Text

Radiological Environ Monitoring Program Summary Rept for 1985
	ML20204A249
Person / Time
Site:	Fort Saint Vrain
Issue date:	12/31/1985
From:	Borst F, Jerrica Johnson; COLORADO STATE UNIV., FORT COLLINS, CO
To:	;
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PDR Purchase Order No. 62383 COLORADO STATE UNIVERSITY l

FORTCOLLINS, COLORADO 80523

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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM I

Summary Report I

for the period January 1, 1985 - December 31, 1985 1

Prepared by:

[

3 2-T $6 Jsnes E. Johns % Professor, Date CoNadoStateUniversity Reviewed by:

At/M c7d&

3/e/k Radiochemistry Super /isor

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Approved by:

Support Servit4s Manager Date I

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v Acknowledgements Many persons have contributed to this project during 1985 and it is important to acknowledge their. effort. We also wish to thank the citizens from whose farms, homes, and ranches we collect the environmental samples. Without their cooperation the project would not be possible.

The persons working directly on the project have been:

Charles Bedford Laboratory Assistant Sheri Chambers Laboratory Technician Sharon Clow Chemist Kenneth Harper Graduate Research Assistant Ken Johnson Graduate Research Assistant Sandy Kienholz Graduate Research Assistant Scott Maxey Graduate Research Assistant Marion Mcdonald Laboratory Coordinator Charles Sampier Chief Electronics Technician S

A Qh ? dun %

,t cejg3 James E. Joh'nson Professor and Project Director l

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I TABLE OF CONTENTS Page No.

List of Tables iii List of Figures v

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INTRODUCTION 1

II.

SURVEILLANCE DATA FOR 1984 AND INTERPRETATION OF RESULTS A.

External Gama Exposure Rates 6

B.

Air Sampling Data 9

C.

Water Sampling Data 34 D.

Milk Data 67 E.

Food Products 77 F.

Aquatic Pathways 79 G.

Sample Cross Check Data 84 H.

Conclusion and Summary 93 III.

ENVIRONMENTAL RADIATION SURVEILLANCE PROGRAM AND SCHEDULE A.

Collection and Analysis Schedule 112 B.

Sampling Locations 118 C.

Land-use Census 127 l

I ii as

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LIST OF TABLES Page No II.A.1 Gama Exposure Rates.

8 II.B.1 Concentrations of Long-lived Gross Beta Activity in Airborne Particles.

I a.

First Quarter,1985.

11 b.

.Second Quarter, 1985.

12 c.

Third Quarter, 1985.

13 d.

Fourth Quarter, 1985.

14 II.B.2 Tritium Concentrations in Atmospheric Water Vapor, pCi/L.

a.

First Quarter,1985 18 b.

Second Quarter, 1985.

19 c.

Third Quarter, 1985 20 d.

Fourth Quarter, 1985 21 3

II.B.3 Tritium Concentrations in Air, pCi/m,

a.

First Quarter, 1985 22 b.

Second Quarter, 1985.

23 c.

Third Quarter, 1985.

24 d.

Fourth Quarter, 1985.

25 II.B.4 Tritium Released in Reactor Effluents.

26 II.B.5.

I-131 Concentrations in Air.

a.

First Quarter,1985 29 b.

Second Quarter, 1985.

30 c.

Third Quarter,1985.

31 d.

Fourth Quarter, 1985.

32 II.B.6 Radiocesium Concentrations in Ambient Air.

33 II.C.1 Gross Beta Concentrations in Bi-weekly Composites 36 of Drinking Water.

I.

II.C.2 Tritium Concentrations in Bi-weekly Composites of 37 Drinking Water.

II.C.3 Radionuclide Concentrations in Bi-weekly Composites 38-of Drinking Water.

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i LIST OF TABLES (continued)

Page No.

II.C.4 Tritium Concentrations in Surface Water.

49 II.C.5 Radionuclide Concentrations in Surface Water.

51 II.C.6 Radionuclide Concentrations in Effluent Water 63 II.C.7 Radionuclide Concentrations in Ground Water.

65 II.C.8 Maximum Permissible Concentrations in Water.

66 II.D.1 Radionuclide Concentrations in Milk.

71 II.E.1 Radionuclide Concentrations in Food Products.

78 II.F.1 Radionuclide Concentrations in Fish.

82 II.F.2 Radionuclide Concentrations in Sediment.

83 II.G.1 EPA Crosscheck Data.

87 II.G.2 Tritium Concentrations in Crosscheck Data, 89 CSU-Fort St. Vrain-Colcrado Dept. of Health.

II.G.3 Gross Beta Concentrations.in Crosscheck Data, 91 CSU-Fort St. Vrain-Colorado Dept. of Health.

II.H.1 Data Sumary.

101 II.H.2 Geometric Means of Selected Sample Types 1982-1985.

109 III.A.1 Radiological Environmental Monitoring Program.

114 III.A.2 Lower Limit of Detection.

116 III.A.3 Reporting Levels.

117 III.B.1 Sampling Locations for Environmental Samples.

118 III.C.1 Land-use Census, 1985.

127 I

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LIST OF FIGURES Page No.

Figure II.B.1 Gross Beta Concentration in Air, 15 1974-1985 I

Figure II.C.1 Tritium Concentration in Water, 50 1974-1985 Figure III.B.1 On-site Sampling Locations 125 Figure III.B.2 Off-site Sampling Locations 126 Figure III.C.1 Land Use Census 128 1

6.

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Introduction to Radiological Environmental Monitoring Data for the Period January 1,1985 - December 31, 1985 During 1985 the Fort St. Vrain Nuclear Generating Station produced thermal energy as follows:

Month Dates with Thermal Gross Thermal Energy Generation Energy Production, (MWH)

July 21-23 110 October 3-31 24,312 November 1-7 8,948 No electrical energy was generated during 1985. Compared to the previous operating year, there was a factor of 10.2 less thermal energy produced in 1985.

The total radioactivty released by all eff1uent routes as a consequence was condsiderably less during 1985 than during 1984.

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.

l Nuclear Regulatory Commission dated February 27, 1986. When possible 1

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.

Table III.A.2 lists the LLD values achievable by the counting systems used during 1985 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.

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2 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).

This approach is analogous to that of Currie (NUREG/CR-4007) where the MDC is the same as S,.,

the

~

critical signal and S, the detectable signal is the LLD. The MDC D

value applies to the actual sample size, counting time and decay time applicable to that individual sample.

It was calculated as:

MDC = 2.33

/E Y Y e-At B

Where:

B = standard deviation of sample count rate E = Counting efficiency, c s-1 pC1-1 Y = Chemical yield V = Sample mass or volume L

t = Decay time between sample collection and analysis A = 0.693/ Half-life 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 I.

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

Environmental radiation surveillance data comonly exhibit non-normal frequency distributions.

Usually the data can be I

3 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 ecch data table. At the end of this report in Section II.H Conclusions and Sumary, we have listed (Table II.H.2) the calculated arithmetic means for the reporting period of 1985. We also list in the same table the geometric means and geometric standard deviations for the period.

If any data points measured resulted in negative values, these values were used in calculating the true mean j

values in Table II.H.2 (negative values are possible due to the statistical nature of radioactivity counting). This is the suggested I

practice by Gilbert (Health Physics 40:377, 1984) and NRC I

NUREG/CR-4007.

It should be noted that we have not used the notation

<MDC for values less than MDC. Rather, we list the measured value as 1ess than the actual MDC value.

Bec'ause 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.

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 =

O.05).

In this report we have added to appropriate tables the maximum permissible concentration applicable to that radionuclide.

We have

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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 mrem / year, but must include the dose from all possible sources, and, therefore, cannot be solely due to reactor effluent. As stated in 10CFR20 these are the maximum concentrations above natural background that a licensee may release to an unrestricted area.

It is 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 maximum 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 I.

These are judged the "As Low as Reasonably Achievable" dose rates from such reactor types and although not directly appitcable to the Fort St.

Vrain gas cooled reactor, can be used for comparison purposes.

A limit that does apply is the independent maximum permissible dose comitment 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. Dose commitments are calculated for any mean concentrations noted in unrestricted areas that are significantly above control mean values.

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The following is the footnote system used in this report.

a.

Sample lost prior to analysis.

b.

Sample missing at site.

c.

Instrument malfunction.

d.

Sample lost during analysis.

e.

Insufficient weight or volume for analysis.

f.

Sample unavailable.

g.

Analysis in progress.

h.

Sample not collected (actual reason given).

i.

Analytical error (actual reason given).

N.A.

Not applicable.

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II.

Surveillance Data for January through December 1985 and Interpretation of Results.

A.

External Gama-ray Exposure Rates The average measured gama-ray exposure rates expressed in mR/ day are given in Table II.A.1.

The values were determined by CaF :Dy 2

(TLD-200) dosimeters at each of 40 locations (see Table III.B.1). Two-TLD chips per package are installed at each site and the mean value is reported for that site.

The mean calculated total exposure is then divided by the number of days that elapsed between pre-exposure and post-exposure annealing to obtain the average daily exposure rate.

The TLD devices are changed quarterly at each location. Fading during field exposure is minimized by the post annealing readout procedure.

The TLD data indicate that the arithmetic mean measured exposure rate in the Facility area for all of 1985 was 0.42 mR/ day. The mean exposure rate was 0.42 mR/ day for the Adjacent area and 0.42 mR/ day for the Reference area.

These mean values were not significantly different from the values measured during any quarter of 1984.

The exposure rate measured at all sites is due to a combination of exposure from cosmic rays, from natural gama-ray emitters in the earth's crust and from ground surface deposition of fission products from previous world-wide fallout. The variation in measured values is due to true variation of the above sources plus the variation due to the measurement method. The purpose of the two TLD rings around the reactor is not to measure gama-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 I

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I 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 produced in a cavity surrounded by Uranium mill tailings. This produces a gamma-ray spectrum nearly identical to that from natural background measured in the reactor environs. The quality control program includes calibration during readout of each qun ;2rly batch of TLD devices.

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8 Table ll. A.1 Gamma Exposure Rates. (mR/ day) 1985

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Facility Area 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter F-1 0.42 0.39 0.45 0.38 F-2 0.43 0.44 0.46 0.39 F-3 0.43 0.42 0.45 0.42 F-4 0.43 0.40 0.46 0.43 F-5 0.45 0.42 0.45 0.43 F-6

_0.44 0.39 0.42 0.37 F-7 0.41 0.39 0.41 0.42 F-8 0.45 0.48 0.44 0.42 F-9 0.41 0.44 0.42 0.39 F-10 0.43 0.39 0.43 0.41 F-11 0.45 0.44 0.47 0.45 I

F-12 0.42 0.37 0.44 0.46 F-13 0.40 0.36 0.38 0.35 F-14 0.40 0.39 0.38 0.34 F-15 0.39 0.43 0.43 0.38 F-16 0.39 0.36 0.41 0.36 F-17 0.44 0.39 0.44 0.50 X (1.96c) 0.42 (0.039) 0.41 (O'.064) 0.43 (0.051) 0.41 (0.042)

Adjacent Area l

A-1 0.47 0.44 0.46 0.42 A-2 0.46 0.45 0.45 0.44 A-3 0.42 0.44 0.47 0.41 A-4 0.41 0.40 0.41 0.37 A-5 C-1 0.40 0.39 0.35 A-6 0.41 0.39 0.41 0.36 A-7 0.41 0.45 0.43 0.45 I

A-8 0.45 0.41 0.46 0.43 A-9 0.48 0.41 0.45 C-1 A-10 0.52 C-1 C-2 0.46 A-11 0.44 0.35 0.45 0.39 A_12 0.42 0.40 0.40 0.35 A-13 0.37 0.39 0.38 0.33 A-14 0.39 0.39 0.39 0.36 A-15 C 0.43 0.43 0.34 0.42 0.40 0.41 0.40 A-16 A-17 0.42 0.40 0.48 0.42 I

A-20 0.46 0.50 0.47 0.47 R (1.9C -)

0.43'(0.073) 0.43'-(0.063) 0.43 (0.063) 0.40 (0.045).

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Reference Area I

R-1 0.41 C-1 0.44 0.39 R-2 0.44 0.39 0.45 0.43 R-3 0.37 0.39 0.38 0.37 R-4 0.45 0.45 0.46 0.36 R-7 0.40 0.38 0.42 0.40 I

R (1.96o) 0.41 (0.063) ~ 0.43 (0.063) 0.43 (0.063) 0.39 (0.'027)

C-1 TLD removed from pole by vandalism.

C-2 TLD and Pole destroyed by fire.

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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 1985.

A-19, while technically in the Adjacen^. zone, is only a few meters from the Facility boundary and logically should be considered a Facility site.

It has been termed a Facility site since the inception of the monitoring program. The Reference sites R-3, R-4, and R-11 are all new locations as of January 1,1984.

I 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 were not significantly different from the mean values for the Reference locations during any of the four quarters of 1985. During the third and fourth quarters, however, there was a statistically signific~ ant increase in the concentrations noted at all seven stations compared to the first half of 1985.

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 p'evious quarter viere still less than those measured during most r

reporting periods, operational and preoperational.

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Figure II.B.1 shows the mean of gross beta air concentrations in the Facility area plotted versus the mean of the values for the Reference area.

It can be observed that overall mean values are not significantly different and that world-wide fallout is the predominant contributor to the measured values.

There has never been a significant difference observed between Facility and Reference sites.

Thus, it can be again concluded that air effluents of particulate fission products or activation products

' is not a source of dose commitment for the Fort St. Vrain environs.

