ML20127K377

Radiological Environ Monitoring Program Summary Rept for 1984

ML20127K377
Person / Time
Site:	Fort Saint Vrain
Issue date:	12/31/1984
From:	COLORADO STATE UNIV., FORT COLLINS, CO
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PROGRAM I

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SUVN.ARY REPOR~

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R PDR cOR $M l Purchase Order No. 43470 1

l COLORADO STATE UNIVERSITY FORTCOLLINS, COLORADO 80523

I Acknowledgements Many persons have contributed to this project during 1984 and it is importt.nt 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 th? project in 1984 have been:

Charles Bedford Laboratory Assistant William Carl, Jr. Graduate Research Assistant Sheri Chambers Laboratory Technician Sharon Clow Chemist Kenneth Harper Graduate Research Assistant Wendy Johnson Student Laboratory Assistant Sandy Kienholz Graduate Research Assistant Steven Maheras Graduate Research Assistant Marion Mcdonald Laboratory Coordinator James E. Murray Graduate Research Assistant Mark Salasky Graduate Research Assistant Charles Sampier Chief Electronics Technician Jennifer Swanson Student Laboratory Assistant I

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TABLE OF CONTENTS

. Page No.

List of Tables - lii List of Figures v 1

I. INTRODUCTION II. SURVEILLANCE DATA FOR 1984 AND INTERPRETATION OF RESULTS A. External Gamma Exposure Rates 8 B. Air Sampling Data . 11

'C. Water Sampling Data 31 -

D. Milk Data . 70 E. Food Products 79 '

F. Aquatic Pathways 81 G. Sample Cross Check Data 84 H. Conclusions and Summary 92 III. RADIOLOGICAL ENVIRONMENTAL tiONITORING 111 PROGRAM AND SCHEDULE A. Collection and Analysis Schedule B. Sampling Locations .

C. Land-use Census I

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I LIST OF TABLES Page No.

II.A.1 Gamma Exposure Rates. 10 II.B.1 Concentrations of Long-lived Gross Beta Activity in Airborne Particles.

a. First Quarter, 13 g 14 5 b. Second Quarter,

c. Third Quarter, 15

d. Fourth Quarter, 16 II.B.2 Tritium Concentrations in Atmospheric Water Vapor, pCi/L.

a. First Quarter, 20

b. Second Quarter, 21

c. Third Quarter, 22

d. Fourth Quarter, 23 II.B.3 Tritium Concentraions in Air, pC1/m3

a. First Quarter, 24

b. Second Quarter, 25

c. Third Quarter, 26

d. Fourth Quarter, 27 I II.B.4 Tritium Released in Reactor Effluents. 28 II.B.5 I-131 Concentrations in Air.

a. First Quarter, 31

b. Second Quarter, 32 lI c. Third Quarter, 33 34 f d. Fourth Quarter,

!E Radiocesium Concentrations in Ambient Air. 35 l5 II.B.6 II.C.1 Gross Beta Concentrations in Bi-weekly Composites 39 of Drinking Water.

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LIST OF TABLES (continued) l Page No.

II.C.2 Tritium Concentrations in Bi-weekly Composites 40 of Drinking Water.

II.C.3 Radionuclide Concentrations in Bi-weekly 41 Composites of Drinking Water.

II.C.4 Tritium Concentrations in Surface Water. 53 II.C.5 Radionuclide Concentrations in Surface Water. 54 II.C.6 Radionuclide Concentrations in Effluent Water. 66 II.C.7 Radionuclide Concentrations in Ground Water. 68 II.C.8 Maximum Permissible Concentrations in Water. 69 II.D.1 Radionuclide Concentrations in Milk. 73 II.E.1 Radionuclide Concentrations in Food Products. 80 II.F.1 Radionuclide Concentrations in Fish. 82 II.F.2 Radio'nuclide Concentrations in Sediment. 83 II.G.l EPA Crosscheck Data. 86 II.G.2 Tritium Concentrations in Crosscheck Data, 88 (I CSU-Fort St. Vrain - Colorado Dept. of Health.

II.G.3 Gross Beta Concentrations in Crosscheck Data, 90 CSU - Fort St. Vrain - Colorado Dept. of Health.

II.H.1 Data. Summary. 99 11.H.2 Geometric Means of Selected Sample Types 1981-1984. 107 III.A.1 Radiological Environmental Monitoring Program. 113 III.A.2 Lower Limit of Detection. 115 III.A.3 Reporting Levels. 116 III.B.1 Sampling Locations for Environmental Samples. 117 III.C.1 Land-use Census, 1984. 126 l

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List of Figures Page No.

I Figure II.H.1 Tritium Concentrations in Water, 1974-1984 110 Figure III.B.1 On-site Sampling Locations 124 Figure III.B.2 Off-site Sampling Locations 125 Figure III.C.1 Land Use Census 127 I

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I I. ' Introduction to Radiological Environmental Monitoring Data for the Period January 1,1984 - December 31, 1984.

I During 1984 the Fort St. Vrain Nuclear Generating Station produced electrical energy as follows:

Month Dates with Electrical Gross Electrical l Generation Energy Production (MWH)

January 1-19 77,412 June 14-22 17,732 I The total electrical energy generated was significantly less than during the previous operating year. There was a factor of 8.7 less energy produced in 1984 as compared to 1983. The total radioactivity released b/ all effluent routes, however, was .

actually greater during 1984 than during 1983. A complete and detailed listing of radioactivity released by all effluent routes may be found in the Public Service Company of Colorado Semi-annual Effluent Release Report 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.

This analysis is found in each sample type section and in the summary section, II.H.

This report covers the first period of operation under revised environmental technical specifications. Since January 1, 1984 this new set of technical specifications (8.0) has been in effect.

Although the intent and major components of the new specifications

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are very similar to the previous set, there are some changes in sample numbers, types and collection frequencies. The current I

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l 2 required sample types, collection frequencies and sampling locations  !

l are given in Tables III.A.3, III.B.1 and shown in Figures III.B.1-2.  !

.Significant changes are discussed in each sample type section. It should be noted, there were no sampling location changes made in 1984.

Sample analytical protocols were also changed effective January 1, 1984. The new technical specifications required analysis for

additional gamma-ray emitting radionuclides which is not possible by NaI spectrometry. Therefore it was decided to analyze all samples requiring gamma-ray spectrometry using high resolution Ge(Li) systems. This transition period was not without problems.

The greatest problem was the reliability of the new large Ge(Li) detector. This was not fully operational until the second quarter of the year. As a result there was unavoidable delay between sample collection and counting in many cases and this meant that

it was impossible to meet Lower Limit of Detection (LLD) requirements for the short lived radionuclides in some of the sample types.

This however did not produce a notable deficiency in the quality of the environmental surveillance program for the following reasons:

5 1. 1-131, the most critical radionuclide for possible population dose commitment, was measured promptly in all air samples by the NaI system during the transition period.

2. If other short lived fission products e.g. Ba-La-140 had been released, a high correlation with the longer lived species would be expected. Since no significant detectable activity of any of the long lived gamma-ray emitting fission products was observed, it can be concluded that no I

q I 3 short lived fission products' were present either.

3. Gross beta concentrations in ambient air were measured promptly and would of course indicate any release of fission products.

Table III.A.1 lists the LLD values achievable by the counting systems used during 1984 on project samples. These values are given for typical sample sizes, counting times and decay times.

The LLD is,therefore,an a priori parameter to indicate the capability of the detection system used. The LLD parameters in Table III.A.2 were calculated as suggested in NUREG-0472. Throughout the report, however, when a sample result is listed as less than a specified value, that value was calculated as the MDC (minimum detectable concentration). The MDC value applies to the actual sample size, counting time and decay time applicable to that

-At individual sample. It was calcu' lated as: 2.33 B

/E Y V e Where: e = standard deviation of sample count rate B

E = Counting efficiency, c s ~1 pCi-1 Y = Chemical yield V = Sample mass or volume t = Decay time between sample collection and analysis Essentially all radioactivity values measured on this project are near background levels and, more importantly, near the MDC values for each radionuclide and sample type. It has been well documented that environmental radioactivity values exhibit great inherent variability. This is partly due to sampling and analytical variability but most importantly due to true environmental or biological I

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variability. As a result, the overall variability of the surveillance data is quite large, and it is necessary to use mean values from a rather large sample size to make any conclusions about the absolute radioactivity concentrations in any environmental pathway.

Environmental radiation surveillance data comonly exhibit nonnormal 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 treatment is tentative.

When a high percentage of data points is'less than MDC, calculation of true mean values is impossible. Therefore in these reports we have chosen (with few exceptions) not to include mean values with each data table. At the end of this report in Section II.H Conclusions and Summary, we have listed the calculated arithmetic means and confidence intervals for the reporting period of 1984.

We also list the geometric means and geometric standard deviations for the last year of data reporting. If any data points measured l resulted in negative values, these values were used in calculating the true mean values in Table II.H.2 (negative values are possible due to the statistical nature of radioactivity counting). 'This is the suggested practice by Gilbert (Health Physics 40:377,1984) and NRC NUREG/CR-4007. It should be noted that we have not used any notation for values less than MDC. Rather, we list the measured value 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.

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Many sets of data were compared in this report. The statistical test used was either a "t"-test or a paired "t"-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 added to appropriate tables the maximum permissible concentration applicable to that radionuclide. We have chosen to list the maximum permissible concentrations as found in Appendix B Table II of 10CFR20. This is the concentration in water or air of any radionuclide which if ingested or inhaled continuously, would singularly produce the maximum permissible radiation dose rate to a member of the general public. That value is 170 millirem / 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 generally assumed that no direct ingestion or inhalation of effluents can occur right 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 n'aximum permissible dose rate or dose commitment for residents near the Fort St. Vrain reactor. Such limits for water cooled reactors are found in 10CFR50 Appendix 1.

These are judged the "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.

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. 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 as the dose to the whole body from all contributing radionuclides. As will be noted in this report, dose comitments are calculated for any mean concentrations noted in unrestricted areas that are significantly above control mean values.

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I 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).

1. Analytical error (actual reason given).

N.A. Not applicable.

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II. Surveillance Data for January through December 1984 and Interpretation of Results. I A. External Gamma-ray Exposure Rates The average measured gamma-ray exposure rates expressed in mR/ day are given in Table II.A.1. The values were determined by

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Dy (TLD-200) dosimeters at each of 40 locations (see Table III.B.1). A significant fraction of these locations have been changed since the previous reporting period.

This is due to requirements of the new technical specifications.

I 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. In previous periods the exchange frequency was monthly.

The TLD data indicate that the arithmetic mean measured exposure rate in the Facility area for all of 1984 was 0.43 mR/ day. The mean exposure rate was 0.43 mR/ day for 1.he Adjacent area and 0.42 mR/ day for the Reference area. There were no significant differences between the values for the Facility, Adjacent and Reference areas. There was also no significant difference from the values measured during any quarter of 1984.

The exposure rate measured at all sites is due to a l combination of exposure from cosmic rays, from natural gamma-ray emitters in the earth's crust and from ground surface deposition of fission products from previous world-wide fallout. The I

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I e variation in measured values is due to true variation of the above sources plus the variation due to the measurement method.

The purpose of the two TLD rings around the reactor is not to measure gamma-rays generated from the reactor facility itself, but to document the presence or absence of gama-ray emitters deposited upon the ground from the reactor effluents. Since the inception of 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 gamma-ray flux 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 during readout of each quarterly batch of TLD devices.

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I l 10 Table II.A.1 Gamma Exposure Rates.'(mR/ day)

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Facility Area 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter I F-1 F-2 F-3 0.41 0.39 0.39 0.40 0.47 0.46 0.44 0.45 0.44 0.42 0.43 0.46 F-4 0.41 0.42 0.40 0.44 F-5 0.39 0.40 0.45 0.47 F-6 0.43 0.44 0.42 0.42 F-7 0.42 0.45 0.42 0.38 F-8 0.42 0.45 0.47 0.51 F-9 0.38 0.43 0.44 0.38 F-10 0.42 0.41 0.45 0.42 F-11 0.47 0.41 0.48 0.52 F-12 0.41 0.46 0.44 0.46 F-13 0.40 0.40 0.41 0.40 F-14 0.38 0.41 0.41 0.39 F-15 0.37 0.40 0.39 0.42 F-16 0.42 0.47 0.44 0.38 F-17 0.45 0.43 0.44 0.47 i ( c) 0.41 (0.026) 0.43 (0.026) 0.44 (0.022) 0.43 (0.043)

Adjacent Area A-1 0.42 0.45 0.45 0.46 '

A-2 0.45 0.46 0.42 0.46 A-3 0.48 0.45 0.41 0.45 -

A-4 0.41 0.39 0.41 0.39 A-5 0.40 0.43 0.43 0.35 A-6 0.43 0.37 -

0.42 0.41 I A-7 A-8 A-9 0.45 0.46 0.46 0.42 0.37 0.43 0.42 0.47 0.44 0.42 0.43 0.47 A-10 0.53 0.49 0.52 b-2 A-11 0.45 0.40 0.44 0.42 A-12 0.41 0.42 0.42 0.39 A-13 0.38 0.37 0.37 0.39 A-14 0.37 0.36 0.40 0.36 A-15 0.40 0.43 0.39 0.41 A-16 0.41 0.40 0.43 0.41 A-17 0.46 0.44 0.42 0.42 A 20 0.48 0.47 0.46 '

O.47 0.44 (0.040) 0.42 (0.038) 0.43 (0.033) 0.42 (0.036)

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Reference Area 0.42 b-1 0.46 R-1 0.46 I R.2 R-3 R.4 0.47 0.41 0.49 0.45 0.39 0.45 0.42 0.40 0.45 0.42 0.33 0.44 R-7 0.41 0.43 0.42 0.37 i (e) 0.45(0.036) 0.43 (0.032) 0.42 (0.026) 0.40(0.053) b-1 Sample missing at site. TLD removed from pole, b-2 Sample missing at site. Pole removed.

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11 II.B. Ambient Air Concentrations

1. Gross beta activity The air concentrations of long lived particulate gross beta activity measured at the Facility and Reference sampling sites are listed in Tables II.B. la-Id for each quarter of 1984. Note that F-7, F-9, F-16 and A-19 are the previous Facility sites. A-19, while technically in the Adjacent zone, is only so by a few meters and logically should be considered a Facility site. The Reference sites R-3, R-4, and R-11 are all new locations as of January 1, 1984.

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 be noted also that the new technical specifications do not require measurement of gross alpha activity. All filters, however, are saved indefinitely for later alpha particle analysis if needed.

The arithmetic mean values for the Facility stations was not significantly different from the mean values for the Reference locations during any of the four quarters of 1984. During the fourth quarter there was an increase in the concentrations noted

-I at all stations compared to the first three quarters of 1984.

No explanation for this increase can be offered other than to note that fall and early winter months are in general periods of dry soil and increased resuspension of surface soil may have occurred.

The concentrations measured during the fourth quarter were still less than measured during most previous reporting periods, operational and preoperational.

12 There has never been a significant difference observed between Facility and Reference sites. Thus it can be again concluded that air effluents of particulate fission products or activation products is not a critical pathway for the Fort St. Vrain environs.

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Table II.B.1 Concentrations of tong-Ilved Gross Beta Particulate Activity in Air. (fC1/m )

a) First Quarter,1984 Facility Sites Reference Sites CoIIection F-7 F-9 F-16 A-19 R-3 R-4 R-Il Date 1-7-84 9.35 (0.953) 18.8 (1.78) 18.0 (1.77) 11.9 (1.49) 6.83 (1.31) 17.3 (1.54) 19.5 (1.78) 1-14-84 4.03 (0.926) 16.3 (1.67) 11.7' (1.46) 4.90 (1.03) 13.6 (1.38) 14.3 (1.32) 18.0 (1.53) 1-21-84 16.7 (1.61) 16.1 (1.80) 13.6 (1.75) 13.0- (1.31) 6.20(1.00) 12.0 (1.34) 16.3 (1.63) 1-28-84 10.7 (1.12) 13.6 (1.62) 13.6 (1.55) 9.07 (1.31) 3.21 (1.12) 10.7 (1.25) 10.7 (1.47) 2-4-84 7.56 (1.08) 15.0 (1.59) 14.9 (1.69) 7.45 (1.14) 7.89 (1.03) 15.9 (1.45) 21.0 (1.81) 2-11-84 15.6 (1.23) 19.9 (1.72) 22.9 (1.83) C 3 17.0 (1.43) 18.1 (1.50) 32.8 (2.37) w 2-18-84 7.73 (0.984) 7.45 (1.23) 8.38 (1.23) 8.15 (0.938) 7.51 (1.23) 9.60 (1.09) 11.1 (1.23) 2-25-84 14.5 (1.20) 18.3 (1.86) 15.2 (1.29) 13.7 (1.20) 16.3 (1.39) 14.4 (1.23) 32.6 (2.04) 3-3-84 Cg 24.1 (2.24) 22.8 (1.66) 24.8 (1.93) 12.8 (1.28) 26.6 (1.80) 28.3 (2.16) 3-10-84 9.11 (1.01) 9.62 (1.44) 9.34 (1.07) 10.5 (1.03) 11.0 (1.17) 9.36 (1.22) 15.3 (1.18) 3-17-84 15.8 (1.38) 14.8 (1.71) 18.0 (1.56) 17.4 (1.35) 9.46 (1.26) 13.8 (1.26) 19.7 (1.65) 3-24-84 10.5 (1.11) 5.59 (1.63) 11.1 (1.26) 11.7 (1.08) 12.5 (1.22) 10.6 (1.16) 7.09 (1.19) 3-31-84 16.2 -(l.30) 15.4 (l.60) 14.8 (l.39) 12.1 (l.09) 11.2 (l.17) 11.2 (0.948) 12.0 (l.19) i 11.5 15.0 14.9 12.1 10.4 14.1 18.8 o 4.16 5.10 4.54 5.17 4.06 4.70 8.22 MAX: 24.1 i: 13.43 MAX: 32.8 X : 14.2 MIN: 4.03 n: 50 MIN: 3.21 n: 39 1.96 o (Due to counting statistics only.)

Cg Fuse bl an on m .

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Table II.B.1 Concentrations of Ion 9-lived Gross Beta Particulate Activity in Air. (fCi/m )

b) Second Quarter,1984.

acility Mtes Reference m es Collection Date F-7 F-9 F-16 A-19 R-3 R-4 R-ll 4-7-84 12.6 (1.11) 13.2 (1.50) 9.75 (1.10) 13.8 (1.13) 15.6 (1.30) 13.1 (1.17) 17.9 (1.58) 4-14-84 8.77 (1.01) C, 10.4 (1.08) 12.3 (1.04) 6.28 (0.923) 11.6 (1.07) 13.0 (1.33) 4-21-84 9.62 (0.989) 2.93 (1.42) 7.55 (0.976) 19.7 (1.40) 10.8 (1.21) 8.66 (1.30) 16.9 (1.98) 4-28-84 7.19 (0.965) 9.96 (1.47) 9.06 (1.11) 11.5 (2.03) 6.54 (0.996) 9.52 (1.04) 7.61 (1.06) 5-5-84 7.53 (0.891) 13.6 (1.56) 3.53 (0.890) 6.64 (0.874 12.5 (1.23) 10.6 (1.06) C 2

5-12-84 10.5 (1.16) 16.5 (1.96) 15.3 (1.49) 10.9 (1.01) 7.61 (1.19) 10.6 (1.13) 12.8 (1.53) ^

5-19-84 13.2 (1.32) 12.8 (1.79) 13.0 (1.26) 14.8 (1.19) 14.9 (1.35) 14.5 (1.37) 18.7 (1.76) 5-26-84 12.5 (1.34) 13.7 (1.12) 16.6 (1.56) 15.6 (1.23) 10.8 (1.11) 17.4 (1.55) 15.0 (1.41) 6-1-84 11.1 (1.35) 10.6 (1.01) 9.06 (1.09) 12.3 (1.06) 11.6 (1.27) 12.3 (1.36) 15.1 (1.64) 6-11-84 9.89 (1.03) 9.78 (0.782) 10.7 (0.980) 10.4 (0.804: 3.15 (0.604) 9.05 (0.794) 6.69 (0.890) .

6-16-84 8.52 (1.37) 11.7 (1.27) 11.7 (1.56) 11.0 (1.21) 10.6 (1.19) 12.4 (2.71) 11.1 (1.60) 6-22-84 15.9 (1.26) 13.1 (1.10) 10.4 (1.14) 15.3 (1.19) 14.5 (1.15) 13.8 (1.45) 7.43 (1.32) 6-30-84 19.1 (1.56) 24.5 (1.58) 20.7 (1.70) 22.6 (1.37) 21.3 (1.46) 15.5 (1.50) 20.6 (1.82)

I 11.3 12.7 11.4 13.6 11.2 12.2 13.6 e 3.41 4.98 4.32 4.15 4.76 -

2.61 4.65 MAX: 24.5 i: 12.2 MAX: 21.3 A: 12.3 MIN: 2.93 n: 51 HIN: 3.15 n: 38

• 1.96 o (Due to counting statistics only.)

C Air filter destroyed during sa:::ple collection.

y C Air cartridge stolen.

