I I I i I i I i i l i I i 1 1 1 1 1 I Gaseous 1.0007671 .004DI .008091 .0158 l .926 i .336 I .983 I .0850 I .0500 1 .108 l .005611 .607 13.13 i i stack I i i I i i i i i i l I i i I i I i I 1 i i 1 1 I I I I I I f I I I i 1 1 I I I I I I I I I I I i 1 1 1 1 I i 1 I I I - 1 I i i i I I i 1 1 1 1 I i 1 1 1 1 1 1 I I l 1 i i i i i TOTAL 11.44 1 .961 12.30 1 .466 123.6 16.46 18.59 12.90 11.14 l .549 11.14 19.61 159.1 l l l l 1 1 I l l l l I i 1 I I I l l I I i 1 1 1 I I I I I I 1 l_ i i i I I I i I i i i i i i l l l
r 27
- 3. Concentrations of Gama-ray Emitting Radionuclides in Ambient Air 1
Tables II.B.5a-5d list the concentrations of I-131 in air as measured by activated charcoal sampling and high resolution gama-ray spectrum analysis. Each sample from the seven air sampling stations is counted within 96 hours after collection. A 100 minute count is typically required to achieve an HDC of 33 fCi/M3 , Radon daughters and Thoron daughters are trapped on the particulate filter ahead of the charcoal trap. Radon-222 daughter in-growth on the charcoal does not ), provide interference to the region of interest for I-131 using the Ge(L1) high resolution spectrometry. Any positive I-131 activity is i 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 in pulses of short duration compered 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 values very near the HDC value and all are assumed to be false positive. 1-131 concentrations due to reactor effluent have never bet ' detected 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 gama-ray spectrum analyses on weekly I air filtars composited quarterly from each of the seven air sampling I stations. The occasional positive Cs-137 concentrations measured are l likely due to resuspension of surface soil. The Cs-137 activity is due to Chernobyl (or previous) f allout which is bound by clay minerals on Q
28 the surf 6ce of undisturbed soil. For the entire year, the mean of the facility stations was not different from the mean of the reference stations. Although only Cs-134 and Cs-137 are reported, each gama-ray spectrum is scanned for evidence of peaks from other fission products and activation products. Normally only gama-ray activity due to the naturally occurrir.g background radionuclides are observed. During the second quarter of 1986, however, many other radionuclides were observed due to the Chernobyl accident. Of these only Cs-137 can still be detected. O O
o o o-Table 11.8.5 Iodine-131 Concentrations in Air. (fCi/mf) a.) Collection Period: First Quarter,1987. Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 Jan 3 < 19 < 31 < 30 < 18 < 22 < 26 < 21 Jan 10 < 30 < 30 < 18 < 28 < 22 < 28 < 18 Jan 16 < 31 < 18 < 9.7 < 27 < 28 < 8.6 < 29 Jan 24 < 13 < 23 < 28 < 32 < 24 < 29 < 19 Jan 31 < 28 < 34 < 20 < 20 < 12 < 29 < 32 0; Feb 7 < 15 < 16 < 12 < 32 < 20 < 30 < 14 Feb 14 < 14 < 14 40 (39)* < 19 < 21 27 (28) < 27 l Feb 20 < 27 < 29 < 13.
< 16 < 17 < 30 < 27 Feb 28 < 25 < 34 < 18 cl < 32 < 13 < 29 Mar 6 < 18 < 14 < 28 c1 < 10 < 16 < 19 Mar 14 < 12 < 32 < 21 < 22 < 14 c2 < 9.5 Mar 21 < 19 < 22 < 18 < 13 < 14 < 19 < 15 Mar 28 < 22 < 34 < 30 < 16 < 13 < 18 < 26
- 1.96 0 (Due to counting statistics .)
1-131 MPC = 105 fCi/m3 . (10CFR20, Appendix B, Table II) c1 Pump inoperative. No replacment pump availabla. c2 Pump inoperative for major fraction of sampling period.
O O O 3 Table II.B.5 Iodine-131 concentrations in Air. (fCi/m ) b.) Collection Period: Second Quarter,1987. Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 Apr 4 < 21 < 34 < 25 < 15 < 26 < 24 < 22 Apr 11 < 21 < 25 < 18 < 29 < 12 < 16 < 30 Apr 18 *
< 28 < 17 < 20 < 22 < 27 < 18 < 24 Apr 24 < 31 < 33 < 26 < 7.1 < 19 < 28 c1 May 1 < 15 < 28 < 16 < 20 < 25 < 29 < 20 g May 9 < 11 < 27 < 17 < 19 < 21 < 19 < 26 May 16 < 25 < 25 < 30 < 25 < 28 < 17 < 32 May 23 < 29 < 12 < 22 < 32 42 (42)* < 33 < 21 May 29 < 18 < 14 < 23 < 24 < 30 < 23 < 28 Jun 6 < 9.4 < 25 < 27 < 26 < 29 < 16 < 25 Jun 11 < 29 < 16 < 30 < 34 < 20 < 19 < 33 Jun 19 < 33 < 25 < 34 34 (37) < 27 < 21 < 11 Jun 27 < 17 < 21 < 15 < 24 < 21 < 12 < 23
*1.96o(Duetocountingstatistics.)
1-131 MPC = 105 fC1/m . (10CFR20, Appendix B, Table II) c1 Pump inoperative for major fraction of sampling period.
__ _ = . O O O 3 Table II.B.5 Iodine-131 concentrations in Air. (fCi/m ) c.) Collection Period: Third Quarter,1987. Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 Jul 2 < 34 < 29 < 32 < 23 < 18 < 15 < 19 Jul 10 < 12 < 19 < 24 < 8.3 < 6.9 < 14 ' 7 (3.6)* Jul 17 < 25 < 15 < 29 < 18 < 26 < 25 < 14 Jul 25 < 24 < 18 < 11 < 19 < 21 < 17 < 27 Aug 1 < 25 < 16 < 21 < 22 < 16 < 16 < 22 S Aug 8 < 18 < 21 < 18 14 (16) < 25 < 6.7 < 7.8 Aug 15 < 24 < 13 < 15 < 17 < 16 < 12 < 7.0 Aug 22 < 15 < 24 < 18 < 23 i < 13 < 15 < 22 Aug 29 < 21 < 28 < 17 < 20 < 21 < 10 < 13 Sept 5 < 20 < 1.4 < 18 < 32 < 34 < 11 < 32 Sept 12 < 13 < 17 < 31 < 3.4 < 31 < 13 < 16 Sept 19 < 19 < 28 < 29 < 35 < 26 < 12 < 21 Sept 26 < 35 < 23 < 19 < 25 < 29 < 17 < 17
*I-131 1.96MPC o (Due
= 10tg counting mci /m3 . (statistics.)
10CFR20, Appendix 8. Table II)
. O O O - 3 Table II.B.5 Iodine-131 concentrations in Air. (fCi/m ) - d.) Collection Period: Fourth Quarter, 1987 i j Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 Oct 3 35 (32f < 33 < 11 < 26 < 27 < 9.7 < 13 J
- Oct 10 < 18 < 11 < 19 < 18 < 11 19 (21) < 21 j Oct 17 < 32 < 21 < 16 < 23 < 31 21 (21) c3
- Oct 24 < 30 < 14 < 26 < 11 < 14 < 20 < 18 1
Oct 31 < 33 < 20 30 (31 < 32 c1 < 29 < 22 . Nov 7 < 29 < 20 < 30 < 19 < 16 36 (33) < 18 w N
- Nov 14 < 22 c2 < 31 < 25 < 35 < 27 < 32.
Nov 21 < 34 < 23 **< 47 < 32 < 29 < 13 < 17 l j Nov 28 < 26 < 19 < 16 < 16 < 33 < 14 < 21 ! Dec 5 < 7.1 < 13 < 8.2 < 6.9 < 20 < 15 < 23 i i Dec 12 < 31 < 19 < 17 < 15 < 21 < 22 < 21 1 Dec 19 < 29 < 21 < 33 < 10 < 35 < 23 < 23 Dec 28 < 12 < 1.9 < 1.6 < 17 < 35 < 16 < 31 l
- 1.96 o(Due to counting statistics.)
** L1!D Could not be met due to a low sample volume.
1-131 Mpt = loS f cif,3 (10CFR20, Appendix B. Table II) c1 Broken cartrica, air filter and charcoal not representative of air flow c2 Instrument ualfunction- no pump available. c3 Not enough volume, pump only ran for one day.
O O O - Table II.B.6 Radiocesium Concentrations in Ambient Air. ( fCi/m 3) , 1987. Facility Sites Reference Sites Collection Radio-Pf fod nuclide F-7 F-9 F-16 A-19 R-3 R-4 R-11 1st Cs-134 < 1.4 1.8 < 2.4 < 2.7 < 1.7 1.6 (1.9) < 2.2 Quarter 1987 Cs-137 < 1.6 < 2.0 < 2.4 2.8 (3.4)* < 1.7 < 1.7 < 2.3 2nd Cs-134 < 1.8 < 1.6 < 2.6 < 1. 9 < 2.3 < 1.7 < 1.6 Quarter 1987 Cs-137 3.5 (2.1) 2.2 (2.0) < 2.8 < 1.9 < 2.4 < 1.7 < 1.7 3rd Cs-134 < 2.4 < 2.4 < 1.4 < 1.7 < 1.9 < 1.4 < 1.7 Quarter 1987 Cs-137 < 2.5 < 2.5 < 1.6 < 1.9 < 2.0 < 1,<4 < 1.8 t! 4th Cs-134 < 2.5 < 2.0 < 1.7 < 1.9 < 3.8 < 1.2 < 2.1 Quarter 1987 Cs-137 < 2.5 < 2.2 < 1.9 < 2.1 < 3.9 < 1.4 2.9 (2.6)
*1.96 o (Due to counting statistics.)
Cs-134 MPC = 1 x 10'CfCi/m3 , Cs-137 MPC = 2 x 10f ' fCi/m3 (10CFR20, Appendix B, Table II).
34 II.C. Radionuclide Concentration in Water O 1. Drinking Water Drinking water is sampled weekly and composited biweekly at two locations. Location R-6 is the well used for drinking water by the town of Gilcrest, Colorado, and R-3 is a water tap located on the CSU dairy farm. The Gilcrest well is the nearest public water supply that could be affected by the reactor effluents. R-3 samples are from the Fort Collins drinking water supply and s n e as a reference location since its source is run-off surface water from the Rocky Mountains to the West. Table II.C.1 shows gross beta concentrations measured in 1987 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 different water treatment practices. The city of Gilcrest i q) coes not filter its water and natural radionuclide concentrations are responsible for the higher measured concentrations. As can be observed in iable II.H.2, the mean for the entire year for the Gilcrest site was not greater than in previous years. Table II.C.2 lists measured tritium concentrations in these same two drinking water sources. The yearly arithmetic mean values for both locations were less than MDC and, therefore, not statistically vifferent from each other. No evidence of the tritium released from the reactor was observed. Figure II.C.1 shows that tritium concentrations in drinking (potable) water sources were less than MDC for 1987. The two drinkirg water supplies are also analyzed for fission product and activation product concentrations. A sample of 18 liters is passed through Dowex 1-x8 anion exchange resin and the resin then Q
m 35 counted by Ge(Li) spectrometry for I-131. This same method is used for milk samples. 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 values of radionuclide concentration, but with the exception of Cs-137, these are interpreted to be randem variations. The Cs-137 is the residue from the 1986 Chernobyl accident fallout as well as from past world-wide fallout from nuclear weapon testing.
/'s O,.
i l 1 l l O i
36 l Table II.C.1 Gross Beta Concentratiu)s in Biweekly Composites of Drinking Water. First Hal f,1987. (pCi/L) Collection Gilcrest City R-6 Fort Collins City R-3 Date (Reference) Jan 3, 10 3.2 (2.2)* 0.90 (0.53) Jan 16, 24 2.2 (2.1) 0.64 (0.54) Jan 31, Feb 7 3.0 (2.2) 0.79 (0.54) Feb 14, 21 3.1 (2.2) 0.47 (0.52) Feb 28, Mar 7 4.1 (2.2) 0.62 (0.53) Mar 14, 21 5.3 (2.3) 0.57 (0.52) Q Mar 28, Apr 4 2.9 (2.2) 1.1 (0.55) Apr 11, 18 5.2 (2.3) 0.47 (0.52) Aor 24, May 1 6.2 (2.4) 0.69 (0.53) ! May 9, 16 5.8 (2.3) 0.57 (0.52) May 23, 29 2.6 (2.2) < 0.45 Jun 6, 12 4.9 (2.2) 0.51 (0.50) l Jun 19, 27 5.2 (2.2) 2.0 (0.56)
*1.96 c(Due to counting statistics.)
i MP = 30 pCi/L Table II, Appendix 8 limit,10CFR20 for an uni (dentified mixture of radionuclides in water if either the identity or the concentration of any radionuclide is not known. t
- O
l 37 l n U Table II.C.1 Gross Beta Concentrations in Biweekly Composites of Drinking Water. Second Half,1987. (pCi/L) Collection Gilcrest City R-6 Fort Collins City R-3 Date (Reference) Jul 3,10 6.1 (2.3)* 0.74 (0.50) Jul 17, 25 2.5 (2.1) 0.83 (0.52) Aug 1, 8 5.0 (2.2) 0.88 (0.51) Aug 15, 22 5.2 (2.2) 0.58 (0.49) Aug 29, Sept 5 4.1 (2.1) 0.90 (0.50) i Sept 12, 19 6.1 (2.2) 1.4 (0.53) Sept 26, Oct 3 5.9 (2.3) 0.74 (0.43) ! c' ' 27 (2 4) 48 ( 5) O 0.88 (0.52) Oct 24, 31 7.6 (2.4) Nov 7, 14 5.9 (2.3) 0.70 (0.51) Nov 21, 28 7.5 (2.3) 1.0 (0.53) Dec 5,12 5.8 (2.3) 1.1 (0.53) l l Dec 19, 28 4.7 (2.2) 1.1 (0.53)
- 1.96 e (Due to counting statistics.)
MPCw = 30 pCi/L Table II, Appendix B limit,10CFR20 for an unidentified mixture of radionuclidas in water if either the identity or the concentration of any radionuclide is not known. lO l l
38 s U Table II.C.2 Tritium Concentrations in Biweekly Composites of Drinking Water. First Hal f,1987.- -(pCi/L) Co~llection Gilcrest City R-6 Fort Collins City R-3 Date (Reference) Jan 3, 10 430 (280)* < 240 Jan 16, 24 < 230 < 230 Jan 31, Feb 7 < 230 < 230 Feb 14, 21 430 (280) 450 (280) Feb 28, Mar 7 < 240 < 240 Mar 14, 21 260 (280) < 230 Mar 28, Apr 4 < 240 < 240 Apr 11, 16 < 230 < 230 Apr 24, May 1 < 230 < 230 May 9, 16 < 230 < 230 May 23, 29 < 230 < 230 Jun 6, 12 < 230 < 230 Jun 19, 27 < 230 < 230
- 1.96 o (Due to counting statistics.)
H-3 MPC = 3 X 106 pCi/L (10CFR20, Appendix B, Table II) O
39 O Table II.C.2 Tritium Concer.trations in B . -ekly Composites of. Drinking Water. Second half,1987. (pCi/L) Collection Gilcrest City R-6 Fort Collins City R-3 Date: (Reference) Jul 3, 10 < 230 250 (280)* Jul 17, 25 < 230 < 230 Aug 1, 8 < 230 < 230 Aug 15, 22 < 230 < 230 Aug 29, Sept 5 < 230 < 230 Sept 12, 19 < 230 < 230
'O sent 26. oct 3 39o (280> < 230 Oct 10, 17 610 (280) < 230 Oct 24, 31 < 230 < 230 Nov 7, 14 < 230 < 230 Nov 21, 28 < 230 < 230 Dec 5, 12 < 230 < 230 Dec 19,26 320 (280) < 290
- 1.96 o (Due to counting statistics.)
6 H-3 MPC = 3 X 10 pCi/L (10CFR20, Appendix B, Table II) O
40
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O O O Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L) Collection Date Jan 3, 10, 1987 Jan 17, 24, 1987 Jan 31, Feb 7, 1987 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 I-131 0.51 (0.54)* < 0.19 < 0.27 < 0.20 < 0.23 < 0.25 Cs-134 < 2.4 < 2.4 < 2.3 < 2.5 < 2.4 < 2.2 Cs-137 < 2.9 < 3.0 5.1 (4.1) < 3.1 < 2.9 < 3.2 Zr-95 < 5.6 < 5.8 < 5.1 < 5.9 < 5.6 < 4.9 ' Nb-95 < 2.2 < 2.3 < 2.1 < 2.3 < 2.2 2.9 (2.4) Co-58 < 2.2 < 2.2 < 2.3 < 2.3 < 2.2 < 2.2 Mn-54 < 2.4 < 2.5 < 2.3 < 2.5 < 2.4 < 2.2 Zn-65 < 5.8 < 5.6 < 5.5 < 5.8 ' 9.0 (6.8) < 5.1 Fe-59 < 4.4 < 4.8 < 4.2 < 4.7 < 5.7 < 5.3 Co-60 < 2.6 < 2.7 < 2.3 < 2.7 < 2.6 < 2.2 Ba-140 < 3.9 < 5.9 < 3.3 < 4.1 < 5.5 < 3.2 La-140 < 4.5 c 6.8 < 3.8 < 4.7 < 6.3 < 3.7
- 1.96 o (Due to counting statistics.)