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3 Table II.B.1 Concentrations of Long-lived Gdoss Beta Particulate Activity in Air. (fCi/m )

a) First Quarter, 1985 i

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' Collection Facility Sites i

Refe ence Sites l

R-3 R-4 R-11 l

Date F-7 F-9 F-16 A-19 l

1-5-85 36.4 (2.86)*

35.0 (2.40) 34.6 (2.29) 34.2 (3.29) I 27.8 (2.80) 30.2 (2.88) 33.0 (2.54) 1-12-85 39.6 (2.74) 35.,4 (2.37) 38.1 (2.44) 37.4 (3.11) 32.3 (3.17) 34.0 (3.03) 41.1 (2.66) 1-19-85 31.9 (2.56) 34.2 (2.48) 33.0 (2.28) 33.6 (3.04) 7.23 (1.83) 28.5 (2.70) 38.2 (2.60) 1-26-85 21.2 (2.99) 27.5 (3.09) 32.3 (2.58) 37.0 (2.61) 20.8 (2.49) 23.3 (2.30) 31.0 (2.33) 2-2-85 37.1 (2.81) 18.1 (1.91) 21.6 (1.81) 19.4 (1.80) 29.6 (3.11) 38.0 (2.99) 36.7 (2.67) 2-9-85 25.7 (2.88) 8.04 (2.82) 27.1 (2.17) 7.84 (2.61) 13.3 (2.33) 30.5 (3.53) 24.7 (2.08) 2-16-85 24.1 (2.61) 24.3 (2.49)

C 22.6 (2.31) 23.1 (2.30) 17.1 (2.54) 28.0 (2.79) i 2-23-85 24.7 (2.59) 35.0 (2.92) 22.5'(2.04) 31.3 (2.59) 24.3 (2.54) 27.0 ( 3. 31) 36.4 (2.77) 3-2-85 21.7 (2.11) 20.7 (1.89) 21.5 (1.82) 18.9 (1.59) 23.7 (2.24) 19.8 (2.49) 25.8 (2.26) 3-9-85 25.2 (2.00) 25.4 (1.79) 25.0 (1.84) 33.8 (2.31) 28.9 (2.51) 30.9 (3.21) 32.4 (2.18) 3-16-85 28.6 (2.35) 33.9 (2.35) 27.7 (1.93) 32.7 (2.31) 38.2 (2.94) 18.1 (1.94) 39.6 (2.74) 3-23-85 37.1 (2.57) 44.8 (2.69) 39.4 (2.54) 39.7 (2.36) 40.2 (3.04) 23.7 (2.29) 48.9 (3.09) 3-30-85 14.6 (1.84) 17.0 (2.02) 15.0 (1.81) 15.0 (1.66) 17.2 (1.92) 7.63 (1.35) 18.5 (2.16) i 28.3 27,6 28.2 28.0 25.1 25.3 33.4 (14.9)

.(21.2)

(14.6)

(19.6).

(18;2)~

(16.0)

(15;7) 1.96 o I8.0 MAX: 48.9 X:

27.9 X:

MAX: 44.8 n:

39 51' MIN:

7. 2,3 MIN:

7.84 n:

I 1.96 o (Due to counting statistics.)'l 3

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Z C - Electricity out at site, pump not runnin9.l i

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Table 11.B.1 Concentrations of Long-lived G(oss Beta Particulate Activity in Air. (fCi/m )

I b) Second Quarter, 1985.

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Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 l

R-3 R-4 R-11 4-6-85 17.5(1.89) 15.6 (1.59) 14.6 (1.54) 13.7 (2.09) 13.5 (1.85) 8.11 (1.49) 23.4 (2.27) 4-13-85 23.4 (2.27) 22.6 (1.89) 23.3 (2.00) 22.3 (1.99) 18.6 (2.39) 12.7 (1.44) 23.9 (2.01) 4-20 21.4 (2.36) 28.3 (2.34) 27.2 (2.16) 26.9 (2.21) 3.29 (1.23) 22.0 (2.95) 25.7 (2.26) 4 ' /-85 11.8 (1.80) 13.2 (1.62) 11.0 (1.55)

C C

21.5 (1.81) 27.1 (2.09) z 1

2 5-4-85 26.1 (1.65) 22.9 (1.76) 25.4 (1.70) 19.7 (1.80) 3.90 (1.27) 11.0 (1.44) 29.0 (2.39) 5-11-85 16.8 (1.75) 15.5 (1.68) 24.2 (1.97) 23.1 (1.84) 25.2 (2.15) 24.6 (2.03) 29.4 (1.88) 5-18-85 19.0 (1.40) 16.9 (1.37) 17.5 (1.54) 12.7 (1.40) 19.1 (1.71) 23.5 ~(1.52) 20.1 (1.65) 5-24-85 31.1 (2.05) 27.8 (1.67) 28.4'(1.62) 23.4 (1.45) 30.5 (2.04) 39.3 (2.68) 23.7 (1.53) 6-1-85 29.6 (1.83) 11.4 (1.22) 29.1 (1.79) 25.8 (2.17) 28.0 (2.00) 26.5 (1.74) 27.3 (1.82) 6-8-85 34.3 (2.19) 31.1 (1.99) 24.8 (1.79) 27.6 (1.68) 19.8 (1.80) 25.2 (1.64) 30.8 (1.76) 6-15-85 31.0 (2.04) 32.1 (2.04) 32.7 (1.83) 32.0 (1.75) 25.6 (1.92) 26.6 (1.90) 28.6 (2.05) 6-22-85 28.8'(1.Q9) 32.8 (2.21) 32.1 (2.17) 33.4 (1.97) 37.8 (2.41) 31.7 (2.13) 35.1 (2.18) 6-29-85 24.8 (1.76) 30.5 (1.84) 25.5 (1.71) 26.2 (1.61) 19.2 (1.70) 25.1 (1.81) 26.4 (1.74) i 24.3 23.2 24.3 23.9 20.4 22.9 27.0 1.96 a (13.1)

(16.0)

(13.7)

(12.4)

(20.0)

(16.5)

(14.6).

E: 23.9 MAX: 39.3 E: 2 5 MAX:

34.3 MIN:

11.0 n: 51 MIN:

3.29

, n: 38 i

1.96 o (Due to counting statistics.)

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C Filter de.troyed by weather.

1 C

Pump not working, fuse blown.

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3 Table II.B.1 Concentrations of Long-lived Ghoss Beta Particu' late Activity in Air. (fCi/m )

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j c) Third Quarter, 1985.

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Collection Facility Sites Reference Sites R-3 R-4 R-11 Due F-7 F-9 F -1.6 A-19 i

7-6-85 56.5 (3.03) 44.2 (2.39) 16.9 (1.37) 44.1(2.21) 23.4 (2.23) 42.2 (2.32) 38.4 (2.33) 7-13-85 40.2 (2.38) 44.2 (2.29) 40.9 (2.19) 27.2 (1.67) 41.7 (2.60) 35.8(2.01) 42.3 (2.13) 7-20-85 26.6 (1.66)

' 20.9 (1.76) 26.1 (1.34) 28.9 (1.71) 7.78 (1.46) 25.3 (1.48) 27.9 (2.03) 7-27-85 25.1 (1.89) 25.6 (1.53) 26.5 (1.77) 25.3 (1.50) 13.4 (1.44) 27.1 (1.67) 29.7 (1.74) 8-3-85 25.4 (1.70) 26.4 (1.83) 23.4 (1.38) 25.5 (1.51) 27.9 (2.0) 31.1 (1.74) 26.8 (2.09) j 8-10-85 34.1 (2.00) 35.8 (1.98) 32.6 (1.96) 32.9 (1.84) 25.0 (1.90) 34.2 (2.03) 15.6 (1.61) 8-17-85 26.7 (1.91 26.4 (1.95) 26.9,(1.60) 23.3 (1.64) 33.2 (2.55) 32.4 (2.06 24.7(2.01) 8-24-85 38.9 (1.98) 35.6 (1.95) 49.0 (2.94) 43.8 (2.59) 31.0 (2.17) 30.7 (1.90) 34.3 (2.23) 8-31-84 38.8 (1.85) 38.6 (2.15) 26.4 (1.55) 26.4(1.66) 41.8 (2.46) 40.5(2.06) 20.5 (1.99) l 9-7-85 32.2 (1.53) 34.4 (1.76) 45.6 (2.53) 26.9 (1.70) 19.9 (1.23) 26.9 (3.17) 33.4 (1.53) 9-14-85 32.7 (1.66) 46.2 (2.25) 25.3(1.50) 28.8(2.19) 38.2 (2.21) 30.6 (1.51) 30.0 (1.73) 9-21-85 19.9 (1.20) 23.3 (1.51) 22.4 (1.46) 20.6 (1.51) 16.2 (1.26) 21.0 (1.53) 25.2 (1.61) 9-28-85 22.2 (1.34) 17.4 (1.56) 24.3 (1.45) c 32.5 (2.21) 22.9 (1.45) 21.0 (1.53)

E 32.3 32.2 29.7 29.5 27.1 30.8 28.4 1.96 o (19.2)

(18.7)

(18.8)

(14.5).

(21.0)

(12.4)

(14.6)

E:: 28.8 MAX:

56.5 X: 31,5 MAX: 42.3 MIN:

16.9 n: 51 MIN:

7.7,8 n: 39 1.96' o (Due 'to counting statisticsi) '

-c Fuse blown on pump.

g

?

M M

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

d) Fourth Quarter, 1985.

Facility Sites Reference Sites Collection Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 10-5-85 8.18 (1.65) e 19.7 (1.55) 28.2 (1.99) 11.6 (1.43) 18.4 (1.65) 25.3 (1.56) 10-12-85 21.7 (1.46).

20.2 (1.43) 20.3 (1.38) b 29.1 (2.73) 2.16 (1.51) 32.1 (2.22) 10-19-85 25.3 (1.43) b 23.4 (1.68) 24.6 (1.42) 16.5 (3.17) 25.1 (1.83) 25.2 (1.51) 10-26-85 16.5 (1.66) 35.7 (1.82) 35.0 (2.33) 34.6 (1.74) 41.1 (2.64) 33.1 (1.86) 35.7 (2.12) 11-2-85 42.9 (2.05) 42.1 (2.22) 40.6 (2.31) 44.7 (2.06) 21.2 (2.62) 34.9 (2.18) 40.8 (2.16) 11-9-85 24.5 (1.52) 18.4 (1.36) 20.2 (1.23) 24.5 (1.39) 27.2 (1.94) 19.9 (1.41) 29.5 (2.02) 11-16-85 b

28.1 (1.57) 20.6 (1.44) 26.8 (1.53) 16.8 (2.26) 30.5 (1.83) 24.2 (1.37) 11-23-65 35.9 (1.83) 30.6 (1.72) 21.1 (1.73) 46.9 (2.19) 31.2 (2.09) 42.9 (2.17) 41.8 (2.26) 11-30-85 44.1 (1.80) 39.9 (1.60) 43.3 (1.93) 46.6 (1.93) 30.7 (2.40) 30.5 (1.63) 47.4 (1.81) 12-7-85 50.6 (1.96) 54.9 (2.10) c 54.3 (1.90) 53.5 (1.99) 52.0 (2.01) 43.8 (1.90) 12-14-85 24.3 (1.69) 26.0 (1.64) 21.5 (1.68) 25.3 (1.58) 12.5 (1.85) 19.0 (1.93) 26.1 (1.82) 12-21-85 27.6 (2.32) 20.1 (1.79) 29.8 (1.95) 30.9 (2.27) 19.8 (2.44) 18.5 (1.39) 22.2 (2.02) 12-28-85 24.3 (1.69) 26.0 (1.64) 21.5 (1.68) 25.3 (1.58) 12.5 (1.85) 19.0 (1.93) 26.1 (1.82)

A 27.4 31.1' 26.4 34.4 24.9 28.1 32.3 1.96 o s19.3)_

(22.0)

(16.8)

.(21.2)

(21.2)

(20.8)

(16.9)

MAX:

54.9 X: 29.8 MAX: 53.5 i: 28.4 39 MIN:

8.18 n: 47 MIN: 11.6 n:

1.96 o (Due to counting statistics only.) i j

b Sample missing from site due to vandalism.

l i

i i

Pump motor malfunctioned during collection period.

c Sample we'Oht insufficient for analysis. l Filter deposition washed off by rain splash.

e I

l L

I 15 Figure II.B.1 l

GROSS BETA CONCENTRATIONS IN AIR l

1000 -.

1974-1985 I

~

e-o Facility Sampling Stations i =52.0 fCi/m3

~

3 A--a Reference Sampling Stations i=55.6 fCi/m g

l l

9 l 's a,

1 I

I l'

E l

'l

.5 10 0 i

~

s l

i l

L 8

I 1

I L

i g

I 1

I t

\\

I

\\;

h

\\

hI

\\

g k'

I

\\ l

\\

'l s

1 t I g

t l I

l...

\\l y

$ f'

~'

s I

~

l

\\

l t

I

, \\'

s I

\\

l t

l k!

h l

10

's l

73 74 75 76 77 78 79 80 81 82 83 84 85 86 TIME (year)

o ow 16 2.

Tritium Activity.

Atmospheric water vapor samples are collected continuously by passive absorption on silica gel at all seven air sampling stations (four in the Facility area and three in the Reference area).

The specific activity of tritium in water extracted from these weekly samples for 1985 is listed in Tables II.B.

2a-2d.

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

During periods when neither hygrothemograph was functional, relative humidity was obtained from the continuous data collected at the FSV meteorological tower.

The principle t-elease mode of tritium from the reactor is batch liquid releases from holding tanks. The tank water is first analyzed and tnen released with sufficient additional dilution, if necessary, in order to not exceed 10CFR20 concentration limits. The summary of tritium released by all modes is given in Table II.B.4.

The tritium released in 1985 was considerably less than in 1984. (See previous annual reports to the USNRC).

Sampling locations F-16 and A-19 are located near the Goosequill ditch, which is the principal route for effluent tritium release.

Inspection of Tables II.B. 2a-2d indicate only slightly elevated atmospheric tritium concentrations corresponding to the batch release of tritium in water along the ditch.

Due to evaporation while in transit, elevated tritium concentrations in air have been observed for these two locations in past years.

17 Inspection of Table II.H.2 reveals that the yearly geometric mean value for all Facility sites was nearly identical to that of the Reference sites.

The arithmetic means were both less than MDC.

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 tritiated water collected on silica gel (pCi/ liter) to activity per 3

unit volume of air (pCi/m ).

This is used if calculation of imersion dose from tritiated water vapor were ever necessary.

Tables II.B.

3a-3d list tritium concentrations in air calculated by this procedure.

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 has always shown the same site dependence on reactor effluent discussed in previous reports.

I

M M

i Table II.B.2 Tritium Concentrations in Atmo, spheric Water Vapo,r.,(pCi/L);

l l

a) First Quarter, 1985.

Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 1-5-85

< 242

< 242 1-12-85

< 240

< 240 f

1-19-85

< 242

< 242 1-26-85

< 242

< 242 2-2-85

< 241

< 241 429 (566)*

< 248

< 248 5

2-9-85

< 244

< 244 290 (574)

< 244 283 (292)

< 244 j

2-16-85

< 247

< 247 2-23-85

< 241,

< 241

< 241 3-2-85

< 235 277 (549) 270 (549) 458 (553)

< 235

< 235 308 (549) 3-9-85

< 246

< 232

< 232 449 (547) 303 (543)

< 232

< 232 456 (547) 3-16-85 3-23-85

< 238

>< 238

< 238

~

3-30-85

< 227 232 (272) 272 (274) 634 (278)

< 227

< 227 1.96 o'(Due to counting statistics.)

i.

l I

M M

M.

M M

M Table II.B.2 Tritium Concentrations in Atmospheric Water Vapor. pCi/L) i b) Second Quarter. 1985.

Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 4-6-85

< 241

< 241 4-13-85 380 (284) 254(286)

< 238

< 238 4-20-85 265 (274) 364 (276) 369 (280) 294 (282)

< 234 292 (274) 241 (274) 4-27-85

< 225 247 (270) 245 (270) 459 (272)

< 225

< 225~

371 (272) 5-4-85

< 232

< 232 357 (280) 285 (279)

< 232

< 232 G

5-11-85

< 233 286(281) 391(282) 386 (282)

< 233

< 233 5-18-85

< 239

~

5-24-85

<245;

< 245

< 231

< 245

< 245 6-1-85

< 231

< 231 270(278)

< 231

< 231 6-8-85

< 232

< 232 261 (280)

< 232

< 232 6-15-85

< 249

< 249 6-22-85 393 (279)

< 230 485 (280) 467 (299)

< 230

< 230 6-29-85

< 239

< 239 292 (288)

< 239

1.96 o (Due to counting statistics.)

i.

i i

t i

W M

M M

M Table II.B.2 Tritium Concentrations in Atmospheric Water Vapor. (pCi/L) c) Third Quarter, 1985.

Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-ll 7-6-85

< 232 243 (278) 897 (287)

< 232

< 232 7-13-85

< 236

< 236 7-20-d5

< 237

< 237 7-27-85

< 235

< 235 650 (288) 8-3-85

< 239

< 239 g

8-10-d5

< 235

< 235 8-17-85

< 234

< 234 274 (281)

< 234

< 234 8-24-d5

< 238 359 (288)

< 238

< 238 8-31-85

< 234

< 234 249 (281) 602 (286)

< 234

< 234 9-7-85

< 238

< 238 9-14-85 e

< 244

< 244 9-21-85 e

< 237

< 237 9-28-85

< 232 387 (273) 305 (279) 825 (286)

< 232

< 232 393 (280)

1.96 o (Due to counting statistics.)

e Insufficient sample volume for analysis.

i 1

e

M M

Table II.B.2 Tritium Concentrations in Atmospheric Water Vapor. (pC1/L)

,~

i d) Fourth Quarter, 1985.

c Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 10-5-85

< 232

< 232 281 (280)

< 232 4;232

< 232 10-12-85

< 250

< 250 263 (301) 276 (301)

< 250

< 250 10-19-85

< 242

< 242 10-26-85

< 234

< 234 11-2-85

< 233

< 233 245 (280) 323 (281)

< 245 281 (281) 240(280) 11-9-85

< 238

< 238 877 (318) 301 (312) 449 (314) 11-16-85

< 231

< 231 11-23-85

< 230 254 (277)

< 230 ~

< 230

< 230 11-30-85

< 230

< 230 270 (277) 351 (278) 422 (279) 314 (277) 12-7-85

< 229

< 229 263(275) 283(276) 416 (277) 461 (278) 12-14-85

< 232

<.232

< 232 12-21-85

< 236

< 236 12-28-85

< 235

< 235 1.96 o (Due to counting statistics.)

l t

M M

M 3

Table II.B.3 Tritium Concentrations in Atmosplieric Water Vapor. (pCl/m )-

a) First Quarter, 1985.

i Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 1-5-85

< 3.16

< 3.16 1-12-85

< 3.96

< 3,96

< 3.96 1-19-85

< 0.819

< 0.819 0.819

< 0.819

< 0.819 1-26-85

< 0.535

< 0.535 5

2-2-85

< 0.529

< 0.529 0.941 (1.24)*

< 0.544

< 0.544 2-9-85

< 0.448

< 0.448 0.532 (1.05)

< 0.448 0.519 (0.536)

< 0.448 2-16-85

< 0.767

< 0.767 2-23-85

< 1.33

< 1.33 3-2-85

< 1.10 1.30 (2.58) 1.27 (2.58) 2.15 (2.60)

< 1.10

< 1.10 1.44 (2.57) 3-9-85

< 1.14

< 1.14 3-16-85

< 1.47

< 1.47 2.85 f(3;47) 1.92 (3.44)

< 1.47

< IJ47 2.89 (3.47) 3-23-85

< 1.56

< 1.56.

< 1.56

< 1.56 3-30-85

< 0.517 0.528 (0.619) 0.619 (0.624) 1.44 (0.631)

< 0.517

l.96 o (Due to counting statistics.)

s.

4

M M

I I

t j

l 3

I Table II.B.3. Tritium Concentrations in Atmosplieric Water Vapor, (pCl/m ).

b) Second Quarter, 1985 I

i i

Reference Siles Collection Facility Siles Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 4-6-85

< 1.09

< 1.09 4-13-85 1.63 (1.22) 1.09(1.23)

< 1.02

< 1.02 4-20-85 2.05 (2.12) 2.81 (2.13) 2.85 (2.16) 2.27 (2.18)

< 1,81 2.26 (2.12) 1.86 (2.12) 4-27-85

< 1.05 1.15 (1.26) 1.14(1.26) 2.14 (1.27)

< 1.05

< 1.05 1.73 (1.27) 5-4-85

< 1.66

< 1.66 2.56(2.00) 2.04 (2.00)

< 1.66

< 1,66 0

5-11-85

< 2.06 2.53 (2.49) 3.46 (2.50) 3.41 (2.49)

< 2.06

< 2.06 5-18-85

< 2.09

< 3.04

< 4.56

< 2.58

< 2.04

< 1.70

< 1.59 5-24-85

< 2.S,1

< 2.51

< 2.51'

< 2.37

< 2.51

~

6-1-85

< 2.17

< 2.17 2.54 (2.62)

< 2.17

< 2.17 6-8-85

< 2.41

< 2.71'

< 2.41

< 2.41 6-15-85

< 2.86

< 2.86 6-22-85 2.58 (1.83)

< 2.58 5.43 (3.14) 5.23 (3.35)

< 2.58

< 2.58 6-29-85

< 1.58

"< 1.' 58 ' '

'< l.58'

' 1'.93 -(1.90)

< 1.58

l.96 o (Due to counting statistics.)

i

.i.

l I

j j

i -

4 i

M M*

M M

j i

1 6

i, i

4 l

l i

i Table II.B.3 Tritium Concentrations in Atmosp'heric Water vapor. (pCi/m )

I i

c.) Third Quarter, 1985.

l i

I i

Collection Facili ty Ites Ref rence Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 7-6-85

< 2.71

'2.83 (3.24) 10.5 (3.36)

< 2.71

< 2.71 7-13-85

< 2.22

< 2.22 7-20-85

< 3.12

< 3.12 7-27-85

< 2.96

< 2.96 8.18 (3.62) 8-3-85

< 2.89

< 2.89 2

8-10-85

< 2.66

< 2.66 8-17-85

< 2.25

< 2.25 2.63 (2.52)

< 2.25

< 2.25 8-24-85

< 0.219 0.303 (0.243)

< 0.219

< 0.219 8-31-85

< 1.72

< 1.72 1.83 (2.07) 4.44 (2.11)

< 1.72

< 1.72 9-7-85

< 1.79

< 1.79 9-14-85 e

< 2.54

< 2.54 9-21-85 e

'< 2.' 03 "" ' '

' ' < 2.'03 '

'T

<'2.03

< 2.03

< 2.03 9-28-85

< 1.18 1.98 (1.40) 1.56 (1.43) 4.21 (1.46)

< 1.18

< 1.18 2.01 (1.43)

1.96 o (Due to counting statistics.)

e. Insufficient sample volume for analysis.

j i

i l

W W

l i

t s

4 Table 11.8.3 Tritium Concentration:

.a Atmospheric Water Vapor. (pci/m )

1 i

d.). Fourth

.,e ter,,1985.

l i

Collection Facility Sites l

Ref rence Sites i

Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 10-5-85

< 0.936

< 0.936 1.13 (1.13)

< 0.936

< 0.936 10-12-85

< 1.24

< 1.24 1.31 (1.50) 1.37 (1.49)

< 1.24

< 1.24 10-19-85

< 0.728

< 0.728 10-26-85

< 1.21

'.808 (0.943) 5 11-2-85

< 0.785

< 0.785 0.825 (0.943) 1.09 (0.948)

< 0.825 0.946 (0.946) 0 11-9-85

< 0.784

< 0.784 2.89 (1.05) 1.48 (1.53) 0.992 (0.694) 11-16-85

< 0.683

< 0.683 11-23-85

< 0.497 0.548 (0.598)

< 0.497

< 0.497 11-30-85

< 0.640

< 0.640 0.751(0.770) 0.977 (0.774) 1.17 (0.774) 0.874 (0.771) 12-7-85

< 0.536

< 0.536 0.615 (0.643) 0.662 (0.646) 0.973 (0.648) 1.08 (0.651) 12-14-85

< 0.392

< 0.392 12-21-85

< 0.610

'< 0.610

<'0.610

< 0.610

< 0.610 12-28-85

< 0.620

< 0.620 1.96 o (Due to counting statistics.)

l I

I

M M

M Table II.B.4 Tritium Released (Ci) in Reactor Effluents,1985.

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Total Continuous 0.046 0.018 0.018 0.0071 0.0078 0.012 0.025 0.026 0.021 0.011 0.47 0.64 1.30 (Turbine building sump and reactor building sump)

Batch Liquid 3.85 0.41 0.0075 0.025 0.0067 0.0097 1.1 2.3 1.5 1.2 2.7 2.2 15.3 Gaseous Stack 0.0 0.0049 0.0058 0.0080 0.0091 0.0051 0.019 0.0070 0.010 0.066 0.017 0.0098 0.16 Total 3.9 0.44 0.031 0.040 0.024 0.027 1.18 2.28 1.55 1.25 3.19 2.86 16.8 g

27 3

Concentrations of Gamma-ray Emitting Radionuclides in Ambient

.l i r.

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 sdven 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 100 minute count is typically 3

required to achieve an LLD of 70.0 fCi/m. Radon daughters and Thoron daughters are trapped on the particulate filter ahead of the charcoal l

trap. Radon-222 daughter in-growth on the charcoal can be corrected by the high resolution spectrometry.

Any positive I-131 activity is corrected for radioactive decay back to the midpoint of the collection period. Decay correction to the midpoint of the sanpling period is appropriate as any I-131 in air would not arrive at the sampling station at a constant rate, but rather in pulses of short duration compared to the collection period. This is the case whether the I-131 source term would be weapons testing fallout or reactor stack effluent.

The mean air concentrations measured for all four quarters of 3

3 1985 wera J 88 fCi/m for the Facility stations, and -1.32 fC1/m for the Reference stations. These means were not statistically different from zero and not statistically different from each other. There were 358 charcoal samples analyzed in 1985.

There were approximately an equal number of negative and positive concentrations distributed around the arithmetic mean which was close to zero.

The Effluent Release Report indicates no release of I-131 during the year.

Table II.B.5 shows only four I-131 concentrations which were greater than the MDC. These values were all in the first quarter of

28 1985.

The values were all very low, the uncertainty limits did J

include zero, but the period, particularly during March, corresponds to a period of elevated I-131 in surface water (See Section II.D.

for further discussion). The source of this I-131 was nuclear medicine uses in hospitals upstream of the reactor.

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

The positive Cs-137 result for F-7 during the first quarter may be explained as a false positive value or attributed to resuspension of surface soil.

The positive Cs-134 result for R-11, during first quarter, can only be a false positive value.

This is a Reference location, Cs-134 was not detected at any Facility sites and no Cs-134 was released in reactor effluents.

Although only Cs-134 and Cs-137 are reported, each gamma-ray spectrum is scanned for evidence of peaks from other fission products and activation products.

Only additional peaks due to naturally occurring radionuclides were observed during 1985.

I I

M M

M l

I l

l l

1 i

i 3

I Table II.B.5 Iodine-131 Concentrations in Air. l(fC1/m )

l i

a) First Quarter, 1985.

Reference Sites Collection Facility Sites i

Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 1-5-85

< 31.1

< 31.3 33.4 (69.2)

< 29.5

< 35.7

< 33.0

< 29.9 1-12-85

< 29.3

< 33.1

< 31.6,

< 34.0

< 28.8

< 15.7

< 30.2 1-19-85

<.32.1

< 30.6

< 30.4

< 25.1

< 31.3

< 27.7

< 30.2 1-26-d5

< 11.4

< 32.9

< 39.3

< 33.6 C

< 31.5

< 43.0 3

2-2-d5

< 35.3

< 31.1

< 33.9

< 24.6

< 33.1

< 32.9

< 29.6 2-9-85

< 29.7

< 32.3

< 32.8

< 33.6

< 29.8

< 29.5

< 32.4 2-16-d5

< 35.2

< 24.4 C

< 33.0

< 31.8

< 33.1

< 31.9 2

2-23-85

< 35.5

< 28.3

< 30.6

< 31.9

< 24.9

< 27.8

< 24.3 3-2-85

< 26..I

< 12.2

< 14.7 17.3 (36.8)

< 22.6

< 26.6

< 14.6 3-9-85

< 21.2

< 22.6

< 22.9

< 27.3

< 30.6

< 21.1

< 12.8 3-16-85

< 25.5

< 18.3

< 18.7

< 14.8

< 2.05

< 18.7

< 16.2 3-23-85

< 13.1

< 14.7

< 9.89 16.3 (29.3)

< 16.5

< 20.8

< 12.6

,.< 10.2

< 13.2 15.1 (25.2)

< 15.8

..,, 9,68.,,

3-30-85

< 12.5

< 14.6 l

1.96 o (Due to counting statistics.)

1311 MPC, = 10 fCi/m. (10CFR20, Appendix B, Table II) f 5

3 g

t C

Sample lost due to extreme winds.

{

3 C

Pump malfunctioned during;the collection period.

2 i

M M

i I

i i

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

b) Second Quarter, 1985.

Collection Facility Sites Reference Sites F-16 A-19 R-3 R-4 R-Il Date F-7 F-9 4-6-85

< 9.43

< 18.2

< 20.8

< 19.5

< 30.6

< 12.6

< 10.4 4-13-85

< 30.7

< 23.2

< 13.4

< 27.9

< 29.0

< 23.8

< 16.0 4-20-85

< 17.8

< 15.4

< 20.4

< 27.9

< 19.9

< 31.2

< 24.4 4-27-85

< 25.8

< 19.4

< 18.5

< 24.5 C

< 19.3

< 12.7 5-4-85

< 17.7

< 30.7

< 23.1

< 32.0

< 32.5

< 19.7

< 31.0 5-11-85

< 16.4

< 21.7

< 18.1

< 18.3

< 29.7

.7.5

< 14.5 5-18-85

< 15.9

< 16.4

< 14.4

< 10.8

< 17.5

< 10.1 5-24-85

< 23.3

< 6.33

< 5.55

< 32.3

< 22.5

< 17.1 6-1-85

< 26;7

< 33.0

< 31.8

< 28.0

< 34.4

< 13.7

< 34.2 6-8-85

< 27.8

< 19.5

< 30.3

< 25.6

< 24.4

< 22.5

< 27.9 6-15-85

< 17.9

< 13.5

< 11.1

< 11.0

< 16.8

< 20.9

< 13.0 6-22-85

< 26.9

< 18.5

< 29.2

< 21.0

< 23.6

< 19.5

< 22.9

' < 17.8

< 19.2

<< 21.7

< 19.9 6-29-85

< 26.6

< 23.4

< 32.3 5

3 131I MPC = 10 fCi/m. (10CFR20, Appendi B. Table II)

I a

I w

C Pump not working, fuse blown.

l i

m m

a m

1 3

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

c) Third Quarter, 1985.

Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 l

I 7-6-85

< 34.5

< 30.0

< 23.9

< 25.9

< 27.8

< 30.1

< 22.5 7-13-85

< 22.3

< 21.6

< 21.3

< 18.5

< 11.0

< 15.0

< 17.7 7-20-85

< 18.1

< 25.6

< 17.2

< 20.9

< 21.4

< 28.5

< 33.4 7-27-85

< 26.5

< 30.9

< 27.0

< 10.0

< 15.4

< 16.9

< 30.9 8-3-85

< 20.3

< 18.2

< 16.8

< 26.9

< 16.2

< 19.4

< 32.9 8-10-85

< 27.2

< 19.2

< 25.1

< 30.2

< 21.3

< 31.4

< 32.5 8-17-85

< 32.2

< 34.6

< 17.5

< 26.6

< 30.2

< 33.2

< 28.6 8-24-85

< 28.1

< 18.4

< 27.4

< 29.5

< 22.6

< 32.8

< 33.0 8-31-85

< 14.9

< 23.8

< 20.8

< 21.8

< 34.4

< 34.2

< 29.9 9-7-85

< 17.3

< 30.4

< 29.4

< 32.8

< 13.5

< 26.8

< 24.2 9-14-85

< 30.8

< 21.6

< 29.3

< 33.1

< 21.9

< 23.3

< 18.9 9-21-85

< 20.4

< 16.7

< 33.5

< 32.1

< 26.2

< 19.7

< 25.9 9-28-85

< 18.7

< 34.8

< 19.3 C

< 24.9

< 18.6

< 34.1 5

3 131I MPC,= 10 fC1/m. (10CFR20, Appendix,8, Table II) l M

C Fuse blown on pump.

f l

m M

M M

M l

l l

Table II.B.5 I-131 Concentrations in Air. (f.Ci/m )

{

3 t

i d.) Fourth Quarter, 1985.

l 8

i I

i Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 10-5-85

< 24.9

< 28.2

< 23.5

< 31.2

< 23.3

< 29.7

< 17.9 10-12-85

< 16.4

< 19.0

< 18.9

< 12.2

< 19.6

< 16.7

< 32.8 6.6d 10-19-85

< 19.3

< 20.2

< 3.39

< 33.9

< 19.9

< 34.5 10-26-85

< 23.5

< 21.9

< 26.2

< 16.8

< 12.5

< 24.5

< 25.2 11-2-85

< 19.1

< 16.7

< 26.4

< 18.0

< 19.0

< 32.4

< 19.2 11-9-85

< 20.6

< 25.2

< 19.8

< 15.8

< 21.1

< 24.7

< 29.2 11-16-85 b'

< 27.9

< 22.3

< 22.7

< 17.8

< 32.9

< 24.6 11-23-85

< 29.7

< 32.5

< 19.1

< 18.7

< 30.4

< 21.4

< 22.0 11-30-85

< 28.2

< 20.7

< 26.3

< 25.5

< 28.9

< 23.6

< 33.6 12-7-85

< 13.6

< 29.2

.C

< 22.6

< 31.7

< 34.1

< 21.0 12-14-85

< 22.1

< 14.4

< 28.0

< 21.8

< 22.8

< 35.0

< 32.7 12-21-85

< 34.1

< 20.2

< 18.0

< 19.5

< 18.6

< 11.1

< 20.0 12-28-85

< 22.9

< 32.8

< 19.2

< 16.1

< 25.9 a

< 16.0

1.96 o (Due to counting statistics.)

5 3

U 131I MPC, = 10 fC1/m. (10CFR20, Appendix,B, Table II) j a.

Sample lost prior to analysis.

l

'b. Sample missing from site due to vandalism.

c.

Pump motor malfunctioned during the c611ection period.

t s

m m

M M

M i

i 3

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

L Facility Sites Reference Sites 1985 Collection Radio-

~

F-9 F-16 A-19 R-3 R-4 R-11 Date Nuclide

'F-7 1st Cs-134

< 3.77

< 3.43

< 3.47

< 3.99

< 4.43

< 4.14 6.07 (5.06)

Quarter Cs-137 4.59 (7.24)

< 3.29

< 4.03

< 4.39

< 4.83

.< 4.41

< 4.04 2nd Cs-134

< 2.94

< 2.19

< 2.23

< 2.16

< 3.09

< 2.47

< 2.57 Quarter Cs-137

< 2.94

< 2.37

< 2.26

< 2.19

< 3.26

< 2.45

< 2.63 3rd Cs-134

< 2.13

< 1.83

< 2.20

< 1.98

< 2.53

< 2.31

< 2.10 Quarter Cs-137

< 2.01

< 2.17

< 2.16

< 2.20

< 2.36

< 2.12

< 2.08 4th Cs-134

< 2.50

< 3.47

< 3.99

< 2.89

< 3.90

< 2.64

< 2.77 Quarter Cs-137

< 2.92

< 3.48

< 3.57

< 3.04

< 3.80

< 2.96

< 2.95

1.96 o( Due to counting statistics only.)

Cs-134 MPC, = 1 x 10 fC1/m, Cs-137 MPC, = 2 x 106 (Ci/m3 [3OCFR20, Appendix B, Table II).

6 l

ii.i i

i O

. i.

4 i

i i

l i

i i

i

I 34 I

II.C.

Radionuclide Concentrations in Water 1.

Drinking Water Drinking water is sampled biweekly at two locations down the hydrological gradient from Fort St. Vrain.

Location R-6 is the well used for drinking water by the town of Gilcrest, Colorado and R-3 is a water tap located on the CSU diary farm. 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 surface water from the Rocky Mountains to the west.

Table II.C.1 shows gross beta concentrations measured in 1985 from each water supply.

The mean for the Gilcrest site was significantly 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 concentratiors are responsible for the higher measured concentrations.

Table II.C.2 lists measured tritium concentrations in these same two drinking water sources.

The yearly arithmetic mean values for both locations were less than MDC and, therefore, not statistically different from each other.

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

A I

sample of 18 liters is passed through Dowex 1-x8 anion exchange resin and the resin then counted by Ge(Li) spectrometry for I-131.

This same method is used for milk samples. A three liter aliquot of the original sample is counted directly for the other gamma-ray emitters.

I I

35 Inspection of Table II.C.3 reveals occasional positive values of radionuclide concentration, but with the exception of Cs-137, these are interpreted to be random variations.

The Cs-137 concentrations

)

are significantly higher in the Gilcrest supply and this is to be expected due to the water treatment practices discussed above.

1 s

I I

l I

I I

e I

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

Collection Gilcrest City R-6 Fort Collins City R-3 I

Date 1985 (Reference) 1-5, 12 4.14 (2.10) 0.753(0.514) 1-19, 26 5.50 (2.15) 0.622(0.498) 2-2, 9 7.68 (2.23) 1.71 (0.559) 2-16, 23 8.74 (2.23) 1.47 (0.549) 3-2, 9 3.09 (2.00) 1.52 (0.523) 3-16, 23 8.11(2.12) 0.484(0.445) 3-30, 4-6 4.54 (2.02) 1.93 (0.517)

I 4-13, 20 6.33 (2.08) 0.563 (0.449) 4-27, 5-4 2.34(1.90) 1.76 '(0.510) l 5-11, 18 1.91(1.94) 0.624 (0.456) 5-24, 6-1 5.41(2.04) 0.472(0.445) 6-8, 15 5.07(2.05) 0.889(0.469)

~ 6-22, 29 4.24 (2.02) 1.03 (0.473) 7-6, 13 5.29(2.04) 1.25 (0.484) 7-20, 27 6.07(2.05) 1.56 (0.514) 8-3, 10 7.80(2.15) 1.06 (0.480) lg 8-17, 24 5.70(2.08) 1.05 (0.478)

'E 8-31, 9-7 6.59(2.17)

< 0.359 9-14, 21 4.95(1.97) 3.82 (0.649) 9-28, 10-5 7.25(2.13) 2.61 (0.546) i 10-12,19 3.26 (1.98) 0.933(0.477) l 10-26, 11-2 3.81(2.16) 1.37 (0.537) 11-9, 11 4.72 (2.25) 1.18 (0.540) 11-23, 30 2.65(2.15) 0.889(0.533)

I 12-7, 14 4.00(2.22) 0.597(0.516) 12-21, 28 5.24(2.58) 0.861(0.523) 1

1.96 o (Due to counting statistics only.)

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

37 Table 11.C.2 Tritium Concentrations in Biweekly Composites of Drinking Water. (pCi/L)

Collection Gilcrest City R-6 Fort Collins City R-3 Date 1985 (Reference) 1-5, 12

< 243

< 248 1-19, 26 355 (294)

< 231 2-2, 9

<237

< 237 2-16, 23

< 235

< 235 3-2, 9

< 249

< 246 3-16, 23 369 (280)

< 231 3-30, 4-6

< 241

< 241 4-13, 20 434 (284)

< 234 4-27, 5-4 461 (281)

< 232 I

5-11, 18

< 239

< 239 5-24, 6-1 533 (282) 631 (282) 6-8, 15

< 249

< 249 6-22, 29

< 239

< 239 7-6, 13

< 237

< 237 7-20, 27

< 234

< 234 8-3, 10

< 235

< 235 I

8-17, 24

< 238

< 237 8-31, 9-7..

497 (289)

< 238 9-14, 21

< 237 303 (285) 9-28, 10-5 274 (280)

< 232 10-12, 19

< 234

< 234 10-26, 11-2 303 (281)

< 233 11-9, 16 350 (278)

< 230 11-23, 30 400 (278) 270 (275) 12-7, 14 315 (279)

< 232 12-21, 28

< 235

1.96 e (Due to counting statistics only.)

3 6

H MPC = 3.10 pCi/L (10CFR20),AppendixB, Table 11 I

M M

M l

l l

l i

I l

l i

Radionuclide Concentration ls in Bi-weekly Corhposite of Drink'ing Water. (pC1/L)

Table II.C.3 i

i i

Collection Date 1/5 & 12/8'5 1/19 & 26/85 2/2 & 9/85 Radionuclide Gilcrest Ft. Collins Gilcrest

Ft. Collins *'

Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 I-131

< 0.445

< 0.496

< 0.397

< 0.423

< 0.227

< 0.495 Cs-134

< 3.90

< 2.61

< 7.50

< 15.0

< 2.53

< 2.70 Cs-137

- 3.72

< 2.35

< 6:60

< 14.9

< 2.42

< 2.60 Zr-95

< 5.62

< 3.71

< 12.2

< 25.3

< 3.81

< 4.11 i

Nb-95

< 2.91

< l.91

< 7.05

< 15.3

< 1.99

< 2.12 Co-58

< 2.45

< 1.75

< 6.75

< 13.7

< 1.82

< 4.20 Mn-54

< 2.43

< l.57

< 6.60

< 13.4

< 1.65

< 1.73 Zn-65

< 5.17

< 3.34

< 16.5

< 38.9

< 3.53

< 3.91 Fe-59

< 5.85

< 4.14

< 15.0

< 29.1

< 4.15

< 4.38 C0-60

< 2.57

< 1.57

< 6.95

< 14.4

< 2.17

< 1.80 Ba-140

< 6.80

< 5.34

< 39.Y 6

< 76.0

< 6.01

< 5.83 La-140

< 7.82

< 6.14

< 45.1

< 87.4

< 6.91

< 6.70

..ii.

...i i.

,i i, i,....

I

' * ' Analyzed by o'utside lab.

w l

..s.

i ii i,iei.

.i6 i

j j

ie i 1 i l

l l

i i

i' i

i n

(

I i

i

M M

i i

l f

l l

Table II.C.3 Radionuclide Concentrations in Bi-weekly Composite cf Drinking Water. (pCi/L) (continued) i Collection Date 2/16 & 23/85 3/2 & 9/85 3/16 & 23/85 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 1-131

< 0.222

< 0.468

< 0.455

< 0.506

< 0.187

< 0.205 Cs-134

< 3.65

< 3.40

< 3.96

< 4.41

< 3.57

< 3.42 Cs-137

< 3.45

< 3.26

< 3.63

< 5.16

< 4.29

< 3.22 Zr-95

< 5.04

< 4.84

< 5.38

< 6.04

< 5.04

< 4.87 Nb-95

< 2.68

< 2.54

< 2.85

< 3.22

< 2.62

< 2.53 Co-58

< 2.39

< 2.23

< 2.49

< 2.75

< 2.32

< 2.20 Mn-54

< 2.23

< 2.14

< 2.41

< 2.72

< 2.21

< 2.11 Zn-65

< 5.16

< 4.42

< 4.75

< 5.62

< 5.20

< 4.42 Fe-59

< 5.22

< 4.98

< 5.67

< 6.10

< 5.20

< 5.08 Co-60

< 2.31

< 2.12

< 2.44

< 2.76

< 2.31

< 2.19 Ba-140

< 5.29

< 4.72

< 5.20-

< 6.07

< 5.78

< 3.46 La-140

< 6.09

< 5.43

< 5.98

< 6.98

< 6.65

< 3.98 e

.I a

i 8.

te

},

.4 e

,4

.4 t

g l

1 8 4 a

i i 4 e

I i

l l

l i

I

.2

M M

M i

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

Collection Date 3/30&4/6/85 4/13 & 4/20/85 4/27 & 5/4/85 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 I-131

< 0.192

< 0.235

< 0.197

< 0.364

< 0.472 Cs-134

< 4.79

< 4.68

< 3.07

< 3.58

< 3.66

< 3.67 Cs-137

< 4.74

< 4.18

< 3.02

< 3.53 4.62 (6.40)*

< 3.65 Zr-95

< 6.97

< 6.04

< 4.30

< 5.11

< 5.22

< 5.19 Nb-95

< 3.58

< 3.46

< 2.29

< 2.32

< 2.85

< 2.88 Co-58

< 3.14

< 2.88

< 2.06

< 2.39

< 2.38

< 2.40 Mn-54

< 2.99

< 2.80

< 1.96

< 2.38

< 2.34

< 2.37 Zn-65

< 6.47

< 5.66

< 4.33

< 4.58

< 4.92

< 4.72 Fe-59

< 7.27

< 6.49

< 4.43

< 5.44

< 5.50

< 5.50 Co-60 '

< 3.24

< 2.33

< 2.01

< 2.44

< 2.48

< 2.49 Ba-140

< 6.70

< 6.22

< 4.51

< 5.80

< 5.70

< 5.73 La-140

< 7.70

< 7.15

< 5.19

< 6.67

< 6.56

< 6.59

1.96o (Due to counting statistics only.)

g i

i i

i

m M

M M

M I

i i

l i

Radionuclide Concentrations in Bi-weekly Cobposite of Drinking Water. (pci/L) (continued)

Table II.C.3 Collection Date 5/11 & 5/18/85 5/24&6/1h85 6/8 & 6/15/85 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins 1

R-6 R-3 R-6 R-3 R-6 R-3 1-131

< 0.472

< 0.364 0.589(0.735f

< 0.345

< 0.314

< 0.267

8.00-l Cs-134

< 3.86

< 3.67

< 3.56

< 3.75

< 3.89 Cs-137

< 3.58 6.72 (6.00)

< 3.39 3.76 (6.77)

< 3.52

< 8.13 >

i Zr-95

< 5.11

< 4.76

< 5.08

< 5.47

< 5.59

< 13. 5' l

Hb-95

< 2.70

< 2.42

< 2.59

< 2.84

< 2.88

< 6.91 Co-58

< 2.47

< 2.15

< 2.17

< 2.38

< 2.20

< 5. 71 '

i Mn-54

< 2.32

< 2.17

< 2.22

< 2.36

< 2.41

.< 5.10 Zn-65

< 5.16

< 4.67

< 4.96

< 5.08

<t11.6 I

l Fe-59

< 5.45

< 4.95

< 4.77

< 5.15

< 5.48

< 11.1 f

Co-60

< 2.39

< 2.34

< 2.33

< 2.48

< 2.27

-< 5.70 Ba-140

< 4.96

< 3.05

< 3.74

< 3.86

< 4.00

< 6.77 La-140

< 5. 70.