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Table II.B.1 Concentrations of Long-lived Gross Beta Particulate Activity in Air. (fCl/m )

c) Third Quarter,1984.

facility Sites Reference Sites ggjy gg, Date F-7 F-9 F-16 A-19 R-3 R-4 R-Il 7-7-P< 12.6 (1.41) 15.0 (2.09) 14.1 (1.40) 15.6 (1.21) 15.9 (1.31) 13.6 (1.32) 14.3 (1.28) 7-14-84 11.8 (1.30) 15.9 (1.27) 13.9 (1.60) 15.4 (1.13) 11.6 (1.02) 11.8 (1.50) 15.5 (1.20) 7-21-84 15.3 (1.08) 3.13 (1.44) 11.3 (1.41) 15.3 (2.02) 15.3 (1.08) Cg 16.0 (1.90) 7-28-84 11.6 (1.20) 14.4 (1.20) 16.0 (1.48) 15.9 (1.41) 18.0 (1.34) 14.7 (1.29) C 3

8-4-84 2.37 (1.06) 13.9 (1.22) 14.5 (1.40) 15.6 (1.71) 13.9 (1.12) 10.2 (1.13) 4.74 (0.856) 16.4 (1.48) 18.1 (1.60) 18.1 (14.4) 14.4 (1.31) 20.6 (1.42) 5 8-II-M 8.17 (0.787) 15.8 (1.21) 8-18-84 14.6 (0.99G) 19.4 (1.31) 18.9 (1.44) 20.7 (1.70) 19.7 (1.28) 16.2 (1.16) 20.9 (1.30) 8-25-84 13.4 (1.10) 15.3 (1.33) 12.9 (1.56) 14.4 (1.68) 19.5 (1.70) 11.0 (1.26) 12.8 (1.20) 9-1-84 10.6 (0.927) 15.3 (1.28) 14.1 (1.34) 12.9 (1.53) 11.8 (0.972) 14.1 (1.33) 14.2 (1.32) 9-8-84 18.0 (1.37) 16.2 (1.46) 15.2 (1.06) 21.9 (1.49) 15.1 (1.36) 16.2 (1.50) 20.0 (1.35) 9-18-84 15.1 (1.16) 16.3 (1.46) 17.2 (1.34) 17.5 (1.34) 19.9 (1.77) 18.4 (1.80) 19.4 (1.42) 9-22-84 17.1 (1.24) 20.8 (1.76) 21.5 (1.44) 22.8 (1.58) 19.8 (1.65) 21.2 (1.71) 28.0 (1.73) 9-29-84 16.1 (1.26) 17.5,(1.51) 13.1 (1.19) 15.7 (1.31) 19.0 (1.76) 17.9 (1.77) 18.3 (1.38) i 13.2 15.3 15.3 17.1 16.7 15.0 16.7 o 4.11 4.14 2.72 3.01 3.01 1 3.22 5.66 max: 22.8 i: 14.9 MAX: 28.0 k: 16.6 Min: 2.37 n: 52 MIN: 4.74 n: 37

• 1.96 o (Due to countin9 statistics only.)

Cg Electricity off at pts:p.

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M M M M M M M M M M M M M M M l i

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! Tablo II.B.1 Concentrations of Long-lived Gross Beta Particulate Activity in Air. (fC1/m )

d) Fourth Quarter,1984.

Facility Sites P,eference Sites Collection Date F-7 F-9 F-16 A-19 R-3 R-4 R-ll 10-6-84 21.4 (1.30) 13.1 (1.13) 22.7 (1.74) 25.5 (1.86) 20.7 (1.55) 8.74 (1.10) 20.6 (1.31) 10-13-84 21.5 (1.41) 7.95 (1.40) 27.9 (2.15) 22.7 (1.42) 26.5 (1.57) 23.5 (1.58) 20.7 (1.55) 10-20-84 23.4 (1.88) 12.0 (1.27) 18.6 (1.71) 17.3 (2.22) 14.6 (1.44) 17.6 (1.67) 12.8 (1.45) 10-27-84 23.2 (1.90) 18.4 (1.49) 23.0 (1.83) 28.3 (2.57) 23.7 (1.72) 22.5 (1.85) 25.3 (1.81) 11-3-84 34.7 (2.45) 34.6 (2.47) 40.6 (2.61) 26.5 (2.20) 27.1 (2.26) 21.7 (2.04) 43.1 (2.78) 11-10-84 20.5 (2.07) 19.4 (2.05) 26.7 (2.29)' 14.9 (1.84) 24.1 (2.19) 17.4 (1.95) 24.3 (2.25) 11-17-84 34.3 (2.56) 32.4 (2.61) 39.4 (2.73) 23.7 (2.14) 28.9 (2.54) 20.2 (2.10) 33.2 (2.68) 11-24-84 50.7 (4.08) 62.1 (3.59) 65.0 (3.28) 58.4 (3.75) 52.3 (3.31) 54.2 (3.50) 58.1 (3.34) 12-1-84 18.5 (2.12) 17.7 (2.43) 19.0 (1.77) 10.0 (1.24)

~

20.6 (2.07) 17.2 (2.41) 21.5 (2.00) 12-8-84 30.7 (2.58) 33.2 (2.33) 32.9 (2.15) 30.6 (2.77) 27.5 (2.32) 26.3 (2.42) 32.3 (2.51) 12-15-84 33.4 (2.71) 37.1 (2.84) 33.5 (2.40) 27.9 (2.84) 32.8 (3.24) 25.5 (2.75) 31.9 (2.37) 12-22-84 37.1 (2.89) 16.6 (1.58) 25.2 (1.86) 35.0 (2.92) 20.3 (1.94) 32.4 (2.81) 38.8 (2.54) 12-29-84 38.1 (2.76) 40.5 (2.43) 36.7 (2.39) 36.8 (3.07) 24.8 (2.78) 26.2 (2.82) 37.4 (2.31) i 29.8 26.5 31.6 27.5 26.5 24.1 30.8 e 9.33 15.1 12.4 12.0 9.01 10.7 11.9 PAX: 65.0 i: 28.9 MAX: 58.1 k: 27.1 MIN: 7.95 n: 52 MIN: 8.74 n: 39 1.96 o (Due to counting statistics only.)

1 7-17 I 2. Tritium Activity.

Tropospheric water vapor samples are collected continuously by passive absorption on silica gel at all seven air sampling l stations (four in the Facility area and three in the Reference area). The specific activity of tritium in water extracted from these weekly samples is listed in Tables II.B.2a-2d.

From the mean relative humidity meisured at F-9 and A-19 the corresponding air concentration of tritium is calculated for all samples and these values are given in Tables II.B.3a-3d.

The principle release mode of tritium from the reactor is batch liquid releases from holding tanks. The tank water is first analyzed and then released with sufficient additional dilution in order to not exceed 10CFR20 concentrations limits.

The summary of tritium released by all modes is given in Table

!! .B.4. It can be observed that the months of greatest tritium release was in March and then again in the period July through November. Sampling locations F-16 and A-19 are located near

, the Goosequill ditch, which is the principal route for effluent tritium release. Inspection of Tables !!.B.2a-2d clearly indicate elevated atmospheric tritium concentrations corresponding to the batch release of tritium in water along the ditch. This is due to evaporation while in transit. This observation has previously been made for these two locations.

Inspection 'of Table !!.H.1 reveals that the yearly mean value for all Facility sites was indeed slightly greater than for reference sites, however this difference was not statistically

18 I significant. Radiation dose commitment calculations are not warranted as a result of this observation as no elevated increase in tritium transport to humans can be postulated.

Using the temperature and relative humidity data from the hygrothermographs it is possible to convert specific activity of trittated water collected on silica gel (pC1/ liter) to activity per unit volume of air (pCi/m3 ). This is used if I calculation of immersion dose from tritiated water vapor were ever necessary.

Two equations are used in the conversion of pCi/ liter of 3

water to pCi/m of air. The first equation is used to determine thevaporpressureofwater(1):

I log 10P = A-B/(C+t), where: P = vapor pressure (m Hg)

I t = temperature (C)

A = 9.10765 B = 1750.286 C = 235.0 The temperature used is the integrated weekly value taken from I the hygrothermograph. The conversion is completed in the second equation which is the " Ideal Gas Equation":

PV = nRT, where: P=vaporpressure(atmosphere)

V= Volume (liters) n = number of moles of gas R = 0.08206 liter-a tmospheres/ mole-K

I T = temperature in K The number of grams of water per cubic meter of air is then determined.

The value of "n" obtained is for saturated air. The relative

19 humidity is therefore integrated over the week and this percentage of the saturated air value is taken. The final value is reported in pL1/m3 . This procedure has been applied to data collected for 1984 and listed in Tables II.B. 3a-3d. The weekly integrated relative humidity at the two sites is relatively constant, and the correlation of measured tritium specific activity in atmospheric water vapor and air concentration is very high. For this reason inspection of Tables II.B. 3a-3d shows the same site dependence on reactor l effluent discussed above.

I I

I I

,I

'I I

lI lI I .

M M M M M M M M M M M M M M" Tabl] II.B.2 Tritium Concentrations in Atmospheric Water Vapor. (pCi/L) a) First Quarter, 1934 Collection Facility Sites Reference Sites hte F-7 F-9 F-16 A-19 R-3 R-4 R-ll 1-7-84 < 247 < 247 < 247 < 247 < 247 < 247 < 247 1-14-84 < 247 < 247 517 (297)* < 247 < 247 < 247 < 247 1-21-84 < 247 < 247 e < 247 < 247 < 247 < 247 1-23-84 302 (230) 351 (280) 414 (280) 787 (285) < 233 < 233 < 233 2-4-84 < 243 < 243 < 243 < 243 < 243 < 243 < 243 2-11-84 < 237 < 237 < 237 422 (285) < 237 < 237 323 (284) 2-18-84 < 244 < 244 < 232 < 244 < 244 < 244 < 244 2-25-84 < 247 < 247 < 247 < 247 < 247 < 247 < 247 3-3-84 < 241 < 241 < 241 < 241 < 241 < 241 < 241 3-10-84 < 246 < 246 < 246 < 246 < 246 < 246 < 246 3-17-84 < 246 < 246 < 246 879 (300) < 246 < 246 < 246 3-24-84 < 246 < 246 < 246 < 246 < 246 < 246 < 246 l

i 3-31-84 < 298 < 298 < 298 < 298 < 301 < 298 < 296 l

l 1.96 o (Due to counting statistics.)

e Insufficient sample voltzne for analysis.

I I

M M M M M M M M M M M Tabla II.B.2 Tritium Concentrations in Atmospheric Water Vapor. (pC1/L) b) Second Quarter, 1934 Collection Facility Sites Reference Sites D E' F-7 F-9 F-16 A-19 R-3 R-4 R-Il 4-7-84 < 245 < 245 461 (294)* < 245 < 245 423 (294) < 245 4-14-84 < 241 < 241 < 241 < 241 < 241 < 241 < 241 4-21-84 < 239 < 239 < 239 < 239 2,680 (313) < 239 < 239 4-23-84 < 239 < 239 382 (286) 3t6 (286) 369 (282) < 235 < 239 5-5-84 < 243 < 243 < 243 < 243 < 243 < 243 < 243 g 5-12-84 < 243 < 243 < 243 < 243 < 243 < 243 < 243 5-19-84 < 243 < 243 < 243 < 243 < 243 < 243 < 243 5-26-64 < 243 < 243 < 243 < 243 < 243 < 243 < 243 6-1-84 < 249 < 249 < 249 < 249 < 249 < 249 < 249 6-11-84 < 244 < 244 < 244 < 244 < 244 < 244 < 244 6-16-84 < 244 < 244 < 244 < 244 < 244 < 244 < 244 6-23-84 < 237 < 237 < 237 303 (283) < 237 < 237 < 237 6-30-84 < 245 < 245 < 245 < 245 < 245 < 245 < 245 1.96 o (Due to counting statistics.)

l l

m M M M M M M M M Tabla II.B.2 Tritium Ccecentrations in Atmospheric Water Vapor. (pC1/L) c) Third Quarter, 1934.

Collectica Facility Sites Reference Sites UI' F-7 F-9 F-16 A-19 R-3 R-4 R-11 7-7-84 .

< 249 < 249 < 249 < 249 < 249 < 249 < 249 7-14-84 .

< 249 < 249 1,310 (309)* 1,360 (309) < 249 < 249 < 249 7-21-84 < 249 < 249 1,520 (311) 1,590 (312) < 249 < 249 < 249 7-28-84 < 246 < 246 697 (293)

• 847 (300 < 246 < 246 < 246 8-4-84 < 244 < 244 272 (293) 447 (293) < 244 < 244 < 244 S-11-84 < 241 < 241 618 (291) 825 (294) < 241 < 241 < 241 8-19-34 < 241 < 241 371 (289) 535 (291) < 241 < 241 < 241 8-25-84 < 241 < 241 391 (289) 463 (290) < 241 < 241 < 241 9-1-84 < 241 < 241 < 241 395 (289) < 241 < 241 < 241 9-3-64 < 241 535 (291) 505 (291) e < 241 < 241 515 (291) 9-15-84 < 242 < 242 433 (291) 414 (291) < 242 < 242 < 242 9-22-84 < 247 < 247 < 247 2,010 (314) < 247 < 247 < 247 9-23-84 < 241 < 241 584 (291) 1,180 (298) < 241 < 241 < 241 1.95 o (Due to ccunting statistics.)

e Insufficient voltre for analysis.

a

M M M M M W W M M M M l Table II.B.2 Triti:m Ccecer.traticas in Atcospheric Water Yapor. (pCi/L) d) Fcurth Quarter,1934 Ccliectico facility Sites Reference Sites

• F-9 F-16 A-19 R-3 R-4 F-7 R-Il 10-6-84 <23 < 243 < 248 629 (299)* < 248 < 248 < 248 10-13-84 ' 245 < 246 991 (297) 714 (294) < 246 < 246 449 (291) 10-20-24 391 (235) < 237 455 (285) 1,060 (293) < 237 < 237 342 (284) 10-27-24 < 2?3 < 243 < 248 < 248 < 248 < 248 < 248 11-3-64

• 233 < 233 < 233 712 (289) s 238 380 (285) 429 (286) g 11-10-24 < 242 < 242 < 242 < 242 < 242 < 242 < 242 11-17-84 *240 < 240 < 240 411 (288) < 240 < 240 < 240 11-24-84 < 247 < 247 < 247 < 247 < 247 e < 247 12-1-E4 < 243 < 243 < 243 < 243 < 243 < 243 < 243 12-3-E4 < 254 < 254 < 254 341 (292) < 254 < 254 < 254 12-15-84 < 2?3 < 243 1,620 (311) 306 (2 % ) < 248 < 248 < 248 12-22-E4 < 243 < 243 < 243 < 243 < 243 < 243 < 243 12-29-84 < 243 < 243 < 243 < 243 <243 < 243 < 243 o

1.95 o (Cue to ccunting statistics.)

o Insuff!cient voire fer analysis.

~

E E W W W W W W l Tabla 11.8.3 Trititm Ccncentrations in Atzospheric Water Vapor. (pCi/m3 )

a) First Cuarter,1934.

Collection Facility Sites Reference Sites Pate F-7 F-9 F-16 A-19 R-3 R-4 R-11 1-7-84 < 0.799 < 0.799 < 0.799 < 0.799 < 0.799 < 0.799 < 0.799 1-14-24 < 0.593 < 0.593 1.25 (0.719) < 0.598 < 0.598 < 0.598 < 0.598 1-21-E4 < 0.171 < 0.171 e < 0.171 < 0.171 < 0.171 < 0.171 1-23-84 9.43 (0.E39) 0.864 (0.689) 1.02 (0.689) 1.94 (0.701) < 0.573 < 0.573 < 0.573 g 2-4-84 < 0.634 < 0.684 < 0.684 < 0.684 < 0.684 < 0.684 < 0.684 2-11-E4 < 0.716 < 0.716 < 0.716 1.28 (0.861) < 0.716 < 0.716 0.976 (0.858) 2-13-84 < 0.725 < 0.725 < 0.689 < 0.725 < 0.725 < 0.725 < 0.725 2-25-E4 < 0.555 < 0.585 < 0.585 < 0.585 < 0.585 < 0.585 < 0.585 3-3-84 < 0.749 < 0.749 . < 0.749 < 0.749 < 0.749 < 0.749 < 0.749 3-10-84 < 0.629 < 0.629 < 0.629 < 0.629 < 0.629 < 0.629 < 0.629 3-17-84 < 0.899 < 0.899 < 0.899 3.21 (1.10) < 0.899 < 0.899 < 0.899 3-24-E4 < 0.953 < 0.953 <0.%3 <0.%3 < 0.963 < 0.963 < 0.963 31-s4 < 0.973 < 0.973 < 0.973 < 0.973 < 0.983 < 0.973 < 0.966 O

1.95 o (Due to counting statistics.)

o Ir. sufficient sample volare for analysis.

Tabla II.B.3 Trititm Concentrations in Atmospheric Water Yapor. (pCI/m )

b) Second Quarter, 1984.

Collecticn Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-ll 4-7-84 < 0.817 < 0.817 1.53 (0.930) < 0.817 < 0.817 1.41 (0.980) < 0.817 4-14-84 < 0.832 < 0.832 < 0.832 < 0.832 < 0.832 < 0.832 < 0.832 4-21-84 < I.21 < 1.21 < l.21 < l.21 < l.21 < 1.21 < l.21 4-28-84 < 1.13 < 1.13 1.50 (1.12) 1.35 (1.11) 1.44 (1.10) < l.13 < 1.13 3 5-5-64 < I.25 < I.25 < l.25 < l.25 < !.25 < l.25 < l.25 5-12-84 < 1.72 < I.72 < l.72 < l.72 < 1.72 < l.72 < l.72 5-19-81 < 2.24 < 2.24 < 2.24 < 2.24 < 2.24 < 2.24 < 2.24 5-26-84 < 2.70 < 2.70 < 2.70 < 2.70 < 2.70 < 2.70 < 2.70 6-1-84 < 2.26 < 2.26 < 2.26 < 2.26 < 2.26 < 2.26 < 2.26 6-11-84 < 2.29 < 2.29 < 2.29 < 2.29 < 2.29 < 2.29 < 2.29 6-17-84 < 3.32 < 3.32 < 3.32 < 3.32 < 3.32 < 3.32 < 3.32 6-23-84 < 2.54 < 2.54 < 2.54 2.66 (2.48) < 2.54 < 2.54 < 2.54 6-30-84 < 3.33 < 3.38 < 3.38 < 3.38 < 3.38 < 3.38 < 3.38 1.96 o (Due to counting statistics.)

W W W W W W TCla II.8.3 Tritium Concentrations in Atmospheric Water Vapor. (pCl/m3) c) Third-Quhrter, 1984. .

,. Co.lection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 7-7-84 <2.6*8 2'.68 < 2.58 ' < 2.68 ' < 2.68 < 2.68 < 2.68 7-14-84 < 3.23 < 3.23 17.1 (4.01)* '17.1 (4.01) < 3.23 < 3.23 ' < 3.23 7-21-84 < 3.40 i < 3.40 20.8 (4.15) 21.7 '(4.26) < 3.40 < 3.40 < 3.40 7-28-84 < 3.83 < 3.88 11.0 h 70) 13.4 (4.75) < 3;88 < 3.88 < 3.88 EN 8 4-84 < 2.9 ; < 2.90 5.61 (6.04 5.91 (?.48) ] '< 2.93 < 2.90 < 2.90 P-li-94 < 1.88 < l.88 4.83 (2.27) C 44.(?.'30) < l.88 < l.88 < l.88 8-19-84 < 3.30  ; 3.30 5.03 (3.96) 7.33 (3.99) < 3.30 < 3.30 < 3.30 8-25-64 < 2.59 < 2.59 4.02 (3.10) 4.97(3.11) < 2.59 < 2.59 < 2.59 9-1-84 < 2.48 < 2.49 < 2.48 4.07 (2.98) < 2.48 < 2.48 < 2.48 9-8-84 < 2.23 4.95 4.67 e < 2.23 < 2.23 4.76 9-15-84 < 2.01 < 2.01 4.02 (2.42) 3.44 (2.41) < 2.01 < 2.01 < 2.01 9-22-84 < l.95 < l.95 < l.95 15.9 (2.48) < l.95 < l.95 < l.95 9-29-84 < l.40 < l.40 3.40 (1.69) 6.86 (1.73) < 1.40 < l.40 < l.40 o

1.96 o (Due to counting statistics.)

e Insufficient sample volume for analysis.

M M M M M M M M M- M M M M T ble II.B.3 Tritium Concentrations in Atmospheric Water Vapor. (pC1/m3) .

d) Fourth Quarter,1984 Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 10-6-84 < l.89 < 1.89 < l.89 4.78 (2.27) < 1.89 < 1.89 < 1.89 10-13-84 < 1.52 < 1.52 6.13 (1.84) 4.42 (1.82) < 1.52 < 1.52 < 2.78 10-20-84 1.35 (0.984) < 0.817 1.57 (0.983) 3.66 (1.48) < 0.817 < 0.817 < 1.18 10-27-84 < 0.944 < 0.944 < 0.944 < 0.944 < 0.944 < 0.944 < 0.944 11-3-84 < 0.806 < 0.806 < 0.806 2.41 (0.979) < 0.806 1.29 (0.966) 1.45 (0.969) 11-10-84 < 0.769 < 0.769 < 0.769 < 0.769 < 0.769 < 0.769 < 0.769 11-17-84 < 0.847 < 0.847 < 0.847 1.45 (1.02) < 0.847 < 0.847 < 0.847 11-24-84 < 0.686 < 0.686 < 0.686- < 0.686 < 0.686 e < 0.686 12-1-84 < 0.622 < 0.622 < 0.622 < 0.622 < 0.622 < 0.622 < 0.622 12-8-84 < 0.588 < 0.588 < 0.588 0.789 (0.764) < 0.588 < 0.588 < 0.588 12-15-84 < 3.62 < 3.62 23.6 (4.53) 4.47 (4.31) < 3.62 < 3.62 < 3.62 12-22-84 < 2.76 < 2.76 < 2.76 < 2.76 < 2.76 < 2.76 < 2.76 12-29-84 < 3.16 < 3.16 < 3.16 < 3.16 < 3.16 < 3.16 < 3.16 1.96 o (Due to counting statistics.)

e Insufficient volume for analysis.

m m M . m 'm m am W W W m m W W. m m e l

l Table II.B.4. Tritium Released (C1) in Reactor Effluents,1984.

l l

Mode Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Total l

Continuous 0.6 0.7 0.8 0.7 0.9 0.5 8.3 0.3 0.2 0.2 0.09 0.1 13.4 l (Turbine building l sump and reactor building sump)

Batch Liquid 6.5 2.7 19.5 0.6 1.7 2.1 24'.0 9.8 28.9 18.5 6.1 3.4 123.8 Gaseous Stack 0.3 0.1 0.01 0.08 0.3 0.2 0.05 0.02 0.005 0.1 0.007 0.0009 1.2 TOTAL 7.4 3.5 20.3 1.4 2.9 2.8 32.4 10.1 29.1 18.8 6.2 3.5 138.4

i 29

3. Concentrations of Gamma-ray Emitting Radionuclides in Ambient Air.

~

Tables II.B. Sa-5d list the concentrations of I-131 in air by activated charcoal sampling and high resolution gamma-ray spectrum analysis. Each sample from the seven air sampling stations is

counted within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after collection. A 300 minute count is typically required to achieve an LLD of 70.0 fCi/m . Radon and Thoron daughters are trapped on the particulate filter ahead of the charcoal trap. Radon-222 daughter in-growth on the charcoal can be corrected by the high resolution spectrometry. Any positive I-131 measured concentration is corrected for radioactive decay I 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 station at a constant rate, 1 but rather in pulses of short duration compared to the collection period. This is the case whether the I-131 source tenn would be weapons testing fallout or reactor stack effluent.