(- w./ w/ 8 .; Table II.C 3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L) Collection Date Feb 14, 20, 1987 Feb 28, Mar 6, 1987 Mar 14, 21, 1987 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 I-131 < 0.46 < 0.19 < 0.19 < 0.31 < 0.22 < 0.15 Cs-134 < 2.2 < 2.8 < 2.6 < 2.4 < 2.2 < 1.8 Cs-137 < 3.4 < 3.4 < 3.3 < 3.6 5.6 (3.8) 3.8 (3.2) Zr-95 < 5.5 < 6.6 < 6.2 < 5.3 < 4.7 < 4.4 Nb-95 < 2.1 < 2.5 < 2.3 2.7 (2.7)* < 1.9 < 1.6 Co-58 < 2.3 < 2.7 < 2.4 < 2.4 < 2.0 < 1.8 Mn-54 < 2.2 < 2.8 < 2.7 < 2.4 < 2.1 < 1.8 Zn-65 < 5.3 < 6.4 < 6.2 9.4 (6.6) < 5.3 < 4.1 Fe-59 < 5.6 < 6.6 < 6.2 < 5.4 < 4.8 < 4.1 Co-60 < 2.3 < 3.0 < 2.8 < 2.4 < 2.1 < 1.9 Ba-140 < 3.4 < 4.6 < 4.3 < 3.6 < 3.1 < 2.7 La-140 < 3.9 : 5.3 < 5.0 < 4.2 < 3.6 < 3.0 l
- 1.96 o (Due to counting statistics.)
i
O O O Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L) Collection Date Mar 28, Apr 4, 1987 Apr 11, 18, 1987 Apr 24, May 1,1987 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 I-131 < 0.47 < 0.36 < 0.24 0.41 (0.47) < 0.27 < 0.39 Cs-134 < 2.0 < 2.4 < 2.1 < 2.5 < 1.2 < 2.2 Cs-137 5.0 (3.5)* < 2.9 < 3.1 < 3.0 < 1.4 4.1 (3.9) Zr-95 < 4.9 e 5.5 < 5.0 < 6.1 < 2.7 < 5.0 Nb-95 < 1.7 < 2.3 < 1.9 < 2.1 < 1.1 < 2.1 Co-58 < 1.9 < 2.3 < 2.1 < 2.2 < 1.1 < 2.1 Mn-54 < 2.0 < 2.4 < 2.1 < 2.4 < 1.2 < 2.2 Zn-GS < 4.5 < 5.4 < 5.0 < 5.6 < 2.7 6.4 (6.2) Fe-59 6.7 (6.5) < 6.1 < 5.2 < 5.8 < 2.7 < 5.0 Co-60 < 2.0 < 2.6 < 2.1 < 2.6 < 1.2 < 2.2 Ba-140 6.9 (6.6) < 6.1 < 4.4 < 5.6 < 3.2 < 3.3 La-140 7.9 (7.6) < 7.0 < 5.0 < 6.4 < 3.7 < 3.8
- 1.96o (Due to counting statistics.)
O O O Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L) Collection Date May 9, 16, 1987 May 23, 29, 1987 Jun 6, 12, 1987 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 I-131 < 0.48 < 0.40 < 0.36 < 0.23 < 0.36 < 0.41 Cs-134 < 2.3 < 1.9 < 2.5 < 2.3 < 1.8 < 2.4 Cs-137 < 2.9 < 2.8 < 3.0 < 3.4 2.5 (2.6) 3.2 (3.5) Zr-95 < 5.4 < 4.3 < 6.0 < 5.0 < 4.2 < 5.8 Nb-95 < 2.1 < 1.7 < 2.3 2.4 (2.4) < 1.6 < 2.2-C0-58 < 2.1 < 1.8 < 2.3 < 2.3 < 1.6 < 2.2 Mn-54 3.5 (2.8)* < 1.9 < 2.4 < 2.2 3.3 (2.2) < 2.5 Zn-65 < 5.4 6.4 (5.3) < 5.7 < 5.1 < 4.3 < 5.8 Fe-59 < 5.5 < 4.7 < 5.8 < 5.4 < 4.9 < 5.8 Co-60 < 2.5 < 1.9 < 2.6 < 2.2 2.1 (2.4) < 2.7 Ba-140 < 5.2 < 2.7 < 3.9 < 3.2 < 2.9 < 4.1 La-140 < 6.0 < 3.2 < 4.5 < 3.7 < 3.4 < 4.7
- 1.96o (Due to counting statistics.)
O O O Table II.C.3 Radionuclide Concentrations in Bi-weekly Composiete of Drinking Water. (pCi/L) Collection Date Jun 19, 26, 1987 Jul 3,10,1987 Jul 17, 25,1987 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 I I-131 < 0.47 < 0.42 < 0.43 < 0.20 < 0.39 < 0.33 Cs-134 < 2.7 < 2.9 < 2.6 < 2.8 < 2.5 2.7 (2.7). Cs-137 5.7 (4.8)* < 3.6 6.9 (4.6) < 3.5 < 3.1 7.0 (4.0) ,, m Zr-95 < 6.2 < 6.8 < 6.2 < 6.5 8.4 (7.5) < 5.2-Nb-95 < 2.6 2.9 (3.1) < 2.3 < 2.4 < 2.3 < 2.0 Co-58 < 2.6 < 2.8 < 2.6 < 2.6 < 2.3 4.4 (2.7) Mn-54 < 2.6 < 2.9 < 2.5 < 2.8 < 2.5 < 2.3 Zn-65 < 6.6 < 6.8 < 6.5 < 6.6 < 5.9 < 5.3 Fe-59 < 6.1 8.4 (9.0) < 6.6 9.9 (8.4) < 6.2 < 5.1 Co-60 < 2.8 < 3.2 < 2.6 < 3.1 < 2.7 2.8 (2.7) Ba-140 < 5.7 < 4.7 7.6 (6.6) < 4.4 < 5.7 < 4.7-La-140 < 6.6 < 5.4 8.8 (7.5) < 5.1 < 6.6 < 5.4
- 1.96o (Due to counting statistics.)
O O O Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L) l Collection Date Aug 1, 8, 1987 Aug 15, 22, 1987 Aug 29, Sep 5, 1987 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 i I-131 < 0.41 < 0.21 < 0.22 < 4.8 < 0.40 < 0.25 Cs-134 < 3.7 < 4.0 < 2.8 2.5 (2.7) < 2.3 < 1.5 ~ Cs-137 9.5 (6.6)* < 5.0 < 3.2 < 2.8 3.6 (3.5) 2.0 (2.2) Zr-95 < 8.2 < 9.9 < 5.0 < 5.5 < 5.9 < 3.5 ,, m Nb-95 < 3.2 8.0 (4.4) < 1. 9 3.3 (2.4) < 2.2 1.8 (1.8) Co-58 < 3.5 < 3.9 < 2.0 < 2.1 < 2.3 < 1.4 i Mn-54 4.3 (4.4) < 4.0 < 2.1 < 2.2 < 3.1 < 1.5 I Zn-65 < 8.8 < 9.5 < 5.2 < 5.5 < 5.6 < 3.9 Fe-59 < 8.2 < 9.5 < 5.0 < 5.6 < 6.0 < 3.8 ! Co-60 < 3.7 7.1 (5.2) < 2.1 2.7 (2.9) < 2.6 < 1.4 Ba-140 < 7.5 < 6.6 < 3.2 < 3.7 < 3.8 < 3.6 l La-140 < 8.6** < 7.5 < 3.7 < 4.3 < 4.4 < 4.1
* : .96c (Due to counting statistics.)
l ** a lab accident caused loss of most of sample so LLD could not be j met.
O O O Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L) Collection Date Sep 12, 19, 1987 Sept 26, Oct 3, 1987 Oct 10, 17, 1987 i Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 I-131 < 0.24 0.63 (0.52) < 3.9 < 0.41 < 0.30 < 0.24-Cs-134 < 2.4 < 2.7 < 2.8 < 2.5 < 2.5 < 2.4
< 3.1 < 2.9 l
Cs-137 < 3.0 < 3.2 < 3.3 < 3.1 Zr-95 < 5.7 < 6.4 < 6.6 < 5.6 < 5.8 < 5.8 a Nb-95 5.3 (2.7)* < 2.4 < 2.6 < 2.2 < 2.3 < 2.1 Co-58 < 2.4 < 2.5 < 2.6 < 2.3 < 2.3 < 2.3 Mn-54 < 2.4 < 2.6 < 2.7 < 2.5 < 2.5 < 2.4 Zn-65 < 6.1 < 6.5 < 7.1 < 6.0 < 6.3 < 6.0 Fe-59 < 6.3 < 6.2 < 6.5 < 5.9 < 5.7 < 5.6
- Co-60 < 2.6 4.5 (3.5) < 3.0 < 2.6 < 2.7 < 2.7 Ba-140 < 4.0 < 6.0 < 6.5 < 6.2 < 6.3 < 4.0 La-140 < 4.6 < 6.9 < 7.5 < 7.1 < 7.2 < 4.6
*1.960 (Due to counting statistics.)
O O O Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L) Collection Date Oct 24, 31, 1987 Nov 7, 14, 1987 Nov 21, 28, 1987
~
Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 I-131 < 2.4 < 0.48 < 0.46 < 0.41 < 0.23 < 0.39 Cs-134 < 2.4 < 1.8 < 1.8 < 1.9 < 1.9 < 2.0
^
Cs-137 < 3.5 < 2.7 4.9 (3.2) 2.8 (3.8) < 2.8 4.0. (3.0) Zr-95 < 5.4 < 4.2 < 4.3 < 4.2 < 4.6 < 5.3 Nb'-95 < 2.4 < 1.7 < 1.6 < 1.8 < l.7 < 1.9 g; Co-58 < 2.4 < 1.7 < 1.7 < 1.8 < 1.8 < 2.0 Mn-54 < 2.4 < 1.8 < 1.8 < 1.9 < 1.9 < 2.1 Zn-65 < 6.0 < 4.3 < 4.4 < 4.5 < 4.4 < 4.9 Fe-59 < 5.5 < 4.0 < 4.5 < 4.3 < 4.2 < 4.9 Co-60 < 2.5 < 0.93 < 1.8 < 1.9 < 1.9 < 2.2 Ba-140 < 3.5 < 4.0 < 5.0 < 2.7 < 2.8 < 3.4 La-140 < 4.0 < 4.6 < 4.8 < 3.1 < 3.3 < 3.9
*1.96o (Due to counting statistics.)
O O
~
O Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L) Collection Date Dec 5, 12, 1987 Dec 19, 28, 1987 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 I-131 < 0.34 < 0.29 < 0.44 < 0.27 Cs-134 < 2.4 < 2.4 < 2.0 < 2.2 Cs-137 < 3.6 < 2.9 < 2.4 < 3.2 Zr-95 < 5.4 < 5.6 < 4.6 < 5.0 Nb-95 < 2.4 < 2.2 < 1.8 < 2.0 g; Co-58 < 2.4 < 2.4 < 1.8 < 2.1 Mn-54 < 2.4 < 2.4 < 2.0 < 2.2 In-55 < 6.2 < 5.7 6.1 (5.9)* < 5.5 Fe-59 < 6.2 < 5.5 < 4.9 < 5.2 Co-60 < 2.3 < 2.6 < 2.1 < 2.1 Ba-140 < 4.1 < 6.0 < 4.4 < 4.4 La-140 < 6.3 < 6.9 < 5.1 < 5.0
*1.96o (Due to counting statistics.)
50
- 2. Surface Water 13 U Surf ace water is collected monthly from four sites. Since the reactor water effluent can be directed to either rivar course, there are upstreaa and downstream sampling locations on both the St. Vrain Creek and on the South Platte River.
Table II.C.4 shows tritium concentrations measured at the four surface water sites. Most of the values were less than HDC. The arithmetic mean value for the downstream locations in 1987 was not significantly different from the two upstream locations (Table II.H.2). The elevated value observed at R-10 on December 19, 1987 was reanalyzed and confirmed to be correct. Table II.C.5 shows measurements of fission product and activation product concentrations in surface water samples collected monthly. There were occasional positive values, but the mean of the downstream sites was not significantly different from the mean of the upstream sites during 1987 for any of the ganma-ray emitting radionuclides measured. This has been the case since the inception of reactor operations at the Fort St. Vrain site. The occasional positive values are either fallout Cs-137, which can be expected, or values close to the uncertainty limits and assumed to be false positives. In addition to the monthly sampling of the South Platte River and St. Vrain Creek, a continuous water sample is collected at station A-25. An aliquot of the farm pond outlet is sampled every 10 minutes and the composite collected weekly. The weekly composites are then combined and analyzed monthly. The results of these samples are shown in Table II.C.6. For every month there was evidence of measurable tritium release. Mean values for the other radionuclides were low and except Q
51 for Cs-137, less than HDC. The correlation with the effluent release O V report is high. Ground water is sampled quarterly at two locations. These are at F-16, a well on the farm immediately north and the closest to the reactor down the hydrological gradient, and at R-5, the Ehrlich feedlot. Table II.C 7 lists the measured concentrations of fission products and activation products in ground water. The Cs-137 results are not surprising due to residue of Chernobyl fallout, and the other results above MOC are assumed to be statistically false positive values. For comparison purposes, Table II.C.8 lists the Maximum Permissible Concentration values for each of the radionuclides listed in Tables II.C.5-7. O O
52
/]IableII.C.4 Tritium 1987.
Concentrations in Surface Water. (pCi/L) Downstream Sites Upstream Sites Collection Date St. Vrain S. Platte St. Vrain S. Platte F-20 R-10 A-21 F-19 Jan 10 400 (280)* < 240 560 (290) < 240 Feb 14 < 240 < 240 < 240 < 240
< 240~
Mar 14 < 240' < 240 280 (290) Apr 11 < 230 < 230 < 230 < 230 May 16 < 230 < 230 < 230 < 230 Jun 12 < 230 < 230 < 230 < 230 j i Jul 10 < 230 < 230 < 230 < 230 Aug 8 240 (280) < 230 < 230 < 230 Sep 12 400 (280) < 230 190 (300) < 230 Oct 10 < 230 < 230 < 230 < 230 Nov 14 < 230 < 230 < 230 < 230 Dec 19 < 300 730 (360) < 300 < 300 f
- 1.96 e (buetocountingstatistics.)
O l l l
O O O Table 11.0,5 Radionuclide Concentrations in Surface Water. (pCi/L) Collection Date: January 10, 1987 Downstream Sites Upstream Sites Radionuclide St. Vrain S. Platte St. Vrain S. Platte F-20 R-10 A-21 F-19 Cs-134 < 2.3 < 3.3 < 2.7 < 3.4 Cs-137 < 3.3 < 4.9 < 4.0 < 4.0 m Zr-95 < 5.1 < 7.6 < 6.1 < 7.6 Nb-95 2.5 (2.4)* < 3.0 2.7 (2.7) < 3.0 Co-58 < 2.2 < 3.1 < 2.6 < 3.1 Mn-54 < 2.3 < 3.4 < 2.6 < 3.3 Zn-65 < 5.3 < 8.2 < 6.0 < 7.6 Fe-59 < 4.1 7.8 (7.7) 9.2 (5.9) < 5.6 Co-60 < 2.2 < 3.6 < 2.6 < 3.6 Ba-110 < 3.3 < 5.1 < 3.9 < 5.9 La-140 < 3.8 < 5.8 < 4.5 < 6.8
- 1.96o (Due to counting statistics.)
~ O O O J Table II.C.5 Radionuclide Concentrations in Surface Water. (pCi/L) J Collection Date: February 14,1987 i Downstream Sites Upstream Sites ] Radionuclide St. Vrain S. Platte St. Vrain S. Platte F-20 R-10 A-21 F-19 Cs-134 < 2.3 < 3.7 < 3.4 < 3.3 Cs-137 < 3.3 < 4.6 < 4.2 < 4.9 Zr-95 < 5.0 12 (10) < 7.8 10 (9.2) Nb-95 < 1.9 < 3.1 < 2.9 < 2.9 i Co-58 < 2.2 < 3.4 < 3.2 < 3.1 Mn-54 < 2.2 < 3.6 < 3.4 < 3.3 Zn-65 8.5 (6.0)* < 8.2 18 (9.2) 8.5 (9.2) Fe-59 < 5.3
< 8.7 < 8.4 < 7.5 Co-60 < 2.3 < 4.2 < 3.5 < 3.2 Ba-140 < 3.8 < 5.9 < 5.5 6.1 (6.6)
La-140 < 4.4 < 6.8 < 6.3 7.0 (7.6)
- 1.96 o (Due to counting statistics.)