< 5.07

< 4.30

< 4.44

< 4.60

< 9.32-1 i

i

1.96o (Due to counting statistics only.)

C i

2' l

t I

M M

M i

i i

Table II.C.3 Radionuclide Concentrations in Bi-weekly Codiposite of Drinking Water. (pCi/L) (continued) i Collection Dat6 6/22 & 6/29/85 7/7 & 7/13/35 7/20 & 7/27/85 readlonuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 I-131

< 0.304

< 0.240

< 0.400

< 0.328

< 0.380

< 0.414 Cs-134

< 3.35

< 4.03

< 2.77

< 3.13

< 3.08

< 3.91 Cs-137

< 3.40

< 3.96 3.98 (4.92)

< 3.22

< 3'.15

< 4.01 Zr-95

< 4.99

< 5.48

< 3.91

< 4.51

< 4.82

< 5.61 Nb-95

< 2.42

< 2.98

< 2.04 3.73 (3.76)

< 2.42

< 2.89 Co-58 2.72 (3.21)

< 2.54

< 1.70

< 2.03

< 2.12

< 2.42 Mn-54

< 2.16

< 2.38

< 1.71

< 1.92

< 1.91

< 2.41 Zn-65

< 4.45

< 5.11

< 3.60

< 4.17

< 4.27

< 5.31 Fe-59

< 4.84

< 5.41

< 3.92

< 4.42

< 4.37

< 5.57 Co-60

< 2.37

< 2.76

< 1.91

< 2.20

< 2.23

< 2.76 Ba-140

< 3.67

< 4.27

< 5.29

< 3.43

, < 5.45

< 5.35 La-140

< 4.22

< 4.91

< 6.09

< 3.95

< 6.27

< 6.15

)

i

1.96o (Due to counting statistics only.)

0 l

o..

o.

1 j

l i.

I i

i l

I

M M

i i

f I

I i

i i

Table II.C.3 Radionucijde Concentrations in Bi-wecyly Composite of; Drinking Water. pC1/L) (continued)

Coll'ection Date 8/17 & 8/24/85 8/31 & 9/7/85 8/3 & 8/10/85 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins G11 crest Ft. Collins' R-6 R-3 R-6 R-3 R-6 R-3 i..

,.i. i I-131

< 0.269

< 0.440

< 0.264

< 0.216

< 0.494

< 0.166 Cs-134

< 3.17

< 2.80

< 2.50 3.40(4.25)

< 2.57

< 2.71

< 3.02 3.56 (4.98) *

< 2.61

< 2.95

< 2.67

< 2.61 Cs-137 Zr-95

< 4.49

< 4.26

< 4.00

< 4.81

< 4.00

< 4.36 tib-95 2.60 (3.81)

< 2.19

< 2.08

< 2.34

< 2.08

< 2.30 Co-58

< 1.89

< 1.72

< 1.71

< 1.97

< 1.70

< 1.61 Mn-54

< 2.66

< 2.03

< 1.57

< 2.25

< 1.90

< 1.89 Zn-65

< 4.65

< 4.34

< 3.36

< 0.457

< 4.10

< 0.407 Fe-59

< 4.21

< 3.90

< 3.62

< 4.25

< 4.18

< 3.68 Co-60

< 2.32

< 2.27

< 1.77

< 2.37

< 2.06

< 2.10 Ba-140

< 4.55

< 3.87

< 2.91

< 3.38

< 2.96

< 3.01 La-140

< 5.23

< 4.45

< 3.35

< 3.89

< 3.40

< 3.46 i s.

.....ii,..

..n, e,

...,..i.

.o.,,i,.

1.96o (Due to counting statistics only.)

l i

c-i l,

l

.i..

.... i l

i l

j i

i i i

j i

f

h m

m m

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

Coll'ection Date 9/14 & 9/21/85 9/28 & 10/5/85 10/12 & 10/19/85 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 1-131

< 0.277

< 0.251

< 0.308

< 0.353

< 0.231

< 0.230 Cs-134

< 3.04

< 2.63

< 3.86

< 3.24

< 3.22

< 3.55 Cs-137

< 2.88

< 2.66

< 3.60 4.93 (5.84) 3.51 (5.70)

< 3.39

< 4,67

< 4.17

< 5.'30

< 4.62

< 4.30

< 5.27 Zr-95 fib-95,

< 2.48

< 1.94

< 3.22

< 2.52

< 2.40

< 2.70

~

. Co-58

< 1.79

< 2.27

< 2.01

< 1.97

< 2.10 Mn-54

< 2.16'

< 1.95

< 2.76

< 2.29

< 2.22

< 2.43 Zn-65

< 4.47

< 4.03

< 5.87

< 5.04

< 5.27

< 5.09

< 3.93

< 4.46

< 4.91

< 4.92

< 4.32

< 4.61 Fe-59

< Z.31

< 2.12

< 2.85

< 2.55

< 2.51

< 2.69 Co-60

< 3.28

< 2.92

< 4.18

< 3.57

< 3.49

< 3.80 Ba-140

< 3.77

< 3.36

< 4.81

< 4.10

< 4.02

< 4.37 La-140

1.960 (Due to counting statistics only.)

2

M M

i i

l i

Table II.C.3 Radionuc1]de Concentrations in Di-wee ly Composite of Drinking Water. (pC1/L)

(continued)

Coll'ection Date 10/26 & 11/2/85 11/9 & 11/16/85 11/23 & 11/30/85 Radionuclide

Gilcrest Ft. Collins Gilcrest Ft. Collins G11 crest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 1-131

< 0.211

< 0.207

< 0.195

< 0.393

< 0.356

< 0.159 Cs-134

< 2.87

< 3.25

< 3.20

< 3.69

< 3.09

< 3.22 Cs-137

< 2.92

< 3.08 4.13 (6.05)*

< 3.52 6.14 (5.38)'

< 3.03 Zr-95

< 4.44

< 4.95

< 4.94

< 5.20

< 4.21

< 4.53 Hb-95

< 2.13

< 2.39

< 2.78

< 2.93

< 2.28

< 2.49 Co-58

< 1.82

< 2.02

< 2.22

< 2.25

< 1.95

< 2.01 Mn-54

< 2.15

< 2.25

< 2.33

< 2.76

< 2.12

< 2.27 Zn-65

< 4.74

< 5.53

< 6.99

< 5.23

< 4.64 fe-59

< 4.15

< 4.31

< 4.76

< 4.98

< 4.60

< 4.16 00-60

< 2.24

< 2.45

< 2.61

< 2.89

< P.38

< 2.47 i

Ba-140

< 3.31

< 3.58

< 3.67

< 4.29

< 3.32

< 3.50 La-140

< 3.80

< 4.12

< 4.23

< 4.93

< 3.81

< 4.02 l

1.96o (Due to counting statistics only.)

i aa iii.

.1 i

1

^

M M

M i

I i

i.

I Table II.C.3 Radionuclide Concentrations in Di-weekly Composite of; Drinking Water. (pC1/L) (continued) i I

Collection Date 12/7 & 12/14/85 12/21 & 12/28/85 Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins Radionuclide R-6 R-3 R-6 R-3 R-6 R-3 1-131

< 0.403

< 0.211

< 0.280

< 0.298 Cs-134

< 3.51

< 3.03

< 3.52

< 3.93 Cs-137

< 3.33

< 3.12

< 3.62

< 4.07 Zr-95

< 5.22

< 4.22

< 5.01

< 5.53 Nb-95

< 2.63

< 2.24

< 2.80

< 2.93 Co-58

< 2.12

< 1.94

< 2.31

< 2.45 cn Mn-54

< 2.51

< 2.29

< 2.63

< 2.93 Zn-65

< 5.45

< 4.82

< 6.29

< 6.31

< 5.17

< 5.67 Fe-59

< 4.80

< 4.38 Co-60

< 2.68

< 2.37

< 2.88

< 3.22 Da-140

< 4.81

< 4.14

< 4.77

< 5.38 La-140

< 5.53

< 4.77

< 5.49

< 6.18

.i

.. i,

f l=

0

'1$$f

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8 0

Il 8e

+l l

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I 47 I

2.

Surface Water.

Surface water is collected monthly from four sites. Since the reactor water effluent can be directed to either river course, there are upstream and downstream sampling locations on both the St. Vrain Creek and on the South Platte River.

Table II.C.4 shows tritium concentrations measured at the four l

surface water sites.

Most of the values were less than MDC.

The arithmetic mean value for the downstream locations in 1985 was not significantly different from the two upstream locations (Table II.H.2).

Table II.B.4 shows that the total liquid effluent release of tritium as tritiated water was lower in 1985 than in past years.

The total release in 1985 was 16.8 Ci compared to 138 Ci in 1984.

Figure II.C.1 shows that upstream, downstream and potable water mean values were nearly the same in 1985 and, in fact, less than MDC which is 247

^

pCi/L (one half of the LLD value in Table III.A.2).

Table II.C.5 shows measurements of fission product and activation product concentrations in surface water samples collected monthly.

There were occasional positive values, but the mean of the downstream sites was not significantly different from the mean of the upstream sites during 1985 for any of the gama-ray emitting radionuclides measured.

This has been the case since the inception of reactor operations at the site.

The occasional positive values are either Cs-137 which can be expected or values with large uncertainty limits.

In addition to the monthly sampling of the South Platte River and St. Vrain Creek, a continuous water sample is collected at station A-25.

An aliquot of the fam pond outlet is sampled every 10 minutes I

48 I

and the composite collected weekly. The weekly composites are then combined and analyzed monthly. The results of these samples are shown in Table II.C.6.

For every month except April and June there is evidence of measurable tritium release.

Mean values for the other radionuclides are low and mostly 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.

The on'iy three positive results have confidence limits that include zero and are assumed to be methodological variation.

If the radionuclides listed in Table II.C.7 were released, and leaching to ground water occurred, then the highest concentrations expected would be for tritium.

This conclusion is valid becausq the activity of tritium released is significantly greater than any of the other radionuclides, and is far more mobile than any other.

{

For comparison purposes, Table II.C.8 lists the Mi,ximum I

Permissible Concentration values for each of the radionuclides listed in Tables II.C. 5-7.

During 1985, I-131 was detected in surface water. The source and consequences of this are discussed in detail in Section II.D. Milk.

I

M M

M I

t Table II.C.4 Tritfum 60ncentrations in Surface Water. (pCi/L) i DQWnsingan Sites Upstream. Sites Collection St. Vrain S. Platte St Vrain S. Platte J

R 10 A-21 F-19 Date F-20 1-12-85

< 243

< 246

< 246 2-9-85 351 (557)

< 237

< 247 **

< 237 3-9-85

_,e 232

< 246

< 232

< 246 4-13-85 445 (288)

< 238

< 238 5-11-85

< 233

< 233 e

6-8-85

< 232

< 232 7-13-85

< 236

< 237

< 236 8-10-85

< 235

< 235 9-14-85

< 244

< 244 10-12-85 295 (301) 319 ~(301)

< 250 353 (300) 11-2-85 270 (281)

< 233

< 233 12-14-85

< 232

.r.

i

1.96 o (Due to counting statistics only.)

- Collection date 2/16/85.

l

se e

uma sus sum uma une em m

m m

Ese e

m e

um N l

\\

j

\\

i

\\

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i l

TRITIUM CONCENTRATIONS IN WATER 1974-1985 i

e-* Surface Upstream l i= 505 pCi/L y

i a--6 Surface Downstream E=658 pCi/L g

^

1500 i =445 pCi/L

{si o...o Potable 1400

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300

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200 E

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$100 e 4 t

j ei,.

I'.,

1 73 74 75 76 77 78 79 80 81 82 83 84 85 TIME (year') '

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W W

W M

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l i

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I.

Table II.C.5 Radionuclide Concentrations in Surface Water.

(pCi/L) l Collection Date:

anuary 12, 1985,

l l

l i

i I

l Downstream sites Upstream ' Sites

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

.i Cs-134

< 2.12

< 2.88

< 1.83

< 2.32 i

Cs-137 3.26 (3.47)

< 2.70

< 1.75

< 2.23 Zr-95

< 3.24

< 4.07

< 3.02

< 3.52 Nb-95

< 4.88

< 2.25

< 1.58

< 1.92 Co-58

< 1.49

< 1.86

< 1.35

< 1.45 Mn-54

< 1.32

< 1.81

< 1.19

< 1.48 Zn-65

< 2.74

< 3.78

< 2.52

< 3.05 Fe-59

< 3.60

< 4.42

< 3.43

< 3.18 Co-60

< 1.33

< 1.92

< 1.19

< 1.51 Ba-140

< 5.83

< 4.68

< 6.30

< 2.57

< 6.71

< 5.38

< 7.24

< 2.96 La,140, ii.s. i..

,,,... i.

.i.

....,i, i

1.96 o (Due to counting statistics only.)

i i'

.4.

l, e'

l Ie i

Ve. t ii 1 l af0.

e

m M

M M

M i

l l

1 l

l I

I I

I l

I I

Table II.C.5 Radionuclide Concerjtrations in Surfach Water.

(pCi/L) l l

'I l

Collection Date: February 9,1985.