During the first two weeks of 1984, it was assumed that the charcoals from all seven stations should be composited before analysis. This had been the procedure since 1972 before the January 1,1984 changes in technical specifications. This error was corrected beginning the 3rd week of 1984. The total composite activity measured for each of the first two weeks was divided by seven to obtain an estimate for each station.

=

The air concentrations measured during 1984 were essentially all less than minimum detectable concentrations. Approximately 50% of the measured values were negative as would be expected if

I

30 the true mean were zero. The overall yearly mean of the four Facility stations was < 35.0 fCi/m3. The yearly mean for the Reference stations was 1.06 fCi/m . This value, of course, is not statistically significant as it is less than MDC. These means were not significantly different from each other and not statistically different from zero. The effluent Release Report data indicated

negligible release of I-131 during the year.

As noted in Section I. early in 1984 there was often excessive delay before counting all of the charcoal samples due to instrument problems. This was responsible for the high MDC values reported.

This problem was corrected by the second quarter of 1984 and has recently been further alleviated by the purchase of a second high efficiency Ge(Li) system.

There is no explanation for the four positive I-131 concentrations observed in 1984. However, the values were indeed low and at least that many false positive values should be expected using a 95% (a = 0.05) hypothesis testing criterion. (See NUREG/Cr-4007).

Table II.B.6 lists measured ambient air concentrations of Cs-134 and Cs-137. These values are from gamma-ray spectrum analysis on weekly air filters composited quarterly from each of the seven air sampling stations. The mean values for each quarter for each station were less than MDC for both radiocesium isotopes.

~

Although only Cs-134 and Cs-137 'are reported, each gamma-ray spectrum is scanned for evidence of absorption peaks from other fission products and activation products. Only peaks due to naturally occurring radionuclides were observed during 1984.

.I I

W W W W M. M W. W W M M M M M~m m- m m m 3

! Table II.B.5 Iodine-131 Concentrations in Air. (fCi/m )

a) First Quarter,1984.

Collection Facility Sites Reference Sites _

Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 l

1-7-84 < 2.84 < 2.84 < 2.84 < 2.84 < 2.84 < 2.84 < 2.84 1-14-84** < 1.19 < 1.19 < 1.19 < 1.19 < 1.19 < 1.19 <1.19 1-21-84 < 180 < 234 < 234 < 156 < 126 < 140 <195 1-28-84 < 122 < 353 < 108 < 103 < 165 < 332 < 135 2-4-84 < 38.7 < 97.4 <.31.0 < 29.3 < 68.7 < 43.0 < 59.4 2-11-84 < 123 < 80.0 < 144 < 171 < 192 < 134 < 140 2-18-84 < 235 < 253

< 148 < 114 < 159 < 93.5 < 191 2-25-84 < 149 < 150 < 152 < 126 < 178 < 67.3 < 242 3-3-84 < 553 < 95.1 < 71.'6 < 79.1 < 69.3 < 25.1 < 105 3-10-84 < 71.9 < 82.6 < 86.4 < 106 < 81.4 < 138 < 16 5 3-17-84 < 63.5 57.7 (38.3) < 56.9 < 41.7 < 51.7 < 25.8 < 44.8 3-25-84 < 43.5 I < 41.3 < 32.6 < 43.2 21.1 < 36.9 3-31-84 < 39.7 < 236 <64.9 < 41.1 < 117 91.6 < 29.6 1.96 o (Due to counting statistics.) g o* Seven sites analyzed as composite sample.

5 1-131 MPC a

= 10 fCi/m3. (10CFR20, Appendix B, Table II)

I Elapsed time too long to accurately calculate concentration.

M M . W :M M M M M M M M .M M M M M M. M 3

Table II.B.5 Iodine-131 Concentrations in Air. (fCi/m )

b) Second Quarter, 1984.

Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 4-7-84 < 34.1 < 125 < 82.7 < 80.4 < 80.4 < 85.1 < 99.2 4-14-84 < 55.4 < 54.5 < 66.7 < 4.79 < 36.6 < 51.7 < 62.5 4-21-84 < 58.3 < 68.2 < 28.4 < 1.80 < 75.7 < 89.8' <-130 4-28-84 < 45.8 < 72.4 < 63.0 < 99.2 < 52.2 < 40.2 < 54.5 5-5-84 < 42.3 < 46.4 < 38.4 < 25.2 < 33.1 < 29.5 C 3

5-12-84 < 30.7 < 48.9 < 33.1 < 23.0 < 35.0 < 29.7 < 44.3 5-19-84 < 17.8 < 102 < 31.2 < 25.9 < 29.5 < 34.6 < 45.4 5-26-84 < 27.2 < 19.8 < 35.9 < 44.5 < 35.7 < 23.8 < 21.5 6-1-84 < 41.1 < 20.4 < 39.3 < 33.5 < 52.6 < 23.3 < 62.0 6-11-84 < 15.8 < 9.92 < 24.5 < 7.57 < 20.4 < 20.0 < 14.8 6-16-84 < 55.0 < 51.2 < 78.5 < 75.7 < 55.9 < 63.0 < 75.7 6-23-84 < 36.8 < 29.4 < 42.0 < 24.5 < 22.2 < 38.1 < 47.9 6-30-84 < 22.5 < 16.7 < 37.8 < 23.7 < 19.8 < 27.3 < 41.1 I-131 MPC = 105 fCi/m 3. (10CFR20, Appendix B, Table II)

C Instrument malfunction, air cartridge stolen.

1 2

W W M M' W M M M M M M M M M M m' W W 3

Table II.B.5 lodine-131 Concentrations in Air. (fC1/m )

c) Third Quarter,15 34.

Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 7-7-84 < 26.5 < 50.9 < 36.5 < 45.6 < 20.6 < 69.7 < 42.3 7-14-84 < 30.7 < 16.8 < 26.1 < 27.7 < 25.3 < 33.0 < 31.7 7-21-84 < 17.0 < 66.1 < 37.1 < 27.8 < 35.0 Cy < 59.5 7-28-84 < 37.1 < 39.6 < 32.1 < 43.4 < 35.8 < 40.8 C 3

8-4-84 < 32.5 < 41.5 < 50.4 < 54.6 < 37.2 < 44.2 < 39.3 8-11-84 < 53.1 < 39.6 < 24.5 < 32.4 < 34.4 < 35.1 < 46.2 8-19-84 < 13.1 < 24.3 < 31.5 < 16.4 < 24.1 < 30.0 < 27.9 8-25-84 < 13.9 < 33.8 < 55.6 < 16.8 < 31.3 < 20.1 < 29.6 9-1-84 < 20.6 < 8.54 < 28.9 < 25.4 < 74.7 < 30.8 < 14.0 9-8-84 < 37.3 < 38.5 < 36.2 < 37.3 < 35.0 < 33.2 < 36.0 9-15-84 < 25.4 < 26.0 < 27.0 < 29.1 < 26.2 < 23.2 < 27.0 9-22-84 < 27.5 < 31.2 < 25.4 < 29.5 < 27.8 < 26.7 < 29.4 9-29-84 < 35.4 '

< 34.8 < 36.9 < 32.0 < 34.0 < 30.4 < 34.0 C y Instrument malfunction - electricity off.

1-131 MPC = 10 5 fCi/m3. (10CFR20, Appendix B, Table II) a

M M M M M ' M- M M M M M M M M M M M. M M' 3

Table II.B.5 Iodine-131 Concentrations in Air. (fCi/m )

d) Fourth Quarter, 1984.

Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 10-6-84 < 31.2 < 27.9 < 20.1 < 26.7 12.2 (18.7)* < 32.6 < 27.3 10-13-84 < 35.7 < 36.7 < 31.5 < 31.5 < 36.7 < 36.4 < 34.1 10-20-84 < 31.1 < 31.9 < 24.5 < 29.0 < 31.7 < 32.6 < 32.3 10-27-84 < 34.9 < 26.5 < 46.7 < 38.5 < 29.0 < 23.9 < 5.50 11-3-84 < 30.6 < 29.9 < 29.4 < 33.2 < 30.0 < 38.9 < 26.9 11-10-84 < 30.6 < 29.3 < 24.4 < 39.8 < 19.3 < 30.0 < 28.0 11-17-84 < 30.8 < 28.5 < 25.6 < 39.5 < 30.7 < 32.4 < 26.8 11-24-84 < 54.3 < 41.4 < 29 1 < 50.3 < 37.7 < 39.5 < 31.8 12-1-84 < 36.2 < 46.1 < 25.4 23.5 (47.7) < 30.4 < 36.0 < 29.3 12-8-84 < 40.5 < 29.8 < 27.2 < 42.2 < 27.5 < 37.0 < 35.7 12-15-84 < 41.3 < 39.2 < 30.2 < 49.2 < 47.3 < 41.9 < 30.4 12-22-84 < 29.7 < 22.1 < 17.9 < 11.5 .< 27.3 < 27.5 < 26.7 12-29-84 < 35.5 < 26.0 < 32.7 < 45.6 < 47.9 < 47.4 28.0 (58.7) 1.96 o (Due to counting statistics.) w 5 3 I-131 MPC, = 10 fCi/m . (10CFR20, Appendix B, Table II)

M M M M M M M M M M M M M M M M M mM' 3

Table II.B.6 Radiocesium Concentrations in Ambient Air. (fC1/m )-

Facility Sites Reference Sites Collection Radio-R-3 R-4 R-11 Date Nuclide F-7 F-9 F-16 A-19 Cs-134 < 6.35 < 14.3 < 7.21 < 6.90 < 5.65 < 13.3 5.35 (4.42) 1st Quarter Cs-137 < 18.2 < 23.5 < 5.02 < 6.30 < 6.30 < 16.9 < 8.70 Cs-134 < 7.09 < 9.20 < 7.12 < 5.60 < 6.05 < 8.95 < 12.3 2nd Quarter Cs-137 < 6.35 < 7.95 < 7.16 < 6.60 < 9.05 < 11.5 < 10.2 l$

3rd Quarter Cs-134 < 4.03 < 9.85 < 9.73 < 8.27 < 6.30 < 2.66 < 10.3 Cs-137 < 3.93 < 10.3 < 7.04 11.8 (17.3) < 6.23 < 2.75 < 8.27 4th Quarter Cs-134 < 14.1 < 14.6 < 19.4 < 12.2 < 34.5 < 16.3 < 10.8 Cs-137 < 11.3 < 10.9 < 11.8 < 16.6 < 32.9 < 13.8 < 9.53 l

l l

• 1.96 o( Due to counting statistics only.)

0 3 6 Cs-134 MPC, = 1 x 10 fCi/m , Cs-137 MPC, = 2 x 10 fC1/m3 (10CFR20, Appendix B, Table II).

l k

36 II.C. Radionuclide Concentrations in Water

1. Drinking Water Drinking water is sampled at two locations only. Location R-6 is the well used for drinking water by the town of Gilcrest, Colorado I and R-3 is a water tap located on the CSU dairy fann. The Gilcrest well is the nearest public water supply that could be affected by the reactor effluents. R-3 is the Fort Collins drinking water supply and serves as a reference location since its source is run-off from the Rocky Mountains to the West.

Table II.C.1 shows gross beta concentrations measured in 1984 from each water supply. The mean for the Gilcrest site was slightly higher than the Reference site in Fort Collins. This is due to different water treatment practices. The city of Gilcrest does not filter its water and natural radionuclide concentrations are slightly higher. The yearly mean values, however, were not statistically different.

I 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 fiDC and, therefore, not statistically different from each other.

A hydrological study of the ground water flow around FSV'was recently conducted by Christopher Dacey, an M.S. graduate student in Geohydrology at CSU. He analyzed all existing ground water flow data and concluded that based on aquifer size and flow direction it would be virtually impossible to detect elevated tritium at the Gilcrest well site. This M.S. thesis is currently being printed and will be available from the CSU library system. Sampling at the

,I I

i-

I '

Gilcrest site was continued because in theory it is the nearest site of public drinking water that could be contaminated by effluent from Fort St. Vrain.

Table II.C.3 shows fission product and activation product concentration measurements from the two drinking water supplies.

Since the technical specification requirement (Table III.A.1) required gamma isotopic analysis on a sample collected weekly but composited every two weeks for analysis it was initially assumed that this requirement precluded I-131 analysis. For that reason water samples for gamma-ray analysis were initially evaporated to dryness and the dissolved and suspended solids analyzed. The evaporation step eliminated the possibility of I-131 detection in the samples collected to April 21, 1984. During the period from April 28, 1984 to June 30, 1984 the drinking water samples were counted without evaporation on a large Nal system separately for I-131 only, but due to counting time problems, it was not possible to attain required LLD values. By October 1, 1984 an ion exchange concentration method was perfected in which 18 liters are passed through Dowex 1-x8 anion exchange resin and the resin then counted by Ge(L1) spectrometry. This same method was adopted for milk samples.

Inspection of Table II.C.3 reveals occasional positive values

'" of radionuclide concentration, but these are interpreted to be

! random variations. For the case dated December 29, 1984, the decay time was excessively long due to detector problems and the calculated value is suspect. In all cases of a positive value, the 95%

l confidence interval includes the MDC value for that particular I

!I I

-4 ._ A *..e. - -+ v. . - - - -- - . - ---A - -.

radionuclide. There was no significant difference between the two drinking water sites during all of 1984 for any of the radionuclides measured.

!I I

I I

I I

I I

I I

I I

I I

lI I - -

r 39 Table II.C.1 Gross Beta Concentrations in Biweekly Composites of Drinking Water. (pCi/L)

I I Collection Date Gilcrest City R-6 Fort Collins City R-3 (Reference) 1-14-84 8.27 (1.27)* 4.03 (3.79) 1-28-84 10.9 (1.32) 1.74 (1.01) 2-11-84 12.4 (3.71) 3.53 (3.40)

I 2-25-84 9.23 (4.46) 4.36 (4.24) 3-10-84 9.49 (5.31) 4.03 (5.05) 3-24-84 15.2 (7.41) 4.97 (6.99) 4-7-84 8.35 (1.25) < 1.57 4-21-84 8.70 (1.28) < 1.57 5-5-84 6.27 (1.07) < 1.57 5-19-84 7.33 (0.831) < 1.55

-I 6-2-84 6.67 (1.85) < 1.55 '

6-16-84 8.39 (0.888) 2.00 (0.662) 6-30-84 3.71 (0.712) 1.90 (0.648) 7-14-84 7.47 (2.82) 3.11 (2.79) 7-28-84 6.72 (2.96) < 1.86 8-11-84 5.12 (2.81) 3.40 (1.94) 8-25-84 6.62 (2.73) 1.96 (2.56) 9-8-84 10.3 (2.15) 6.92 (2.16) 9-22-84 10.2 (2.17) 1.35 (0.519) 10-6-84 9.02 (2.19) 1.72 (0.502) 10-20-84 9.11 (2.29) 0.798 (0.532) 11-3-84 4.74 (2.08) 0.827 (0.520) 11-17-84 5.91 (2.13) 2.07 (0.459) 12-1-84 7.57 (2.22) 1.13 (0.539) 12-15-84 5.70 (2.14) 1.49 (0.545) 12-29-84 6.29 (2.17) 1.41 I 4-(0.542) 1.96 c (Due to counting statistics only.)

MPC = 30 pCi/L Table II, Appendix B limit 10 CFR20 for an unidentified miEture of radionuclides in water if either the identity or the concentration of any radionuclide is not known.

I

40 Table II.C.2 Tritium Concentrations in Biweekly Composites of Drinking Water. (pCi/L)

Collection Gilcrest City R-6 Fort Collins City R-3 Date (Reference) 1-14-84 447 (286)* 382 (286) 1-28-84 447 (281) 539(282) 2-11-84 326 (284) < 237 2-25-84 < 244 < 244

< 244 I 3-10-84 3-24-84

< 244

< 248 1,050 (303)

< 247 4-7-84 317 (294) 4-21-84 649(285) < 235 5-5-84 816 (287) < 235 5-19-84 < 243 < 243 6-2-84 363 (203) < 249 6-16-84 459(200) < 235 6-30-84 437 (201) 369 (199) 7-14-84 < 249 < 249 I 7-28-84 8-11-84 372 (196) 345 (204) 345 (244)

< 246 8-25-84 < 241 < 241 9-8-84 < 241 < 241 9-22-84 < 247 < 247 10-6-84 < 248 < 248 10-20-84 < 238 < 238 iI 11-3-84 < 238 < 238 11-17-84 670 (291) < 240 12-1-84 < 243 < 243 12-15-84 < 248 < 248 12-29-84 < 243 < 243

• 1.96 o (Due to counting statistics only.)

H-3 MPCf 3.106pCi/L (10CFR20), Appendix B, Table II I -

m M M M M M M M M- M M M M M M M M M Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L)

Collection Date 1/7, 14/84 1/21,28/84 2/4,11/84 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 I-131 ** ** ** ** ** **

Cs-134 < 1.60 < 7.75 < 6.70 < 4.56 < 4.39 < 10.0 Cs-137 < 1.70 < 6.40 < 5.85 < 5.85 < 5.85 < 9.59 Zr-95 < 0.465 < 34.4 < 27.3 < 35.5 < 22.5 < 37.5 Nb-95 < 0.805 < 59.5 < 47.2 < 61.5 < 39.0 < 6.57 Co-58 < 6.15 < 33.6 < 16.9 < 21.9 < 14.5 < 17.4 Mn-54 < 1.80 < 6.45 9.21 (7.65)* < 6.05 < 5.50 < 8.28 Zn-65 < 41.1 < 17.1 < 16.5 < 14.1 < 12.5 < 6.95 Fe-59 < 38.4 < 137 < 76.5 < 112 87.2 (84.0) < 6.75 C0-60 < 1.27 < 3.94 < 4.73 < 4.73 < 3.86 < 19.0 Ba-140 La-140

• 1.960 (Due to counting statistics only.) 8

• • Ana ysis performed on evaporated sample.

• • • Elapsed time too lor.9 to accurately calculate concentration.

M M M M M M M M M M M M- M M M M M M Table II.C.3 Radionuclide Concentrati6ns in Bi-weekly Composite of Drinking Water. (pCi/L) (continued)

Collection Date 2/18, 25/84 3/4,11/84 3/18, 25/84 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 1-131 ** ** ** ** ** **

Cs-134 < 14.6 < 22.2 < 6.66 < 4.59 < 9.45 < 6.96 Cs-137 < 18.4 < 29.7 < 6.51 < 4.62 '9.27 8.16 (12.2)

Zr-95 < 22.8 < 11.2 < 12.4 < 8.40 < 15.0 < 11.5 fib-95 < 39.5 < 19.4 < 6.90 < 4.55 < 8.13 < 6.30 C0-58 < 16.5 < 27.3 < 5.97 < 4.13 < 7.41 < 5.40 Mn-54 < 15.7 < 25.7 < 4.62 3.15 (7.47) < 6.54 < 4.68 Zn-65 < 31.8 < 49.3 11.7 (17.6) < 6.94 13.4 (23.9) < 10.9 Fe-59 < 41.8 < 85.5 < 17.5 < 11.4 < 19.4 < 14.6 00-60 < 14.6 < 21.8 < 4.'6 8 < 3.32 < 6.66 < 5.16 Ba-140 La-140 *** *** *** *** *** ***

• 1.960 (Due to counting statistics only.) ,

• • • Elapsed time too long to accurately detennine concentration.

• • Analysis performed on evaporated sample.

M M M M M M M M M M M M M M Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pC1/L) (continued) bilectionDate 3/31,4/7/84 4/14, 21/.84 4/28. 5/5/84 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 1-131 ** ** ** ** < 1.94 < 1.93 Cs-134 < 6.20 < 7.75 < 7.35 10.9 (7.65) < 6.65 < 6.53 Cs-137 < 8.70 < 10.9 < 6.96 < 5.97 < 6.97 < 6.95 Zr-95 < 3.06 < 3.87 < 11.8 < 10.2 < 12.8 < 10.5 Nh-95 < 5.30 < 6.70 < 6.63 < 5.27 < 6.99 < 5.62 00-58 < 7.90 < 12.1 < 6.02 < 4.85 < 6.95 . < 5.24 Mn-54 < 7.20 < 9.30 < 5.12 < 4.33 < 4.70 < 4.82 Zn-65 < 12.0 < 17.1 < 10.1 < 9.71 < 10.6 < 10.6 Fe-59 < 21.1 < 27.0 < 17.0 < 12.4 < 18.2 < 13.2 Co-60 < 6.50 < 8.05 < 5.04 < 4.42 < 5.11 < 4.99 Ba-140 *** *** *** *** < 1.02 < 1.02 La-140 *** *** *** *** < 1.18 < 1.18

• 1.96o (Due to counting statistics only.) -

• • Analyses performed on evaporated sample. g

• • • Elapsed time too long to make accurate calculation of concentration.