-, _ 7, - , -
O O O Table II.C.5 Radionuclide Concentrations in Surface Water. (pCi/L) Collection Date: March 14,1987 Downstream Sites Upstream Sites Radionuclide St. Vrain .S. Platte St. Vrain S. Platte F-20 R-10 A-21 F-19 Cs-134 < 2.3 < 2.4 < 1.8 < 2.3 Cs-137 < 3.4 < 3.0 6.1 (3.3)* < 3.4 on on Zr-95 < 4.9 < 5.8 < 4.1 < 5.0 Nb-95 < 1.9 < 2.2 < 1. 7 < 2.0 . Co-58 < 2.1 < 2.3 < 1.8 < 2.2 Mn-54 < 2.2 < 2.5 < 1.8 < 2.2 l Zn-65 < 5.1 < 5.6 < 4.1 < 5.2 i Fe-59 < 5.2 < 5.8 < 4.5 < 5.1 Co-60 < 2.3 < 2.6 < 1.8 < 2.3 Ba-140 < 4.0 < 4.6 < 2.7 < 3.8 La-140 < 4.6 < 5.3 < 3.1 < 4.4
- 1.96 o (Due to counting statistics.)
_. _ _ _ - . _ _ _ _ - . _ . - . . . = . - -- . . O O O Table II.C.5 Radionuclide Concentrations in Surface Water. (pCi/L) Collection Date: April 11,1987 Downstream Sites Upstream Sites Radionuclide St. Vrain S. Platte St. Vrain S. Platte F-20 R-10 A-21 F-19 Cs-134 < 1.8 < 2.2 2.9 (3.0) < 2.0 Cs-137 3.0 (3.2)* < 2.8 3.2 (3.6) < 2.5 m Zr-95 < 4.2 < 5.2 < 5.8 < 4.9 Nb-95 < 1.6 < 1.9 < 2.2 < 1.8 Co-58 < 1.7 < 2.1 < 2.3 < 1.9 Mn-54 < 1.8 < 2.3 < 2.4 < 2.0 Zn-65 < 4.2 < 5.1 < 5.8 < 4.7 Fe-59 < 4.3 < 5.3 < 5.9 < 5.1 Co-60 < 1.8 < 2.5 < 2.7 < 2.2 Ba-140 < 2.6 5.1 (5.2) < 4.4 < 3.3 La-140 < 3.0 5.8 (6.0) < 5.0 < 3.8
- 1.960 (Due to counting statistics.)
O O O Table II.C.5 Radionuclide Concentrations in Surface Water. (pCi/L) Collection Date: May 16,1987 Downstream Sites Upstream Sites Radionuclide St. Vrain S. Platte St. Vrain S. Platte F-20 R-10 A-21 F-19 Cs-134 < 2.8 < 3.2. < 2.9 < 2.8 Cs-137 < 4.0 7.4 (5.7) < 3.5 < 3.4 Zr-95 < 6.0 < 7.1 < 6.9 7.7 (8.1) Nb-95 4.6 (2.8)* < 2.8 < 2.5 < 2.4 Co-58 < 2.6 < 3.1 < 2.7 < 2.7 Mn-54 < 2.7 < 3.2 < 2.9 < 2.8 Zn-65 < 6.4 < 7.3 < 6.8 < 6.2 Fe-59 < 6.1 < 8.5 < 6.9 < 6.4 Co-60 < 2.8 < 3.1 < 3.2 < 3.0 Ba-140 < 4.4 < 4.8 < 5.3 < 4.5 La-140 < 5.1 < 5.5 < 6.1 < 5.2
- 1.96c (Due to counting statistics.)
O O O Table II.C.5 Radionuclide Concentrations in Surface Water. (pCi/L) Collection Date: June 12, 1987 i Downstream Sites ! Upstream Sites Radionuclide St. Vrain S. Platte St. Vrain S. Platte F-20 R-10 A-21 F-19 Cs-134 < 3.2 < 2.1 < 1.8 < 3.4 Cs-137 < 4.7 4.5 (3.0) 5.5 (3.3) < 4.1 g; , Zr-95 < 7.4 < 4.8 < 4.2 < 9.4 Mb-95 < 2.8 < 1.9 < 1.6 < 3.1 Co-58 < 3.0 < 1.9 < 1.8 < 3.2 Mn-54 3.6 (3.8)* < 2.1 < 1.8 < 3.4 Zn-65 < 7.4 7.5 (5.5) 6.3 (5.1) < 8.0 Fe-59 < 7.4 < 4.8 < 4.6 < 8.2 Co-60 < 3.3 < 2.2 < 1.9 < 3.7 Ba-140 < 4.7 < 4.6 < 2.8 < 5.6 La-140 < 5.4 < 5.3 < 3.2 < 6.4
- 1.96o (Due to counting st.itistics.)
i
O O O Table II.C.5 Radionuclide Concentrations in Surface Water. (pCi/L) Collection Date: July 10,1987 Downstream Sites Upstream Sites Radionuclide St. Vrain S. Platte St. Vrain S. Platte F-20 R-10 A-21 F-19 Cs-134 < 2.6 < 1.9 < 2.0 2.2 (2.6) Cs-137 < 3.9 4.2 (3.4) < 2.5 < 2.7 3; Zr-95 < 6.0 < 4.4 < 4.6 < 5.1 Nb-95 < 2.3 2.0 (2.1) 3.6 (2.2) 3.8 (2.2) Co-58 < 2.5 < 1.9 < 1.9 < 2.0 Mn-54 3.5 (3.1)* < 2.0 < 2.0 < 2.1 Zn-65 < 6.7 < 4.8 < 4.7 < 5.1 Fe-59 < 6.1 < 4.6 < 4.9 < 5.2 Co-60 < 2.6 < 2.0 < 2.2 < 2.3 Ba-140 < 4.5 < 2.9 < 3.3 < 3.5 La-140 < 5.1 < 3.3 < 3.8 < 4.1
- 1.96o (Due to counting statistics.)
- .- . _=_ __-- . . . - - . . . , - - , - - _ - . . - _ _-
O O O-Table II.C.5 Radionuclide Concentrations in Surface Water. (pCi/Li Collection Date: August 8, 1987 Downstream Sites Upstream Sites Radionuclide . St. Vrain S. Platte St. Vrain S. Platte F-20 R-10 A-21 F-19 Cs-134 < 2.7 < 3.6 < 3.3 < 2.3 Cs-137 < 3.1 6.1 (6.4)* < 4.8 6.3 (4.0) Zr-95 < 6.6 8
< 7.9 < 7.2 < 5.4 Nb-95 < 2.4 < 3.4 < 2.9 < 2.0 Co-58 < 2.4 < 3.3 < 3.3 < 2.2 Mn-54 < 2.6 < 3.6 < 3.1 < 2.2 . Zn-65 < 6.5 < 8.2 - < 7.7 < 5.5 Fe-59 < 6.1 < 8.5 < 7.7 < 5.2 Co-60 < 2.8 < 3.8 < 3.2 < 2.4 Ba-140 < 4.2 < 5.1 < 4.7 < 3.3 La-140 < 4,8 < 5.9 < 5.4 < 3.8
- 1.960 (Due to counting statistics.)
0 0 6 loole II.C.5 Radionuclide Concentrations in Surface Water. (pCi/L) Collection Date: September 12, 1987 Downstream Sites Upstream Sites Radionuclide St. Vrain S. Platte St Vrain S. Platte R-10 F-20 A-21 F-19 Cs-134 < 3.7 < 2.5 < 2.1 3.9 (4.5) Cs-137 < 5.6 2.9 (3.5)* 4.0 (3.8) < 4.7 c) Zr-95 < 8.6 < 5.8 < 4.8] < 8.9 Nb-95 < 3.5 < 2.2 < 1.9 3.8 (4.1) Co 's 8 < 3.5 < 2.3 2.7 (2.5) 4.2 (4.3) Mn-54 < 3.8 < 2.4 < 2.1 < 3.8 , Zn-65 < 10. < 5.9 < 5.1 < 9.2 1 l Fe-59 < 8.4 < 6.0 < 5.2 e 8.7 Co-60 < 3.8 1, < 2.7 2.2 (2.1) < 4.0
?< ;40 < 6.6 < 4.1 < 3.3 < 6.1 La-140 < 7.6 < 4.5 < 3.7 < 7.1 o
- 1.9f o (Due to ccunting statistics.)
r,v >- - , ,
Table II.C.5 Radionuclide Concentrations in Surface Water. (pCi/L) ':ollection Date: October 10, 1987. Downstream Sites Upstream Sites Radionuclide St. Vrain S. Platte St. Vrain S. Platte F-20 R-10 A-21 F-19 Cs-134 < 2.5 < 1.7 < 3.3 < 2.2 Cs-137 5.3 (3.6) * < 2.0 7.8 (5.9) 4.3 (3.2) cn Zr-95 < 5.8 < 3.5 < 7.6 < 5.0 Nb-95 < 2.3 < 1.6 < 3.2 < 2.1 Co-58 < 2.3 < 1.6 < 3.1 < 2.2 Mn-54 < 2.5 < 1.7 < 3.3 < 2.2 Zn-65 < 5.8 < 4.0 < 8.0 < 5.3 Fe-59 < 6.0 < 4.2 < 8.0 < 5.0 Co-60 < 2.6 < 1.5 < 3.4 < 2.3 Ba-140 < 4.6 < 3.5 < 5.7 < 4.2 La-140 < 5.4 < 4.0 < 6.5 < 4.8
- 1,96 o (Due to counting statistics.)
7
(y ~\ ,,. U (V v Table II.C.5 Rad,f onuclide Concentrations in Surface Water. (pCi/L) Collection Date: November 14, 1987. Downstream Sites Upstream Sites Radionuclide St. Vrain S. Platte St. Vrain S. Platte F-20 R-10 A-21 F-19 Cs-134 < 2.5 < 3.4 < 3.3 < 2.7 Cs-137 < 3.8 < 5.1 < 6.0 3.5 (3.9) Zr-95 < 5.5 < 7.4 < 7.6 s 6.3 c; Nb-95 < 2.2 < 3.0 < 3.3 2.7 (3.0) Co-58 < 2.3 < 3.3 < 3.2 < 2.5 Pn-54 < 2.4 < 3.5 < 3.4 < 2.8 Zn-65 < 6.1 < 8.2 < 8.1 < 6.5 Fe-59 < 5.6 < 7.7 < 7.8 8.5 (7.9) Co-60 < 2.5 < 3.3 < 3.5 < 3.0 Ba-140 < 4.5 7.2 (7.3)* 7.4 (7.8) < 5.5 La-140 < 4.1 8.3 (8.4) 8.5 (8.9) < 6.3
- 1.960 (Due to counting statistics.)
.. - -.mm _ ._--m_...m --
. . . . - - .m. .-= .._m...m... -
O o. O Tat;e II.C.5 Radionuclide Concer.trations in Surface Water. (pCi/L) Collection Date: December 19, 1987. Downstream Sites Upstream Sites St. Vrain S. Platte St. Vrain S. Platte Padionuclide A-21 F-19 F-20 R-10
< 2.4 < 3.8 < 3.6 Cs-134 < 2.2
< 2.9 < 4.6 < 5.4 Cs-137 4.9 (4.0)*
< 5.6 < 8.9 < 8.0 m Zr-95 < 4.9 s
< 2.2 < 3.4 < 3.3 Nb-95 < 2.1
< 2.2 < 3.5 < 3.4 Co-58 : 2.1 2.9 (2.8) < 3.7 < 3.5 Mn-54 < 2.2
< 5.8 < 8.8 < 8.7 Zn-65 < 5.6
< 5.1 < 5.4 < 8.8 7.9 (9.6)
Fe-59
< 2.5 < 4.0 < 3.7 Co-60 < 2.2
< 3.9 < 6.1 < 5.3 Ba-140 < 3.2
< 4.5 < 7.0 < 6.0 La-140 < 3.7
- 1.96 o (Due to counting statistics.)
O O O + Table II.C.6. Radionuclide Concentrations in Monthly Composites of Surface Water A-25. (pCi/L). Collection Year: 1987 Radionuclide January February March April May June Cs-134 < 2.0 < 2.4 < 2.5 < 2.3 < 1.6 < 2.4 Cs-137 < 2.4 8.0 (3.5)* < 2.9 < 3.4 < 2.4 < 2.9 Zr-95 < 5.8 < 5.4 < 5.7 < 5.1 < 3.5 < 5.6 Nb-95 < 1.7 < 2.4 < 2.4 3.6 (2.8) < 1.7 2.7 (3.0) ,, , u, Co-58 < 1.8 < 2.2 < 2.3 < 2.5 < 1.5 < 2.2 Mn-54 2.5 (2.4)* < 2.4 < 2.4 < 2.3 < 1.6 4.8 (3.6)- 2n-65 5.3 (5.7) < 5.5 < 5.6 5.4 (6.6) 9.4 (4.6) < 5.6 Fe-59 < 4.8 < 5.4 < 5.6 < 6.6 < 5.0 < 5.5 Co-60 < 2.2 < 2.5 < 2.6 < 2.3 < 1.6 < 2.5 Ba-140 < 3.3 < 4.0 < 3.9 < 3.4 < 2.3 < 3.8 , La-140 < 3.8 < 4.6 < 4.5 < 3.9 < 2.7 < 4.4 H-3 3700 (320) 3000 (310) 6000 (340) 1500 (290) 18000 (450) 13000 (400)
- 1.960 (Due to counting statistics.)
- , , , _, - , , - - - - , --,-- ,-, , ,, -,. ~ ,- -, , - . . - , - , ,
O O O Table II.C.6 Radionuclide Concentrations in Monthly Composites of Surface Water, A-25 (pC1/L). Collection Year: 1987 Radionuclide July August September October November December i Cs-134 < 2.3 < 1.7 < 2.2 < 1.8 < 2.2 < 2.3 Cs-137 3.6 (4.0)* < 2.1 2.7 (3.2) 2.8 (3.2) < 2.6 I < 2.8 Zr-95 < 5.0 < 4.0 < 5.2 < 4.0 < 5.7 < 5.2 Nb-95 < 2.2 < 1.7 < 2.0 < 1.6 < 1.9 < 2.0 Co-58 < 2.2 < 1.6 < 2.0 < 1.7 < 2.0 < 2.1 g; Mn-54 < 2.2 < 1.7 < 2.3 < 1.9 < 2.1 < 2.3 Zn-65 < 5.5 < 4.0 < 5.5 < 4.3 < 5.0 < 5.6 Fe-59 < 5.2 < 4.0 < 6.9 < 5.3 < 6.0 < 6.5 Co-60 < 2.3 < 1.8 < 2.4 < 1.9 < 2.3 < 2.5 Ba-140 < 3.3 < 6.4 < 3.6 < 2.7 < 3.5 < 3.6 La-140 < 3.8 < 7.3 < 4.1 < 3.1 < 4.0 < 4.2 H-3 11,000 (390) 3700 (317) 1300 (300) 2300 (310) 330 (280) 29000 (640)
- 1.96o (Due to counting statistics.)
= - _ . _ . . _ - . .-
J O O O Table II.C.7 Radionuclide Concentrations in Ground Water. (pCi/L) Collection year: 1987
- Radio- 1st Quarter I 2nd Quarter nuclide F-16 3rd Quarter 4th Quarter R-5 F-16 R-5 F-16 R-5 F-16 R-5 4
Cs-134 2.6 (2.9)* < 2.6 < 2.5 < 2.4 < 3.4 < 2.2 < 3.9 < 3.2
- Cs-137 4.3 (4.3) 3.9 (3.7) < 3.1 7.9 (4.2) < 5.2 < 3.3 8.4 (5.5) < 3.8 Zr-95 < 5.4 < 6.0 < 6.0 < 5.2 < 7.9 < 5.0 < 9.1 < 7.9 Nb-95 < 2.6 < 2.4 < 2.4 < 2.2 < 3.3 < 2.0 < 3.7 < 2.9 1
Co-58 < 2.3 < 2.3 < 2.4 < 2.3 < 3.3 < 2.1 < 3.8 < 2.9 i Mn-54 < 2.4 < 2.6 < 2.5 < 2.4 < 3.4 < 2.3 < 3.9 < 3.2 os
%J Zn-65 < 8.0 < 6.8 < 6.4 9.4 (7.9) < 9.7 < 5.6 L.0 (1.2) < 7.7 Fe-59 < 5.7 < 5.9 < 6.1 < 5.5 < 8.1 < 5.1 < 9.3 < 7.6 Co-60 2.7 (2.8) < 2.8 < 2.8 < 2.4 < 3.6 < 2.1 < 4.1 < 3.4 Ba-140 < 3.7 < 4.6 < 4.9 < 4.2 < 5.3 < 3.6 < 6.1 < 5.2 La-140 < 4.2 < 5.3 < 5.6 < 4.9 < 6.1 < 4.2 < 7.1 < 6.0 H-3 350 (280) < 230 < 230 < 230 < 230 < 230 -
< 230 < 300
- 1.96cr(Due to counting statistics.)