I l

t i

Downstream Sites Upstream ' Sites Radio-St. Vrain S. Platte St. Vrain**

S. Platte Nuclide F,-20 i.

,,, i R-10 A-21 F-19 l

...,i.,:

Cs-134

< 3.46

< 3.21 2.96 (4.09)*

< 3.21 Cs-137

< 3.28

< 3.09

< 2.84

< 3.12 Zr-95

< 5.27

< 4.73

< 4.92

< 4.67 m

Nb-95

< 2.74

< 1.99

< 2.19

< 2.54 Co-58

< 2.47

< 2.21

< 2.00

< 2.25 Mn-54

< 2.18

< 2.07

< 1.89

< 1.91 1

Zn-65

< 4.67

< 4.50

< 4.15

< 4.53 Fe-59

< 5.62

< 5.09

< 4.46

< 5.03 Co-60

< 2.26'

< 2.10

< 1.99

< 2.09 Ba-140

< 6.99

< 6.03

< 4.66

< 5.36 La-140

< 8.04

< 6.94

< 5.36

< 6.16

.,i.,

,,ii..

., i n.i..

ii.,i

1.96 o (Due to counting statistics only.)

Collection Date 2/16/85,.

j l

l l

i 4.

M M

M l

t Table II.C.5 Radionuclide Conces trations in Surfac Water.

(pCi/L)

Collection Date: March 9. 1985 Downstream Sites Upstream Sites Radio-St. Vrain S. Platte St. Vrain S. Platte Nuclide F-20 R-10 A-21 F-19 Cs-134

< 3.88

< 4.86

< 2.79

< 3.55 Cs-137

< 3.74

< 4.57

< 2.67 7.79(5.90)

Zr-95

< 5.54

< 6.79

< 3.98

< 4.71 Nb-95

< 2.85

< 3.50

< 2.12

< 2.95 0

Co-58

< 2.48

< 3.06

< 1.83

< 2.23 Mn-54

< 2.42

< 3.01

< 1.82

< 2.13 Zn-65

< 4.89

< 6.44

< 3.96

< 4.70 Fe-59

< 5.52

< 6.84

< 4.15

< 4.90 Co-60

< 2.49

< 3.17

< 1.87

< 2.22 Ba-140

< 4.95

< 5.80

< 4.36

< 4.87 La-140

< 5.69

< 6.67

< 5.01

< 5.60 s1.96 o (Due to counting statistics only.)

t I

i4

m M

M M

m m

M M

i 3

{

l l

i l

Table II.C.5 Radionuclide Concentrations in Surface Water.

(pCi/L)

Collection Date: April 13, 1985 l

Downstream Sites Upstream Sites Radio-St. Vrain S. Platte St. Vrain S. Platte Nuclide F-20 R-10 A-21 F-19 Cs-134

< 4.78

< 4.85

< 3.58

< 5.21 Cs-137

< 4.80

< 4.65 4.31 (6.02)

< 5.06 Zr-95

< 6.44

< 6.63

< 4.77

< 7.31 m*

Nb-95

< 3.44

< 3.37

< 2.52

< 3.83 Co-58

< 3.16

< 2.87

< 2.11

< 3.36 Mn-54

< 3.11

< 3.44

< 2.18

< 3.28 Zn-65

< 6.50

< 6.29

< 4.61

< 6.64 Fe-59

< 6.91

< 6.75

< 4.93

< 7.39 Co-60

< 2.99

< 3.11

< 2.26

< 3.44 Ba-140

< 5.98

< 5.42

< 4.32

< 6.06 La-140

< 6.88

< 6.23

< 4.97

< 6.97

1.96 o (Due to counting statistics only.)

l

M M

i i

l l

l i

i i

i Table II.C.5 Radionuclide Conce trations in Surface !Jater.

(pCi/L)

Collection Date: May 11, 1985 l

t l

i I

i

~

Downstreamsites Upstream ' Sites Radio-St. Vrain S. Platte St. Vrain S. Platte Nuclide F-20 R-10 A-21 F-19 Cs-134

< 3.68

< 3.59

< 4.35

< 4.11 Cs-137

< 3.56

< 3.49

< 4.23

< 3.86 Zr-95

< 5.10

< 5.22

< 5.94

< 5.60 m

Nb-95

< 2.59

< 2.86

< 3.03

< 2.81 Co-58

< 2.32

< 2.46

< 2.83

< 2.63 Mn-54

< 2.33

< 2.28

< 2.70

< 2.53 Zn-65

< 4.81

< 4.79

< 5.46

< 5.50 Fe-59

< 5.22

< 5.66

< 6.23

< 5.74 Co-60

< 2.44

< 2.37

< 2.84

< 2.71 Ba-140

< 4.85

< 5.87

< 5.49

< 5.29 La-140

< 5.58

< 6.75

< 6.32

< 6.08 u,

e m

1 l

4 i

i

M M

M i

i i

i I

Table II.C.5 Radionuclide Concedtrations in Surface Water. '(pCi/L) i l

Collection Date: June 8. 1985 i

Downstream Sites Upstream Sites Radio-St. Vrain S. Platte St. Vrain S. Platte Nuclide F-20 R-10 A-21 F-19 Cs-134

< 5.28

< 4.78

< 3.89

< 4.55 Cs-137

< 5.14

< 4.40

< 4.05

< 4.12 Zr-95

< 7.08

< 6.33

< 5.74

< 5.78 Nb-95

< 3.72

< 3.24

< 2.94

< 3.27 E

Co-58

< 3.25

< 2.78

< 2.44

< 2.77 Mn-54

< 3.37

< 2.81

< 2.62

< 2.65 Zn-6S

< 7.02

< 6.08

< 5.42

< 5.98 Fe-59

< 6.85

< 6.04

< 5.77

< 5.84 Co-60

< 3.52

< 3.05

< 2.78

< 2.87 Ba-140

< 5.54

< 4.84

< 4.70

< 4.78 La-140

< 6.37

< 5.57

< 5.41

< 5.50

\\.

6 i.....

i, i: i..

oi,i i1-i 4 in e'

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1' ie e

i l

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i,i

M M

M W

I l

I i

I I

i Table II.C.5 Radionuclide Con'centrations in Surface Water.

(pCi/L)

Collection Date: July 13, 1985 j

l Downstream Sites Upstream Sites Radio-St. Vrain S. Platte St. Vrain S. Platte R-10 A-21 F-19 Nuclide.

.,,,,,., F-20,,.

.4, Cs-134

< 5.07

< 4.26

< 4,07

< 4.48 Cs-137

< 4.95

< 4.54

< 3.87 4.53 (7.69)

Zr-95

< 7.03

< 6.54

< 5.59

< 5.93 m

Nb-95

< 3.57

< 3.27

< 2.84

< 3.08

'~

Co-58

< 3.25

< 2.82

< 2.40

< 2.68 l

Mn-54

< 3.05

< 2.74

< 2.34

< 2.52 Zn-65

< G.69

< 6.05

< 5.09

< 5.75 Fe-59

< 6.96

< 6.02

< 5.41

< 6.04 Co-60

< 3.49

< 3.09

< 2.65

< 3.06 Ba-140

< 5.29

< 4.89

< 5.17

< 5.39

< 6.08

< 5.62

< 5.94

< 6.20 La-140 i

.i.

i,

,i4 4

i i,

i1 g 1.96 o (Due to counting statistics only.)

,i I

l l

i 4

i, 3

M M

M i

i j

r l

i i

I t

Table II.C.5 Radionuclide Concentrations in Surface Water.

(pCi/L)

I i

Collection Date: August 10, 1985 t

l l

l Downstream Sites Upstream ' Sites t

Radio-St. Vrain S. Platte St. Vrain S. Platte Nuclide F-20 R-10 A-21 F-19 4

Cs-134

< 4.33

< 3.83

<3[B2

< 4.40 Cs-137

< 4.31

< 3.64

< 3.83

< 4.16 Zr-95

< 6.31

< 5.81

< 5.30

< 6.27 m*

Hb-95

< 3.41

< 3.05

< 2.92

< 3.41 Co-58

< 2.64

< 2.35

< 2.50

< 2.62 Mn-54

< 3.07

< 3.20

< 2.38

< 3.55 i

Zn-65

< 5.47

< 5.70

< 5.37

< 6.11 Fe-59

< 5.98

< 5.25

< 5.58

< 5.73 Co-60

< 2.93

< 2.82

< 2.67

< 3.18

< 5.03'

< 4.80

< d.33

< 6.02 Ba-140

< 5.78

< 5.52

< 4.98

< 6.93 La-140 i.,,i, 2...

i 4

Y 9

2 i

<i.

l

i i

I j

\\

r i

i i

l i

Table II.C.5 Radionuclide Concentrations in Surface Water.

(pC1/L) l l

Collection Date: September 14, 1985.

a f

Downstreamdites Upstream Sites Radio-St. Vrain S. Platte St. Vrain S. Platte Nuclide F-20 R-10 A-21 F-19 Cs-134

< 3.41

< 3.52

< 3.76

< 3.35 Cs-137 4.58(6.01)

< 3.58

< 3.72

< 3.39 Zr-95

< 4.67

< 5.30

< 5.74

< 4.68 m*

Nb-95

< 2.40

< 2.61

< 3.04

< 2.58 Co-58

< 2.36

< 2.32

< 2.28

< 2.08 Mn-54

< 2.40

< 2.69

< 2.75

< 2.42 Zn-65

< 5.31

< 5.65

< 0.752

< 5.43 Fe-59

< 4.75

< 5.32

< 5.14

< 4.76 Co-60

< 2.65

< 2.85

< 2.98

< 2.70 Ba-140

< 3.71

< 4.25

< 4.03

< 4.16

< 4.27

< 4.89

< 4.63

< 4.79 La-140

1.96 o (Due to counting statistics only.)

j i

i i

E i

I l

l l

l i

l Table II.C.5 l

l l

Radionuclide Concentrations in Surface Water.

(pCi/L)

Collection Date: Oc'tober 12, 1985 I

i I

Downstreamsites Upstream Sites Radio-St. Vrain S. Platte St. Vrain S. Platte Nuclide F-20 R-10 A-21 F-19 Cs-134

< 3.65

< 3.38

< 3.70

< 3.98 Cs-137

< 3.50 5.29 (6.05)*

< 3.57

< 3.73 Zr-95

< 5.44

< 4.75

< 5.38

< 5.47 Nb-95 5.12 (4.06)

< 2.48

< 2.93 3.61(4.24)

Co-58

< 2.44

< 2.77

< 2.76

< 2.39

.F Mn-54

< 2.57

< 2.40

< 2.58

< 2.65 Zn-65

< 5.41

< 5.46

< 5.59

< 5.61 Fe-59

< 4.81

< 4.94

< 5.01

< 5.30 Co-60

< 2.79

< 2.62

< 2.87

< 3.10 Ba-140

< 3.97

< 3.75

< 4.04

< 4.78 La-140

< 4.56

< 4.32

< 4.65

< 4.77 a,

i,

.i i

1 l

!*ei

1.96 o (Due to counting statistics only.)

, i.

l

, m

m M

M M

m W

i i

i 4

i s

!TableII.C.5 Radionuclide Co'nceritrations in Surface Water.

(pCi/L) i Collection Date: November 2.1985 i

i Downstream $1tes Upstream Sites Radio-St. Vrain S. Platte St. Vrain S. Platte R-10 A-21 F-19 l

, Nuclide F-20,,.

,i,;

i Cs-134

< 3.91

< 4.31

< 4.49

< 3.55 1

Cs-137

< 3.90

< 4.01

< 4.30

< 3.68 l

Zr-95

< 5.56

< 5.85 10.8 (14.3)

< 4.99 m

~

Nb-95

< 2.98

< 3.16

< 3.30

< 2.79 Co-58

< 2.43

< 2.51

< 2.65

< 2.23.

l Mn-54

< 2.76

< 3.02

< 3.08

< 2.58 i

Zn-65

< 6.35

< 6.14

< 6.41

< 5.80 Fe-59

< 5.69

< 5.68

< 5.98

< 5.10 i

Co-60

< 3.15

< 3.27

< 3.32

< 2.95 l

l' Ba-140

< 4.53

< 4.52

< 4.91

< 4.98 La-140

< 5.21

< 5.20

< 5.65

< 5.73 i

......i

..i i,

1.96 o (Due to counting statistics only.)

t l.

6.

ti.

i l

i

-,.ii.

,i i.

W W

i i

i Table II.C.5 l

l Radionuclide Concer}trations in Surface Water.

(pCi/L) i 1

Collection Date: De'cember 14, 1985,

l l

Downstreamdites Upstream!ites S

Radio-St. Vrain S. Platte St. Vrain S. Platte Nuclide F-20 R-10 A-21 F-19 4

Cs-134

< 3.41

< 3.90

< 4.16

< 3.77 i

Cs-137

< 3.35

< 3.64

< 3.90

< 3.87 Zr-95

< 4.99

< 5.49

< 5.67

< 5.23 cn l

Nb-95

< 2.51

< 2.89

< 3.06

< 3.05 Co-58

< 2.21

< 2.28

< 2.52

< 2.37.

Mn-54

< 2.43

< 2.62

< 2.89

< 2.76 Zn-65

< 5.15

< 5.81

< 6.13

< 6.53 Fe-59

< 5.06

< 5.43

< 5.51

< 5.27 Co-60

< 2.62

< 2.88

< 3.13

< 2.89 Ba-140

< 4.21

< 5.46

< 5.19

< 5.15 La-140

< 4.84

< 6.28

< 5.97

< 5.92 i

i.

i e i e.. e i i

ei I4 f

i 1

1

/e 6-i e

M M

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

Radio-nuclide January February March April May June Cs-134

< 1.14

< 2.82

< 5.02

< 2.56

< 2.32

< 4.11 Cs-137 2.84 (1.95)*

3.25(4.98)

< 4.78 3.24 (4.24) 3.50 (4.05)

< 4.09 Zr-95

< 1.88

< 4.23

< 6.56

< 3.68

< 3.61

< 7.29 Nb-95

< 1.00 2.44 (2.82)

< 3.46

< 1.92

< 1.87

< 2.82 Co-58

< 1.58

< 1.92

< 3.05

< 1.66

< 1.67

< 2.31 4

Mn-54

< 0.729

< 1.82

< 2.91

< 1.55

< 1.47

< 2.54 Zn-65

< 1.59

< 3.98

< 6.37

< 3.22

< 3.05

< 5.22 g

Fe-59

< 2.15

< 4.68

< 6.87

< 3.94

< 3.20

< 8.04 Co-60

< 0.740

< 1.89

< 3.22

< 1.60

< 1.52

< 2.75 Ba-140

< 4.31.