M M M M M M M M M M M M M M M Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pC1/L) (continued)

Collection Date 5/12, 19/84 5/26,6/2/84 6/11, 18/84 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 *

• R-3 R-6** R-3 R-6 R-3 1-131 < 2.15 < 0.252 < 2.95 < 3.11 < 1.35 < 1.51 Cs-134 < 14.4 < 9.40 < 6.82 < 11.3 < 7.33 < 6.99 Cs-137 < 12.9 < 12.0 < 7.23 < 10.2 < 7.59 < 7.09 Zr-95 < 38.4 < 4.25 < 14.3 < 25.0 < 18.5 < 14.2 rib-95 < 40.0 < 7.35 < 7.72 < 21.5 < 10.6 < 8.14 Co-58 < 21.2' < 10.4 < 7.28 < 13.4 < 8.70 < 7.15 Mn-54 < 14.5 < 9.73 < 5.22 < 9.76 < 5.62 < 5.05 Zn-65 < 41.1 < 18.0 < 10.9 < 23.0 < 12.3 < 11.0 Fe-59 < 64.3 < 28.8 < 21.1 < 9.50 < 18.2 < 21.4 00-60 < 14.1 < 9.18 < 5.41 < 10.5 < 5.33 < 5.16 Ba - 140 *

• 3.42 (1.43) < 1.42 < 1.19 < 1.32 < 0.771 < 0.829 La - 14 0 *

• 3.96 (0.701) < 1.63 < 1.37 < 1.40 < 0.884 < 0.956

• 1.96o (Due to counting statistics only.)

• • Analyzed by an outside lab.

M M M M M M M M M M Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinkin9 Water. (pCi/L) (continued)

Collection Date 6/23,30/84 7/7 , 14/84 7/21,28/84 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 I-131 2.02 (1.27) 1.97 (1.01) < 0.219 < 0.155 < 0.302 < 0.201 Cs-134 < 3.02 < 8.46 4.63(4.96) < 3.03 < 5.28 < 2.92 Cs-137 3.00 (3.54) < 8.13 < 3.31 < 2.72 < 5.25 4.23 (4.77)

Zr-95 < 8.04 < 16.5 < 10.5 12.7 (17.5) < 13.0 < 7.17 tib-95 4.44 (4.32) < 9.40 3.80 (8.00) 7.29 (5.91) 14.4 (10.4) 5.19 (5.43) 00-58 < 6.84 < 8.25 5.85(6.57) < 3.33 < 6.00 < 3.12 Mn-54 < 2.10 < 5.99 < 2.57 < 2.03 < 4.08 < l.97 Zn-65 < 4.97 < 14.3 < 6.14 < 4.80 < 9.69 < 4.56 Fe-59 < 11.0 < 27.5 < 14.9 < 10.7 < 20.9 < 9.39 C0-60 < 1.94 < 6.43 < 2.28 < l.88 < 3.96 < 1.80 Ba-140 < 0.543 < 0.557 < 0.635 < 0.977 < 0.786 < 1.19 La-140 < 0.625 < 0.640 < 0.730 < 1.12 < 9.05 < 1.36

• 1.96o (Due to counting statistics only.)

M M M '

M M Table II.C.3 Radion~uclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L) (continued)

Collection Date 8/4, 11/84 8/19, 25/84 9/1,8/84 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 ** R-3 ** R-6 R-3 R-6 R-3 1-131 < 0.419 < 0.475 < 0.194 < 0.155 < 0.400 <-0.474 Cs-134 < 71.6 < 14.2 < 8.91 < 8.23 < 7.80 < 8.34 Cs-137 < 64.9 < 13.3 < 7.71 < 7.70 9.54 (12.4)* 12.5 (12.2)

Zr-95 < 151 < 29.3 < 13.8 < 13.1 < 11.6 < 12.1 Nb-95 < 114 < 23.3 10.2 (10.0) < 7.02 < 6.45 6.90 (9.12) 00-58 < 83.1

< 17.7 < 6.06 < 6.54 < 5.58 < 5.58 Mn-54 < 67.8 < 13.6 < 5.07 < 5.25 < 4.62 5.82 (10.8)

Zn-65 < 182 < 35.3 < 11.7 < 11.2 < 10.5 < 11.7 Fe-59 < 223 < 46.7 < 14.6 < 14.1 13.0 (27.7) < 14.3 Co-60 < 66.0 < 14.5 < 5.13 < 5.46 < 5.07 < 4.92 Ba-140 < 2.20 < l.77 < 0.640 < l.77 < l.59 < 1.77 La-140 < 2.53 < 2.04 < 0.737 < 2.04 < l.83 < 2.04

• 1.960 (Due to counting statistics only.)

• • Analyzed by outside laboratory.

Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L) (continued)

Collection Date 9/15, 22/84 9/29, 10/6/84 10/13,20/84 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 I-131 < 0.435 < 0.475 < 0.219 < 0.366 < 0.211 < 0.183 Cs-134 < 5.85 < 7.11 3.27 (3.27)* < 5.76 < 8.22 < 5.82 Cs-137 < 6.21 7.65 (13.2) 2.35 (4.17) < 5.70 < 8.49 < 6.30 Zr-95 < 8.58 11.6 < 3.36 < 8.94 < 12.5 < 9.96 Nb-95 < 4.92 < 6. 81 3.33 (2.51) < 5.10 < 7.05 <5.76 C0-58 < 4.41 < 5.91 < l.55 < 4.38 < 6. 51 < 5.37 Hn-54 < 4.29 < 5.37 < l.50 < 3.99 < 6.73 < 4.26 Zn-65 < 9.45 < 12.2 < 3.54 < 9.45 < 12.4 < 9.91 Fe-59 < 10.7 < 15.7 < 3.45 < 11.2 < 16. 5 < 13. 5 00-60 < 4.47 < 5.16 < 1.57 < 4.08 < 5.76 < 4.29 Ba-140 < l.68 < 1.77 < 0.692 < l.51 < 0.656 < Q977 La-140 < l.93 < 2.04 < 0.796 < 1.73 < 0.754 < 0J54

• 1.960 (Due to counting statistics only.)

0

m m m m M M M M M Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pC1/L) (continued) ecdon Date 10/27, 11/3/84 11/10, 17/84 11/24, 12/1/84 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 I-131 < 0.422 < 0.477 < 0.530 < 0.479 ** < 0.475 Cs-134 11.1 (11.2)* < 7.05 < 2.56 < 4.00 < 3.66 5.34 (3.66)*

Cs-137 < 7.99 < 7.22 2.65(4.43) < 4.11 < 3.54 < 3.65 Zr-95 < 13.3 < 10.2 < 3.77 < 5.95 < 5. 41 < 5.40 tib-95 < 7.18 < 5.48 < 1.98 < 3.32 5.41(4.06) < 2.90 C0-58 < 7.04 < 4.56 < 1.68 < 3.08 < 2.52 < 2.56 Mn-54 < 5.74 < 4.53 < 1.60 < 2.83 < 2.37 < 2.43 Zn-65 < 13.2 < 10.1 < 3.84 < 6.45 < 5.77 < 5.36

< 17.6 < 10.2 < 4.08 < 7.69 < 5.84 < 5.77 Fe-59

< 6.07 < 4.86 < 1.66 < 2.96 < 2.51 < 2.51 C0-60

< 29.5 < 10.2 4.85 < 8.20 < 6.16 < 5.88 Ba-140

< 33.9 < 11.7 < 5.58 < 9.43 < 7.08 < 6.77 La-140

• 1.96o (Due to counting statistics only.)

• • Sample could not be analyzed due to contamination. $

m M M M M M M M M M M M M M M M M Table ll.C.3 Radionuclide Concentrations in Bi-weekly Composite of Drinking Water. (pCi/L) (continued)

Collection Date 12/8, 15/84 12/22, 29/84 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collint R-6 R-3 R-6 R-3 1-131 < 0.546 < 0.534 < 6.577 < 0.722 Cs-134 < 3.72 < 3.52 < 2.91 3.38 (4.18)

Cs-137 < 3.56 < 3.31 < 2.68 < 2.91 Zr-95 < 5.29 < 5.02 < 4.18 < 4.54 Hb-95 < 2.82 < 2.54 < 2.18 < 2.36 00-58 < 2.45 < 2.35 < l.89 < 2.02 Hn-54 < 2.39 < 2.20 < l.80 < l.94 Zn-65 < 5.72 < 4.72 < 3.89 < 4.07 Fe-59 < 5.58 < 5.10 < 4.56 5.26 (11.1)

C0-60 < 2.48 3.00(5.10) < l.86 < 1.94 Ba-140 < 4.76 < 4.09 < 5.42 < 6.09 La-140 < 7.19 < 6.34 < 6.23 < 7.00

• 1.96o (Due to counting statistics only.)

e

50

2. Surface Water.

Surface water is collected and analyzed from two sites downstream from the reactor effluent. Since the water effluent can be directed to either river, there are upstream and downstream sampling locations on each river.

Table II.C.4 shows tritium concentrations measured at the four surface water sites. Most of the values were less than MDC.

However, the samples collected July 14, 1984 show evidence of elevated tritium concentrations at the downstream site. (Table II.B.2 confirms release of tritium in water during the second and third weeks of July.) These elevated downstream concentrations were significantly higher than upstream for the sampling date. The magnitude of the increase, however, was small and was not sufficient to cause the yearly mean of the downstream concentrations to be significantly higher than the upstream mean. Both means in fact were less than MDC.

Table II.C.5 shows measurements of fission product and activation product concentrations in surface water samples collected monthly. As pointed out earlier, for January, February and part of March, detector problems did not allow prompt counting of water samples and the decay time was too great for measurement of Ba-La-140. This was corrected partially during March by counting samples on the large Nal detector and finally in June by use of the additional Ge(L1) detector. If indeed Ba-La-140 had been present in any of the water samples analyzed during the deficient periods, elevated concentrations of the other fission or activation I

51 products would have been expected. Inspection of Table II.C.5 reveals that this was not the case during any period of 1984. There were occasional positive values but the mean of the downstream sites was not significantly different from the mean of the upstream sites during 1984 for any of the gamma-ray emitting radionuclides measured. This should be expected as the Effluent Release Report shows negligible release in water of all radionuclides measured in this contract with the exception of tritium.

A continuous water sampler is located at station A-25 (E-38 in previous reports). An aliquot of the farm pond outlet is sampled every 10 minutes and the composite collected weekly.

The weekly composites are then combined for the monthly sample.

The results of these samples are shown in Table II.C.6. For every month except February there is evidence of measurable tritium release. Mean values for the other radionuclides are less than MDC.

Ground water is sampled quarterly at two locations. These are F-16, a well on the farm immediately North and the closest to the reactor down the hydrological gradient, and at R-5, the Milliken city well which serves as a Reference location. Table II.C.7 lists the measured concentrations of possible fission products and activation products in ground water. Positive results have confidence limits that include zero and are assumed to be methodological variation. For example, the positive Nb-95 values are suspect because it is assumed that Nb follows the behavior of its parent Zr and corresponding positive Zr concentrations were I

I

I 52 not observed on those dates. In fact it is assumed that 95% of the Zr-95 which enters the soil system will be rapidly absorbed or precipitated, particularly in basic soils.I If the radionuclides listed in Table II.C.7 were present in ground water then tritium would be observed in the highest concentration.

This conclusion is valid because the activity of tritium released is significantly greater than any of the other radionuclides, and is far more mobile than any other. The apparent elevated La-140 value in the sample collected at F-16 on March 10, 1984 is considered also to be a false positive value. It should be noted that the gama-ray of the daughter product La-140 is actually measured and Ba-140 is calculated from that result assuming transient equilibrium. No measured values exceeded reporting levels for any of the radionuclides. -

.I 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.

I I

I

.I 1

I Radionuclide Distribution and Trans3 ort in Terrestrial and Aquatic Ecosystems; P.J. Coughtrey and 14.C. Thorne; A.A. Balkema-Rotterdam, 1983.

I I

I

m m M M M M M M M M M M M M M M M m Table II.C.4 Tritium Concentrations in Surface Water. (pci/L)

Qownstreaq'_Si_t es Upstream Sites Collection St. Vrain 'i. Platte St. Vrain S. Platte Date F-20 R-10 A-21 f-19 1-14-84 804 (291) < 238 238 577 (288) 2-11-84 414 (285) 427 (285) 596 (287) < 247 3-10-84 < 244 < 244 < 244 < 244 4-21-84 270 (281) < 235 < 235 441 (283) g 5-19-84 < 243 < 243 < 243 < 243 6-16-84 312 (282) 3'26 (283) < 235 380 (283) 7-14-84 1,090 (307) 2,400 (321) < 249 < 249 8-19-84 < 241 < 241 < 241 < 241 9-15-84 < 246 < 246 < 246 < 246 10-13-84 321 (289) < 242 < 242 < 242 11-10-84 < 242 < 242 < 242 < 242 12-8-84 < 253 < 253 < 253 < 253 l.96 o (Due to counting statistics only.)

~

g ~~~ - - - -

u.

E Table II.C.5 Radionuclide Concentrations in Surface Water. (pCi/L) (continued) r .

Collection Date: January 16, 1984 . .

it 1

~, <l

i Downstream Sites Upstream Sites i ' --

,);

Radio- 'St. Vrain S. Platte St . Vrain ' _ S. Pla tig '

Nuclide F-20 R-10 A-21 F-19 ,

Cs-134 < 1.64 < 4.39 < 6.75 < 4.62 i l

Cs-137 < 1.89 < 6.15 < 5.25 <6Y40 ,

q a,

Zr-95 < 5.38 < 22.1 < 34.4 < 31.2 /*

Hb-95 < 9.30 -< 38.3 4 59.6 < 54.0 Co-58 < 4.24 < 23.5 < 22.7 < 22.9 Mn-54 < 1.77 < 6.05 < 6.20 < 7.60 Zn-65 < 3.89 < 15.9 < 17.1 < 19.0 fe-59 < 14.7 < 72.5 < 92.5 < 168 Co-60 < 1.28 < 4.56 < 2.66 < 4.75 Ba-140 La-140

'* No Ba-La calibra' tion available on bags, elapsed time too long to accurately determine concentration.

m m M M M m M M M M M M M m M M m e m Table II.C.5 Radionuclide Concentrations in Surface Water. (pCl/L) (continued)

Collection Date: February 11, 1984, Downstream Sites Upstream Sites Radio- St. Vrain S. Platte St. Vrain S. Platte Nuclide F-20 R-10 A-21 F-19 Cs-134 < 6.85 < 5.90 < 3.81 < 5.40 Cs-137 < 7.90 < 5.25 < 5.85 < 6.90 u,

, Zr-95 < 25.8 < 25.7 < 23.4 < 28.4 Nb-95 < 44.6 .< 44.5 < 40.6 < 49.2 Co-58 < 13.9 < 19.1 < 17.6 < 17.4 Mn-54 < 5.80 < 5.85 < 7.15 < 5.85 Zn-65 < 13.9 < 11.2 < 11.3 < 13.5 Fe-59 < 80.0 < 109 < 89.5 < 61.0 Co-60 < 5.00 < 3.90 < 4.71 8.74 (7.36)

Ba-140 ** ** ** **

La -140 1.96 o (nue to counting statistics only.)

• • No Ba-La calibration available on bags, elapsed timetoo long to accurately determine concentration.

M M M. M .M M M M M M M M M M M W~M M 'M i

Table II.C.5 Radionuclide Concentrations in Surface Water. (pCi/L) (continued)

Collection Date: March 10, 1984 .

Downstream Sites Upstream Sites ,

l Radio- St. Vrain S. Platte St. Vrain S. Platte Nuclide . F-20 R-10 A-21 F-19 1

l Cs-134 < 4.81 < 4.73 < 6.90 < 6.80 Cs-137 < 4.62 4.84 (8.73) < 9.25 < 9.40 l m

Zr-95 < 7.25 < 8.20 < 2.75 < 2.79 Nb-95 < 4.21 ,< 4.72 < 4.75 < 4.83 Co-58 4.94 (5.51) < 4.21 < 6.90 < 6.85 Mn-54 . < 3.41 < 3.33 < 7.20 < 7.50 Zn-65 < 7.44 < 7.13 < 13.3 < 13.7 Fe-59 < 9.59 < 11.2 < 18.5 < 18.7 Co-60 < 3.53 3.73 (7.70) < 6.75 < 6.80

• • < 7.43 ** < 6.65 Ba-140 La-140

• • < 8.55 ** < 7.65 1.96 o (Due to counting statistics only.)

• • Elapsed time to'o long to accurately determine concentration.

m .M M M M 'M' M M M M M M M M M M. M Mm Table II.C.5 Radionuclide Concentrations in Surface Water. (pCi/L) (continued)

Collection Date: April 21, 1984 ,

Downstream Sites Upstream Sites Radio- St. Vrain S. Platte St. Vrain S. Platte Nuclide F-20 R-10 A-21 F-19 Cs-134 < 6.49 < 8.87 < 6.93 < 6.09 Cs-137 < 6.83 < 8.40 < 6.67 < 6.60 Zr-95 < 11.4 < 14.0 < 12.2 < 11.0 Nb-95 < 6.56 , < 8.07 8.59 (9.42) < 5.92 Co-58 < 11.4 < 7.87 < 5.77 < 5.69 Mn-54 < 4.72 < 6.29 < 4.73 < 4.70 Zn-65 < 10.7 < 13.5 < 11.0 < 10.4 Fe-59 < 15.9 < 20.1 < 16.6 < 15.0 Co-60 < 5.36 < 6.83 < 5.02 < 4.81 Ba-140 < 1.58 < 1.49 < 1.58 < 1.49 La-140 < 1.81 < 1.72 < 1.81 < 1.72 1.96 o (Due to counting statistics only.)

M M M M M M M M -M M M M M M M M M- M

$ Table II.C.5 Radionuclide Concentrations in Surface Water. (pCi/L) (continued)

Collection Date: May 19, 1984 .

Downstream Sites Upstream Sites Radio- St. Vrain S. Platte St. Vrain S. Platte l

Nuclide F-20 R-10 A-21 F-19 Cs-134 < 5.16 6.43 (6.14) < 4.13 < 7.24 Cs-137 < 5.02 < 4.89 < 4.06 < 7.19 m

Zr-95 < 9.73 < 9.19 < 7.83 < 13.2

Nb-95 < 5.13 ,< 4.90 < 4.50 < 7.33 Co-58 < 4.63 < 4.44 < 3.81 < 6.70 i

< 3.35 < 2.92 < 5.31 Mn-54 < 3.66 Zn-65 < 8.44 < 7.53 < 6.41 < 11.1 Fe-59 < 14.3 < 13.4 < 11.7 < 20.4 Co-60 - 3.92 < 3.41 < 2.92 < 4.77 Ba-140 < 20.9 < 1.76 < 1.14 1.76 (2.00)

La-140 < 31.5 < 2.02 < 1.31 2.02 (2.30)

~

1.96 o (Due to counting statistics only.)

mm W M .M M M M M M M- M M M M M MW W Table II.C.5 Ratlionuclide Concentrations in Surface Water. (pCi/L) (continued)

Collection Date

June 16., 1984 .

Downstream Sites Upstream Sites Radio- St. Vrain S. Platte St. Vrain S. Platte Nuclide' F-20 R-10 A-21 F-19 Cs-134 < 2.56 < 0.971 ** < 5.24 Cs-137 < 0.868 ** < 5.11 3.06 (4.35) m Zr-95 6.63 (13.3) < 2.82 ** < 12.6 ")

lib-95 < 2.94 ,< 1.49 **

7.17 (9.97)

Co-58 < 2.56 < 1.22 ** < 6.06 Mn-54 < 1.75 < 0.674 ** < 3.89 Zn-65 < 3.96 < 1.55 ** - < 8.66 Fe-59 < 7.71 < 3.88 ** < 20.4 Co-60 < 1.67 < 0.596 ** < 3.67 Ba-140 < 0.781 < 0.740 < 0.603 < 0.789 La-140 < 0.898 < 0.851 < 0.694 < 0.898 1.96 o (Due to counting statistics only.)

• • Sample counted on HaI detector, system not calibrated for other isotopes.

M M M M .M M M M M M'M M M M M M M M M Table II.C.5 Radionuclide Concentrations in Surface Water. (pCi/L) (continued)

Collection Date: July 14, 1984 .

~

Downstream Sites Upstream Sites Radio- St. Vrain S. Platte St. Vrain S. Platte Nuclide F-20 R-10 A-21 F-19 Cs-134 < 3.15 < 2.13 < 3.51 < 3.12 Cs-137 < 2.83 3.75 (3.51) < 3.51 < 2.75 Zr-95 < 8.01 < 5.79 < 11.0 < 7.29 8 Nb-95 < 4.29 , < 3.09 < 6.18 4.14 (5.67)

Co-58 < 3.48 < 2.49 < 5.28 < 3.24 Mn-54 < 2.16 < 1.48 < 2.79 < 2.01 Zn-65 < 4.98 < 3.39 < 6.66 < 4.83

, re-59 < 11.2 < 8.22 < 20.0 < 9.90 Co-60 2.47 (4.56) < 1.33 < 2.56 < 1.91 Ba-140 < 11.8 < 11.7 < 0.584 < 9.33 La-140 < 13.5 < 13.4 < 0.672 < 10.7 4

1.96 o (Due to counting statistics only.)

MM M M mM M M M M M M M M M .M-Table II.C.5 Radionuclide Concentrations in Surface Water. (pCi/L) (continued)

Collection Date: August 19, 1984 .

Downstream Sites Upstream Sites Radio- St. Vrain S. Platte St. Vrain S. Platte Nuclide F-20 R-10 A-21 F-19 Cs-134 < 14.5 < 14.6 < 14.5 < 14.1 Cs-137 < 13.3 < 13.4 < 13.3 < 13.6 Zr-95 < 26.7 < 27.3 < 26.7 < 27.1 23 Nb-95 < 19.5 . < 17.5 < 19.5 < 18.4 Co-58 < 15.0 < 16.1 < 15.0 < 15.2 Mn-54 < 12.4 < 13.0 < 12.4 < 12.6 Zn-65 < 34.2 < 34.8 < 34.2 < 32.9 Fe-59 < 38.0 < 37.7 < 38.0 < 36.3 Co-60 < 13.3 < 14.0 < 13.3 < 14.3 Ba-140 < 176 < 155 < 176 < 168 La-140 < 202 < 178 < 202 < 193

• Analyzed by out' side laboratory.

Table II.C.5 Radionuclide Concentrations in Surface Water. (pCi/L) (continued)

Collection Date: September 9,1984 .