68 O Table II.C.8 Maximum Permissible Concentrations in Drinking Water. (10CFR20, Appendix B, Table II) H-3 3 x 106 pCi/L I-131 3 x 102 pCi/L Cs-134 9 x 103pC1/L Cs-137 2 x 104pCf/L Zr-95 6 x 104 pCi/L Nb-95 1 x 105 pCi/L 1 x 105pC1/L Q Co-58 Mn-54 1 x 105pCf/L j Zn-65 1 x 105 pCi/L l Fe-59 6 x 104pC1/L j l Co-60 5 x 104 pCi/L Ba-140 3 x 104 pCi/L 1 l 4 La-140 2 x 10 pCi/L O t _ - - -_
1 69 i l l II.C. Hilk l The dairy food chain is the critical pathway for possible radiation , dose commitment around any nuclear facility. The critical individual would be an infant consuming milk produced from cows grazing local pastures. Hilk is the critical pathway for possible dose commitment to humans from environmental contamination of H-3, I-131, Cs-137 and Sr-90. For this reason milk is sampled extensively to document the presence or absence of radioactivity due to reactor operationc. There are no dairies (or personal milk cows) in the facility area, 1.6 km radius. The six dairies in the adjacent area, 1.6-8 km radium, were selected as they are located in the highest X/Q areas (refer to updated FSAR). The description of these locations can be found in Table III.B.1 and Figure III.B.2. The single reference location dairy, R-8, is 22.5 km West of the reactor in the least predominant wind direction. O Herd management practices are virtually identical at all dairy locations. The cows are rarely, if ever, out on pasture and under dry-lot man &gement typical of Eastern Colorado. Table II.D.1 lists the concentrations of all radionuclides that are investigated in milk samples. During 1987, elevated concentrations of I-131 were again consistently observed at site A-22. The source of this I-131 is from nuclear medicine used in the Denver hospitals. The t release enters the S. Platte River just North of Denver. A-22 dairy uses irrigation ditch water for its herd rather than well water. The ditch (Independence) receives S. Platte water upstream of FSV. This observation was first made in 1985 and discussed at length in the 1985 REMD sumary report. O !
70 Figure !!.0.1 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 and June of 1986 is of course due to Chernobyl fallout, but all other peaks are due to hospital use in Denver. Currently, we have initiated a study to investigate this observation in greater detail. A continuous water sampler is in place at the Henderson River gauging station and milk from dairies on the Platte River north of Denver will be sampled when the irrigation season starts. K-natural, as measured by K-40, is very constant in milk. The mean literature value is 1.5 g/L. K concentrations are homeostatically controlled and independent of K intake. K-nat is measured in all milk samples as a quality control measure for the other radionuclides determined in the same sample by gama-ray spectrometry, but K-nat concentrations are no longer reported in Table 11.0.1. Elevated tritium concentrations in milk due to reactor effluents have never been observed in the post-operational period of the reactor. This implies the tritium from reactor effluents 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 I milk. Contamination of milk samples by any radionuclide due to reactor
- effluents has never been observed during the operational per iods of Fort St. Vrain.
O
~
O O O i Table II.D.1 Radionuclide Concentrations in Milk. (pCi/L) Collection Year: 1987 Radionuclide A-6 A-18 A-22 A-23 A-24 A-26 R-8 Collection Date Jan 3 Jan 31 Jan 16 Jan 10 Jan 24 Jan 16 Jan 3 l I-131 < 0.21 < 0.38 < 0.36 0.56 (0.53) < 0.37 < 0.40 < 0.30 Cs-134 < 2.9 < 2.6 < 2.3 < 3.8 3.0 (2.8) < 2.9_ 5.0 (3.6) Cs-137 9.2 (5.2)* < 3.2 4.8 (3.9) < 4.4 6.2 (4.2) 7.0 (4.2) 14 (4.4) Ba-140 < 4.2 < 4.1 < 3.3 < 6.1 < 4.0 < 4.7 < 4.7 La-140 < 4.8 < 4.7 < 3.8 < 7.0 < 4.6 < 5.4 < 5.4 H-3 < 230 < 230 < 240 390 (280) < 230 < 240 < 230
)
Collection Date Feb 7 Feb 28 Feb 28 Feb 14 Feb ?0 Feb 28 Feb 7 I-131 < 0.19 < 0.29 < 0.27 < 0.39 < 0.20 < 0.35 < 0.27 Cs-134 < 2.4 < 2.6 2.6 (2.8) 4.2 (3.0) < 3.1 4.8 (2.9) < 2.4 Cs-137 4.3 (4.1) < 3.1 4.3 (4.1) 6.9 (3.8) < 3.7 18 (4.4) < 3.5 Ba-140 < 3.7 < 4.1 < 3.9 < 4.2 < 6.4 < 3.8 < 4.5 La-140 < 4.3 < 4.7 < 4.5 < 4.8 < 7.4 < 4.4 < 5.2 H-3 < 230 230 (280) < 230 < 240 < 230 < 230 < 230 1 Collection Date Mar 21 Mar 21 Mar 28 Mar 6 Mar 14 Mar 28 Mar 6 i I-131 < 0.36 < 0.34 < 0.40 < 0.41 < 0.30 < 0.29 < 0.50 1 Cs-134 < 2.3 < 2.6 < 2.0 < 2.3 < 2.6 4.4~(2.9) < 2.6 Cs-137 4.6 (4.1) < 3.1 5.4 (3.4) 5.6 (4.2) < 3.1 12 (4.4) 4.8 (3.7) I Ba-140 < 3.3 < 4.5 < 2.8 < 3.3 < 4.2 < 3.5 < 4.8
- La-140 < 3.8 < 5.2 < 3.2 < 3.8 < 4.8 < 4.0 < 5.5 j H-3 < 230 290 (280) < 230 < 2'O < 230 < 230' < 230 l ,
$
- 1.96 o (Due to counting statistics.)
l
O O (pCi/L) O Table II.D.1 Radionuclide Concentrations in inik.
-l Collection Year: 1987 Radionuclide A-6 A-18 A-22 A-23 A-24 A-26 R-8 Collection Date Apr 4 Apr 24 Apr 18 Apr 11 Apr 24 Apr 24 Apr 4 I-131 < 0.28 0.45 (0.35)* 2.1 (0.56) < 0.39 < 0.22 < 0.29 < 0.18 Cs-134 < 2.5 < 3.0 < 2.3 4.2 (2.9) < 2.4 3.0 (3.5) < 2.3 Cs-137 < 3.1 < 3.7 5.9 (4.1) 15 (4.3) < 3.5 12 (5.3) 5.9 (4.1)
Ba-140 < 4.5 < 4.9 < 3.7 < 3.4 < 3.9 < 4.0 < 3.4 La-140 < 5.2 < 5.7 < 4.3 < 3.9 < 4.5 < 4.6 < 3.9 H-3 < 240 < 240 < 230 < 230 < 240 < 240 < 240 Collection Date May 9 May 1 May 9 May 9 May 9 May 9 May 1 I-131 0.58 (0.47' < 0.47 0.68 (0.46) < 0.36 < 0.27 < 0.22 < 0.41 Cs-134 < 2.8 < 2.6 < 1. 5 < 3.0 3.5 (3.5) 3.8 (3.3) < 2.5 Cs-137 < 3.4 5.2 (3.8) < 2.3 < 3.6 < 3.6 20 (5.0) < 3.1 , Ba-140 < 4.4 < 4.8 4.5 (3.5) < 6.9 < 5.6 < 4.3 < 4.0 La-140 < 5.1 < 5.6 5.1 (4.0) < 7.9 < 6.5 < 5.0 < 4.6 H-3 < 230 < 230 340 (280) < 230 < 230 < 230 < 230 Collection Date May 16 May 16 May 23 May 29 May 29 May 23 May 16 I-131 < 0.27 < 0.42 < 0.32 < 0.39 < 0.28 < c.27 < 0.34 Cs-134 < 2.8 3.7 (4.5) 3.7 (3.7) < 2.2 < 3.7 6.8 (3.2) < 2.7 Cs-137 6.1 (4.1) < 4.5 6.4 (4.5) 5.4 (4.0) < 4.4 14 (4.0) 9.6 (4.8) Ba-140 < 4.6 < 5.9 < 5.7 < 4.4 < 5.9 < 5.1 < 3.9 La-140 < 5.4 < 6.8 < 6.5 < 5.1 < 6.8 < 5.8 < 4.4 H-3 < 230 < 230 < 230 < 230 < 230 < 230 < 230
- 1.36 o (Due to counting statistics.)
O O O Table II.D.1 Radionuclide Concentrations in Milk. (pCi/L) Collection Year: 1987 Radionuclide A-6 A-18 A-22 A-23 A-24 A-26 R-8 Collection Date Jun 12 Jun 6 Jun 6 Jun 6 Jun 12 Jun 12 Jun 6 I-131 < 0.37 < 0.36 2.4 (0.35) * < 0.25 < 0.32 < 0.42 < 0.33 Cs-134 < 3.3 < 2.7 < 2.4 4.7 (3.5) < 3.5 < 2.6 2.9 (2.3) Cs-137 < 4.8 < 3.9 7.7 (4.1) 9.5 (4.3) 4.9 (5.1) 6.5 (3.8) < 2.3 Ba-140 < 6.6 < 3.8 < 3.5 < 4.5 < 7.9 < 4.5 < 4.3 La-140 < 7.6 < 4.3 < 4.0 < 5.2 < 9.1 < 5.2 < 5.0 H-3 < 230 < 230 < 230 < 230 < 230 < 230 < 230 Collection Date Jun 26 Jun 19 Jun 26 Jr:i 19 Jun 26 Jun 26 Jun 19 U I-131 < 0.46 < 0.25 < 0.38 < 0.27 < 0.27 < 0.37 < 0.31 Cs-134 < 3.0 < 2.4 < 2.8 3.4 (3.0) < 3.1 < 3.9 < 2.4 Cs-137 < 4.4 3.8 (4.2) < 4.1 < 3.1 < 3.7 6.8 (5.7) < 2.9 Ba-140 < 6.2 < 3.5 < 4.1 < 4.1 < 4.9 < 6.2 < 5.2 La-140 < 7.1 < 4.0 < 4.8 < 4.7 < 5.7 < 7.2 < 6.0 H-3 < 230 < 230 < 230 < 230 < 230 < 230 < 230 Collection Date Jul 3 Jul 3 Jul 3 Jul 3 Jul 10 Jul 10 Jul 3 I-131 < 0.33 < 0.20 < 0.44 < 0.40 4.7 (4.2) < 0.28 < 0.35 Cs-134 < 2.6 < 2.5 < 2.7 < 2.4 < 3.1 < 3.5 2.9 (3.2) Cs-137 < 3.8 < 3.0 < 3.2 6.2 (4.2) < 3.7 < 5.1 < 3.3 Ba-140 < 3.7 < 4.9 < 5.5 < 4.9 < 5.0 < 4.8 < 4.2 La-140 < 4.3 < 5.6 < 6.3 < 5.6 < 5.7 < 5.5 < 4.8 H-3 < 230 230 (280) < 230 < 230 < 230 < 230 380 (280)
- 1.96 o (Due to counting statistics.)
__ ___ __ _ __ _ _ - . _ _ . --- ~. . _ _ - . _ _ . -_ _. - -_ . O O O~ Table II.D.1 Radionuclide Concentrations in Milk. (pCi/L) Collection Year: 1987 I Radionuclide A-6 A-18 A-22 A-23 A-24 A-26 R-8 Collection Date Jul 17 Jul 17 Jul 17 Jul 17 Jul 25 Jul 25 Jul 25 I-131 < 0.25 < 0.32 5.5 (4.0) < 0.69 < 0.43 < 0.46 < 0.41 Cs-134 < 2.3 < 2.5 < 2.5 < 2.2 < 2.9 < 3.9 < 2.5 Cs-137 < 3.4 < 3.1 4.6 (4.3) 4.3 (3.9) < 3.6 < 5.8 4.2 (3.6) Bc-140 < 4.1 < 4.0 < 4.0 5.9 (5.4) < 5.2 < 6.6 < 3.9 La-140 < 4.7 < 4.5 < 4.6 6.8 (6.2) < 5.9 < 7.5 < 4.5 H-3 < 230 < 230 < 230 < 2?0 < 230 < 230 < 230 Collection Date Aug 1 Aug 1 Aug 1 Aug 1 Aug 8 Aug 8 Aug 8 ]
; 2d
! I-131 < .34 < 0.21 3.2 (0.35) < 0.20 < 0.27 < 0.32 < 0.36 i Cs-134 < 2.8 < 2.7 < 2.5 < 3.1 < 3.8 < 1.4 < 3.9 1 Cs-137 < 3.3 < 5.4 6.0 (4.3) < 3.9 < 4.4 < 3.5 5.2 (5.5) 1 Ba-140 < 4.4 < 4.1 < 3.7 < 6.2 < 5.8 < 3.1 < 6.3 La-140 < 5.1 < 4.7 < 4.3 < 7.2 < 6.6 < 3.5 < 7.2 H-3 < 230 < 230 < 230 < 230 < 230 < 230 < 230 Collection Date Aug 15 Aug 15 Aug 15 Aug 15 Aug 22 Aug 22 Aug 22 i I-131 < 0.34 < 0.40 0.72 (0.47)* < 0.22 < 0.3 < 1.7- < 0.28 Cs-134 < 2.6 < 1.6 < 2.3 3.4 (2.6) < 3.0 < 1.8 < 1.8 i Cs-137 < 3.4 < 1.9 < 3.5 < 2.6 3.9 (4.2) 2.2 (2.5) 4.1 (2.6) Ba-140 < 5.0 < 2.5 < 3.5 < 3.4 < 5.2 < 3.1 < 3.0 i La-140 < 5.7 < 2.8 < 4.0 < 3.9 < 6.0 < 3.5 < 3.4 ! H-3 < 230 < 230 < 230 < 230 < 230 < 230 < 230 I j
- 1.96 o (Due to counting statistics.)
___ . . . _ _ _ ._ . . _ _ _ _ - . _ . _ - _ - _ _ .._-- __ _ _ - . - ~
O O O Table II.D.1 Radionuclide Concentrations in Milk. (pCi/L) Collection Year: 1987 Radionuclide A-6 A-18 A-22 A-23 A-24 A-26 R-8 Collection Date Sept 12 Sept 5 Sept 12 Sept 5 Sept 12 Sept 12 Sept 12 I-131 < 0.21 < 0.5 < 0.74 < 3.3 < 0.29 0.30 (0.31) < 4.0 Cs-134 < 1.2 < 2.9 < 2.5 < 4.1 1.7 (1.9) < 1.7 < 2 . "- Cs-137 2.3 (1.8)* < 3.2 < 3.0 < 4.9 < 1.9 2.0 (2.3) 5.2 (2.5) Ba-140 < 2.0 < 5.5 < 4.0 < 6.4 < 3.2 < 3.1 < 3.8 La-140 < 2.3 < 6.3 < 4.5 < 7.3 < 3.7 < 3.6 < 4.3 H-3 < 232 < 228 < 232 < 228 < 230 < 232 < 228 Collection Date Sept 26 Sept 19 Sept 26 Sept 26 Sept 26 Sept 26 Sept 19
~
m I-131 < .46 < .17 4.2 (0.52) < 1.9 < 0.23 < 0.27 < .18 Cs-134 < 2.7 < 1.5 < 2.7 < 2.1 < 1.9 < 1.4 < 2.1 Cs-137 < 3.9 3.9 (2.0) < 3.3 < 2.6 < 2.3 < 1.8 < 2.6 Ba-140 < 4.0 < 2.3 < 4.2 < 4.7 < 3.0 < 2.2 < 3.9 La-140 < 4.6 < 2.6 < 4.9 < 5.4 < 3.5 < 2.5 < 4.5 H-3 Collection Date I-131 Cs-134 Cs-137 Ba-140 La-140
- 1.96o (Due to counting statistics..