< 5.81

< 5.64

< 5.07

< 5.56

< 3.17 La-140

< 4.96

< 6.68

< 6.49

< 5.83

< 6.39

< 4.78 11-3 2,880 (631) 7,560(704) 807 (288)

< 231 465(277)

< 237

1.95 o (Due to countin9 statistics.)

j i

l

m m

M M

M i

i l

1 l

Ta b'l e I I. C. 6 Radionuclide Concentra ions in Monthly Composites of Surface Water, A-5 (nci/L) (continued) i

_a Radio-nuclide July August September October November December Cs-134

< 2.41

< 3.81

< 2.41

< 3.83

< 1.72

< 2.17 Cs-137

< 2.32

< 3.64

< 2.49

< 3.59

< 1.66

< 2.19 Zr-95

< 4.02

< 6.19

< 3.43

< 6.34

< 3.04

< 3.05 Nb-95

< 2.13

< 2.90

< 1.82

< 2.91

< 1.60

< 1.60 Co-58

< 1.46

< 2.52

< 1 73

< 2.25

< 1.03

< 1.48 Mn-54

< 1.70

< 2.73

< 1.74

< 2.76

< 1.26

< 1.62 Zn-65

< 3.02

< 0.567

< 3.92

< 5.50

< 2.57

< 3.36 g

Fe-59

< 4.06

< 5.04

< 3.42

< 6.35

< 2.34

< 3.67 Co-60

< 1.55

< 2.86

< 1.94

< 2.90

< 1.34

< 1.70 Ba-140

< 2.59

< 4.09

< 2.78

< 4.04

< 1.90

< 2.95 La-140

< 2.98

< 4.70

< 3.19

< 4.65

< 2.18

< 3.39 1,270 (294)

2,950(319) 1,300 (291) 1,800 (300) 7,020 (351) 6,390 (349) 11 - 3

1.96 o (Due to counting statistics.)

,f 1

9

M M

M l

i.

I l

l l

I i

i j

l Table II.C.7 Radionuclide Concentrat ons in Ground Water. (pCi/L) f i

I 1st Quarter 3/9/85 2nd Quarter 6'/8/85 3rd Quarter! 9/14/85 4th Quarter 12-14-85 Radio-nuclide F-16 R-5 F-16 R-5 F-16 R-5 F-16 R-5 Cs-134

< 3.40

< 3.96

< 4.49

< 4.28

< 3.42

< 3.74

< 3.93

< 3.49 Cs-137

< 3.20 5.71(7.03)

< 4.55

< 3.91

< 3.56

< 3.66

< 3.70

< 3.41 Zr-95

< 4.62

< 5.62

< 6.27

< 5.55

< 5.20

< 5.67

< 5.50

< 4.82 Hb-95

< 2.70

< 2.69

< 3.27

< 2.97

< 2.73

< 2.93

< 3.02

< 2.64 Co-58

< 2.25

.< 2.50

< 2.83

< 2.57

< 2.30

< 2.45

< 2.35

< 2.26 Mn-54

< ?.17

< 2.53

< 2.99

< 2.56

< 2.59

< 2.80

< 2.72

< 2.41 g

Zn-65

< 5.11

< 5.69

< 5.85

< 4.96

< 6.08

< 0.571

< 5.83

< 5.58 Fe-59

< 4.82

< 5.90

< 6.34 5 5.59

< 4.96

< 5.27

< 5.51

< 4.80

< 2.19

< 2.71 3.44 (7.20)

< 2.62

< 2.85

< 2.97

< 2.96

< 2.67 C0-60

< 5.59 Ba-140

< 4.20

< 56.8

< 4.46

< 4.06

< 4.32

< 5.24

< 4.50 La-140

< 4.83

< 6.43

< 65.3

< 5.13

< 4.67

< 4.97

< 6.02

< 5.17 H-3

< 232

< 241 270 (280)

< 232

< 237

< 244

< 232

1.96 o (Due to counting statistics'.)'

i l.

l l

I

--+swhe*

w.

6&

am eeem ee m.

A.

M.e..

a avsm a*ers*

e sw e.Wh-,

awe.w we.e-+ee-wee =.e l

66 1

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

(10CFR20, Appendix B Table II) 2 1-131 3 x 10 pCi/L 3

Cs-134 9 x 10 pCi/L 4

Cs-137 2 x 10 pCi/L 4

I Zr-95 6 x 10 pC1/L 5

Nb-95 1 x 10 pCi/L 5

Co-58 1 x 10 pCi/L 5

Mn-54 1 x 10 pCi/L 5

2n-65 1 x 10 pCi/L 4

Fe-59 6 x 10 pCi/L I'

4 Co-60 5 x 10 pCi/L 4

Ba-140 3 x 10 pCi/L 4

La-140 2 x 10 pCi/L I

I I

I

,I

l 67 I

II.D.

Milk The dairy food chain is the critical pathway for possible radiation dose commitment around any nuclear facility. The critical individual would be an infant consuming milk produced from cows grazing local pastures.

Milk is the critical pathway for possible dose comitment to humans from environmental contamination of H-3, I-131, Cs-137 and Sr-90. For this reason milk is sampled extensively to document the presence or absence of radioactivity due to reactor operations.

There are no dairies (or personal milk cows) in the Facility area,1.6 km radius.

The six dairies in the Adjacent area, 1.6-8 km radius, were selected to be in the highest x/Q areas (Refer to updated FSAR).

The description of these locations can be found in Table III.B.1 and Figure III.B.2. The single Reference location dairy, R-8, is 22.5 km west of the reactor in the least predominant wind direction.

Herd management practices are virtually identical at all dairy locations.

Table II.D.I lists the concentrations of all radionuclides that are investigated in milk samples.

It is necessary to discuss the positive I-131 concentrations observed on 4/27, 5/18, 8/10, 8/26, 9/14 and 9/28/85 at Dairy A-22.

The milk sample collected on 4/27 was recounted, verified to contain I-131 by the presence of the secondary gamma-ray line at 0.637 MeV, and sent to an outside laboratory for confinnation. A lengthy investigation traced the source of the I-131 to release from nuclear medicine departments in hospitals upstream of Fort St. Vrain. Dairy A-22 is directly between and close to dairies A-23 and A-18.

In fact, all are owned and operated by members of the same family. The I-131 was noted only at A-22.

It was discovered I

I

I 68 l

l that the operation at A-22 uses surface water from a ditch (Independence) for part of the herd drinking water while dairies A-23 and A-18 use only well water.

The irrigation ditch receives water from the South Platte river near Platteville and considerably upstream of the reactor.

Discussions with Colorado Department of Health licensing officials revealed that nuclear medicine departments often use I-131 for diagnostic and therapeutic purposes in humans. There is no restriction or hold-up of the patient excreta.

It was verified that the ditch water was the source of I-131 by directly sampling the di tch. Review of surface water I-131 concentrations (which are not reported as part of this monitoring program) revealed several positive I-131 concentrations in surface water on both water courscs both upstream and downstream of the reactor.

During November, a bolus of I-131 (200 mci), given to a patient in a Boulder hospital, was traced down the St. Vrain creek and concentrations as,high as 70 pCi/L were observed.

These medical releases are, of course, more noticeable during times of low water flow, but need. to be monitored more I

carefully in the future, as the measur 2d I-131 must be included in the radiation " background" of the site.

Further inspection of-Table II.D.1 shows occc sional other positive values. Only the Cs-137 values are considereJ to be real.

These 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, however, 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 I

I

69 I

homeostatically controlled and independent of K intake.

K-nat is measured in all milk samples as a quality control measure for the other radionuclides determined in the same sample by gama-ray spectrometry, but K-nat concentrations are no longer reported in Tabie II.D.1.

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 j

expected only if the cows were on pasture or fed green cut forage.

This 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.

Elevated tritium concentrations in milk that were due to reactor l

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 j

tritium concentrations of the forage water intake or drinking water intake to the cow. This is due to the short biological half-life for water in the cow (about three days for the lactating cow). As~ noted in previous reports, the reported tritium concentration in milk is the tritium in water extracted from the milk.

Contamination of milk I

I 70 samples due to reactor effluents has never been observed during the pre and post-operational periods of Fort St. Vrain.

Dairies A-18 and A-26 refused to supply milk samples during October through December of 1985.

This was because they were trying to optimize production records and could notrelinquishthe sample.

Dairy A-18 has agreed to allow sampling to renew in 1986 and dairy A-26 has been replaced in 1986.

I I

I

/

(

l

~

I I

~

M M

i t

Table 11.D.1 Radionuclide Concentrations in Milk. (pC1/L) i Collection Date 1/12/85 1/26/85 1/26/85 1/ 12/85 1/5/85 1/19/85 1/19/85 A-6 A-18 A-22 A-23 A-24 A-26 R-8 Radio-nuclide 1-131

< 0.293

< 0.510

< 0.383

< 0.347

< 0.337

< 0.308

< 0.447 Cs-134

< 3.13

< 2.97

< 3.56

< 5.60

< 4.60

< 7.90

< 1.18 Cs-137.

< 2.88 3.50 (5.12)*

< 3.46

< 5.30 5.86(8.17)

< 6.35

< 1.13 Ba-140

< 4.85

< 4.37

< 4.71

< 6.91

< 6.50

< 50.0

< 1.6/

La-140

< 5.58

< 5.02

< 5.42

< 7.95

< 7.47

< 57.5

< 1.92 11-3

< 248

< 246

< 231

< 248 246

< 246

< 246 Collection Date 2/9/85 2/23/85 2/23/85 2/23/85 2/2/85 2/16/R5 2/2VB5 I-131

< 0.232

< 0.260

< 0.247

< 0.284

< 0.323

< 0.291

< 0.268 Cs-134

< 3.32

< 4.79

< 3.89

< 3.80

< 4.42

< 4.40

< 4.47 Cs-137

< 3.34

< 4.34 4.06 (6.57)

< 3.45

< 4.21

< 4.13

< 4.00 Ba-140

< 5.29

< 5.32

< 4.57

< 4.40

< 5.97

< 5.67

< 5.13 La-140

< 6.08

< 6.12

< 5.25

< 5,62

< 6.87

< 6.53

< 5.90

(

11-3 272 (279)

< 235

< 244

_< 24n

< 247 e 215 Collection Date 3/16/85 3/23/85 3/23/85 3/9/85 3/2/85 3/16/85 3/9/85 I-131

< 0.326

< 0.172

< 0.219

< 0.205

< 0.426

< 0.299

< 0.270 Cs-134

< 4.14

< 3.02

< 4.94

< 3.56

< 4.27~

< 5.03

< 3'.43 Cs-137

< 3.94

< 2.84

< 4.67 -

< ' 3. 51 -

< 4.13

< 4.73

< 3.20 B a-140

< 4.57

< 4.25

< 6.09

< 4.74

< 4.86

< 4.70

< 4.06 La-140

< 5.25

< 4.89 i

< 7.00

< 5.45

< 5.59

< 5.40

< 4.67 I

f

< 241

< 232

< 246 11 - 3

< 232

< 231

< 232

< 246 1.96 o (Due to counting statistics only.)

0 131

Analyzed by outside lab, except for 7,

I r

l

M M

M m

W f

i i

Table II.D.1 Radionuclide Concentrations :in Milk. (pC1/L)

(continued) bollection Date 4-20-85 4-27-85 4-27-85 4-13-85 4-27-85 4-20-85 4-13-85 Radio-A-6 A-18 A -22 A-23 A-24 A-26 R-8 nuclide l-131

< 0.206

< 0.160 2.13(0.61U)4

< 0.321

< 0.315

< 0.261

< 0.262

^

Cs-134

< 4.68

< 4.17

< 5.35

< 4.44

< 5.05

< 3.72

< 4.21 Cs-137

< 4.21

< 4.12 5.16 (9.15)

< 4.41

< 4.67

< 3.42 5.53 (7.16) lla-140

< 5.01

< 5.14 s 5.63

< 5.71

< 5.19

< 5.69

< 5.22 1.0-140

< 5.76

< 5.91

< 6.47

< 6.57

< 5.97

< 6.5'4

< 6.00 11-3

< 231

< 233

< 231

< 238 I

Collection Date g_4-85 6-4-85 5-4-85 5-11:85 5-11-85 5-4-85 5-11-85 l-131

< 0.248

< 0.298 0.489 (0.559)

< 0.292

< 0.325

< 0.469

< 0.250 C s-1-34

< 4.76

< 3.59

< 4.79 4.04

'< 4.67

< 2.47

< 4.77 Cs-137

< 4.98 4.02 (5.88)

< 4.Ei

< 4.04 5.58 (7.92)

< 2.27

< 4.32 j

Ila-140

< 6.01

< 5.10

<.5.00

< 5.28

< 5.16

< 3.84

< 5.10 1.a-140

<691i

< 5.87

< 5.75

< 6.07

< 5.94

< 4.42

< 5.86 11-3 267 (279)

< 232

< 233

< 233 359 (280)

< 233 t.uilection Date

, 5-18-85 5-18-85 5-18-85 5-24-85 5-25-85 5-18-85 5-24-85

\\

'l-131

< 0.231

< 0.454 1.32 (1.09)

- < 0.446

< 0.423

< 0.291

< 0.386 ts-134

< 4.65

< 3.99

< 4.24 4.54

< 2.67 4.54 (5.97)

< 4.91 ts-137

,6.92 (7.84) 3.65.(6.63)

<,4.05 t.<J4.65 2.84 (4 57)

< 4.48

< 4.73 Ila-140

< 5.39

< 4.73

< 4.44

< 4.75

< 3.18

< 5.18

< 6.37 1.a -140

< 6.20

< 5.44

< 5.11

< 5.46

< 3.66

< 5.96

< 7.32 ll-3

< 224

< 237

< 237 241 (285)

< 224

< 237 1.96 o(Due to counting statistics only.)

^

i l

M i

i j

I L :

l 9

3

)

3 3 5 2 2 5

0 4 3 0 4 9 5

7 2

8 3 5 8 9 6 2 8

8 4 7 2 6 3 M

3 0 4 4 4 5 2 2

0 4 4 4 5

(

8 R

2

< < < < < 9 6

6 6

3 M

0 5

9 5 6 5 1 9

)

8 0 4 0 1

3 5

0 4 2 5 8 5 9

6 3 3 9 2 9 8 5

8 4

2 0 5 4 5 5 2 1

0 4 4 4 5 2 1

(

A 6

6 78 3

4 lI i

)

M deu 6

5 3

n 5

3 9 0 8 3 8

3 1 7 7 4 4

0 2 9 1

9 8

t 4

3 2 7 9 7 9 i

3 4

4 n

6 2

0 5 4 4 5 2 2

0 4 4 3 4 2 o

1 c

A 6

6

(

Mll' i

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l L

/

1 Cp 6

5 7

(

3 8 8 6 0 6 8

7 3 1 3 3 5

2 1

2 3

2 6 3 3 4 7 5 2 1

8 3

3 2

k A

0 5 5 5 6 2 2

0 4 4 4 5 2

'i 8

i 6

M 6

n Ml 1

!!I I

i sno 5

0 i

1 5 6 9 5 5

8 0 0 9 1 t

5 5 6 2 3 0 1

2 2

8 2

3 4 3 3 a

8 2

3 r

2 0 4 4 4 5 2 2

0 6 5 5 6 2 t

8 2

n A

e 6

6 cno

!i C

4 e

d i

l 0

)

5 1

)

5 c

4 2 5 5 8 0 8

3 8 4 2 3 8

8 4 5 4 8 5 2 5

8 9

y 3 4 1 9 9 u

4 l

n 1

o 0 4 4 4 5

(

1 0 3 3 2 3 2 n

i 1

A o

i 6

< < < < < 2 6

i d

3 s

M a

4 c

R i

ts i

1 ta D.