Downstream Sites Upstream Siles Radio- St. Vrain S. Platte St. Vrain S. Platte Nuclide F-20 R-10 A-21 F-19 Cs-134 < 0.528 < 2.89 < 7.38 < 7.23 Cs-137 0.919 (0.862) 3.60 (5.01) < 7.20 6.84 (12.5) cn Zr-95 < 1.28 < 4.44 < 10.2 < 10.2 Hb-95 1.30 (0.980) . < 2.36

, 5.64 (8.25) 5.58 (7.53)

Co-58 < 0.566 < 2.07 < 4.98 < 4.65 Mn-54 < 0.354 < 1.87 < 4.92 < 4.41 Zn-65 < 0.826 < 4.23 < 12.2 < 10.7 re-59 < 1.71 < 4.74 < 11.5 < 10.4 Co-60 0.353 (0.752) < 1.93 < 4.68 < 4.50 Ba-140 < 15.7 < 0.695 < 1.18 < 1.01 La-140 < 18.1 < 0.799 < 1.36 < 1.16 1.96 o (Due to counting statistics only.)

Table II.C.5 Radionuclide Concentrations in Surface Water. (pCi/L) (continued)

Collection Date: October 13, 1984 .

Downstream Sites Upstream Sites Radio- St. Vrain S. Platte St. Vrain S. Platte Nuclide F-20 R-10 A-21 F-19 Cs-134 < 0.912 < 1.19 < 2.55 < 1.92 Cs-137 < 0.884 < 1.18 2.41 (4.27) 2.43 (3.31)

O Zr-95 < 1.30 < 1.72 < 3.45 < 2.85 Nb-95 1.11 (0.966) ,< 0.915 < 1.78 < 1.33 Co-58 < 0.617 < 0.912 < 1.51 < 1.39 Mn-54 < 0.586 < 0.812 < 1.50 < 1.25 Zn-65 < 1.31 < 1.85 < 3.50 < 2.87 Fe-59 < 1.33 < 2.22 < 3.44 < 2.64 Co-60 < 0.599 < 0.848 < 1.59 < 1.26 Ba-140 < 1.02 < 1.92 < 2.44 < 2.10 La-140 < 1.54 < 2.90 < 3.69 < 3.17 1.96 o (Due to counting statistics only.)

Table II.C.5 Radionuclide Concentrations in Surface Water. (pC1/L) (continued)

Collection Date: November 10, 1984.

Downstream Sites Upstream Sites Radio- St. Vrain S. Platte St. Vrain S. Platte Nuclide F-20 R-10 A-21 F-19 Cs-134 < 6.94 < 7.04 < 7.43 < 7.10 Cs-137 < 6.74 < 6.49 < 7.96 < 6.52

• cn Zr-95 < 10.3 < 9.87 < 11.8 11.2 (23.5)

Nb-95 6.43 (7.37) ,< 5.55 < 6.57 8.21' (7.30)

Co-58 < 4.47 < 4.30 < 5.60 < 4.88 Mn-54 < 4.55 < 4.57 < 5.57 < 4.60 Zn-65 < 10.1 < 9.50 < 11.8 < 9.91 Fe-59 < 9.92 < 10.0 14.3 (32.7) < 10.9 Co-60 < 4.39 < 4.43 < 6.07 < 4.91 Ba-140 < 9.47 < 10.26 < 16.3 < 11.4 La-140 < 11.2 < 11.8 < 18.7 < 13.1 1.96 o (Due to counting statistics only.)

W W W W .Q Table II.C.5 Radionuclide Concentrations in Surface Water. (pCi/L)

Collection Date: December 8, 1984.

Downstream Sites Upstream Sites Radio- St. Vrain S. Platte St. Vrain S. Platte Nuclide F-19 R-10 A-21 F-20 Cs-134 < 3.05 < 6.06 < 3.02 < 3.46 Cs-137 < 2.85 < 3.39 3.16 (4.89)

• 9.08 (11.4)

Zr-95 < 4.07 < 5.26 < 4.14 < 9.57 E Hb-95 < 2.17 < 2.67 < 2.20 < 5.24 C0-58 < 1.94 < 2.36 < l.86 < 4.78 Mn-54 < l.91 < 2.30 < 1.83 < 4.38

< 4.13 < 5.01 < 4.04 < 9.14 Zn-65

< 4i30 < 5.53 < 4.41 < 9.99 Fe-59 Co-60' < 1,99 < 2,43 1.93 (4.23) < 4.26 Ba-140 < 3.08 < 4.45 < 3.48 < 7.09 La-140 < 4.78 < 6.90 < 5.40 < 11.0 1.96 o (Due to counting statistics only.)

W M M M M M M M Table II.C.6 Radionuclide Concentrations in Monthly Composites of Surface Water. (pCi/L)(continued)

Radio- ,,,

nuclide January February March April May June Cs-134 < 2.70 < 5.05 < 8.40 < 8.75 < 7.85 < 7.98 t

Cs-137 < 3.31 < 4.99 < 8.94 < 14.1 < 9.30 < 7.76 Zr-95 < 6.07 < 38.1 < 12.9 < 4.05 < 5.50 < 19.4 Nb-95 < 10.5 < 65.9 < 7.44 < 7.00 < 9.50 < 15.2 C0-58 < 4.37 < 11.8 < 6.42 < 10.7 < 9.20 < 10.1 Mn-54 < 2.79 < 5.40 < 6.12 < 10.5 < 9.89 < 6.97 g Zn-65 < 6.45 < 10.1 < 13.3 < 20.0 < 17.1 < 16.7 Fe-59 < 11.1 < 98.0 < 15.9 < 28.0 < 25.8 < 29.6 Co-60 < 2.54 < 4.28 < 6.30 < 9.60 < 7.56 < 6.96 Ba-140

• • ** < 30.4 < 1.58 < 1,68 < 0.770 La-140

• • ** < 20.3 , < 1.81 < 1.93 < 0.827 11 - 3 13,900 (415) 7,190 (364) '24,100 (589) 6,160 (172) < 243 3,000 (696) 1.96 o (Due to counting statistics.)

• • Elapsed time too long to accurately determine concentration.

• • • Analyzed by outside laboratory. -

W M W W W- M M W M M M M W W M M M MW a

e Table II.C.6 Radionuclide Concentrations in Monthly Composites of Surface Water, A-25, (pC1/L).

Radio-nuclide July August September October November December

. Cs-134 < 2.72 < 7.32 < 2.97 < 5.39 < 2.17 < 1.51

• I Cs-137 < 5.57 < 6.57 5.71 (4.98) < 5.14 2.68 (3.67) 2.91 (2.52) '

Zr-95 < 6.12 < 13.4 < 2.10 < 11.4 < 3.34 < 2.61 Nb-95 8.94 (4.62) 8.52 (10.2) < 2.79 < 6.37 2.18 (2.55) < 1.36 C0-58 < 2.77 < 6.90 < 2.33 < 5.87 < l.54 < 1.18 Mn-54 < l.90 < 4.80 < l.91 < 3.80 < 1.37 1.27 (2.18)

O Zn-65 < 4.38 < 11.3 < 4.29 < 8.50 < 3.09 < 2.05 Fe-59 < 7.62 < 19.1 < 5.94 < 17.6 < 3.69 < 3.04 Co-60 < l.76 < 5.04 < 1.88 < 3.77 < 1.40 < 0.968 Ba-140 < 4.83 < 6.56 < 1.50 < 6.38 < 5.32 < 5.87 La-140 < 5.55 < 7.54 < 1.73 < 9.64 < 6.12 < 8.87 H-3 9,468 (188) 11,395 (198) 19,684 (203) 24,600 (505) 24,600 (505) 15,600 (436) l.96 o (Due to counting statistics.)

W W W W W W W M W W W W W W W m W g Table II.C.7 Radionuclide Concentrations in Ground Water. (pCi/L) 6-16-84 3rd Quarter 9-19-84 4th Quarter 12-8-84 1st Quarter 3-10-84 2nd Quarter Radio-nuclide F-16 R-5 F-16 R-5 F-16 R-5 F-16 R-5 Cs-134 < l.23 < 14.1 < 4.39 < 2.79 < 7.03 9.84(10.I} < 2.99 < 2.83 Cs-137 < 2.33 < 18.5 < 4.46 2.83 (4.58) < 6.81 < 8.93 < 2.82 < 2.75 Zr-95 < 6.01 < 9.98 < 5.63 < 11.6 < 10.7 < 4.16 < 4.04 6.08 (8.14)

Nb-95 < 1.92 < 10.4 < 5.37 7.48 (4.25) 12.1 (7.65) 5.37 (7.41) 4.79 (3.24) < 2.12 Co-58 < 1.94 < 14.1 < 4.97 < 2.47 < 4.71 < 4.44, < 2.05 < 1.95 g Hn-54 < 1.74 < 15.1 < 3.43 < 1.81 < 4.38 < 4.59 < l.88 < 1.82 Zn-65 < 3.64 < 26.8 < 8.15 < 4.27 < 11.6 < 10.5 < 3.88 < 4.00

< 42.0 < 15.0 < 6.78 < 11.3 < 10.9 < 4.48 < 4.20 Fe-59 7.67 (11.9)

Co-60 2.19 (4.08) < 14.6 < 3.21 < 1.77 < 4.77 < 4.59 < l.96 < l.89 11.5 (14.6) < 16.5 < 62.8 < 0.709 < 1.60 < l.59 < 4.73 < 3.25 Da-140 13.2 (16.8) < 19.0 < 94.9 < 0.816 < 1.84 < l.82 < 5.44 < 4.91 La-140 11- 3 < 244 < 244 452 (283) , 314 (283) < 246 < 246 < 253 < 253 1.96 o (Due to counting statistics.)

9

I e9 I Table II.C.8 Maximum Permissible Concentrations in Water.

(10CFR20, Appendix B, Table II)

I-131 3 x 10 2 Ci/L 3

Cs-134 9 x 10 pCi/L 4

Cs-137 2 x 10 pCi/L 4

Zr-95 6 x 10 pCi/L Nb-95 1 x 105pC1/L Co-58 1 x 105 pC1/L 5

Mn-54 1 x 10 pCi/L 5

Zn-65 1 x 10 pCi/L 4

Fe-59 6 x 10 pCi/L Co-60 5 x 104pC1/L Ba-140 3 x 104 pCi/L La-140 2 x 104 pCi/L I

'l I

I I

I I

I - ._ . _ . . __

9 70 II.D. Milk The dairy food chain is the critical pathway for possible radiation dose commitment. The critical individual would be an infant consuming milk produced from cows grazing local pastures.

Milk is the critical. pathway for possible dose commitment to humans from environmental contamination of H-3. I-131, Cs-137 and Sr-9'). For this reason milk is sampled extensively to document the presence or absence of radioactivity due to reactor operations.

During January there were three sampling locations within 5-8km distance from the reactor. An additional three dairies were h located after the January collection, one within Skm and two within the 5-8km range from the reactor. To meet the required technical specifications, these sites were included in the milk sampling locations. .These six dairies are located in five sectors.

The description of these locations can be found in Table III.B.1 and Figures III.B.1 and III.B.2. There are no dairies within the Facility area (1.6 km radius). In previous reports location A-23 (formerly F-44) was termed a Facility dairy as it is the closest operation to Fort St. Vrain. The single Reference location dairy, I R-8, is 22.5 km West of the reactor in the least predominant wind direction. Herd management practices are virtually identical at all dairy locations.

Table II.D.1 lists the concentrations of all radionuclides that are investigated in milk samples. There'was no significant difference in the mean of the Adjacent samples compared to the Reference samples. The yearly arithmetic mean for the 6 Adjacent area dairies was less than MDC and not statistically different from I

.I

71 the mean of the only Reference dairy (R-8). Elevated tritium concentrations in milk that were 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 milk.

During the 1st and 2nd quarters of 1984, milk was counted directly for I-131. However, due to detector problems, often adequate counting time was unavailable to achieve LLD values. The ion exchange concentration method was not adopted until October 1, 1984, and this corrected the problem. To achieve an LLD of 1.0 pCi/L for I-131, 18.0 liters of milk are now collected and concentrated on an anion exchange resin. The resin is counted by gamma-ray spectroscopy.

During the last quarter of 1984, there were seven measured values in which the required MDC value was not obtained. In all cases the

values were close to the required value, but slightly higher due to changes in background. Analysis of Cs-134, Cs-137, and Ba-La-140 is accomplished by direct counting of the whole-milk sample.

Inspection of Table II.D.1 reveals that statistically significant concentrations were not observed in milk samples collected during 1984. Occasionally positive values for Cs-137 were observed and I

I I

72 I would be expected due to the reservoir of this radionuclide still present in the biosphere as a result of past weapons test fallout.

Arithmetic mean values for all radionuclides were less than the respective MDC values.

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 detennined in the same sample by gamma-ray spectrometry. K-nat concentrations are no longer reported in Table II.D.I.

A close relationship between release and forage deposition of the fission products H-3, Cs-134, Cs-137, I-131, and Ba-La-140 should be expected only if the cows were on pasture or fed green cut forage. This, unfortunately, is not the general feeding practice at the dairies around the reactor. Nearly all cattle feed is hay harvested locally or brought in from Nebraska or from the North Park region of Colorado. At times it can even be cuttings from the previous year. This makes correlation of milk concentrations with air concentrations very difficult. On the other hand, if elevated I-131, H-3, or Ba-La-140 concentrations in milk were noted, the surface depositions must have been reasonably related in time and location due to the short effective half-lives of these radionuclides in the dairy ecosystem.

Contamination of milk samples due to reactor effluents have never been observed during the pre and post-operational periods of Fort St. Vrain.

I

M M M M 'M M M M M M M N M M M M M M M Table II.D.1 Redionuclide Concentrations in Hilk. (pCi/L)

Collection Date 1-30-84 1-30-84 1-30-84 1-30-84 1-30-84 1-30-84 1-30-84 Radio- A-6 A-18 A-22 A-23 A-24 A-26 R-8 nuclide

• • < 0.170 < 0.148 ** ** < 0.154 I-131 < 2.54 Cs-134 < 0.513 < 0.530 < 0.483 < 0.483 Cs-131 3.57 (0.858) < 0.561 < 0.512 < 0.157 Ba-140 < 1.06 < 0.791 < 0.550 < 0.161 La-140 < l.06 < 0.909 < 0.633 < 0.875 11- 3 < 234 < 241 < 237 < 241 _ _ _ _

Collection Date 2-15-84 2-15-84 2-15-84 2-15-84 2-15-84 2-15-84 2-15-84 1-131 < 0.853 < l.31 < 1.10 < 1.01 < l.56 < 1.56 < 1.01 Cs-134 < 0.483 < 0.483 < 0.483 < 0.483 < 0.483 < 0.483 < 0.483 Cs-137 < 0.152 < 0.152 < 0.164 < 0.164 < 0.152 < 0.214 < 0.116 Ba-140 < 0.521 < 0.683 < 0.613 < 0.581 < 0.761 < 0.761 < 0.581 La-140 < 0.600 < 0.785 < 0.705 < 0.668 < 0.875 < 0.875 < 0.668 11- 3 < 238 < 238 < 238 < 238 < 238 < 238 < 238 Collection Date 3-11-84 3-11-84 3-11-84 3-11-84 3-11-84 3-11-84 3-11-84 I-131 < 1.20 < 0.148 < l.56 < 2.02 < 2.84 < 0.783 < l.43 Cs-134 < 0.483 < 0.483 < 0.483 < 0.483 < 0.483 < 0.483 < 0.483 Cs-137 < 0.152 < 0.152 < 0.512 < 0.152 < 0.152 < 0.134 < 0.152 Ba-140 < 0.647 0.929 (0.277) < 0.761 < 0.895 < 1.11 < 0.494 < 0.721 La-140 < 0.744 1.44 (0.430) < 0.875 < 1.03 < 1.28 < 0.568 < 0.829

_3 < 244 < 244 < 244 < 244 < 244 < 244 < 244 1.96 o(Due to counting statistics only.) O Sampling locations not determined.

M M M M M M M M M M M M M M M M M M M Table II.D.1 Radionuclide Concentrations in Milk. (pCi/L) (continued)

Collection Date 4-16-84 4-16_81 8 4-16-84 4-16-84 4-16-84 4-16-B4 -

4-16.-84 _..

I A-24 A-26 R-8 A-6 A-18 A-22 A-23 I{e l-131 < 0.182 < 0.257 < 0.853 < l.56 < 0.167 < 2.02 C

• 1 Cs-134 < 0.483 1.55 (1.36) < 0.483 < 0.483 < 0.483 < 0.483 Cg Cs-137 0.753 (0.813) 2.01 (1.41) < 0.512 < 0.512 < 0.512 < 0.512 Cy Ba-140 < 0.647 < 0.613 < 0.521 < 0.761 1.99 (1.41) < 0.895 Cy La-140 < 0.744 < 0.705 < 0.600 < 0.875 2.29 (1.62) < 1.03 Cg 11- 3 < 235 < 242 < 244 < 244 < 244 < 244 < 241 ColIcction Dat 5-12-84 5-12-84 5-12-84 5-12-84 5-12-84 5-12-84 5-12-84 C- < 0.853 ** < 3.68 < 1.43 I-131 < 1.01 g

< 0.134 Cs-134 2.11 (0.806) Cg 0.530 (0.796) 0.546 (1.12) < 0.483 < 0.483 Cs-137 0.747 (0.831) C < 0.512 1.24 (1.15) < 0.512 < 0.512 3

Ba-140 < 0.581 C 3

< 0.521 < 1.31 < 0.683 < 0.721 La-140 < 0.668 Cg < 0.600 < 1.50 < 0.685 < 0.829 ll-3 < 243 < 243 < 243 < 243 < 243 < 243 Collection Date 5-26-84 5-26-84 5-26-84 5-26-84 5-26-84 5-26-84 _ 5-26-84

< l.20 **

I-131 < l.43 < 1.56 < l.43 < l.10 < l.70 Cs-134 < 0.483 < 0.483 1.09 (1.35) 1.16 (0.942) < 0.483 1.19 (1.52)

Cs-137 0.863 (1.13) < 0.892 1.49 (1.38) 1.09 (0.966) 0.653 (0.935) < 0.512 Ba-140 < 0.721 < 0.761 < 0.721 < 0.613 < 0.803 < 0.647 La-140 < 0.829 < 0.875 < 0.829 < 0.705 < 0.924 < 0.744 I-3 < 243 < 243 < 243 < 243 407 (281) < 235 1.96 o(Due to counting statistics only.) C Instrument malfunction, spectrum printout error detected after sample

• • Sample unavailable, no milk available at dairy.g was destroyed.  %

M M M M M M M M M M M M M M M M' M M M Table II.D.1 Radionuclide Concentrations in Milk. (pCi/L) (continued)

Collection Date 6-11-84 6-11-84 6-11-84 6-11-84 6-11-84 6-11-84 6-11-84 Radio- A-6 A-18 A-22 A-23 A-24 A-26 R-8 nuclide I-131 < l.01 < 0.783 < 0.718 < 0.853 < 0.853 < 0.659 < 0.930 Cs-134 < 0.483 < 0.483 0.910 (1.24) < 0.483 < 0.483 < 0.483 2.15 (0.966)

Cs-137 < 0.512 < 0.512 0.665 (1.27) < 0.512 < 0.512 < 0.512 1.38 (0.989)

Ba-140 < 0.581 < 0.494 < 0.468 < 0.521 < 0.521 < 0.443 < 0.550 I.a - 14 0 < 0.668 < 0.568 < 0.538 < 0.660 < 0.600 < 0.510 < 0.633 11- 3 < 234

< 241 < 235 < 235 < 235 < 235 < 235 follection Date 6-23-84 6-23-84 6-23-84 6-23-84 6-23-84 6-23-84 6-23-84 I-131 < 0.698 < 0.718 < 0.605 < 0.605 < 0.642 < 0.605 < 0.605 Cs-134 < 0.513 < 0.483 < 0.483 < 0.530 < 0.513 < 0.483 < 0.530 Cs-137 < 0.514 < 0.512 < 0.512 < 0.561 < 0.545 < 0.512 1.06 (1.20)

Ba-140 < 0.472 < 0.468 < 0.420 < 0.420 < 0.447 < 0.420 < 0.420 La - 140 < 0.542 < 0.538 < 0.483 < 0.483 < 0.514 < 0.483 < 0.483 11- 3 < 245 < 245 < 245 < 245 < 245 < 244 < 245 Collection Date 7-7-84 7-7-84 7-7-84 7-7-84 7-7-84 7-7-84 7-7-84 I-131 < 2.14 < l.80 < l.65 < l.51 < 2.14 < 2.33 < 1 96 Cs-134 < 0.513 < 3.27 < 3.33 < 12.0 < 3.42 < 3.12 < 5.91 Cs-131 1.29 (1.49) 2.97 (5.40) < 3.00 15.8 (20.6) < 3.09 < 2.38 < 5.55 Ba-140 < 0.952 < 0.854 < 0.809 < 0.767 < 0.952 5.51 (1.18) < 0.902 La-140 < 1.09 < 0.982 < 0.931 < 0.882 < l.09 6.33 (1.36) < 1.04 II-3 < 230 < 236 < 235 < 235 < 235 < 235 < 235 1.96 a(Due to counting statistics only.)