O O O Table II.D.1 Radionuclide Condentrations in Milk. Ipti/L) Collection Year: 1987. Radionuclide 4 A-b A-18 A-ZZ. A-23 A-24 A-26 i R-8 . I 1 i Collection Date: Oct 31 Oct 3 Oct 31 Oct 31 Oct 10 Oct 10 ; Oct 3 l I-131 < 0.32 < 0.33 < 0.35 < 0.30 < 0.Z3 0.Il (0.42) < 0.21 Cs-134 < 2.2 < 1.9 , < 2.1 < 2.2 < 3.5 < 1.9 < 1.5 Cs-137 < 2.5 < 2.1 '2.9 (2.9)* < 2.5 < 4.9 < 2.1 < 1.8 Ba-140 < 3.3 < 3.2 >
< 3.1 < 3.3' < 6.1 < 3.5 < 2.5 La-140 < 3.8 < 3.7 i < 3.6 < 3.8 < 7.0 < 4.1 < 2.8 H-3 < 230 < 230 < 290 < 240 < 230 250 (270) < 230 i
Collection Date: Nov 6 Nov 21 l Nov 21 Nov 21 Nov 14 Nov 14 , Nov 21 I-131 < 0.49 < 0.31 i < 0.42 < 0.Z3 < 0. " < 0.39 < Z.6 Cs-134 < 3.3 < 1.4 ! < 1.7 < 1.8 < 2. < 2.5 < 1.6 ~4 Cs-137 < 4.8 < 1.7 2.36 (2.3) < 1.9 < 2., 3.1 (3.5) < 2.0 Ba-140 < 5.1 3.6 (3.9) < 2.7 < 3.6 < 4.4 < 4.6 < 2.7 La-140 < 5.9 4.2 (4.5) < 3.1 < 4.2 < 5.1 < 5.2 < 3.1 H-3 < 230 < 230 < 230 < 230 < 230 < 230 < 230 i Collection Date: Dec 12 ~~~Dec 5 Dec 5 Dec 5 Dec 12 Dec 12 Dec 5 I-131 < 0.3/ < 0.33 < 0.49 < 0.34 < 0.30 < 0.33 < 0.Z8 Cs-134 < 2.8 < 2.4 < 2.6 < 2.3 < 2.4 < 1.5 < 2.2 Cs-137 4.4 (4.8) < 3.5 6.5 (3.8) < 2.7 < 3.5 < 1.8 3.3 (3.2) Ba-140 6,0 (5.8) < 3.5 < 4.6 < 4.1 < 3.8 < 2.4 < 4.1 La-140 6.9 (6.7) < 4.0 < 5.3 < 4.7 < 4.3 < 2.7 < 4.7 H-3 < 290 < 230 < 230 < 230 < 230 < 230 < 230 1
- 1.96o (Due to counting statistics.)
q 77 Figure II,0,1 (]) I 131 Concentrations in Milk at Site A-22 SC 30 - 70 - 60 - 50 -
.:0 -
/
ao - 20 - 10 - 9.0 - 8.0 - 7.0 - 6.0 - " ' 5.0 - (J' g 4.0 - 2 3 r 0 3.0 - S
)
2.0 - f , 10 - 09 - 1 ' 1 08 - , 0.7 - 0.6 - o.5 - I *~ - : : -- = * ' " MDC 0 4 o.3 - 0.2 - m..-
,,,,,,,i,,,,,,,,,,,t ,,,,,,,,,,,
g, M S N S N J M M J S N J M J J M M J 1985 1986 1987
M 78 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 fitrm pond. The locations of these food product collection sites are described in Table 111.B.1. One sample of each principal class of food products was collected from these locations. Locations and available produce often change due to owner needs, harvest time, harvest size, etc. Each sample is homogenized without drying immediately af ter collection. The sample is then counted by gamma-ray spectroscopy. Table II.E.1 lists the results for the 1987 harvest. No significant activity of any of the principal radionuclides was observed. The gamma-ray spectra were scanned for other radionuclides, but only the O naturally occurring were observed, presumably due to surface soil deposits. O
79 O i d Table II.E.1 Radionuclide Concentrations in Food Products (pCi/kg). Collection Date: September 10, 1987 Location Food Type I-131 Cs-134 Cs-137 R-13 Corn < 2.5 < 2.6 3.3 (3.7)* R-13 Carrots < 8.9 < 5.1 6.9 (7.9) A-30 Zucchini < 2.9 < 3.1 < 3.5 A-29 Cucumber < 9.4 < 9.6 < 13 A-27 Zucchini < 1.1 11 (12) 13 (14) O A-31 Cabbage < 9.9 < 9.4 < 14 l A-31 Brocolli < 20 < 19 < 22 A-9 Watermelon < 2.5 < 2.3 4.4 (4.1) R-13 Tomato < 2.2 < 2.3 4.5 (3.1) { A-23 Cucumber < 2.1 < 1.9 2.9 (2.7) A-31 Cauliflower 3.7 (3.4) < 2.8 7.9 (4.8) l R-13 Turnips 5.8 (6.3) < 3.6 <4.5 I l
- 1.960 (Due to counting statistics.)
1 1 O
80 l II.F. Aquatic Pathways ! Table II.F.1 shows radionuclide concentrations measured in fish samples collected at F-19, A-25 and R-10 on two dates in 1987. The fish were collected by netting and the composite sample was homogenized without cleaning and analyzed on a wet weight basis. The occasional positive values are considered to be methodological fluctuation (false positives). During the second half of 1987 fish collection efforts at R-10 were unsuccessful. Repeated sampling was conducted but no fish f could be collected before the ice set in. Since no detectab M activity was observed in fish at A-25, in the effluent pathway, it can be concluded that no activity could be present further downstream. Collection problems have been remedied for 1988. Table II.F.2 shows the measured concentrations of both Cs-137 and Cs-134 in surf ace sediment collected at R-10, the downstream location. O There was measurable activity of radiocesium clearly due to the l l Chernobyl fallout. The cesium ions are bound nearly irreversibly by the clay mineral matrix in the sediment. Monitoring for Corbicula Fluminea, a species of freshwater clam, was conducted at all fish sampling sites. These monitoring dates coincided with the fish collection dates. Corbicula have been introduced to North America from Asia. The freshwater clams are now found in large river systems in the U.S. from coast to coast. The Colorado Division of Wildlife has stated that Corbicula have been found in Northern Colorado at Boyd Lake, some 30 miles from the Fort St. Vrain Nuclear Generating Station. However, to this date, our samplings have indicated no evide.1ce of Corbicula in any cf the sampling sites of the reactor ;urface water courses.
O O O Table II.F.1 Radionuclide Concentrations in Fish. (pCi/L), 1987. Collection Date: First Half Second Half Radionuclide Upstream Effluent Downstream Upstream Effluent Downstream F-19 A-25 R-10 F-19 A-25 R-10
< 4.3 < 4.8 < 7.4 < 7.0 **
Cs-134 < 4.2
< 5.4 < 8.6 < 8.2 **
Cs-137 < 5.0 < 5.2
< 4.0 < 4.2 < 16 < 6.5 **
Co-58 < 3.9 m
~~
< 4.2 < 4.2 < 4.6 < 7.3 < 6.7 **
Mn-54
< 12 < 2.4 < 17 **
Zn-65 < 11 12 (13)
< 7.7 < 13 < 12 **
Fe-59 < 6.8 13 (13)*
< 4.5 < 4.6 < 5.1 < 8.2 < 7.4 **
Co-60
- 1.96 o (Due to counting statistics.)
l
** Sample unavailable.
l o c" O 0 1 R n o i t f a l c a9 o H2 ) ) L 3 3 dt 1 1 m ns ( ( o ou r cg 5 0 f eu 1 3 SA 1 t n e i m d O S e n i s n o i t a ) r f . t l s n a1 ) ) c e H1 5 7 i c 2 2 t n tl ( ( s o si i C . rr 1 0 t 7 ip 4 3 a e8 FA 2 t d9 s i1 l g c , n u) i t nL o/ n ii u dC o ap c R( o t e e 2 d u i D l ( F. c I u I n 4 7 0 o 3 3 e i d 1 1 6 9 l b a s s a R C C 1 T O i l
83 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 intralaboratory quality assurance programs. The U.S. Environmental Protection Agency (EPA) sponsored laboratory intercomparison studies program is the principal crosscheck. This involves the analysis of a variety of environmental media containing various levels of radionuclides. The media, type of analysis and frequency of analysis for the EPA program are summarized below. I Medium Analysis (radionuclide) Frequency Water H-3 Triannually Water Gross beta, gross alpha Bimonthly O Weter Co-so. zn-es. Cs-134. Cs-137 Trieanueiiy Water I-131 Semiannually Air partic- Cs-137, gross beta, Semianr.u ally ulate filters gross alpha Milk I-l'31, Cs-137 Triannually For each radionuclide analysis of a particular medium, three independent measurements are performed and all results are reported to the EPA. Table II.G.1 gives the EPA crosscheck data for 1987. The EPA uses l the term, Estimated Laboratory Precision (ELP), calculated as one standard deviation for one determination. The normalized deviation of our mean from the known is calculated as: O i
84 CSU mean value - EPA known value 0 ofii f Where: o = standard ueviation of the mean of all participating laboratory results [ n = number of analyses by our laboratory, normally n=3 The control limit is determined by the mean range of all results t 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 1987 all results except 10 were within the warning level. The results exceeding the warning level have the notation (n) in Table II.G.I. The corrected values are shown in the table. The recheck process and conclusion are given below for these samples. , 1. A recalibration resulted in revised counting yields that i produced acceptable accuracy.
- i
- 2. One result of the three determinations was concluded to be an "outlier" (systematic error) and omitted. I
- 3. Dilution procedures were improperly conducted.
Table II.G.2 lists independent results for H-3 in water samples split between this laboratory and the Colorado Department of health, Radiation Control Division and the laboratory at the Fort St. Vrain Generating Station. The comparison between laboratories was acceptable. Table II.G.3 lists the results of gross beta analyses of the split water samples. Currently, procedural differences between the laboratories are being investigated for the discrepancy. O
85 i ; Table II.G.4 shows results of an intralaboratory crosscheck ' i program. Replicate samples are independently analyzed. The replicate ; results are not statistically different and imply that the precision of the methods is acceptable, i
! I t
i i i t' [ r i i O , I, 1 l O ~ i i )
~.__._._,._._-...__..--..____-,_x.__.. . - . , . _ . . . _ . . . _ _ _ _ _ _ _ _ . , _ _ _ _ , . _ - _ _ . , _ , _ . . , , . _
86 Table II.G.1 EPA Cross-Check Data Sumary. 1987 Radio CSU EPA 1 E.L.P.* Normalized Deviation Date nuclide Yalue Value from known** WATER TRITIUM Feb 13 H-3 3800 4209 421 - 1.40 Jun 12 H-3 2700 2895 357 - 1.10 Oct 16 H-31 4194 4492 449 - 1.15 WATER Jan 23 alphal 13 11 5 + 0.46 beta 1 9 10 5 - 0.34 Mar 20 alpha 2 7 3 5 + 1.03 beta 2 11 13 5 - 0.86 May 22 alpha 3 11 6 - 2.88 beta 7 7 5 0.0 Jul 24 alpha 4 5 5 - 0.23 beta 5 5 5 0.0 O Sep 18 alpha beta 3 11 4 12 5 5
- 0.23
- 0.35 Nov 20 alpha 5 7 5 - 0.69 beta 16 19 5 - 0.92 WATER l-131 Apr 9 I-131 7.67 7 0.70 + 1.65 Aug 7 I-131 53 48 6 + 1.44 Dec 4 I-131 25 26 6 - 0.38 PERFORMANCE Oct 21 alpha 21 28 7 - 1.73 beta 66 72 5 - 2.19 Co-60 17 16 5 + 0.35 Cs-134 15 16 5 - 0.46 Cs-137 28 24 5 + 1,39
- E.L.P. = Expected laboratory precision.
** Norralized deviation = (CSU mean - EPA known)/(o //N), if this value falls between upper A lower warning levels, the accuracy is e.cceptabl9.
b 87 Table II.G.1 EPA Cross-Check Data Summary. 1987. llh Radio CSU EPA 1 E.L.P.* Normalized Deviation Date nuclide Value Yalue from known** WATER Feb 6 Co-60 3 395 50 5 Zn-65 3 682 91 5 Ru-106 3 622 100 5 ' Cs-134 3 429 59 5 Cs-137 3 646 87 5 Jun 5 Cr-51 39 41 5 - 0.81 Co-60 63 64 5 - 0.46 Zn-65 11 10 5 + 0.23 Ru-106 71 75 5 - 1.38 Cs-134 35 40 5 - 1.73 Cs-137 92 80 5 + 4.27 Oct 9 Cr-51 63 70 5 - 2.31 Co-60 14 15 5 - 0.46 Zn-65 37 46 5 - 3.00 Ru-106 49 61 5 - 4.27 Cs-134 23 25 5 - 0.81 Cs-137 51 51 5 - 0.12 O MILK Feb 27 I-131 9 9 0.90 + 0.00 Jun 26 I-131 62 59 6 + 0.96 Cs-137 71 74 5 - 1.15 K 1653 1525 76 + 2.92 AIR FILTER Ap r 10 Alpha 12 14 5 - 0.58 Beta 44 43 5 + 0.46 Cs-137 10 8 5 + 0.69 Aug 28 Alpha 8 10 5 - 0.69 Beta 29 30 5 - 0.35 Cs-137 13 10 5 + 1.15
- E.L.P. 2 Expected laboratory precision.
** Normalized deviation = (CSU mean - EPA known)/( o //N), if this value falls between upper & lower warning levels, the accuracy is acceptable.
88 o U Table II.G.2 Tritium Crosscheck Analyses on Split Water Samples Determined by Colorado State University, Colorado Department of Health, and Public Service Company. 1987 Collection Sample Tritium Concentrations pCi/L Date Location CSU CDH PSC Jan 10 A-25 330 (280) 816 (181) 875 (430) Jan 10 A-21 < 240 < 350 < 347 Jan 5 E-41 < 240 < 350 < 347 Feb 14 A-25 800 (360) 691 (186) 1450 (423) Feb 14 A-21 < 240 < 350 s 596 (410) Feb 2 E-41 < 240 355 (182) 833 (414) Mar 14 A-25 8600 (370) 9814 (269) 9510 (544) Mar 14 A-21 < 230 < 350 < 346 Mar 16 E-41 < 230 < 350 < 346 Apr 11 A-25 2000 (303) 2005 (196) 2590 (443) Apr 11 A-21 < 240 < 350 < 337 Apr 6 E-41 260 (280) < 350 < 337 O May 16 A-25 7900 (360) 7674 (244) 7970 (522) May 16 A-21 < 270 < 350 < 337 May 11 E-41 260 (280) < 350 < 344 Jun 12 A-25 10,000 (380)
- 12,000 (575)
Jun 12 A-21 < 270 * < 349 Jun 8 E-41 < 270 * < 349
- Data not received from Colorado Department of Health.
d \ l i t _ _ _ _ _ _
. ~
89 O Table II.G.2 Tritium Crosscheck Analyses on Split Water Samples Determined by Colorado State University, Colorado Department of Health, and Public Service Company. 1987 Collection Sample Tritium Concentrations pCi/L Date Location CSU CDH PSC Jul 10 A-25 24,000 (500) 18,789 (341) 26,000 (712) Jul 10 A-21 < 230 154 (178) 508 (409) Jul 6 E-41 < 230 342 (180) 377 (407) Aug 8 A-25 5600 (340) 6,226 (229) 5980 (488) Aug 8 A-21 < 230 234 (167) < 335 Aug 10 E-41 < 230 192 (166) < 335. Sep 12 A-25 1100 (290) 828 (175) 1160 (416) Sep 12 A-21 < 230 313 (169) < 332 Sep 7 E-41 1200 (290) 1,738 (186) 958 (413) Oct 10 A-25 4300 (300) 318 (170) 3300 (456) Oct 10 A-21 < 230 -12 (167) < 339 Oct 5 E-41 44000 (610) 40,839 (462) 43100 (852) Nov 14 A-25 390 (280) 537 (172) 985 (419) Nov 14 A-21 < 230 87 (167) 584 (413) Nov 2 E-41 < 230 104 (167) < 346 Dec 19 A-25 21000 (590) 28,208 (393) 29700 (752) Dec 19 A-21 < 410 303 (170) < 341 Dec 7 E-41 940 (430) -43 (166) < 341 0
90 Table II.G.3
. Gross Beta Crosscheck Analyses on Split Water Samples Determined by Colorado State University, Colorado Department of Health, and Public Service Company. 1987 Collection Sample Gross beta Concentrations pCi/L Date Location CSU CDH PSC Jan 10 A-25 7.4 (5.4) 13 (4) < G.54 Jan 10 A-21 7.8 (5.4) 7 (4) 10.20 (8.75)
Jan 5 E-41 11 (5.6) 10 (4) 12.90 '8.96) Feb 14 A-25 8.1 (5.4) 12 (4) .12.00 (9.37) Feb 14 A-21 1.7 (5.1) 9 (4) 8.92 (9.21) Feb 2 E-41 19 (5.9) 14 (4) 15.40 (9.76) Har 14 A-25 7.0 (5.3) 11 (4) 11.40 (8.33) Har 14 A-21 3.5 (5.2) 13 (4) 15.60 (8.84) Mar 16 E-41 5.6 (5.3) 16 (4) 13.10 (8.58) Apr 11 A-25 5.1 (5.3) 11 (4) Apr 11 18.30 (9.61) A-21 7.9 (5.4) 12 (4) 8.56 (8.79) Apr 6 E-41 4.0 (5.2) 10 (4) 19.10 (9.68) May 16 A-25 4.4 (5.2) 12 (4) May 16 8.71 (7.99) A-21 5.3 (5.2) <5 11.00 (8.13) May 11 E-41 4.8 (5.2) 7 (4) 9.78 (8.01) Jun 12 A-25 2.2 (5.0)
- 11.50 (9.37)
Jun 12 A-21 8.2 (5.3) *
< 6.97 Jun 8 E-41 < 4.1 *
< 6.89
- Data not received from Colorado Department of Health, s
O
., . _-_____--__-___--__]
l 91 ! O Table II.G.3
- Gross Beta Crosscheck Analyses on Split Water Samples Determined by !