U

M M M M M M M M M M M M M M M M M M M Table II.D.1 Radionuclide Concentrations in Milk. (pCi/L) (continued)

Collection Date 7-28-84 7-28-84 7-28-84 7-28-84 8-4-84 ~ 7-28-84 7 28 84

" A-18 A-22 A-23 A-24 A-26 R-8 u

A-6 e

l-131 < 0.698 < 0.904 < 0.985 < 0.829 < 1.17 < 0.829 < 0.761 Cs-134 < 5.79 < 5.34 < 5.79 < 6.21 3.42 (3.30) < 3.69 < 5.67 Cs-137 < 5.58 < 5.07 < 5.64 < 5.61 < 2.55 < 3.54 < 5.79 Ba-140 < 0.472 < 0.555 < 0.585 < 0.525 < 0.652 < 0.525 < 0.525 La-140 < 0.542 < 0.638 < 0.673 < 0.604 < 0.750 < 0.604 < 0.604 11- 3 < 246 < 246 < 246 < 244 < 244 < 246 < 252 Collection Date 8-11-84 8-11-84 8-11-84 8-11-84 8-20-84 8-11-84 8-11-84 1-131 < 0.904 < 1.17 < 1.65 < 1.51 C < 1.65 < 0.985 3

Cs-134 < 5.61 < 7.65 < 8.85 < 6.96 < 8.01 < 7.26 < 8.01 Cs-137 7.41 (9.42) 10.1 (13.3) < 7.35 < 6.87 < 6.99 < 7.20 < 7.41 Ba- 140 < 0.555 < 0.652 1.04 (1.43) 5.24 (1.44) C < 0.809 < 0.585 1

La-140 < 0.638 < 0.750 1.19 (1.65) 6.02 (1.66) C < 0.931 < 0.673 1

11- 3 < 241 < 248 < 248 < 248 < 241 < 241 < 241 Collection Date 8-25-84 8-25-84 8-25-84 8-25-84 9-1-84 8-25-84 8-25-84 h*

I-131 < 0.698 < 0.698 Cy < 0.904 < 0.641 < 0.761 < 0.641 Cs-134 < 4.50 < 10.5 < 10.1 < 4.11 < 7.50 < 7.59 < 9.36 Cs-137 < 4.75 11.8 (19.2) < 9.06 5.61 (7.02) < 7.20 < 7.47 < 9.06 Ba-140 < 0.472 < 0.472 C < 0.555 < 0.447 < 0.498 < 0.441 3

La-140 < 0.542 < 0.542 C < 0.638 < 0.514 < 0.572 < 0.514 3

11- 3 < 237 < 237 < 245 < 245 < 245 < 245 < 245 e

1.96 o(Due to counting statistics only.)

Cy Instrument malfunction. Nal printout not available, Cs-134 & Cs-137 detennined by Ge(L1) detector. M

mm M M M M M M M M M M M M M M M M m~

Table II.D.1 Radionuclide Concentrations in Hilk. (pCi/L) (continued)

Collection Date 9-8-84 9-8-84 9-8-84 9-8-84 9-15-84 9-8-84 9-8-84 R^ A-23 A-24 A-26 R-8 A-6 A-18 A-22 u e 1-131 1.78 (1.25) < 0.829 < 0.985 < 0.904 < 0.761 < 0.641 < 0.761 Cs-134 10.4 (9.66) < 7.47 ,

< 7.38 < 7.83 < 7.98 < 7.17 < 7.98 Cs-137 < 7.50 < 7.29 < 7.20 < 7.26 7.83 (12.8) < 7.50 < 7.44 Ba-140 < 0.472 < 0.525 < 0.588 < 0.555 < 0.498 < 0.447 < 0.498 La-140 < 0.542 < 0.604 < 0.673 < 0.638 < 0.572 < 0.514 < 0.572

< 241 < 241 < 241 _M41 < 241 < 241 < 241

_II-3 Collection Date 9-22-84 9-22-84 9-22-84 9-22-84 9-22-84 9-22-84 9-22-84 __

1-131 < 1.17 Cg < 1.28 < 0.761 < 0.904 < 0.985 < 0.985 Cs-134 < 7.17 < 5.25 8.58 (3.57) < 8.25 < 7.02 < 2.76 < 2.39 Cs-137 < 6.78 < 5.31 < 2.55 < 7.83 10.7 (12.5) < 2.55 < 2.24 Ba-140 < 0.652 C < 0.688 < 0.498 < 0.555 < 0.585 < 0.585 3

La-140 < 0.750 C < 0.791 < 0.572 < 0.638 < 0.673 < 0.673 3

ll-3 < 247 < 247 < 247 < 247 < 247 < 247 < 24_7_ _

Collection Date 11-3-84 10-20-84 10-20-84 10-20-84 10-22-84 10-22-84 10-2_2-81 1-131 < 0.484 < 0.447 < 0.423 < 0.502 < 0.529 < 0.516 < 0.486 Cs-134 < 6.92 < 1.03 < 1.51 < 0.737 < 1.03 < 3.39 < 7.69 Cs-137 < 7.07 < 0.981 < 1.37 < 0.699 1.80 (1.83) < 3.27 < 7.03 Ba-140 < 0.511 < 0.555 < 0.541 < 0.570 < 0.540 < 0.511 < 0.485 La-140 < 0.588 < 0.638 < 0.621 < 0.655 < 0.621 < 0.588 < 0.557 11 - 3 < 254 < 237 < 237- < 247 < 237 < 237 < 248 1.96 o(Due to counting statistics only.) y Cg Instrument malfunction, NaI printout not av,ailable, Cs-134 & Cs-137 detennined by Ge(Li) detector.

M M M M M M MM M M M M N M M M M M Table II.D.1 Radionuclide Concentrations in Milk. (pCi/L)

Collection Date 11-17-84 11-17-84 11-17-84 11-17-84 11-24-84 11-24-84 11-24-84 Nd A-18 A-22 A-23 A-24 A-26 R-8 A-6 c

l-131 < 0.398 < 0.485 0.361 (0.631) < 0.443 < 0.505 < 0.523 < 0.197 Cs-134 < 4.27 < 5.41 < 8.43 < 5.13 < 4.10 < 3.11 < 3.45 Cs-131 5.66 (7.31) 3.36 (8.75) < 8.79 < 5.24 < 3.87 5.09 (5.34) < 3.24 Da- 140 < 5.47 < 6.11 < 11.7 < 9.13 < 5.44 < 4.57 < 5.60 La-140 < 6.30 < 7.03 < 13.5 < 10.5 < 6.26 < 5.25 < 6.44 ll-3 < 240 < 240 < 243 < 248 < 247 < 247 < 247 Collection Date 12-29-84 12-29-84 12-15-84 12-8-84 12-29-84 12-22-84 12-15-84 1-131 < 0.303 < 0.502 < 0.325 < 0.460 < 0.343 < 0.527 < 0.285 Cs-134 < 4.93 < 5.26 < 3.56 3.35 (4.51) < 4.39 < 6.01 < 5.15 Cs-137 < 4.80 < 4.58 < 3.70 < 3.11 4.12 (7.38) 9.26 (10.2) < 4.89 na- 140 < 6.48 < 6.70 < 8.00 < 4.08 < 5.10 < 8.29 < 6.25 La-140 < 7.45 < 7.70 < 9.20 < 4.69 - 5.87 < 9.53 < 7.19 ll-3 < 247 < 243 < 243 < 248 < 254 < 243 < 243 1.96 o(Due to counting statistics only.)

5

I 79 I II.E. Food Products.

One sample of each principal class of food products was collected from areas in which there was some likelihood of I 1

I irrigation by surface water downstream of the discharge point or by well water from the aquifer most likely to be contaminated by seepage from the farm pond. The locations of these food product collection sites are shown in Figure III.B.2.

l Each sample is homogenized without drying immediately after collection. The sample is then counted by gamma-ray spectroscopy. Table II.E.1 lists the results for the 1984 harvest. No significant activity of any of the principal radionuclides was observed. The gama-ray spectra were scanned for other radionuclides but only the naturally occurring were observed presumably due to surface soil deposits.

The MDC's for several of the results in table II.E.1 exceeded the required value. The reason in all cases was improper calculation of required counting time. This has been corrected for all subsequent samples.

I I

I I

I I

I 80 I l

)

Table II. E.1 Radionuclide Concentrations in Food Products. (pCi/kg)

I '

Location Food Type l-131 'Cs-134 Cs-137 A-9 ** Tomatoe < 10.7 < 9.85 < 9.23 R-15 *** Potatoe < 28.4 < 30.8 < 38.3 A-29 *** Squash < 30.9 < 8.70 < 8.37 A-84

• Carrot < 48.6 < 13.7 < 15.1 A-27** Corn < 31.7 < 26.6 < 24.8 A 28** Cabbage < 33.0 24.2 (31.5) < 22.3 I A-8 *** Onions < 55.0 < 38.3 < 35.9 I

I I

I

• 1.96 e (Due to counting statistics.)

• • Collected 9-6-84.

l

• • • Collected 9-11-84.

I I

lI lI lI

l 81 I 1

I II.F. Aquatic Pathways Table II.F.1 shows radionuclide concentrations measured in fish samples collected in 1984. The fish are collected by ,

l electro-shoc' king and the composite sample is ground without cleaning and analyzed on wet weight basis. Essentially all l results were less than MDC values.

Table II.F.2 shows results for analysis of the cesium radioisotopes in sediment collected at R-10, a downstream location. Cs-137 is to be expected in measureable concentrations in sediment due to previous surface deposition of weapons testing fallout. Sediment in this region has high clay mineral fractions and high cation exchange capacity for Cs-137.

The presence of Corbicula Fluminea, a species of freshwater clam, was monitored at several sites around the Fort St. Vrain Nuclear Generating Station in Platteville. 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 I that Corbicula have been found in Northern Colorado at Boyd Lake, some 30 miles from the Fort St. Vrain Nuclear Generating Station.

However, to this date, our samplings have indicated no evidence of Corbicula in any of the sampling sites of the reactor surface water courses.

I I

!I

M M M 'M M M M M M M M M M M M M M M M Table II.F.1 Radionuclide concentrations in Fish. (pci/k9)

Radionuclide First llalf Second llalf F-19 A-25 R-10 F-19 A-25 .

R-10 Cs-134 < 13.7 < 13.5 < 8.65 < 3.36 8.25 (11.3)~ < 15.5 Cs-137 < 17.7 < 18.0 < 11.6 < 3.37 < 7.89 < 14.8 .

Co-58 < 12.9 < 10.4 < 9.56 < 2.63 < 5.55 < 10.1 l3 Hn-54 < 14.3 < 16.5 < 9.38 < 2.39 < 5.34 < 9.91 Zn-65 < 27.7 < 14.5 < 18.6 < 5.80 < 13.1 < 16.6 Fe-59 < 30.3

< 28.6 < 26.5 < 7.04 < 13.7 < 11.1 Co-60 < 15.8 < 46.4 < 9.93 < 2.81 < 6.15 < 22.7

• 1.96 (Due to counting statistics only.)

83 Table II.F.2 Radionuclide Concentrations in Sediment from location R10. (pCi/kg)

I Radionuclide First Half Cs-134 < 54.5 I

Cs-137 88.6 I

I Second Half Cs-134 < 45.3 Cs-137 89.5(92.8)*

I

• 1.96 o (Due to counting statistics.)

I I

I I

I I

I I .. _ _ _ _ - _ - - - . _ _ . -

84 I 11.0 Sample Crosscheck Program.

To assure the precision and accuracy of the environmental data obtained from the radiation surveillance program provided for the Fort St. Vrain reactor, Colorado State University participates in the U.S. Environmental Protection Agency (EPA) sponsored laboratory intercomparison studies program. This involves the analysis of a variety of environmental media containing various levels of radioactivity. The media, type of analysis and frequency of analysis are summarized below.

1 I Medium Analysis (radionuclide) Frequency Water H-3 Simon.thly Water gross 8 bimonthly Water Co-60, Zn-65, Cs-134, triannually Cs-137 Water I-131 triannually I

~

Air particulate Cs-137, gross a triannua11y filters Milk I-131, Cs-137 I

triannually For each radionuclide analysis of a particular medium, three independent measurements are performed and all results are reported to EPA. .The percentage deviation of our determined mean value from the EPA specified value is also calculated. ,

Table II.G.1 gives the EPA crosscheck data for all of 1984.

The EPA uses the term, Estimated Laboratory Precision (ELP),

calculated as 3 o/ n as the control parameter, where n = the

'I I

~

85 l

f I number of analyses. Whenever our mean value falls outside this limit, the sample calculations are rechecked and the sample reanalyzed if possible. Of.the cross check results reported for this period, most were within the ELP. These samples have a superscript notation (n) in Table II.G.I. The recheck process and conclusion lE l5 is given below for each of these individual samples.

(1) (3) (7) (8) The sample recalculated, numerical error in original calculated value. The recalculated value was within the EL?.

i (2) The sample was reanalyzed and resultant concentration was within ELP.

(4) (5) (6) This sample was counted on the Ge(Li) detector calibrated at 10 kev / channel. This was during the change-over period previously described. Later calibration was repeated at 2 kev / channel which allowed much better peak identification. Inspection of subsequent crosscheck results verify this. No actual sample data were calculated at the 10 kev / channel l calibration for this report.

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.

lI I

lI lI y .-

-i

'. .: ^'? j ' % ' , ,

.,t ,- ' ., -

,. *u

86 Table II.G.1 EPA Cross-Check Data Su=ary I  : Radio Date ' nuclide CSU Value EPA Value S:andard Deviation e Estimated Labor l '. deviation aterv Precision

• from known Water, pCi/L 2-10-84 H-3 2,135 2,383 364 607 -

2.9 6-8-84 'H-3 3,397 3,051 359 622 + 11 I 8-10-84 10-12-84 12-14-84 H-3

1) H -3 H -3 2,916 2,943 3,007 2,917 2,810 3,182 356 356 360 617 617 624

- 0.03

+ 4.7

- 5.5 Water, pCi/L 11-18-83 gross 8 18 16 5 - 8.7 + 18 1-20-84 12 12 5 8.7 0 I 3-18-84 7-18-84 -

2) gross 5-18-84 l gross 8 gross s8 gross s 18 12 7

20 6

13 5

5 5

8.7 8.7 8.7

+ 10

- 17

- 7.7 I 9-21-84 11-16-84 gross 8 gross 6 15 13 16 20 5

5 8.7 8.7

- 6.3

- 35 Water, pCi/L 4-6-84 I-131 <6 6 0.87 1.5 --

8-3-84 3)1-131 24 34 6 10.4 - 38 12-7-84 I-131 33 36 6 10.4 - 8.3 I Water, pCi/L 2-3-84 4)Co-60 33 10 5 8.7 + 230

5) Zn-65 14 50 5 8.7 - 72 Cs-134 38 31 5 8.7 + 23

6) Cs-137 40 16 5 8.7 + 150 6-10-84 Co-60 27 31 5 8.7 -13 Zn-65 64 63 5 8.7 + 1.6 Cs-134 30 47 5 8.7 - 36

'I ,7) Cs-137 46 37 5 8.7 + 14 10-5-84 Co-60 21 20 5 8.7 - 5.0 I .

Zn-65 Cs-134 1 l

144 36 27 147 31 24 ,

5 5

5 8.7 8.7 8.7

- 2.0

+ 16

+ 13

{Cs-137 I l i

I  !

• 3:/ G j u ** Recalculated, numerical error in original calculated value.

• • • Sample reanalyzed.

I

87 Table II.G.1 EPA Cross-Check Data Summary (continued)

I Date '

I Radio nuclide CSU Value EPA Value Standard Deviat ion , .c Estimated 1. abor-aterr Pr ecis ion *

• $ deviation from known l

l/ Filter I 1-25-84 l

l gross 8 Cs-137 50 20 Air, pC 48 20

. 5 5

8.7 8.7

- 4.0 0

j l

3-23-84 gross 8 50 51 5 8.7 + 1.4 Cs-137 11 11 5 8.7 0 I 8-24-84' gross 8 Cs-137 47 7

51 15 5

5 8.7 8.7

- 7.8

- 53 I 11-23-84 i

I gross 8 Cs-137 54 10 51 10 I

5 5

8.7 8.7

+ 5.9 0

l Milk, pCi/L I 1-27-84 I-131 Cs-137 26 23 20 22 6

5 10.4 8.7

+ 30

+ 4.5 I

3-2-84 I-131 < 16 6 0.92 1.6 --

6-22-84 I-131 36 43 6 10.4 - 16 Cs-137 33 35 5 8.7 - 5.7 10-26-84 8) I-131 42 42 6 10.4 0

• Cs-137 36 32 5 8.7 + 13

.I I

I

~

lI lI lI I I

• 3:/>i i

• • Recalculated, numerical error in original calculated value.

!I

83 Table II.G.2 Tritium Crosscheck Analyses on Split Water Samples Determined by Colorado State University (CSU), Colorado Department of Health (CDH),

and Public Service Company (PSC).

I Collection Sample Tritium Concentrations DCi/L Da te Location CSU CDM PSC 1-27-84 A 25 113,000 (929P 100,000 ( 1,870) 98,125 (965)

A 21 1,070 (303) 1,100 (179) 1,800 (775) 2-17-84 A 25 2,440 (303) 2,903 (209) 1,390 (1,070)

A 21 398 (296) < 350 < 872 E 41 < 301 1,199 (190) < 872 3-20-84 A 25 132,000 (999) 120,384 (784) 125,000 (2,390 )

A 21 373 (297) < 350 < 842 E 41 < 302 521 ( 171) < 842 4-17-84 A 25 16,100 (434) 14,634 (313) 16,100 (997)

A 21 2,090 (302) 1,217 (190) < 600 E 41 865 (278) 1,461 (187) 716 (733) 5-17-84 A 25 977 (298) 890 (188) < 590 g A 21 < 296 428 (182) < 590 5 E 41 < 296 .359 (182) < 590 6-19-84 A 25 3,620 (321) 1,644 3,010 (688)

I A 21 < 289 1,850 (301)

< 350 2,083 (206)

< 525 1,490 (659) 6-23-84 E 41 (211)

• 1.96 e (Due to counting statistics only.)

I l

'I l l

I

' 89

. Table II.G.2 Tritium Crosscheck Analyses on Split Water Samples Determined by Colorado State University (CSU), Colorado Department of Health (CDH),

and Public Service Company (PSC).

I Collection Sample Tritium Concentrations oCi/L Date Location CSU  ! CDH PSC 7-14-84 A 25 1,590 (3127 1,983 (196) 988(1,050)

A 21 < 304 1,416 (190) 1,370(1,060) 7-15-84 E 41 2,180 (315) 1,999 (197) 1,990(1,060) 8-25-84 A 25 9,200 (375) 1,644 (206) 7,030 (786)

~

A 21 < 294 < 350 < 573 8-26-84 E 41 353 (284) 2,083 (211) < 573 9-15-84 A 25 14,700 (424) 13,177 (308) 13,600(1,180)

A 21 < 294 < 350 < 545 9-18-84 E 41 598 (297) 539 (190) < 573 10-13-84 A 25 88,100 (831) 88,213 (638) 88,700 (1,430)

A 21 < 295 43I (183) < 552 10-15-84 E 41 < 290 464 (183) < 548 I 11-17-84 A 25 4,180 .(332) 4,393 (230) 4,230. (711)

I 11-23-84 A 21 E 41

< 295

< 301

< 350

< 350

< 546

< 568 12-10-84 A 25 36,700 (585) 33,115 (433) 36,600 (1,070)

A 21 < 308 < 350 < 569 12-11-84 E 41 < 308 566 (188) < 569

• 1.96 o (Due to counting statistics only.)

I I

90 Table II.G.3 Gross Beta Crosscheck Analyses on Split Water Samples Determined by Colorado State University (CSU), Colorado Department of Health (CDH),

and Public Service Company (PSC).

I Collection Sample Gross Beta Concentrations DCi/L Date Location CSU  ! CDH l PSC 8.1 10 (4) 9.0 (11.4 )

I 1-27-84 A 25 A 21 8.0 (2.0)

(2.0)

• 9 (4) 11.4 (11.6 )

2-17-84 A 25 15.8 (4.7 ) 10 (4) 13.8 (11.3)

A 21 12.1 (4.6) 10 (4) 29.2 (12.4 )

E 41 9.0 (4.5) 7 (4) 9.2 (11.0) 3-20-84 A 25 15.8 (4.9) 11 (4) ..,.J1. 3 (11.2)

A 21 10.8 -(4.4) 8 (4) < 8.81 E 41 9.9 (4.5) 10 (4) < 8.63 4-17-84 A 25 12.5 (4.8) 10 (4) < 10.3 A 21 12.4 (4.6) 7 (4) < 10.5 E 41 5.2 ( 4. 3) 10 (5 ) < 10.3 5-8-84 A 25 16.7 (4.7) 8 (4 ) 20.3 (11.6)

A 21 11.4 (4.6) 5 (4 ) 24.7 '(11.8)

E 41 5.7 :(4.4) 6 . (4 ) 17.5 .(11.3)

I 6-19-84 A 25 11.3 (4.4 ) <5 38.7 -(12.0)

A 21 26.6 (5.3) 11 (4 ) 8.5 (9.9)

-I 6-23-84 E 41 7.7 (4.6) 7 (4) < 7.7 I

*1.96 o (Due to counting statistics only.)

I

• ~~' -

=n m -y-- n _. e n _,,

91 Table II.G.3 Gross Beta Crosscheck Analyses on Split Water Samples Determined by Colorado State University (CSU), Colorado Department of Health (CDH),

and Public Service Company (PSC). (continued)

Collection Sample Gross Beta Concentrations pCi/L Date Location CSU } CDH l PSC 7-14-84 A 25 11.3 (4. 6 )

• 9 (4) 23.9 -(10.6)

A 21 21.8 (5.1) 7 .(4) 26.6 .(11.2) 7-15-84 E 41 7.7 (4.6 ) 19 :(4) 19.4 -(10.2) 8-19-84 A 25 11.0 (4.5) <5 13.8 (10.2)

A 21 10.8 (4.5 ) 11 (4) 11.6 (10.?)

8-20-84 E 41 5.5 (4.5) 7 (4) 11.2 (9.89) 9-15-84 A 25 10.5 -(4.75) 14 (4) 15.9..(11.3)

A 21 11.0 (4.50)' 8 (4) 16.3 .(11.3) 9-18-84 E 41 10.6 (4.72) 6 (4) 11.8 -(11.3)

I 10-13-84 A 25 7.03 (5.15) 11 (4) 17.6 (12.1)

A 21 10.6 (5.00) 14 (5) 10.4 (11.8) 10-24-84 E 41 9.37 (4.82) 11 (4) 17.8 (11.7) 11-17-84 A 25 12.4 (5.25) 11 (4) 19.2 (11.2)

A 21 7.47 (4.91) 8 (4) 11.4 (10.6) 11-23-84 E 41 5.01 (4.82) 10 (4) 21.5 (12.0) 12-10-84 A 25 18.5 (6.95) 7 (4) 15.5 (11.6)

A 21 3.63 (2.46) 12 (4) 8.90(11.0) 12-11-84 E 41 3.89 (2.45) 20 (5) 9.30(11.0) i

• 1.96 o (Due to counting statistics only.)

I  :

l 1

)

92 II.H. Summary and Conclusions )

Table II.H.1 summarizes the radiation and environmental radioactivity measurements conducted during 1984 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 post-operational periods for this reactor, as well as to the values from other US reactors. It must be emphasized, however, that the mean values in Table II.H.1 are only the means of the values greater than MDC, the statistically minimum detectable concentration. The range also is given only for detectable measurements. The mean and range values, therefore, are not the true means or ranges if any of the values in the sample population were less than MDC. Only for the categories of external gamma exposure rate and gross beta activity concentrations in air, were all the measured values above detectable limits. For these two categories the mean for the Facility locations was identical to the mean for the Adjacent and Reference locations. It can be concluded, therefore, that the measured exposure rates and all conce'ntrations of particulate gross beta activity are due only to naturally occurring radioactivity and reactor effluents make no detectable addition.

Inspection of Table II.H.1 also reveals that there were no individual measurements that exceeded the Reporting Level (RL) (See

-I Table III.B.4). For the category of gross beta concentrations in drinking water, the mean for the Gilcrest well was significantly greater than for the reference supply located in Fort Collins. This difference cannot be due to reactor effluent activity for the following reasons:

93 I

. a. None of the individual radionuclides measured were significantly higher in the Gilcrest drinking water.

b. Tritium concentrations measured at Gilcrest were statistically the same as those in Fort Collins. Tritium is the only measureable radionuclide in the air or water effluent from FSV and since it is far more mobile than any of the specific radionuclides, if effluent activity was reaching the Gilcrest aquifer, elevated tritium concentrations would be the first and most sensitive indication of this.

c. The city of Gilcrest does not filter and treat its water to the same degree as Fort Collins. This has been verified and evidenced by the fact that the gamma-ray spectra of the suspended solids from Gilcrest water samples show 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, and Th-232 decay products. The dissolved solids are higher in Gilcrest water samples due to less filtration of the water.

For the category of tritium in surface water, as has been the case since reactor operation, elevated concentrations were noted at station A-25, the outlet of the (Goosequill) farm pond. 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 l

l

94 occasionally been elevated but there is sufficient dilution before any human use of this water.

For all other categories of sample types and radionuclides there were only occasional values from the Facility Area samples that were detectable above MDC. In all cases these were very close to the MDC.

These are interpreted to be false positive values (Type 1 error, when using hypothesis testing, a = 0.05) . In fact, most of the positive values reported were actually less than the MDC. All positive values are reported even if they are less than MDC.

Table II.H.2 presents an additional summary of mean values for selected sample types. The sample types and radionuclides were chosen on the basis of their importance in documenting possible radiation dose to humans. Air and surface water would be the predominant environmental transport routes and drinking water and milk would be the predominant sources of radiation dose if there were significant radioactivity release from FSV. Table II.H.2 also allows comparison to the three most recent years of operation. From log-normal analysis of each data set for each 12 month period the geometric mean and geometric standard deviations are presented. The arithmetic mean for all sample results was also calculated for each year. It should be repeated that the tabular data presented in the body of this report contain only positive calculated values. Any calcul.ated values less than zero or less than the minimum detectable concentration (MDC) are listed as less than the actual MDC for that sample analysis. However, the actual result in all I

cases was used in the calculation for the arithmetic mean values for the period. Therefore all values, negative as well as positive, were lI I

I 95 I included. This procedure is now generally accepted and gives a proper f 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 while it is true that no sample can contain less than zero radioactivity, due to the random nature of radioactive decay, it is statistically possible to obtain sample count rates less than background and hence a negative result. It is equally. true that the many sample types do in fact have zero concentrations of certain radionuclides (e.g. Ba-La-140).

Therefore, to obtain the correct mean value from the distribut. ion 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 af'lsely biased high.

The log-normal probability treatment is to plot all data for each 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 versus the activity concentration on the log ordinate. The geometric mean value xg  !

is determined directly from the 50th percentile point. The geometric standard deviation is simply the slope of the line which can be l calculated from .the ratio between 84.1 percentile and the 50th percentile. In a normal distribution the arithmetic standard deviation is an additive parameter to the arithmetic mean; i.e., (x io), whereas in the log-normal distribution the geometric standard deviation go is a

~

multiplicative parameter to the geometric mean (x + o g). The area between x g multiplied by a g should contain 68% of the frequency I

.e ie

96 I values. With the log-normal analysis, no bias results from using either

actual values or less than MDC values in estimating the geometric mean.

From the values presented in Tables II.H.1 and II.H.2, and the II tabular data of the report, the following observations and conclusions

may be drawn

)

1; Tritium was the only radionuclide that was detected in any of the effluent pathways that can be attributed to reactor operation. Since the tritium is released as tritiated water, the dilution by the surrounding hydrosphere is great. Although on several occasions elevated concentrations of tritiated water could I

be detected in downstream surface water samples, the mean values for the year were not statistically greater than upstream concentrations. The tritium concentrations measured in milk produced by the nearest dairy herd were also all less than MDC.

Thus no dose commitment to humans can be calculated for the effluent tritium in any pathway.

2. The fallout from the October 1980 Chinese atmospheric nuclear weapon test was no longer detectable in air samples. Only the previous der sition as observed in soil and food chain samples was still observed. Milk samples showed detectable but extremely low concentrati'ons of Cs-137. Cs-137 has a half-life of 30 years and the biosphere still contains this radionuclide from all past atmospheric weapons tests in the northern hemisphere. Nuclear weapon test fallout, however, has since the inception of the

.I project been noted to be the predominant contribution to background. It is the variation in fallout deposition in addition

'I I

97

'I to the variation in naturally occurring radionuclides that requires so many environmental samples to detect any possible increase due to reactor effluents. A simple comparison of preoperational and postoperational values is of little value for most sample types because the fallout deposition was considerably greater during the preoperational period.

3. Figure II H.1 is a plot of tritium measured in surface water samples over the period 1974-1984. During the entire period the overall pattern is that of fallout deposition. There is some delay period in the peaks due to the mean residence' time of tritium in the hydrosphere and input from other areas. Beginning in 1981 there can be observed an increase in the downstream locations I relative to upstream. This small increase is statistically significant, but has not produced any increase in tritium concentration in potable water or any food products measured. It was less apparent in 1984.

4. As in every previous report, it was again apparent that for most sample types the variability observed around the mean values was great. This variability is due to counting statistics and

-I methodological variation, but principally due to true environmental variation (often termed sampling error). It must be recognized and accounted for in analysis of any set of environmental data before meaningful conclusions can be drawn.

5. It can be concluded again that the radiation dose comitments I calculated for the closest inhabitants or other parts of the nearby  !

. ecosystems from current reactor effluents are negligible compared I

I _ - - - -

98 to natural background radiation dose rate and the dose commitment from atmospheric weapon testing fallout.

6. It can also be concluded that the changes instituted in this environmental surveillance program during 1984 were advantageous.

The principal changes in the analytical methods were to switch entirely to high resolution Ge(Li) spectrometry for all spectrometry and to improve the LLD for I-131 in milk and water by using an anion exchange methcd. This allowed measurement of many more gama-ray emitting radionuclides and even lower LLD values with only modest increases in counting time. The changes in the sampling protocols were principally to eliminate several sample types. This in no way compromised the objective of the program, which is to document the existing radioactivity in the Fort St.

Vrain Nuclear Generating Station environs, to show that operational releases produce negligible risk of radiation dose and to be prepared for prompt and comprehensive emergency response.

I I

lI lI

'I l3 I

m W W W M M M M M M M M M M M -m M M M Table II.H.1 1984 Environmental Radiological Monitoring Program Annual Sununary 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 Location Location Annual Mean cations Nonroutine measurement) of Analysis Mean(f)g Mean(f)g Name Mean__(f)b Mean (f)b Reported Performed range range Distance & Range Range Measurements Direction Direct Radiation TLD (158) 0.43 (68/68) 0.43 (71/71) A-10 Old FSV 0.51 (3/3) 0.43 (19/19)

(mR/ day) (0.37-0.52) (0.35-0.53) School 7.8 km (0.49-0.53) (0.33-0.49) 2150 Air, Particulates Gross 8(358) 17.5(205/205) F-16 3 Bar (18.3 (52/52) 17.5 (153/153) 3 (2.37-65.0) Ranch o (3.53-65.0) (3.15-58.1)

(fCi/m ) 1.2 km 0 m Gamma Spectrometry Cs-134 (28) < 25 A-19 Hunting 4.35 (4/4) < 25 Cabin, Goose- (0-10,5) quill 1.7 km 50 Cs-137 (28) 11.8 (1/16) A-19 Hunting 11.8 (1/4) < 30 (11.8-11.8) Cabin, Goose- (11.8-11.8) quill 1.7 km 50 Air oCharcoal 1-131 (360) 23.5 (1/207) A-19 Hunting 23.5 (1/52) 20.1(2/153) 3 (pCi/m ) (23.5-23.5) Cabin (23.5-23.5) (15.4-28.0)

Goosequill

1. 7 k m 50

, Air, Atmospheric H-3 (297) 687 (45/198) ~A-19 Hunting 738 (23/49) 657 (9/149)

! Water Vapor (303-2010) Cabin (303-2010) (323-2680)

(pCi/L) s "

k b

Mean and range based upon detectable surements only. Fraction of detectable measurements at specified locations is indicated in parentheses. (f) i l

M M M M M M M M M M M M M M M M M M-Table II.H.1 1984 Environmental Radiological Monitoring Program Annual Surinary fort St. Vrain Nuclear Generating Facility, Platteville Colorado (continued)

Medium or Pathway Type and Facility Adjacent locations with Highest Reference Number of Sampled (Unit of Total Number location location Annual Mean location Nonroutine measurement) of Analysis Mean(f)g) Mean(f)g Name Meaii (f)b Mean(f)g Reported Perfonned range range Distance & Range Range Measurements Direction Drinking Water (pCi/L) Gross 8(52) 8.06 (26/26) R-6, Gilcrest 8.06 (26/26) 2.71(18/26)

(3.71-15.2) City Water (3.71-15.2) (0.798-6.92) 9.3 km 600 H-3(52) 473 (12/26) R-6, Gilcrest 473 (12/26) 537 (5/26)

(317-816) City Water (317-816) (345-1050) 4 Gamma Spectrometry 9.3 km 600 I-131(34) < O'. 5 N/A 1.97 (1/18) 5 (1.97-1.97)

Cs-134 (52) 6.33 (3/26) R-6 Gilcrest 6.33 (3/26) 6.54 (3/26)

(3.27-11.1) City Water (3.27-11.1) (3.38-10.9) 9.3 km 600 Cs-137 (52) 4.39(4/26) R-6 Gilcrest 4.39 (4/26) 8.14(4/26)

(2.35-9.54) City Water (2.35-9.54) (4.23-12.5) 9.3 km 600 Zr-95 (52) < 15.0 N/A 12.7 (1/26)

(12.7-12.7)

Nb-95(52) 7.43 (5/26) R-6 Gilcrest 7.43 (5/26) 6.46(3/26)

(3.33-14.4) City Water (3.33-14.4) (5.19-7.29) 9.3 km 60 b

Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses. (f)

m M M MM M M M M M M M M M M M M M M Table II.H.11984 Environmental Radiological Monitoring Program Annual Sunmary fort St. Vrain Nuclear Generating Facility, Platteville Colorado (continued)

Medium or Pathway Type and Facili ty Adjacent Locations with flighest Reference Number of Sampled (Unit of Total Number Location Location Annual Mean Locations Nonrou tine measurement) of Analysis Mean (f)pu Mean(f)g Name Heaii(f)0 Mean (f)b Reported Perfonned range range Distance & Range Range Measurements Direction Drinking Water (pCi/L) Co-58 (52) 5.85 (1/26) R-6 Gilcrest 5.85 (1/26) < 7.5 (5.85-5.85) City Water (5.85-5.85) 9.3 km 600 Mn-54 (52) 9.21 (1/26) R-6 Gilcrest 9.21(1/26) 4.49 (2/26)

(9.21-9.21) CityWateg (9.21-9.21) (3.15-5.82) 9.3 km 60 Zn-65 (52) 12.6 (2/26) R-6 Gilcrest 12.6 (2/26) < 15.0 (11.7-13.4) City Wateg (11.7-13.4) 9.3 km 60 -

Fe-59 (52) 50.1 (2/26) R-6 Gilcrest 50.1 (2/26) 5.26 (1/26) O (13.0-87.2) City Wateg (13.0-87.2 (5.26-5.26) 9.3 km 60 Co-60 (52) < 7.5 N/A 3.00 (1/26)

(3.00-3.00)

Ba-140 (37) 3.42 (1/19) R-6 Gilcrest 3.42 (1/19) < 30.0 (3.42-3.42) City Wate5 (3.42-3.42) 9.3 :km 60 La-140 3.96 (1/19) R-6 Gilcrest 3.96 (1/19) < 7.5 (3.96-3.96) CityWateg (3.96-3.96) 9.3 km 60 b

Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses. (f)

M M M M M M M M M M M M M M M M M M M i

l Table II.H.1.1984 Environmental Radiological Monitoring Program Annual Summary.

Fort St. Vrain Nuclear Generating Facility Platteville Colorado (continued) l Medium or Pathway Type and Facility Adjacent Locations with Highest Reference Number of Sampled (Unit of Total Number Location Location Annual Mean Location Nonroutine measurement) of Analysis Mean(f)s D Mean(f)g Name Mean (f)b Mean (f)sD Reported Perfonned range range Distance & Range Range Measurements Direction Surface Water H-3 9,547 (17/36) A-25 Goosequill 9,547 (17/36)

(312-24,600) 2.2 km 200 (312-24,600)

Gamma Spec Cs-134 (60) 6.43(1/36) R-10, S. Platte 6.43 (1/12) < 7.5 (6.43-6.43) on C0 60 10.1 (6.43-6.43) km 35 Cs-137 (59) 3.43 (8/36) R-10, S. Platte 4.45 (3/12) 3.89 (4/23) -

5 (0.919-9.38) on C0 60 10.1 km (3.60-4.84) (2.41-6.84) 350 Zr-95 (59) 6.63 (1/36) F-20, St. Vrain 6.63 (1/12) 11.2 (1/23)

(6.63-6.63) 1.5 km 3400 (6.63-6.63) (11.2-11.2)

Nb-95 (59) 4.74 (6/36) A-25, Goosequill 6.55 (3/12) 6.56 (6/23)

(1.11-8.94) 2.2 km 20 (2.18-8.94) (4.14-8.59)

Co-58 (59) < 7.5 N/A 4.94 (1/23)

(4.94-4.94)'

Mn-54 (59) 1.27 (1/36) A-25,Googequill 1.27 (1/12) < 7.5 (1.27-1.27) 2.2 km 20 (1.27-1.27)

Zn-65 (59) < 15.0 N/A < 15.0 Fe-59 (59) < 15.0 N/A 14.3 (1/23)

(14.3-14.3)

Co-60 (59) 2.18 (3/36) R-10, S. Platte 3.73 (1/12) < 7.5 (0.353-3.73) on C0 60 10.1 km (3.73-3.73) 35 m b Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis.

M M .M M M M. M M M M M M M M M M - M m Table II.H.1 1984 Environmental Radiological Monitoring Program Annual Summary Fort St. Vrain Nuclear Generating Facility, Platteville Colorado (continued)'

Medium or Pathway Type and Facility Adjacent Locations with liighest Reference Number of Sampled (Unit of Total Number location location Annual Mean location Honroutine measurement) of Analysis Hean(f)g Mean(f)g Name Mean (f)b Mean(f)g Reported Performed range range Distance & Range Range Measurements Direction Surface Water (pCi/L) Gamma Spec Ba-140 (50) < 30 N/A < 30 -

1.76 (1/18)

(1.76-1.76)

La-140(50) < 7.5 N/A < 7.5 2.02 (1/18)

(2.02-2.02)

Ground Water g (pCi/L) H-3 (8) 452 (1/4) F-16 3 Bar 452 (1/4) 314 (1/4)

(452-452) Ranch 1.2 km 0 (452-452) (314-314)

Gamma Spectrometry Cs-134 (8) < 7.5 N/A 9.84 (1/4)

(9.84-9.84)

Cs-137 (8) < 9.0 N/A 2.83 (1/4)

(2.83-2.83)

Zr-95 (8) 6.08 (1/4) F-16, 3 Bar 6.08 (1/4) < 15.0 (6.08-6.08) Rgnch 1.2 km (6.08-6.08) 0 Nb-95(8) 8.45 (2/4) F-16, 3 Bar 8.45 (2/4) 6.43 (2/4)

(4.79-12.1) Ranch 1.2 km (4.79-12.1) (5.37-7.48) 0 Co-58 (8) < 7.5 N/A < 7.5 Mn-54 (8) < 7.5 N/A <-7.5 b Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis. (f)

_ _.__________--________..___J

m W W W W W W W W .m m m M m m m Table II.H.1 1984 Environmental Radiological. Monitoring Program Annual Summary Fort St. Vrain Nuclear Generating Facility, Platteville Colorado.(continued)

Medium or Pathway Type and Facility Adjacent locations with liighest Reference Number of Sampled (Unit of Total Number Location loca tion Annual Mean locations Nonroutine measurement) of Analysis Hean(f)g Mean(f)g Name Mean(f_)b Mean (f)b Reported Performed range range Distance & Range Range Measurements Direction Ground Water Gamma Spectrometry (pCi/L) < 15.0 < 15.0 Zn-65(8) N/A Fe-59(8) 7.67 (1/4) F-16, 3 Bar 7.67 (1/4) < 15.0 (7.67-7.67) Ranch 1.2 km (7.67-7.67) 00 Co-60(8) 2.19 (1/4) F-16,'3 Bar 2.19 (1/4) < 7.5 (2.19-2.19) Ranch 1.2 km (2.19-2.19) -

00 g Ba-140 (8) 11.5 (1/4) F-16, 3 Bar 11.5 (1/4) < 30.0 (11.5-11.5) Rgnch 1.2 km (11.5-11.5) 0 La-140 (8) '13.2 (1/4) F-16, 3 Bar 13.2 (1/4) < 7.5 (13.2-13.2) Ranch 1.2 km (13.2-13.2) 00 b

Mean and rance based upon detectable measurements only. Fraction of detectable measurements at specified locations i is indicated in parentheses. (f)

M M M M M M M M M M M M M M M M M Table II.H.1 1984 Environmental Radiological Monitoring Program Annual' Summary Fort St. Vrain Nuclear Generating Facility, Platteville Colorado (continued)

Medium or l'a thway Type and Faci 1ity Adjacent Locations with liigliest Reference Number of Sampled (Unit of Total Number Locations loca tion Annual Mean Location Nonrou tine nasurement) of Analysis Mean (f)D Mean (f)s D Name Meaii (f)b Mean(f)g Reported Perfonned range range Distance & Range Range Measurements Direction Sediment Gamma Spectrometry (pCi/kg, dry) < 75 < 75 Cs-134(2) N/A Cs-137 (2) < 90 N/A 89.5 (1/2)

(89.5-89.5)

Milk (pCi/L) E H-3(119) < 407 N/A < 302 Gamma Spectrometry I-131 (109) < 0.5 N/A < 0.5 Cs-134 (112) 2.91 (12/97) A-6 Hendrickson 4.72 (3/17) 2.15 (1/15)

(0.530-10,5) Daigy7.1km (1.55-10.5) (2.15-2.15) 115 Cs-137 (112) 4.84 (25/97) A-23 Odenbaugh 7.50 (3/16) 1.22 (2/15)

(0.653-15.8) Dafry4.1km (1.09-15.8) (1.06-1.38) 85 Ba-140 (109) 2.94 (5/97) A-26 Cotton- 5.51(1/16) < 30.0 (0.929-5.51) wood Dairy (5.51-5.51) 7.8 km 108 La-140 (109) 3.45 (5/97) A-26 Cotton- 6.33 (1/16) < 15.0 (1.19-6.33) Wood Dairyg (6.33-6.33) 7.8 km 108 b

Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses. (f)

M M M M M M M M M M .M M M M M W.

Table II.H.1 1984 Environmental Radiological Monitoring Program Annual Sunmary Fort St. Vrain Nuclear Generating Facility, Platteville Colorado Medium or Pathway Type and Facility Adjacent Locations with Nighest Reference Number of Sampled (Unit of lotal Number Location Loca tions Annual Mean Locations Nonrou tine iceasurement) of Analysis Mean(f){) Mean (f)b Name Meaii(f)b Mean (f)b Reported Performed range range Distance & Range Range Measurements Direction Food Products Gamma Spectrometry (pCi/kg, wet)

I-131 (7) < 30.0 N/A < 30.0 Cs-134 (7) < 30.0 N/A < 30.0 Cs-137 (7) 24.2 (1/6) A-24Marosgica 24.2 (1/6) < 40.0 (24.2-24.2) 6.9 km 338 (24.2-24.2)

Fish Gamma Spectrometry G (pCi/kg, wet) '

Cs-134 (6) < 65 < 65 N/A < 65 Cs-137 (6) < 75 < 75 N/A < 75 Co-58(6) < 65 < 65 N/A < 65 Mn-54(6) < 65 < 65 N/A < 65 Zn-65(6) < 130 < 130 N/A < 130 Fe-59(6) < 130 < 130 N/A < 130 Co-60(6) < 65 < 65 N/A < 65 b

Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations l is indicated in parentheses. (f) l i

{

l

m M M M M M M M M M M 'm W Table II.H.2 Summary Table of Geometric Means, Geometric Standard Deviations and Arithmetic Means for Selected Sample Types, 1981-1984. (continued) 1981 1982 1983 1984 Sample Typm 2 X H 9  % g '9 g "a

~

o  %

i Atmospheric Water Vapor H-3 (pCi/L)

Facility 399 2.90 527 316 2.81 157 249 2.52 137 252 2.23 296 Reference 267 2.94 171 259 1.78 277 208 2.46 52.6 313 2.36 263 Air 3

Gross Beta (fCi/m )

Facili ty 75 2.6 115 19.4 1.48 20.8 13.6 1.81 15.8 15.1 1.70 17.4 Reference 74 2.8 114 18.7 1.46 1.46 13.1 1.94 16.1 15.9 1.58 17.6 3

I-131 (fCi/m )

Facility ** ** ** ** ** ** ** ** ** 22.5 3.65 < 35.0

• • ** ** ** ** ** ** ** ** 22.3 3.43 1.06 Reference 3

Cs-137 (fCi/m )

• • ** ** ** ** ** ** ** ** 5.96 2.59 0.674 Facility

• • ** ** ** ** ** ** ** ** 5.94 3.01 < 30.0 Reference

• • In prior reports I-131 and Cs-137 means were composite.