Colorado State Univarsity, Colorado Department of Health, and ' Public Service Company. 1987 . i Collection Sample Gross beta Concentrations pCi/L - Location Date CSU CDH PSC Jul 10 A-25 3.8 (2.1) 6 (4) < 6.47
; Jul 10 A-21 6.3 (2.2) 11 (4) 16.10 (9.58) j Jul 6 E-41 3.9 (2.1) 15 (5) 13.30 (9.41)
Aug 8 A-25 11 (5.3) 13 (4) 11.60 (8459) , J Aug 8 A-21 12 (5.3) 3 (4) 17.40 (9.30) : Aug 10 E-41 6.0 (5.0) 11 (4) 13.90 (8.93) Sep 12 A-25 5.7 (5.1) 10 (4) 8.14 (8.21) Sep 12 A-21 5.3 (4.1) 9 (4) 11.10 (8.57) Sep 7 E-41 5.6 (5.1) 10 (4) 13.00 (8.63) Oct 10 A-25 11 (5.0) 14 (4) 10.70 (9.39) Oct 10 A-21 5.9 (5.1) 15 (4) 12.10 (9.60) Oct 5 E-41 36 (18) 14 (4) 13.80 (9.81) Nov 14 A-25 8.5 (5.3) 8 (4) < 6.39 l Nov 14 A-21 7.9 (5.2) 13 (4) 7.66 (8.47) ' Nov 2 E-41 11 (5.4) 8 (4) 19.90 (9.70) Dec 19 A-25 5.8 (5.1) 14 (4) 13.30 (8.84) -l Dec 19 A-21 11 (5.3) 10 (4) 11.80 (8.78) i l Dec 7 E-41 11 (5.3) 13 (4) 15.30 (9.01) t l t i k i !
- l l
i l 1 O l
O O O Table II.G.4 Intralabatory Crosheck Results, (pCi/L) 1987. Drinking Water (R-6) Radio- 1st '.)uarter 2nd Quarter 3rd Quarter 4th Quarter Nuclide Trial 1 Trial 2 Trial 1 Trial 2 Trial 1 Trial 2 Trial 1 Trial 2 Cs-134 < 2.6 2.8 (2.9) < 2.5 < 2.4 < 2.0 < 2.3 < 1.8 < 2.8 Cs-137 < 3.3 < 3.0 < 3.0 3.7 (3.4) < 2.4 3.6 (3.5) 4.9 (3.2) < 3.4 Zr-95 < 6.2 < 6.2 < 6.0 < 5.5 < 5.0 < 5.9 < 4.3 < 6.4 Nb-95 < 2.3 < 2.3 < 2.3 < 2.2 < 1.8 < 2.2 < 1.6 < 2.6 Co-58 < 2.4 < 2.3 < 2.3 < 2.2 < 1.8 < 2.3 < 1.7 < 2.9 Mn-54 < 2.7 < 2.4 < 2.4 < 2.4 < 2.0 3.1 (2.8) < 1.8 < 2.9 Zn-65 < 6.2 + < 5.8 < 5.7 < 5.3 < 4.7 < 5.6 < 4.4 < 6.6 Fe-59 < 6.2 < 6.4 < 5.8 < 5.6 < 5.2 < 6.0 < 4.5 < 6.8 Co-60 < 2.8 < 2.6 < 2.6 < 2.6 < 2.1 < 2.6 < 1.8 < 3.0 Ba-140 < 4.3 < 4.0 < 3.9 < 6.0 < 3.2 < 3.8 < 4.3 < 4.5 X3 La-140 < 5.0 < 4.6 < 4.5 < 6.9 < 3.6 < 4.4 < C.0 < 5.2 Gross Beta 4.1 (2.2)*1.0 (2.1) 2.6 (2.2) 3.9 (2.2) 4.1 (2.1) 5.7 (2.1) 5.9 (2.3) 5.1 (2.2) H-3 < 240 < 230 < 230 < 230 < 230 < 230 < 230 < 230 Milk (A-23) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Trial 1 Trial 2 Trial 1 Trial 2 Trial 1 Trial 2 Trial 1 Trial 2 Cs-134 < 2.4 < 2.3 4.7 (3.5) < 2.7 < 4.1 < 1.8 < 3.9 < 2.8 Cs-137 6.8 (4.1)*5.6 (4.2) 9.5 (4.3) 8.6 (3.9) < 4.9 2.1 (2.6) < 5.7 < 2.7 En-140 < 3.4 < 3.3 < 4.5 6.2 (5.5) < 6.4 < 2.9 < 6.4 < 4.1 La-140 < 3.9 < 3.8 < 5.2 7.1 (6.3) < 7.3 < 3.3 < 7.4 < 4.7 h-3 < 240 < 230 < 230 < 230 < 230 < 230 < 230 < 230
- 1.96 o (Due to counting statistics.)
93 II.H. Summary cnd Conclusions Table II.H.1 summarizes the radiation and environmental radioactivity measurements conducted during 1987 in the environs of the Fort St. Vrain Nuclear Generating Station, owned and operated by Public Service Company of Colorado. The values for each sample type may be compared to pre-operational and operational periods for this reactor, as well as to the values from other U.S. reactor monitoring programs. It must be emphasized, however, that the mean values in Table II.H.1 are only the neans of the values greater than HDC, the statistically minimum detectable concentration. The range also is given only for detectable measurements. T5e mean and range values, therefore, are not the true means or ranges if any of the values in the sample population were less than MDC. The format of Table II.H.1 is a requirement of the NRC. Inspection of Table II.H.1 reveals that there we*e no individual O measurements except those due to release from Denver hospitals that exceeded the Reporting Level (RL) (see Table III.A.3). The Chernobyl fallout was observable in only a few sample types. For the category of gross beta concentrations in drir. king 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 activation product radionuclides measured were significantly higher in the Giltrest drinking water.
- b. Tritium concentrations measured at Gilcrest were statistically the same as those in Fort Collins. Tritium is the only significant radionuclide measured in the air or water effluent
r 94 from FSV. Since it is far more mobile than any of the specific radionuclides, if in the unlikely event that effluent activity were reaching the Gilcrest aquifer, elevated tritium concentrations would be the first and most sensitive indicator,
- c. The city of Gilcrest does not filter and treat its water to the same degree as Fort Collins. This has been verified and evidenced by the fact that the gama-ray spectra of the suspended solids from Gilcrest water samples show elevated natural radionuclides. It has been concluded in previous reports that the elevated gross beta concentrations in Gilcrest water are due to elevated concentrations of the naturally occurring U-238, end Th-232 decay products. The suspended solids are higher in Gilcrest water samples due to less filtration of the water.
For the category of tritium in surf ace water, as has been the case since reactor operation, elevated concentrations were noted at station A-25, the outlet of the (Goosequill) f arm pond. This, of course, is directly in the principal effluent route and should be expected. Elevated concentrations of tritium have never been observed, however, in any human food source in direct or indirect contact with the farm. pond ! water. Downstream surface water concentrations of tritium have occasionally been elevated, but there is significant dilution before any human use of this water. During 1987 elevated tritium concentrations were observed downstream on several occasions but the mean values for the first and second half of 1987 were not significantly greater than in upstream surface water. An historical summary of tritium concentration l in upstream, downstream and potable surface water for six month periods I l
t 95 i from 1974 to 1987 is depicted in Figure II.C.1. Tne potable water ' 4 concentrations plotted are those for the Gilcrest city water well. 1-131 was observed again in milk samples from Dairy A-22. Because che reactor did not release any significant fission products during 1987, the source of the I-131 concentrations in cilk could not be reactor effluent. It was noted 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, i therefore, the only likely source of the I-131 observed again in milk , samples during 1987. ! O Cs-137 and Cs-134 and other fission products were also observed in t many environmental samples due to the Chernobyl fallout. Table II.H.2 presents an additional summary of mean values for selected sample types. The sample types and radionuclides were chosen 1
! on the basis of their importance in documenting possible radiation dose to humans. Air and surface water would be the predominant environmental transport routes and drinking water and milk would be the predominant sources of radiation dose if significant radioactivity release from FSV !
occurred. Table II.H.2 also allows comparison to the three most recent : years of operation. l J The arithmetic means in Table II.H.2 were calculated for all sample results. It should be noted that the tabular data presented in the body of this report contain only positive calculated values. Any calculated
96 values less than zero or less than the minimum detectable concentration (HDC) are listed as less than the actual MDC for that sample analysis. , However, the actual result in all cases was used in the calculation for the arithmetic mean values for the period. Therefore, all values, negative as well as positive, were included. This procedure is now generally accepted and gives a proper estimate of the true mean value. Because of this procedure, however, the values listed in Table II.H.2 cannot be calculated directly from the tabular values in the report. It must be emphasized that wille 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 corcentrations of certain radionuclides. Therefore, to obtain the correct mean value from the O distribution of analytical results, all positive results must be averaged with all negative results. If the negative results were omitted, the resulting arithmetic mean would be falsely biased high. From log-normal analysis of each deta set for each 12 month period, the geometric mean and geametric standard deviations are also presented in Table II.H.2. The log-normal probability treatment is to plot all l data for ea:h sample type over the year on log-probit coordinates. The samples are ranked by increasing activity concentration and the
- cumulative percentage of rankings are plotted on the probit abcissa f
versus the activity concentration of the log ordinate. The geometric ; meanvalue,i,isdetermineddirectlyfromthe50thpercentilepoint. g The geometric standard deviation is simply the slope of the line which ) can be calculated from the ratio between 84.1 percentile point and the l 1
97 50th percentile. In a normal distribution, the arithmetic standard O V deviation 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 mean (Xg iog ). The area betweeng X multiplied by og and Xg divided by o g should contain 68% of the frequer.cy values. With the log-normal analysis, no bias results from using either actual values or less than MDC values in estimating the geometric mean. The geometric mean is identical to the median. From the values presented in Tables II.H.1 and II.H.2 and the tabular data of the report, the following observations and conclusions may be drawn:
- 1. Tritium was again the only radionuclide that was detected in i
significant concentrations in any of the effluent pathways that O could be attributed to reactor operation. Since the tritium is released as tritiated water, the dilution by the surrounding hydrosphere is great. Although in 1987 a few elevated levels 3 of tritiated water could be detected in downstream surf ace ; water samples, the mean values of downstream surface and Gilcrest drinking water were not statistically greater than upstream concentrations. The tritium concentrations measured 4 in milk produced by the nearest dairy herd were also all less than MDC.
- 2. Figure II.C.1 is a plot of tritium measured in surface water samples over the period 1974-1987. During the period the j l
i predominant source term is that of fallout deposition. There ] is some delay period in the peaks due to the mean residence
... 1, . . .. . . . . .
98 time of tritium in the hydrosphere and input from other areas. O Beginning in 1981, an increase can be' observed in the downstream locations relative to upstream. This small increase is statistically significant, however, the radiation dose comitment that can be calculated as a result of possible ingestion of this as drinking water was found to be negligible as compared to natural background radiation dose rates. This was discussed in the 1986 annual report.
- 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 st0tistics and methodological variation, but principally due to true environmental variation (of ten termed sampling error). It must be recognized and accounted for in analysis of any set of O environmental data before meaningful conclusions can be drawn.
- 4. The Chernobyl accident fallout has totally obscured what fission product debris has remained in the FSV environs from the October 1980 Chinese atmospheric nuclear weapon test. The biosphere will contain the Chernobyl fallout for an equally long period. Nuclear weapon test fallout has since the inception of the project been noted to be the predominant source term above ratural background. It is the variation in fallout deposition, in addition to the variation in naturally occurring radionuclides, that mandates the large number of environmental samples to detect any possible radioactivity due to reactor effluents. A simple comparison of pre-operational and operational values is of little value for most sample types
99 because the fallout deposition was considerably greater during the pre-operational period,
- 5. The prompt and sensitive detection of the Chinese weapon test and Chernobyl fallout iq the past assures that the environmental monitoring program is of adequate scope and j sensitivity to detect any accidental releases from the FSV reactor operation. It can be concluded from the data collected by the environmental monitoring program that the radiation dose 1
commitments calculated for the closest inhabitants or other parts of the nearby ecosystems due to current reactor effluents are negligible. Natural background radiation and the dose l l commitment from atmospheric fallout are the only known l l significant sources of radiation dose to the residents of the l g area. V l l 1 O l