J 1

M M M M M . M M Table II.H.2 Stmimary Table of Geometric Heans, Geometric Standard Deviations and Arithmetic Heans for Selected Sample Types, 1981-1984.(continued) 1981 1982 1983 1984 Sample -

Type i o i i i i o i E i 3 9 9 3 0 -- 9 b. -.. . . - - .

Drinking Water H-3 (pCi/L)

Composite 337 2.76 322 273 2.95 186 354 1.90 311 Gilcrest ** ** ** ** ** ** ** ** ** 305 1.60 201

• • ** ** ** ** ** ** ** ** 251 2.25 75.5 Ft. Collins Gross Beta (pCi/L)

Composite 2.97 3.79 5.23 6.11 1.91 7.32 6.43 1.46 6.23

• • ** ** ** ** ** ** ** ** 7.70 1.37 8.05 Gilcrest

• • ** ** ** ** ** ** ** ** 1.71 2.32 2.26 Ft. Collins I-131(pCi/L)

Gilcrest ** ** ** ** *4 ** ** ** ** 0.426 3.70 < 0.500 Ft. Collins ** ** ** ** ** ** ** ** ** 0.340 4.12 < 0.500 Cs-137 (pCi/L)

Composite 0.954 2.05 0.941 0.545 2.58 0.162 0.898 3.13 1.27

• • ** ** ** ** ** ** ** ** 2.54 2.99 1.63 Gilcrest

• • ** ** ** ** ** ** ** ** 4.14 2.33 2.80 Ft. Collins 00 Not available.

U m

m M M M M -

m Table II.H.2 1981 - 1984 Summary Table of Geometric Means, Geometric Standard Deviations and Arithnetic Heans for . Selected Sample Types , 1981-1984.

1981 1982 1983 1984

"~~

lample _ ,, _ _ _ , .. _ _ _

lype X o X X o X X o X X o X g g g g g g g g Surface Water H-3 pCi/L~

Effluent 1,560 7.13 16,300 273 2.95 186 563 4.54 4,620 8,270 4.451 13,317 Downstream 556 3.58 951 471 3.06 1,070 319 3.37 528 339 1.84 219 Upstream 406 1.90 242 281 1.54 15.0 254 2.01 229 278 2.35 139 Cs-137 pCi/L Effluent 1.06 3.19 1.40 0.981 3.21 1.32 1.58 2.34- 0.631 3.39 2.49 0.830 Downstream 1.03 2.42 < 0.677 0.908 2.77 0.115 1.02 3.27 0.976 2.84 2.50 0.570 Upstream 1.05 2.53 1.42 0.676 3.61 0.356 1.44 2.66 2.03 3.23 2.87 1.84 Milk .

H-3 pCi/L Adjacent 280 2.40 277 170 4.36 < 284 183 2.84 < 300 196 2.07 < 296 Reference 230 2.74 157 259 1.78 < 284 257 1.72 < 300 199 1.66 < 296 I-131 pCi/L Adjacent 0.799 11.6 0.161 0.243 4.35 < 0.115 0.626 4.49 < 0.116 0.753 2.33 < 0.500 Reference 0.555 10.5 0.197 0.262 4.29 < 0.117 0.528 4.40 < 0.141 0.604 2.94 < 0.500 Cs-137 pCi/L Adjacent 2.91 7.81 < 0.219 0.285 4.29 < 0.117 0.251 2.33 < 0.720 1.28 3.58 < 9.00 Reference 3.52 5.94 7.05 0.168 2.13 < 0.101 0.204 1.64 < 0.132 1.06 5.28 < 9.00 5

m

E E E E E E M M M M M .m m_ m m m g g - g Figure II.H.1 TRlTIUM CONCENTRATIONS IN WATER, 1974 -1984

- W Surface Upstroom Y = 506 pCl/L A- 4 Surface Downstroom Y = 760 pCl/L 1500 - A o...o Poloble 1 = 576 pCl/L 4 I400 - it it i 1300 - 3g h

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1 111 III. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM III.A. Sample Collection and Analysis Schedule.

Table III.A.1 outlines the sampling design, the collection frequency and the type of analysis. It should be repeated that this schedule was only adopted January 1, 1984 and while different in certain aspects from the previous schedule has as its intent a the same objective. That objective is to document the radiation

.g 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.

Table III.B.1 gives the description of each sampling location by number, sector and distance from the reactor. Each of these sampling locations (except certain reference locations) can be identi.fied on scale maps (Figures III.B.1 and III.B.2). Topographical maps showing greater detail, as well as photographs of principal sampling sites are on file in the CSU laboratory.

During July, August and September of 1984 a land-use census was conducted to determine the locations of the nearest residence, the nearest milk animal, and the nearest garden producing broad leaf vegetation in each of the 16 meteorological sectors around the reactor.

These locations by address are shown in Table III.C.1. Figure III.C.1 shows these locations in each sector. This census is to be repeated annually.

I I

I

112 Table III.A.2 lists the LLD concentration values for each sample type and radionuclide measured in this report. These LLD I values are the actual values pertinent to the sample sizes, counting -

yield, and counting times used in the project. Typical decay -

periods were used in the calculations. It should be noted that those values are in most cases less than those required by the technical specifications. E I Table III.A.3 lists the USNRC reporting level for sample w

type and radionuclide concentration.

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Table III.A.l. nrumuoNAt RADIOLOGICAL. ENVIRONHtNTAL HONHolHNO PHOGlWf

'Typbsure Pathway Number of Samples Sampling Type and frequency sent/or Samplo and Locations Collection frequency or Analysis AIR 50fylE Irltlitz Oxido Samplos from seven locationst Continuous sampler operation stadiolodino Cassisters lladiglodine anJ with sample collection voehly Analyze wookly for 1-131 Partloulates four samples from ort-site locations or as required by dust loading, liquid scintillation (In dirrorent sectors) or the highest whichever is more frequent. counting for tritium on calculated annual averego ground water vapor extracted level D/Q and airborne X/Q. From silica gol on each sample collected.

One seaple from the vicinity or a community having the highest calculated Particiale to Samplors annual average grotand level D/Q. Gross beta radlonctivity following filter chango, Iwo samples from control location composite (by location) 15 to 30 kliomoters (10 to 20 miles) for gamma I

. distant and in the least prevalent quarterly. gotopic wind direction.

Quarterly exposure. Gamma doso quarterly.

DillEC1 RAl)l All0N rorty stations with two or more dosimotors or one Instrument . For measuring and recording dose rate continuossly to be placed as rollows:

. I) an inner ring or stations in the general area or the site boundary and an outor ring in the 8e to 5 salle range from thu site with a station in each .

sector of each ring (16 sectors x 2 rings = 32 stations). The balance or i the stations, eight, shall be placed in special Intesent areas sucle an l population contors, nearby residences, e schools, and in two or three areas to serve as control stations.

WAIEltBOSHL i Camplos collected econthly. Comme isotopic analysis i Surfaco one sample upstream, escip stream, ono

• saeplo downstream, and tritium moeithly.

Surrace Ono samplo les immodleto area or Composite sample over one Gamma isotopic analysis dischargo, wook porlod. The weekly and composite for tritium (rarm Pond) compositos will be combinud monthly, for the monthly sample, a

ir gross bott activity lie air or vator is greater than tun timos the yearly muan or control samplo for any medium, gamma Isotopic analysi s should t-e perrormed on the leidividual samplos.

m M A, m m m m m m a m. g a g g g g O G G Table III.A.I. ntLML19nLEplotoGl CAL [MVIRONHEMIAL N0Hil_ORlRG PROCHAH (Continued)

Sampilng Tipe and~Trequency Tiposuro Pathway Number or Samples Collection Frequency of Analysis and/or Sample and Locations Gamma isotopic and Ground Samplos from two sources most likely Quarterly t ri t inua, to be arrected.

composite sample over two Compo s i t e f o r t r i t i um, prinking one sample from the nearest water gross beta, and gamma supply wlilch could be arrected by week period.

Isotopio analysos ovary foollity's dischargo.

two weeks.

One samplo from a control location.

Comma isotopic asialysos Sudament from One sample from downstream area with Soul-arinually semi-annually, Shoreline existing or potential recreational value.

INGESilON Gamma Isotopic and 1-138 Hlik Samples from allking animals in all Semi-monthly wheti animals are on pasture, suinthly at analysis soml-monthly locations, up to a total or three locations, within 5 kilometers. other times. when animals are on pasturel monthly at One samplo from milking animals in other times. ,_,

each of three areas between 5 to 8 A kilometers distant havinti,the highest doso potential. U Soml-monthly when animals Gamma isotopic and 1-131 Ono samplo from milking animals at a analysis soml-monthly control location (15 to 30 kilometers) are on pasture, montlity at distant and in.the least prevalent other Lines, when animate are on pasture; montlity at wind direction). other times.

Sample soml-annually. Comma isotopic analysos, A*guatic Dicta Sample rlsh in vicinity of discharge point, upstressa and downstream, Gamma lsutopic analyses, food Products One sample or each principal class or At time or harvest.

food proilucts from any area which la irrigated by water in which liquid plant wastes have basse discharges.

bihu doso shall be calculated for the maximum organ and ago gsoup assing the methodology contained in stogulatory Quido I.th9 and the actual paramotoss partictilar to the sito.

i i

Table III.A.2. Detection Capabilities For Environmental Sample Analysis Lower Limit of Detection (LLD)*

Analysis Water Airborne Particulate Fish Milk Food Products Sediment (pCi/L) or Gas (fC1/m3) (pCi/kg, wet) (pC1/L) (pCi/kg, wet) (pCi/kg, dry)

Gross Beta 3.86 3.25 H-3 494 I-131 0.890 66.4 0.890 56.8 Cs-134 5.58 8.06 19.5 5.58 44.4 90.6 Cs-137 5.34 7.86 18.5 5.34 44.6 100 Zr-95 7.96 -

Nb-95 4.24 5 Co-58 3.66 12.8 Mn-54 3.64 12.7 Zn-65 7.92 Fe-59 8.30 31.4 Co-60 3.74 14.5 Ba-140 8.87 8.87 La-140 10.2 10.2 o As suggested in NUREG-0472. All values are at or below values listed in Table 8.2-2. of Technical Specifications.

M M M M M M M M M M. M M M .M M .M M M Table III.A 3. . Reporting Levels (RL) For Nonroutine Operating Reports Reporting Level (RL)

Analysis Water Airborne Particulate or Gas Fish Milk Broad Leaf Vegetation (pCi/L) (fC1/m3) (pCi/kg, wet) (pCi/L) (pCi/kg, wet)

H-3 2 x 104 (a) 3 4 Mn-54 1 x 10 3 x 10

' 2 4 Fe-59 4 x 10 1 x 10 Co-58 1 x 10 3 3 x 104 Co-60 3 x 10 2 1 x 104 $

2 4 Zn-65 3 x 10 2 x 10 Nb-95, 4 x 10 2 .

Zr-95 I-131 2 9 x 10 2 3 1 x 10 2 ,

Cs-134 30 1 x 10 4 1 x 10 3 60 1 x 10 3 Cs-137 50 2 x 104 2 x 10 3 70 2 x 10 3 Ba-140, 2 x 10 2 3 x 102 La-140 a

For drinking water samples. This is 40CFR Part 141 value.

'M M M M M M M M M .M M '

M M M -

M-0 '

y 9 Table III.B.1 ItAllI01.0GICAI. f.IIVlitoliili.fil AI. flottl T0ltillG Pit 0GilAll (continued)

SAMPLING SITE 1)i.SClllPIIDHS

.( fi.f.a_c_ility Arca 0-l.6 km. A; Adjacent Arca 1.6-8 km. R; Reference Area)

Iypnsure Pathway Si te flo. (01:1Siteflo.) location Description (see map) Sector Distanco, km Ilirect Radiation F-1 F-7 1.3 km NNE, pole by gate at corner of 1 1.3 Goosequill Road F-2 0.5 km, NW pole on top level 2 1.1 ,_,

F-3 On first pole N of E-W road 3 0.7 C F-4 2nd pole S of pump road, midway between 4 0.7 F-3 and F-5 F-5 F-47 Pole near drive to pump house 5 0.6 F-6 Pole on E-W concrete ditch, 5 of bridge 6 0.8 F-7 F-3 Old dairy barn, ist pole N of drive 7 1.2 F-8 F-9 lst pole W of pump house on N side of road 8 1.3 F-9 F-4 First shed along drive 9 1.5 F-10 F-Il Pole on SE corner of intersection of 19's and 34 10 1.5 F-ll F-12 7th pole N of intersection 11 1.2 F-12 F-13 Pole nearest intersection 12 1.0 F-13 On metal staircase going down off dike, 13 0.5 take road 5 of Visitor Center across RR track i

W pM @ W W M-yu. W .

.m Wi m-Table III.B.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (continued)

SAMPLING SITE DESCRIPTIONS i

(F; Facility Area 0-1.6 km. A; Adjacent Area 1.6-8 km. R; Reference Area)

Exposure pathway Site No. (Old Site No.) 1.ocation Desciiption (see map) Sector Distance, km

.l i

Direct Radiation .

F-14 F Pole 0.1 km S intersection Rd 36 & Rd 19 14 1.5 F-15 3rd pole 0.7 km S of Rd 38 on Rd 19 '15 1.5 F-16 F-1 Pole on NE corner ofp' otato cellar 16 1.2 F-17 Visitor Center, S end of cross-beam 13 0.2 -

i over entrance 5 A-20 Turkey fann S of reactor,1 pole N of KS 9 2.5 farm sign on S end of bldg parallel to rd A-1 Corner of Rd 44 and Rd 21 1 6.7 A-2 NE corner, intersection of 42 & 255 2 6.8 A-3 A-30 Intersection of 42 and C0 60 3 7.5 A-4 1st pole NE of intersection of 29 and 38 4 7.4 take Rd 29 easterly out of Gilcrest to

. Rd 38 A-5 A-32 SE corner of 34 and 29, fence post 5 7.2 A-6 A-50 Pole on S side of 32 near drive to dairy 6 7.1 A-7 A-33 Niles Miller dairy. 0.4 km E of US 85 7 7.3 A-8 A-35n On C0 66, farm on S side of road on end 8 4.7 l of chicken coop.1 km E of 19 A-9 A-350 Corner of CO 66 and 19, Miller produce 9 4.6 stand, pole on SW corner A-10 Pole on 26h, on pole SW of old FSV school, 10 7.8 across road from school j

A-11 . Corner of C0 66 and 13, pole on NE corner, 11 7.2 opposite 13 road sign

m Sm . m W M M M i -)

M M M 'M M - ..M

.q-M Table III.B.1 RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAll (continued)-

SAMPl.ING SITE DESCRIPTIONS

_(F; facility Area 0-1.6 km. A; Adjacent Area 1.6-8 km. R; Reference Area)

Exposure Pathway Site No. (Old Site No.) location Description (see nap) Sector Distanco, km Direct Radiation A-12 On Rd 34, pole E of white h'ouse N.of Lake 12 7.2 Thomas A-13 Pole opposite lake, N.of silage pits E side 13 5.8' of Rd 13 A-14 Intersection of 13 and 40, NW corner 14 6.9  ::

e A-15 Intersection of 42 and 15, NW corner 15 6.7 A-16 . Corner of 44 and 19, SW corner 16 6.8 A-17 Platteville School, NW corner just outside - 5.9 .

school yard R-1 Milliken School, on 21's, pole on SW corner 9.3

, R-2 Johnstown School (elementary), pole on S end 10.8 i of drive R-3 CSU air sampler, dairy farm on W ' Drake, Ft Collins 45.1 R-4 Air sampler corner of US 287 and C0 66, Dairy 20.5 store R-7 Behind Gilcrest School auditorium, pole 9.3 on SW end of school property, just before garage e

l

E E E E E E E

%M M Table III.B.1 RADIOLOGICAll ENVIRONMENTAL NONITORING PROGRAM (continued)

SAN,PLING SITE DESCRIPTIONS

]F;FacilityArea0-1.6km.A;AdjacentArea1.6-8km.R;ReferenceArea)

Exposure Pathway Site No. (Old Site No.) location Description (see map) Sector Distance, km Airborne F-16 F-1 Potato cellar at 3 Bar Ranch 16 1.2 k-19 F-2 Hunting cabin between Goosequill ditch and 1 1.7 Platte river F-7 F-3 Fann at intersection of Rd 21 and Rd 34 7 1.5 b F-9 F-4 First shed along drive at end of Rd 19\ 9 1.5 R-11 Next to garage behind PSC office, 13b 10.5 Main street, Johnstown, C0 Colorado State University dairy W Drake rd, R-3 45.1 Ft. Collins, C0. S side of shed directly N of main dairy bldg R-4 Intersection of US 66 and US 287, east side of 20.5 i dairy store.

'I e

M, M M M

~

M M ff e r Table III.B.1 RADIOLOGICAL ENVIRONMENTAL N0filTORING PROGRAM (continued) i SAMPLING SITE DESCRIPTIONS r

(F; f acility_ Area _0-1.6 km, A; Adjacent Area 1._6-8 km, R; Reference A_re_a,)

! Distance, km location Description (see map) Sector Eupnsure Pathway Site flo. (Old Site No.)

Waterborne S Platte at dam and inlet pond 4 1.2 Surface F-19 U-43 St. Vrain creek at bridge on 34 11 2.4 A-21 U-42 S Platte at C0 60 10.1 b!

R-10 0-40 St. Vrain creek on 19 h, 0.3 km from 16 1.5 F-20 D-45 l discharge Goosequill Pond outlet 1 2.2 A-25 E-38 Well behind residence at 3 Bar Ranch 16 1.2 Ground F-16 at (F-16)

Milliken city well, behind town hall 9.8 R-5 i

.CSU dairy W Drake Rd, Ft. Collins, 00 45.1 Drinking R-3 Gilcrest city water, US Post Office 9.3 R-6 l

Table III.B.1 RADIOLOGICAL ENVIRONMENTAL M0tilTORING PROGRAM (continued)

SAMPLING SITE DESCRIPTIONS Q; Facility _A_rea _0-_1.6 km. A; Adjacent Area 1.6-8 km. R; Reference Area)

Exposure Pathway Site No. (Old ' Site flo.) 1.ocation Description (see map) Sector Distanco, km Waterborne Sediment from R-10 D-40 S Platte at CO 60 10.1 Shoreline C

N Ingestion Milk A-6 A-50 llendrickson dairy on 32,1.3 km E of 6 7.1 Platteville A-23 F-44 Leroy Odenbaugh dairy 4'. 4.1 A-26 Cottonwood dairy, corner of Rd 19 and 26 9 7.8 A-22 Percy Odenbaugh dairy 5 ' 3.2 A-18 Cullen'0denbaugh dairy 5 2.8

! A-24 ,

Marostica dairy 16 6.9 i R-8 R-16 Mountain View Farms, N side of 00-402 W 22.5 of I-25 Fish A-25 E-38 Goosequill Pond outlet 1. '2.2 l F-19 U.-43 S Platte at dam and inlet pond ,

4 1.1

, R-10 D-40 S Platte at C0 60 10.1

E W W W W W RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM SAMPLING SITE DESCRIPTIONS (F; Facility Area 0-1.6 km. A; Adjacent Area 1.6-8 km. R; Reference Area)

Exposure Pathway Site No. (Old Site No.) location Description (see map) Sector Distance, km Feod Products A-9 -

Hiller Store Rd 19 & C0 66 9 4.6 A-8 Walter Maler Farm, 9704 C0 66 8 4.7 A-27 Willard Wolfe Farm, 13031 Co Rd 38 4 5.8 -

O!

4.0 A-28 Odie liindenbrandt Farm,16500 Co Rd 25 4 A-29 Ben Gutfelder Farm, 12027 Co Rd 42 2 7.4 R-12 Jean Lewis Farm, 13255 Co Rd 46 2 9.8 R-13 Harry Hatashima Farm,1/3 mile N of Rd 3 13.7 46 on Rd 33 R-14 Kawata Farms, E of Co Rd 31 on Rd 46 3 12.2 R-15 Jim Kissler Fann,14368 Co Rd 42 3 10.0 J

e

aw 124 Figure III.B.1 On-Site Sampling Locations I

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126 Table III.C.1 1984 Land Use Census I Location of:

Sector Nearest Nearest Nearest Residence Garden Milk Animal 21692 Rd 21 **

1 17578 Rd 19h 2 18451 Rd 23 18451 Rd 23 11248 Rd 40 11113 Rd 38 **

3 11420 Rd 38 4 11247 Rd 36 11733 Rd 36 11733 Rd 36 5 16519 Rd 23 16134 Rd 23 16520 Rd 23 6 16101 Rd 23 11056 Rd 32 13278 Rd 32 7 9999 Rd 34 10218 Rd 32h 8 15883 Rd 21 14500 Rd 21 9867 Rd 26 9 9434 Rd 34 15275 Rd 19 9033 Rd 26 10 9061 Rd 34 15499 Rd 19 7388 Co Hwy 66 11 8512 Rd 34 8512 Rd 34 6165 Rd 32 12 9053 Rd 34 6519 Rd 34 5879 Rd 34 13 17038 Rd 17 17038 Rd 17 4709 Rd 38, 5416 Rd 36 14 8900 Rd 36h 8900 Rd 36h 19390 Rd 17 **

15 8903 Rd 38 1

16 17250 Rd 19 18250 Rd 19 20700 Rd 17 l

• Census date: August, 1984.

• • No milking animals available.

I I

127 Figure III.C.1 1984 Land Use Census i

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