O O O TARIX II.N.1 havironmental Radiological Homitoring Program hl Summary Fort St. Vrain Nuclear Generating Facility, Platteville, Colorado Medium or Pathway Type and Facility Adjacent Locations with Highest Reference Number of Sampled (Unit of Total Number Locations Locations Annual Mean Iocations Nonroutine. measurement) of Analysis Mean (f)b Mean (f)b Name Mean(f)b Mean (f)b Reported. Performed range range Distance & Range Range Measurements' Direction Direct Radiation TLD (164) 0.43(72/72) 0.44 (72/72) A-10 old FSV 0.52 (4/4) 0.43 (20/20) 0 (mR/ day) (0.36-0.52) (0.32-0.56) School 7.8 km (0.34-0.49) 215 Air, Particulates Gross S (354) 26.4(202/206) 27.0 (49/52) F-7 Inter- 28 (52/52) 25.1 (152/156) 0 fCi/m3 (4.0-62) (8.6-62) section of , CR21 & CR34 1.5 km 170 Gamma Spectrometry Cs-134 (28) <2.7 (0/16) R-4 Iongeont 1.6 (1/4) 1.6 (1/4) 0 Dairy store ~- 20.5 km 250 8 Cs-137 (28) 2.8 (3/16) F-7 Farm at 3.5 (1/4) 2.9 (1/4) 0 (2.2-3.5) intersection of CR21 & CR34 1.5 km 160 0 Air, Atmospheric H-3 (356) 450 (27/48) A-19 Hunting 466 (13/51) 354 (11/152) 0 w:ter vapor (1000-250) cabin (1000-270) (230-580) (pci/L) Goosequill 1.7 km 5 Air, Charcoal I-131 (357) 31 (5/205) R-3 CSU Dairy 42 (1/62) 24.?6/152) 0 3 (pCi/m ) (14-40) W. Drake Rd. ( 3.7-42 ) FtCollins 45 km 330* __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . ._-_. _ __. -_ . . - - ~ _ . - _ . _ . - _ _ . _ - _ _ . . . _ _ . . , _
O O O vam m II.N.1 havironmental Radiological Monitoring Program hl Ehmmmmary Fort St. Vrain Nuclear Generating Facility, Platteville, Colorado Medium or Pathway Type and Facility Adjacent Locations with Highest Reference Number of Sampled (Unit of Total Number Iocations Locations Annual Mean Locations Nonroutine measurement) of Analysis Mean (f)b Mean (f)b Name Mean(f)b Mean (f)b Reported Performed range range Distance & Range Range Measurements Direction Milk H-3 (119) 301 (7/102) A-23 Leroy 390 (1/17) 380 (1/17) 0 (230-390) Odenbaugh Dairy 4.1 km 90 Gamma Spectrometry I-131 (119) 2.0 (13/102) A-22 Percy 2.7 (7/17) < 0.40 (0.17) 0 (.45-5.5) Odenbaugh (.68-5.5) Dairy 3.2 km 90 0 Cs-134 (119) 3.8 (16/102) A-26 L&F Dairy 4.6 (5/17) 3.6 (3/17) 0 - (1.7-6.8) E.of Rd.13 on (3.0-6.8) (2.9-5.0) O
~
Rd. 32 7.8 km 255 0 Cs-137 (119) 6.5 (45/102) A-26 L&F Dairy 10.1 (8/17) 7.1 (6/17) 0 (2.0-20) E.of Rd. 13 on (2.0-20) (14-3.3) Rd. 32 7.8 km 255 0 Ba-140 (119) 5.0 (4/102) A-26 Hendrick- 6.0 (1/17) <6.3 (0/17) 0 (3.6-6.0) son Dairy 13278 Rd. 32 7.1 km 115 I4-140 (119) 5.9 (4/102) A-6 Hendrick- 6.9 (1/17) <7.2 (0/17) 0 (4.9-6.9) son Dairy 13278 Rd. 32 7.1 km 115*
~
O O O-Tam u II.N.1 E.wironmental Radiological Monitoring Program Annual hry ., Fort St. Vrain Nuclear Generating Facility, Platteville, Colorado I Medium or Pathway Type and Facility Adjacent Locations with Highest Reference Number of Sampled (Unit of Total Number Iocations Locations Annual Mean Iocations Nonroutine measurement) of Analysis Mean (f)b Mean (f)b Name Mean(f)b Mean (f)b Reported Performed range range Distance & Range Range Measurements Direction Drinking water Gross S(52) 5.0 (26/26) R-6 Gilcrest 5.0(2u/26) 0.83(25/26) < 0 (pci/L) ( 2.2 -10 ) City water (2.2-10) (0.47-2.0) 9.3 km 60 0 H-3 {3::) 424 (5/26) R-6 Gilcrest 424(5/26) 350(2/26) 0 (260-610) City water (260-610) (250-450) 9.3 km 60 0 Gamma Spectrometry I-131 (52) 0.51 (1/26) R-3 Ftcollins (0.52(2/26) 0.52(2/26) O City water (0.41-0.63)-(0.41-0.63) 45 km 330 0 o Cs-134 (52) < 3.7 (0/26) R-3 PtCollins 2.6 (2/26) 2.6 (2/26) 0 , City water (2.5-2.7) -(2.5-2.7) 45 km 330 0 Cs-137 (52) 5.4 (9/26) R-6 Gilcrest 6.4 (9/26) '3.8 (7/26) 0 (2.5-9.5) City water (2.5-9.5) (2.0-7.0) 9.3 km 60" Zr-95 (52) 8.4 (1/26) R-6 Gilerest 8.4 (1/26) < 9.9 (0/26) O City water 9.3 km 60 0 Nb-95 (52) 5.3 (1/26) R-6 Gilcrest 3.4 (7/26) 3.4 (7/26) O City water ( 1.8-8.0 ) (1.8-8.0) 9.3 km 60 0 Co-58 (52) < 3.5 (0/26) R-3 FtCollins 4.4 (1/26) 4.4 (1/26) O City water 45 km 330* f
.m._m...____- .____________.___.__.._.m . ._m _ ._... _ _.m._ . . _ _ . . _ _ . _ _ ____ . _ _ _ _ . __
O O O TREEE 11.0.1 Environmental Radiological Nomitoring Program hl hry Fort St. Vrain Nuclear Generating Facility, Platteville, Cblorado Medium or Pathway Type and Facility Adjacent Locations with Highest Reference Number of Sampled (Unit of Total Number Iocations locations Annual Mean Iocations Nonroutine measurement) of Analysis Mean (f)b Mean (f)D Name Mean(f)b Mean (f)b Reported Performed range range Distance & Range Range Measurements Direction Mn-54 (52) 3.7 (3/26) R-6 Gilcrest 3.7 (3/26) <4.0 (0/26) 0 (3.3-4.3) City water (3.3-4.3) 9.3 km 60 0 Zn-65 (52) 7.6 (2/26) R-6 Gilcrest 7.6 (2/26) 7.4 (3/26) 0 (6.1-9.0) City water 0 (6.1-9.0) (6.4-9.4) 9.3 km 60 Fe-59 (52) 6.7 (1/26) R-3 FtCbilins 9.2 (2/26) 9.2 (2/26) 0 City water (8.4-9.9) (8.4-9.9) 9.3 km 330' Co-60 (52) 2.1 (1/26) R-3 FtCollins 4.6 (4/26) 4.6 (4/26) O City water (2.7-7.1) ( 2 .7-7.1 ) g 9.3 km 330 W Ba-140 (52) 7.3 (2/26) R-6 Gilcrest 7.3 (2/26) <6.6 (0/26) 0 (6.9-7.6) City water (6.9-7.6) 9.3 km 60 0 La-140 (52) 8.4 ;2/26) R-6 Gilcrest 8.4 (2/26) <7.5 (0/26) 0 (7.9-8.8) City water (7.9-8.8) 9.3 km 60 0 l i l 1 i
O O O TABLE II.H.1 Environmental Radiological Mmitoring Program Annual Summaary Fort St. Vrain Nuclear Generating Facility, Platteville, Colorado Medium or Pathway Type and Facility Adjacent Locations with Highest Reference Number of S;mpled (Unit of Total Number Locations Locations Annual Mean Iocations Nonroutine measurement) of Analysis Mean (f)b Mean (f)b Name Mean(f)b Mean (f)b Reported Performed range range Distance & Range Range Measurements Direction Surface water H-3 (60) 5900 (16/36) A-25 Goosequill 7700(12/12 340 (3/24) 0 (pC1/L) 240-29,000 2.2 km 20 (330-29,000) (190-560) Gamma Spectrometry Cs-134 (60) <3.7 (0/36) -- -- 3.0 (3/24) 0 (2.2-3.9) Cs-137 (60) 4.6 (12/36) R-10 S.Platte 5.0 (5/12) 5.1 (8/24 ) 0 ( 2.7-8.0 ) at Go 60 ( 2 .9 -7.4 ) ( 3 .2 -7 .8 ) 0 km 290 Zr-95 (60) 12 (1/36) R-10 S.PIstte 12 (1/12) 8.9 (2/24) 0 ,, at Go 60 (7.7-10) C[ 10 km 290 Nb-95 (60) 3.1 (5/36) F-20 St.Vrain 3.6 (2/12) 3.2 (5/24) 0 (2.0-4.6) 1.5 km 340 (2.5-4.6) (2.7-3.8) 00-58 (60) < 3.5 (0/36) -- -- 3.5 (2/24) 0 (2.7-4.2) Mn-54 (60) 3.5 (5/36) A-25 Goosequill 3.7 (2/12) < 3.8 (0/26) 0 (2.5-4.8) 2.2 km 20 ( 2 .5 -4 .8 ) Zn-65 (60) 7.2 (5/36) F-20 St.Vrain 8.5 (1/12) 5.5 (3/24) 0 (5.3-9.4) 1.5 km 340 (1.8-8.5) Fe-59 (60) 7.8 (1/36) R-10 S.Platte 7.8 (1/12) 8.5 (3/24) O at Go 60 ( 7.9 -9. 2 ) 10 km 290 0 00-60 (60) <4.2 (0/36) -- -- 2.2 (1/24) 0
O O O 1mBER II.C.1 Emwircasm==tal mediologion1 Mmmitoring Program Amamal hry Fort St. Vrain Nuclear Generating Facility, Platteville, Colorado Medium or Pathway Type and Facility Adjacent Iocations with Highest Reference Number of Stapled (Unit of Total Number Iocations Iocations Annual Mean Locations Nonroutine mecsurement) of Analysis Mean (f)b g,,,ggy b Name Mean(f)b Mean (f)b Reported Performed range range Distance & Range Range Measnuements Direction t Ba-140 (60) 6.2 (2/36) R-10 S.Platte 6.2 (2/12) 6.8 (2/24) 0 (5.1-7.2) at Co 60 (5.1-7.2) (6.1-7.4) 10 km 290 La-140 (60) 7.1 (2/36) R-10 S.Platte 7.1 (2/12) 7.8 (2/24) 0 (5.8-8.3) at Co 60 (5.e-8.3) ( 7.C -8 .5 ) 10 km 290 0 Fish Gamma Spectrometry (pC1/kg, wet) Cs-134 (5) <7.0 (0/3) - -
<7.4 (0/2) O Cs-137 (5) <8.2 (0/3) - -
<8.6 (0/2) 0 .--
Co-58 (5) O
<6.5 (0/3) - -
<16 (0/2) 0
<6.7 (0/3) i k-54 (5) - -
<7.3 (0/2) 0 Zn-65 (5) 12 (1/3) A-25 Goosequill 12 (1/3) <11 (0/2) O Pond 2.2 km 0 0 Fe-59 (5) 13 (1/3) A-25 Goosequill 13 (1/3) <13 (0/2) O Pond 2.2 km 0 0 Co-60 (5) <7.4 (0/3) - -
<13 (0/2) 0 k
.___ ... ____._ _ -_ _ . . _ . _ _ . _ . .__m._ __m. . - . . . _ _ _ . _ _ _ . _ __m . . _ . _ _ _ . _ _ . . . , _ . _ _ _ _ _ _ _ _ _ _ . . _ . . _ _ _ _ _ O O O : Tam m II.N.1 Environmental Radiological Nomitoring Program Amamal hry Fort St. Vrain Nuclear Generating Facility, Platteville, Colorado Medium or Pathway Type and Facility Adjacent Locations with Highest Reference Number cf Sampled (Unit of Total Number Locations Locations Annual Mean Iocations Nonroutine - measurement) of Analysis Mean (f)b y,,, ggy b Name Mean(f)D han (f)b Reported Performed range range Distance & Range Range. Measurements Direction Cround water H-3 (8) 350 (1/4) F-16 3 Bar 350 (1/4) <300 0 (pC1/L) Ranch 1.2 km 0* Gamma Spectrometry Cs-134 (8) 2.6 (1/4) F-16 3 Bar 2.6 (1/4) <3.2 (0/4) 0 Ranch 1.2 km 0 0 Cs-137 (8) 6.4 (2/4) F-16 3 Bar 8.4 (1/4) 5.9 (2/4) 0 (4.3-8.4) Ranch 1.2 km 0 (3.9-7.9) Zr-95 (8) <9.1 (0/4) - --
<7.9 (0/4) 0 Nb-95 (8) <3.7 (0/4) - -
<2.9 (0/4) O h co-58 (8) <3.8 (0/4) -- -
<2.9 (0/4) O Mn-54 (8) <3.9 (0/4) - -
<3.2 (0/4) 0 Zn-65 (8) 1.0 (1/4) F-16 3 Bar 1.0 (1/4) 9.4-(1/4) 0 Ranch 1.2 km O O l
, Fe-59 (8) <9.3 (0/4) - - <7.6 (0/4) ; O l Co-60 (8) 2.7 (1/4) F-16 3 Bar 2.7 (1/4) <3.4 (0/4) 0 Ranch 1.2 km 0 Ba-140 (8) <6.1 (0/4) - -
< 5.2 (0/4) 0 Ia-140 (8) <7.1 (0/4) - -
<6.0 (0/4) O t
1 l l 1 !,_=.__._--.__-_-____-._______.____.__.-..___.-_,..--__.--__-._.,___. _
- _ . - _ , . . . - _ _ ~ . . = - , - - . - - - - - - - , . = - - _ _ _ - - _ . . - . . . _ . - . . _ - - . _ _ - - . . - __
l O O O TARIE II.E.1 hevironmental End.iological Monitoring Program hl hry Fort St. Vrain Nuclear Generating Facility, Platteville, Colorado i Medium or Pathway Type and Facility Adjacent Locations with Highest Reference Number of Sampled (Unit of Total Number Locations Locations Annual Mean Iocations Nonroutine measurement) of Analysis Mean (f)b y,,,gg)b Name Mean(f)b Mean (f)b Reported Performed range range Distance & Range Range Measurements Direction i Sediment Gamma Spectrometry (PC1/kg, dry) Cs-134 (2) R-10 S.Platte 28 (2/2) 28 (2/2) O at Co 60 (15-41) (15-41) 10 km 290* Cs-137 (2) R-10 S.Platte 180 (2/2) 180 (2/2) O at Co 60 (130-230) (130-230) 10 km 290 l l Food Products Gamma Spectrometry l (pCi/kg, wet) i I-131 (12) 3.7 (1/12) A-31 Moran Farm 3.7 (1/3) N/A 0 19801 C.Rd. 25 o 6.9 km 45 l l l Cs-134 (12) 11 (1/12) A-27 Scottsdale 11 (1/1) N/A 0 Ranch 18311 Cty. M. 23 3.1 km 450 t Cs-137 (12) 6.1 (7/12) A-27 Scottsdale 13 (1/1) N/A 0 (2.9-13) Ranch 18311 Cty. Rd. 23 3.1 km 45 4 1 i l - - . . - . - _ _ , . . . . - , , . . - - _ . . - - . . . . , . , - - . , - . . _ - - , . . . , - - . - , - ~ - . - . - - - - . ,
O O O Table II.H.2 Surnary Table of Geometric Means, Geometric Standard Deviations and Arithmetic Means for Selected Sample Types. 1984 1985 1986 1987
! Xg og i ig og i ig og i ig og i i
Drinking Water (pCi/L) l H-3 Gilcrest 300 1.6 200 190 1.1 160 130 2.9 <240 150 2.6 75 Ft. Collins 250 2.2 76 180 1.0 <250 210 1.4 <240 210 1.7 <230 Gross Beta Gilcrest 7.7 1.4 8.0 4.8 1.0 5.2 3.8 1.4 4.0 4.7 1.5 5.1 Ft. Collins 1.7 2.3 2.3 1.0 1.1 1.2 1.3 1.9 1.6 0.7 1.5 .79
, ~
I-131 8 pilcrest 0.4 3.7 0.5 0.2 1.3 0.004 0.2 2.4 0.14 0.2 2.1 .052 Ft. Collins 0.3 4.1 0.5 0.2 1.0 0.077 0.2 1.7 <0.49 0.2 3.5 .071 1 Cs-137 Gilcrest 2.5 3.0 1.6 1.8 1.1 1.5 2.6 2.1 1.4 1.8 2.1 2.1 Ft. Collins 4.1 2.3 2.8 1.4 1.1 1.7 2.0 3.3 1.3 1.9 3.1 1.1
O O O Table II.H.2 Susanary Table of Geometric Means, Geometric Standard Deviations and Arithmetic Means for Selected Sample Types. 1984 _ _ 1985 _ _ 1986 _ _ 1987 _ _Xg og X Xg og X Xg og X Xg og X Surface Water (pCi/L) H-3 Effluent 8300 4.4 13000 1300 1.3 2700 7800 4.3 15000 4200 3.5 7700 Downstream 340 1.8 220 340 1.8 220 180 3.3 72 170 2.3 21 Upstream 280 2.4 140 140 2.0 <250 230 1.4 <240 160 2.3 <230 Cs-137 Effluent 3.4 2.5 0.83 2.2 1.2 1.4 2.8 1.6 2.8 1.5 4.5 1.7 5 Downstream 2.8 2.5 0.57' 2.2 1.1 2.1 1.8 2.5 1.7 2.2 2.7 0.01 Upstream 3.2 2.9 1.8 1.9 1.3 1.3 1.9 3.1 1.5 2.3 3.0 0.32 I Milk (pC1/L) i H-3 Adjacent 200 2.1 <300 170 1.1 <2504 190 1.8 <240 200 1.6 <230-Reference 200 1.7 <300 190 1.1 <250 140 3.6 <240 160 2.5 <230 1-131 Adjacent 0.75 2.3 <0.50 0.22 1.0 0.02 0.46 12 3.9 0.22 3.1 0.15 Reference 0.60 2.9 <0.50 0.21 1.1 0.47 0.68 5.9 3.8 0.14 5.2 0.02 I Cs-137 Rdjacent 1.3 3.6 <9.0 2.1 1.0 . 1.7 5.8 3.4 11 3.1 2.3 3.2 Reference 1.1 5.3 <9.0 1.9 1.2 1.6 7.6 4.2 13 2.7 3.2 3.6 . ______-.-.-,---,~.-n.._-----__-.-,,,-n,.,---._------.-,.-----...-_,,_,.-,-.--,n.-, . _ _ _ _ , - , - _
O O O l Table II.H.2 Sumary Table of Geometric Means, Geometric Standard Deviations and Arithmetic Means for Selected Sample Types. 1984 _ 1985 _ 1986 _ 1987 _ _Xg og X _Xg og X _Xg og X _Xg og X Atmospheric Water Vapor (pCi/L) H-3 Facility 250 2.2 300 200 1.0 <250 220 2.1 <240 190 2.2 <230 eference 310 2.4 260 190 1.1 <250 180 2.4 <240 190 1.9 <230 Air (fCi/m ) i C Gross Beta o facility 15 1.7 17 27 1.0 28 29 2.0 44 24 1.5 26 Reference 16 1.6 18 25 1.0 27 31 2.0 51 24 1.4 25 l I-131 Facility 22 3.7 < 35 11 1.1 < 43 18 2.5 14 12 2.9 1.1 Reference 22 3.4 1.1 13 1.1 < 36 16 5.5 19 12 2.9 1.2 Cs-137 Facility 6.0 2.6 0.67 1.7 1.3 <4.4 2.5 3.3 4.1 1.3 2.6 0.33 Reference 5.9 3.0 < 30 2.1 2.1 <4.4 2.0 4.7 4.5 1.1 2.6 0.44
111
!!I. Radiological Environmental Monitoring Program A. Sample Collection and Analysis Schedule f Table !!!.A.1 outlines the sampling design, the collection frequency and the type of analysis for all environmental samples. It 2
should be repeated that this schedule was only adopted January 1,1984, and while dif ferent in certain aspects from the previous schdule, has as its intent the same objective. That objective is to document the j radiation and radioactivity levels in the critical pathways of dose to
! humans. Such data is necessary to prove that reactor radioactivity effluents produce environmental concentrations that are within appropriate environmental protection limits and at the same time are as low as reasonably achievable.
During 1987, R-5 is the or.ly sampling location that was changed. The previous loiction was one mile South of the present location, which l ) is described in Table III.B.1. The change was required due to the i closure of tne old site by the feedlot owners. All other sampling locations remained as in 1986. q Table III.B.1 gives the description of etch sampling location by l number, sector and distance from the reactor. These descriptions were 1 expanded somewhat in this report. Each of these sampling locations ,
! (except certain reference locations) can be identified on scale maps j t d
(Figures III.B.1 and III.B.2). Topographical maps showing greater l detail, as well as photographs of principal sampling sites are on file j in the CSU laboratory. l During August of 1987 the land-use census was conducted to
! determine the locations of the nearest residence, the nearest milk i
animal, and the nearest garden producing broad leaf vegetation in e d '1 l 1
112 of the 16 meteorological sectors around the reactor. These locations by address are shown in Table !!!.C.1. Figure !!!.C.1 shows these ,
- locations in each sector. From the 1987 census it v's verified that the ,
closest permanent residence in Sector 16 is still the critical receptor with regards to mean annual dose comitment, i No resident in the sampling sectors up to a distance of 8 km from the plant has cows or goats used for personal milk consumption. All milk produced is transported to comercial processors. The milk produced .iy is diluted by a large milk shed, processed and distribui- .ver a large area for consumption. Table !!!.A.2 lists the LLD concentration values for each sample type and radionuclide measured in th's report. These LLD values are the actual values pertinent to the sag i. U tes, counting yields, and counting times used in the project. Typical decay periods were used in the calculations, it should be noted that the LLO values are in all cases equal to or less than those required by the technical specifications. Table III.A.3 lists the USNRC reporting level for each sample type - and radionuclide, i 1 O U l i
I 113 . l k 1
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l O O O - i i i i l Table III.A.1 arllMllallSIRlui noipt. I yygporpqq mtmal:1 Ioillncylior:rpri i mposuro ratievey flasmfenr or Samples SampfIsig type anil I roquosicy and/or Samplo anst Locations Collection Tscqisoncy or Analysis Cs onind T. amp l e s f rom two sou rce s mo s t Ilhely Quarterly Goema Isotopic and to be ef fected, tritium. Drinking Osio samplo frose the noe ront ve tor Composito sample over two Composite for t ri t t um, sospply which could be af fected by vook period. gross Isota, and gamma racility's discleargo. Isotopic asietysns ovosy two vooks. One samplo from a control loca t losa. Sodfment reos one samplo from duvnstream area villa Semi-ennase l ly Camma lentopic esialysos Sharolino existisig or potential recrostional semi-annually, voluo. IItGI512on I tillk Samples from milking animals in sII Seel-monthly when anteels Comme lootop;c and 1-131 loca t insis, esp to a total of tisres are on pasture, mosittily at ana lysis soml-montisly loca tlosis, wi tt:In 5 kilomotors. ottier times. when animals are oin posture; monthly at ,_, Ono semplo from milking antaals In other tipos. .-. cacle of throo areas botvoen 5 to 8 A hilomators distant lievina the highest dose potential. U , One samplo from allking animals at a Soml-monthly when animals Comme isottspic and 1-131 control locatless il5 to 30 kilometers) are on posture, monttily at analysis soml-isosittily distent ased in the least prevalent otleer times. ' vlien erelmals era on visul direction). posturo; inos:Lisly at other timos. Agustic ulote Samplo risin in vicinity or discharge ' ample S soml-annuntly. Comme Isotopic analyses. ' point, upstream and dovenstroom.
. Iond Prodiscts Ono samplo or oncle patteolpal class or . At Limo or hervost. Comme isotopic enelycos.
Food psoducts f rom any area wisicle Is Irrigated by vetor in viilcle liquid plesat ve stes leave haess disclierges.
, la flese doso shall be calcselatest for tiso massimum orgass and age group using ties sootloodology enntalseed in Itogulatory Quido 3.109 steal ,
tim a n tasa l pesamotors particoster to tlus alto. 9
, ,e
O O O ?, Table III.A.2 Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD)* j Analysis Water Airborne Particulate Fish Hilk Food Products Sediment (pC1/L) or Gas (fC1/m 3 ) (pC1/kg, wet) (pCf/L) (pCf/kg, wet) (pC f /kg. dry) Gross Beta 3.06 3.25 11 - 3 494 1-131 0.89 66.4 0.89 56.8 Cs'-134 5.58 8.06 19.5 4.98 44.4 90.6 Cs-137 6.68 7.86 18.5 6.14 44.6 100 Zr-95 10.12 Nb-95 4.12 Co-58 4.60 12.8 Hn-54 4.68 12.7 = m Zn-65 10.94 23.6 , Fe-59 8.40 31.4 Co-60 4.40 14.5 Ba-140 6.66 8.00 La-140 7.66 9.16
- As suggested in NUREG-0472. All values are at or below values listed in Table 8.2-2 of technical specifications.
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o o o Table III.B.1 Radiological Environmental Monitoring Program (continued) Sampling Site Descriptions (F: Facility Area 0-1.6 km. A: Adjacent Area 1.6-8km. R: Reference Area) , l l Exposure Site No. Location Description (see map) Sector Distance, Pathway km Direct Radiation F-1 Pole by gate to Goosequill road on dirt extension of 1 1.3 CR 21. F-2 21st pole N of ditch on dirt extension of CR 21 just 2 1.1 before road drops down to river bottom. F-3 17th pole N of ditch on dirt extension of CR 21 or 3 0.7 first pole N of E-W road. 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. tl ' F-5 11th pole N of ditch on dirt extension of CR 21, near 5 0.6 drive to pump house. F-6 8th pole N of ditch on dirt extension of CR 21, 6 0.8 , by E-W concrete ditch, S of bridge. t F-7 Old dairy barn,1st pole N af ter crossing ditch on 7 1.2 dirt extension of CR 21. F-8 1st pole W of pump house on N side of road 0.4 km E 8- 1.3 of CR 194 F-9 Pole E of first shed at intersection of CR 194 9 1.5 and CR 34. L F-10 Pole on NW corner of intersection of dirt extension 10 1.5 of CR 19 and 34.
, _ . - - _ . _ _ m . . _ . - ___ _ _ _ _ __ . _ . . _
O O d Table III.B.1 Radiological Environmental Monitoring Program (continued). Sampling Site Descriptions (F: Facility Area 0-1.6 km. A: Adjacent Area 1.6-8km. R: Reference Area) Exposure Site No. Location Descri;, tion (see map) Sector Distance, Pathway km Direct Radiation F-11 7th pole N of intersection of dirt extension of CR 19 11 1.2 with CR 34. F-12 0.5 km S of FSV Visitor Center take dirt road W 12 1.0 l across field, go into farmyard of Aristocrat Brangus. l (If chain across road enter from CR 36). TLD is located on pole at SE corner of corral across from l Aristocrat Brangus office. F-13 Take rirst dirt road S of Visitor Center. Go W across- 13 0.5 ,, i railroad tracks, follow dirt road to metal staircase g; I going down off dike. TLD is taped to railing. l l F-14 2nd pole 0.1 km S intersection CR 364 & Rd 19. 14 1.5 l F-15 2nd pole 0.7 km S of intersection of CR 38 on CR 19. 15 1.5 l 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 194 . 16 -0.8 l The address of 17250 is taped to the Mountain Bell underground cable warning post. l k _ . _ _ _ _ . _ _ _ _ _ . _ . _ _ _ _ _ . _ - . _ _ _ _ . _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ . _ . _ _ _ - m_ _______m _ _ _ _ _ _ - - - . _ _ - . , , , . . , . , -
O O O Table III.B.1 Radiological Environmental Monitoring Program (continued) Sampling Site Descriptione (F: Facility Area 0-1.6 km. A: Adjacent Area 1.6-8km. R: Reference Area) ., l 1 Exposure Site No. Location Description (see map) Sector- Distance, Pathway km
~~ Direct l Radiation A-1 Pole on NW corner of intersection of CR 44 and CR 21. 1 6.7 A-2 Pole on NE corner intersection of CR 42 and CR 25%. 2 6. 8 '
A-3 Pole on NE corner of intersection of CR 42 and CO 60. 3 7.5 A-4 let pole NE of intersection of CR 29 and CR 38, take 4 ~ 7.4 CR 29 E cut of Gilcrest to CR 38. A-5 SE corner of CR 34 and CR 29. Taped to road sign on 5 7.2 ,. SW corner of intersection. ;g l A-6 Pole on S side of CR 32 near drive to dairy 13278 CR 6 7.1
- 32.
A-7 Niles Miller dairy. 0.4 km E of US 85 on CR 30. TLD. 7- 7.3 is located on pole at NE corner of house. , A-8 On CO 66 (CR30) farm on S side of road (address 9476) 8 4.7
- Pole in front of house.
- A-9 Corner of Co 66 (CR 30) and CR 19, Miller produce 9 4.6
] stand.- Second pole S on CR 19, on E side of road. I A-10 Pole on SE corner lat intersection CR 26% & CR 15. 10 7.8 l $ ~A-11 At intersection of CO 66 and CR 13, 2nd pole N of 11 7.2 i corner. , ) j 1 _ _ . _ _ . . . - _ - _ _ . _ . - - . . _ . _ . _ - . . _ - . - . _ - _ _ . _ _ _ . _ - - . . . - - - _ - . - - - ---_-----n - - _ _ -w - . . - . - r-- - = w ,w --
t 1 O O O Table III.B.1 Radiological Environmental Monitoring Program (continued) Sampling Site Descriptions (F: Facility Area 0-1.6 km. A: Adjacent Area 1.6-8km. 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. l A-13 Pole opposite lake, N of silage pits E side of CR 13 13 5.8 l- 2.9 km N of CR 34. ? I A-14 Intersection of CR 13 and CR 40, NW corner. 14 6. 9 l A-15 Intersection of CR 42 and CR 15, NW corner. 13 6.7 l l A-16 Intersection of CR 44 and CR 19, SW corner. 16 6.8 EI C) r A-17 Platteville school (S edge of town on Main St.) 6 5.9 l pole on NW corner just outside school intramural l field. l A-20 1st pole N of. white picket fence and driveway 9 2.5 l into turkey farm on S end of building that is j parallel with CR 19. i l l l
-- - - - . - -- - . - . . _ . = . . . .- . .
~ . . . - . . . - . ~ . _=. .~ ..~_-.-.- -. - ~ . - _ . __ . .- . . , _ _
I O O O Table III.B.1 Radiological Environmental Monitoring Program (continued) Sampling Site Descriptions (F: Facility Area 0-1.6 km. A: Adjacent Area 1.6-8km. R Reference Area) Exposure Site No. Location Description (see map) Sector Distance, Pathway km Direct Radiation R-1 Milliken School, on CR 214 TLD is loccted on pole 9.3 which is located at SE corner of Lola pa*k, across the street from school. R-2 Johnstown School (Letford Elementary), turn lef t at 10.8 school crossing on Idaho St. onto Joy Ave. and proceed to echool. TLD is located on pole at SE corner of main entrance to school on W side of town. R-3 CSU dairy farm on W Drake, N of Vet Hospital, Ft. 45.1 Collins, CO. Pole is E of hay barn next to EG
~
railroad tracks. 51 - 4 Air sampler- corner US 287 and CO 66, Longmont Dairy 20.5 Store. TLD is located on pole directly behind air
- sampler.
R-7 Behind G11 crest School quonset auditorium, pole 9.3 ' on SW end of school property, just before garage. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . , ~ . - . _ . , - . . . . - _ . . . _ . - _ - _
O O O-l Table III.B.1 Radiological Environmental Monitoring Program (continued) Sampling Site Descriptions (F: Facility Area 0-1.6 km. A: Adjacent Area 1.6-8km. R: Reference Area) Exposure Site No. Location Dcscription (see map) Sector Distance , Pathway km , 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 gel inside building on N end of workbench. F-9 First shed along drive at end of Rd 194 intersection 9 1.5 with Rd 21. Silica gel is located in shed. F-16 Potato cellar at 3 Bar Ranch (Russell's). Silica 16 1.2 gel in mailbox on tree to S or pump. A-19 Hunting cabin between Goosequill ditch and Platte 1 1.7 hh River. Air sampler is on W side or cabin, silica gel is in box on tree north of air sampler. R-3 Colorado State University Dairy, W. Drake Rd., Ft. 45.1 Collins, CO. W side or 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 store, north edge or Longmont. Silica gel in mailbox attached to utility pole. R-11 Air sampler is located in alley behind Johnstown, CO 10.5 ' PSC office,13712 Main St., next to garage. Silica gel is located next to air sampler in mailbox. l l l f 1 I
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O O O Table III.B.1 Radiological Environmental Monitoring Program (continued) Sampling Site Descriptions (F: Facility Area 0-1.6 km. A: Adjacent Area 1.6-8km. R: Reference f.rea) l Exposure Site No. Location Description (see map) Sector Distance, ; Pathway km l Waterborne Surface F-19 S. Platte at dam located or. dirt road E of pump 4 1.2 i house #3 directly E of reactor. F-20 St. Vrain creek on Rd.194 0.3 km from discharge 16 ,1. 5 into St. Vrain creek. Directly N of reactor. A-21 St. Vrain creek at bridge on Rd. 34, E of Rd. 19. 11 2.4 A-25 Goosequill Pond outlet. Continuous sampler located 1 2.2 ,, in green box adjacent to the green shed on the N end gj of the pond. R-10 S. Platte river at bridge on CO 60 where highway 10.1 has just turned and headed South. Ground- F-16 Well behind residence at 3 Bar Ranch (Russell's). 1~ 1. 2. . R-5 Erlich feed lot, North side of CO 66 approximately 9.0 0.8 km East of WCR 25. Drive north along dirt road approximately 0.27 km to field water spigot on West side of road. 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. .
.A 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.
. . - - . _ . __ _.,m_ . _ . .. . _ _. . . .
O O O Table III.B.1 Radiological Environmental Monitoring Program (continued) Sampling Site Descriptions (F: Facility Area 0-1.6 km. A: Adjacent Area 1.6-8km. R: Reference Area) i Exposure Site No. Location Description (see map) Sector Dis tance , Pathway km Waterborne ! Sediment R-10 Sediment from S. Platte River at bridge on CO 60. 10.1 I from Shoreline )- 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. E$ s A-22 Percy Odenbaugh Dairy, S on dirt rd from "Percy 5 3.2 ** Odenbaugh Dairy" sign on Rd 36 E of Rd 23 A-23 Leroy Odenbaugh Dairy, 11733 Rd 36, W or Rd 25. 4 4.1 i A-24 Marostica Dairy, 20718 Rd 17, 4 miles S of CO 60. 16 6.9 j A-26 L & F Dairy (Fiechtner), E of Rd 13 on Rd 32. 11 7.8 I a R-8 Arlo Johnston Farm, located off Exit 255 W.of I-25 22.5 { directly N of Johnson's Corner restaurant. l' i Fish ! F-19 S. Platte at dam located on dirt Rd E of pump '4 1.1 j house #3 directly E of reactor. 4 , A-25 Goosequill pond outlet. 1 . 2.2 l l R-10 S. Platte river at bridge on CO 60. 10.1 I i l ' 4, .
(\ p (v- L.) L j' Table III.B.1 Radiological Environmental Mor.itoring Program (continued) Sampling Site Descriptions (F: Facility Area 0-1.6 km. A: Adjacent Area 1.6-8km. R: Reference Area) Exposure Site No. Location Description (see map) Sector D istance , Pathway km Food Products A-9 Miller Store, CR 19 and CO 66. 9 4.6 A-23 Leroy Odenbaugh Dairy, 11733 CR 36, W of CR 25 4 4.1 A-27 Scottsdale Ranch, 18311 CR 23, N of CR 38. 3 3.1 A-29 19277 CR 25, S of CR 40Y,. 2 5.8 A-30 19440 CR 25Y. 2 3 6.5 _ A-31 Moran Farm, 19801 CR 25Y. 2 2 6.9 R-13 Richardson Truck Farm, 21210 CO 60. 9.5
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128 (^) Table III.C.1 1987 Land Use Census * %.) l l Nearest Nearest Nearest Sector Residence Garden Milk Animal 1 17578 CR 194 21692 CR 21 21692 CR 21** 2 18311 CR 23 19027 CR 23** 11248 CR 40 3 11250 CR 38 11165 CR 38** 11165 CR 3855 4 11247 CR 36 11247 CR 36** 11247 CR 36** 5 16543 CR 23** 16134 CR 23 16134 CR 23 6 16017 CR 23 11056 CR 32% 13278 CR 32 7 9999 CR 34 9999 CR 34 8 15225 CR 21** 15225 CR 21** 9867 CR 26 9 9434 CR 34 9434 CR 34 9033 CR 26 {T s-) 10 9061 CR 34 8416 Co 66** 7388 Co 66 11 8745 CR 34 6165 CR 32 15266 CR 13** 12 16465 CR 17** 5660 CR 34 5492 CR 34 13 17038 CR 17 17038 CR 17 *
- 4709 CR 38 l l
14 8900 CR 364 8900 CR 36% 18426 CR 15*
- l l
15 8903 CR 38 8903 CR 38** 8903 CR 38** l l 16 *** 17250 CR 194 17250 CR 194 l l
- Census date: August 4 & 8, 1987
** New location
*** No milk animals
,O L.)
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