5 t

9 8

8 s

I 2 9 3 4 1 8 0 6 7 8

6 2

9

2., 30 4 5 0 9 I

5 1

1 5

1 9

g 3

1 4

n e

l 1

A 0 5 4 5 6 2 0 5 5 6 6 2 i

6 t

b n

a 6

u T

oc o

t e

e t

t e

a a

u D

D D

(

n n

o o

M i

i 0

t e

t 6

c d

4 7 0 0 c

4 7 0 0 9

e oi 1 3 3 4 4 e

1 3 3 4 4 l

il 3

1 1

l 3 1 1

1 1

1 l

dc 1

3 l

1

- 3 M

o au

- s s a a.

l C

C C D l

l o

- s s a a.

I C C l

1 t

i C

Rn 1

1 (I

t'

M M

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

(continued)

Collection Date -

7-6-85 7-6-85 7-13-85 7-13-85 7-13-85 7-6-85 7-13-85 A-6 A-18 A-22 A-23 A-24 A-26 R-8

{e I-131

< 0.371

< 0.296

< 0.439

< 0.422

< 0.279

< 0.216

< 0.349 Cs-134

< 4.03

< 3.82

< 4.71

< 4.22

< 4.14

< 4.26

< 3.91 Cs-137

< 4.15

< 3.76

< 4.37

< 4.03

< 4.04

< 4.34

< 4.11 Ba-140

< 4.17

< 4.00

< 4.39

< 4.19

< 4.90

< 4.33

< 4.20 La-140

< 4.80

< 4.60

< 5.05

< 4.82

< 5.64

< 4.98

< 4.83 11 - 3

< 232

< 236

< 232

< 236 Collection Date 7-20-85 7-20-85 7-27-85 7-27-85 7-27-85 7-20-85 7-27-85 I-131

< 0.155

< 0.294

< 0.408

< 0.441

< 0.290

< 0.248

< 0.291 Cs-134

< 3.88

< 3.50

< 4.65

< 5.17

< 4.23

< 4.03 Cs-137

< 3.83

< 3.78

< 3.52

< 4.42

< 5.26

< 4.30 5.26 (7.61)

Ba-140

< 4.05

< 4.37

< 3.63

< 5.17

< 5.40

< 4.56

< 4.32 La-140

< 4.66

< 5.03

< 4.47

< 5.95

< 6.31

< 5.25

< 4.97 11 - 3

< 237

< 235

< 237

< 239 Collection Date 8-3-85 8-3-85 8-10-85 8-10-85 8-10-85 8-3-85 8-3-85 I-131

< 0.309

< 0.375 0.992 (1.01)

< 0.275

< 0.405

< 0.418

< 0.356 Cs-134

< 3.71

< 4.08

< 3.57

< 3.45

< 3.42

< 3.31

< 4.04 Cs-137

< 3.70

< 4.21,

< 3.57i

, < 3.31

< 3.50

< 3.32

< 3.98 Ba-140

< 4.17

< 4.52

< 3.80

< 3.79

< 3.41

< 3.37

< 4.13 La-140

< 4.79

< 5.20

< 4.37

< 4.36

< 3.92

< 3.88

< 4.96 11 - 3

< 239

< 235

< 239

< 239 I

O 1.96 a(Due to counting statistics only.)

f

m m

i i

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

Collection Date 8-17-85 8-17-85 8-26-85 8-24-85 8-24-85 8-17-85 8-17-85 A-6 A-18 A-22 A-23 A-24 A-26 R-8 u

e I-131

< 0.280

< 0.279 1.42 (0.868)

< 0.361

< 0.310

< 0.425

< 0.332 Cs-134

< 4.50

< 4.38

< 5.00

< 3.95

< 4.32

< 3.65

< 4.34 Cs-137

< 4.37

< 4.01

< 4.77

< 4.00

< 4.43

< 3.78

< 3.97 Ba-140

< 4.93

< 5.97

< 5.72

< 4.33

< 5.06

< 4.28

<5.42 La-140

< 5.68

< 6.86

< 6.'57

< 4.98

< 5.82

< 4.93

< 6.24 H-3

< 234

< 239

< 238

< 234

< 234 Collection Date 9/7/85 9-7-85 9-14-85 9-14-85 9-14-85 9-7-85 9-7-85 I-131

< 0.356

< 0.370 0.701 (1.04)

< 0.269

< 0.275

< 0.206

< 0.295 Cs-134

< 2.43

< 3.23

< 4.02

< 3.95

< 4.18

< 3.55

< 4.47 Cs-137 4.88 (4.49)

< 3.33 4.45 (7.32)

< 3.92

< 3.97

< 3.57

< 4.39 Ba-140

< 2.65

< 3.67

< 4.43

< 4.15

< 4.50

< 3.82

< 4.87 La-140

< 3.04

< 4.23

< 5.10

< 4.77

< 5.18

< 4.39

< 5.61 H-3

< 238

< 244

< 238

< 238 Collection Date 9-21-85 9-21-85 9-28-B5 9-28-85 10-1-85 9-21-85 9-21-85 I-131 0.440

< 0.396 0.674 (0.648 i

< 0.406

< 0.365

< 0.398

< 0.487 Cs-134

< 3.50

< 3.72

< 4.04

< 4.67

< 4.01

< 4.16

< 4.06 Cs-137 4.34 (6.31)

< 3.56

< 3.78

< 4.44

< 4.03 5.21 (7.33)

< 3.74 Ba-140

< 3.88

< 4.14

< 4.05

< 4.60

< 4.65

< 4.38

< 4.12 La-140

< 4.46

< 4.76

< 4.66

< 5.29

< 5.34

< 5.04

< 4.74 324 (282)

< 232

< 250

< 237

< 234 Il-3

< 237 258 (285)

, 1.96 o(Due to counting statistics only.)

{

y i

i i

l

M I

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

Collection Date 10-12-85 10-19-85 10-19-85 10-19-85 10-12-85 10-5-85 10-5-85 a

A-6 A-18 A-22 A-23 A-24 A-26 R-8 u

e 1-131

< 0.229

< 0.369

< 0.476

< 0.445

< 0.360

< 0.241 Cs-134

< 3.98

< 3.52

< 4.01

< 4.03

< 4.78

< 4.05 Cs-137 5.24 (7.42)

< 3.56

< 3.73

< 4.35

< 4.46

< 3.77 Ba-140

< 4.42

< 3.74

< 4.17

< 6.69

< 5.04

< 5.09 La-140

< 5.08

< 4.30

< 4.80

< 5.81

< 5.80

< 5.85 H-3

< 232

< 242

< 250

< 250 250 (281)

Collection Date 11-9-85 11-2-85 11-2-85 11-2-85 11-9-85 11-9-85 11-2-85 I-131

< 0.387

< 0.397

< 0.470

< 0.390

< 0.421

< 4.47

< 3.59

< 3.83

< 3.47 Cs-134

< 4.26 Cs-137

< 4.05

< 4.02

< 3.56

< 3.63 3.61 (6.51)

Ba-140

< 4.51

< 5.60

< 3.85

< 3.98

< 3.92 La-140

< 5.19

< 6.45

< 4.43

< 4.58

< 4.51 11 - 3

< 230

< 233

< 230

< 233 Collection Date 12-7-85 12-7-85 12-7-85 12-14'85 12-14-85 12-14-85 12-7-85 1-131

< 0.390

< 0.432

< 0.415

< 0.400

< 0.469 Cs-134

< 3.46

< 4.13

< 2.94

< 3.31

< 4.56 Cs-137 4.56 (6.14)

< 3.84

< 2.96,

< 3.14

< 4.38 Ba-140

< 3.61

< 4.21

< 3.72

< 4.50

< 4.76 La-140

< 4.15

< 4.84

< 4.28

< 5.18

< 5.48 H-3 360 (277)

< 232

< 232 i

o l

1.96 o(Due to counting statistics only.)

y*

Sample unavailable, refer to Milk write-up. '

i

77 II.E.

Food products.

I One sample of each principal class of food products was collected from areas in which there was some likelihood of 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. At two of the sites selected in 1984 (A-28, R-12),

produce was not available in 1985.

However, 6 additional sites A-8, A-30, A-31, R-12, R-13, and R-14 were sampled in 1985. Since garden locations and available produce often change due to owner needs, harvest time, harvest size, etc., it is difficult to keep the same locations each year.

Each sample is homogenized without drying imediately after collection. The sample is then counted by gamma-ray spectroscopy.

Table II.E.1 lists the results for the 1985 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.

I l

.I

I 78 Table II.E.1 Radionuclide Concentrations in Food Products (pCi/kg)

I Collection Date 9/16/85 I-131 Cs -134 Cs-137 Location Food Type A-8 Carrots

< 14.7

< 20.5

< 23.1 A-9 Tomatoes

< 12.1

< 16.6

< 16.0 Corn

< 15.9

< 23.4

< 24.1

- A-27 Potatoes

< 10.2

< 14.2

< 14.3 A-28 H

< 8.76

< 12.3

< 12.0 A-29 Cantalope A-30 Cucumbers

< 14.5

< 21.4

< 18.7 A-31 Watermelon

< 10.3

< 13.2

< 13.2 R-12 H

R-13 Onions

< 16.0

< 24.1

< 20.8 R-14 Potatoes

< 13.0

< 18.4

< 17.7 R-15 Potatoes

< 9.19

< 14.1

< 13.4 7

_ _ _ - - - ~ _ - -

H. Sample not collected because there was no produce available at sampling site.

I I

I

79 I

II.F.

Aquatic Pathways Table II.F.1 shows radionuclide concentrations measured in fish samples collected at F-19, A-25 and.R-10 on two dates in 1985.

The fish were collected by electro-shocking and the composite sample was homogenized without cleaning and arialyzed on a wet weight basis.

The only significant radionuclide concentrations measured were Fe-59 in the sample collected at A-25, the farm pond, on June 27, 1985, and I-131 measured in the sample collected at all three sites on October 19, 1985. The Semi-Annual Radioactive Effluent Release Report lists only one release of Fe-59 on January 14, 1985. The total release was I

only 6.07 uCi.

No release of I-131 was reported at any time during the year by any route.

I Extrapolating the measured concentration by the physical half-life of Fe-59 to the release date would procace a maximum fish concentration of Fe-59 of 364 pCi/kg.

Using Regulatory Guide 1.109 i

models, the maximum dose commitment would be to the GI tract of an adult consuming the standard man intake of fish caught immediately r,

after this period. The resulting annual dose ccmmitment would be:

364 pCi X 3.4 X 10-5 mrem X 21kg

= 0.26 mrem kg liCT year year Such a total dose commitment is negligible, but unlikely as well for the following reasons:

1.

No sport fishing is allowed or has ever been observed in the farm pond.

2.

The only fish observed are carp which are usually' not consumed.

80 I

3.

A yearly intake of 21 kg of fish is unlikely for reasons 1 and 2 above.

4.

While consideration of biological half-life in the fish would elevate the fish concentration calculated for January 27, 1985, it is unlikely that fish muscle would be as high as the total fish contents which includes skin, GI tract and liver.

Fe-59 was, also, detected in 1985 in the sediment of Goosequill ditch leading to the pond.

I-131 was measured in fish samples from all three sites for the collection made on October 19, 1985. The source of this I-131 was due to releascs from nuclear medicine uses upstream of Fort St. Vrain (See discussion in II.D. Milk). The I-131 was observed at upstream as well as downstream sampling sites.

The mean of the three fish samples averaged 24 pCi/kg of I-131. There is no reporting requirement for I-131 in surface water or fish samples, but when positive values are observed from gamma-ray spectra analysis, these are always noted.

Table II.F.2 shows results for analysis of the cesium radioisotopes in surface sediment, collected at R-10, a downstream location.

The table shows significant measurable Cs-137 concentrations.

While there was some release of Cs-137 from the reactor during the year, it was negligible compared to the Cs-137 still in the biosphere resulting from nuclear weapons testing.

The fallout Cs-137 is still retained in surface soil and sediment due to the extremely high ion exchange capacity of the clay mineral soils of this region. Cs-137 is still frequently observed in air particulates I

81 from surface soil resuspension and even in milk samples due to its high transfer coefficient.

The total reactor release of Cs-137 for the year was 174 u Ci.

If the average of the two measured Cs-137 concentrations shown in Table II.F.2 are taken as representative for the region, and assuming a mixing depth of 20cm, then the entire reactor effluent would need be mixed over a surface area of only 1.05 acres to produce the same concentration. This is obviously small compared to the surface soil inventory of fallout 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 I

with the fish collection dates.

Corbicula have been introduced to i

North America from Asia. The freshwater clams are now found in large river systems in the U.S. from coast to coast. The Colorado Division of Wildlife. has stated that Corbicula have been found in Northern Colorado at Boyd Lake, some 30 miles from the Fort St. Vrain Nuclear Generating Station.

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

I I

I

m m

M M

M l

J t

t I

l I

I Table II.F.1 Radionuclide concentrations in Fish. (pC1/kg)

Collection Date First Half June 27, 1985 Second Half October 19, 1985 Radionuclide Upstream Effluent Downstream Upstream Effluent Downstream F-19 A-25 R-10 F-19 A 25' R dQ Cs-134

< 5.37

< 4.36

< 6.58

< 6.68

< 6.8'O

< 3.08 Cs-137

< 5.68

< 4.26

< 6.41

< 5.96

< 6.98

< 2 79 g

Co-58 3.70 (5.74)*

< 3.26

< 4.00

< 5.13

< 4.40

< 1.77 Mn-54

< 3.50

< 3.08

< 4.71

< 5._25

< 4.89

< 2.58 Zn-65

< 8.34'

< 5.80

< 9.20 15.5 (19.1)

< 11.6

< 4 67 Fe-59

< 8.51 30.6 (20.5)

< 10.3

< 8.97

< 10.2

< 4 94 Co-60

< 4.43

< 3.14

< 4.61

< 5.32

< 6.54

< ?_10 4 1.96o (Due to counting statistics.)

..:.,i..,

,,,i,i.

i.i i, 4 t

9

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

I Radionuclide Collection Date 6/15/85

< 68.8 Cs-134 Cs'-l'37 '

222 (115)

Collection ~Date 9/14/85 Cs-134

< 55.1 i

I Cs-137 125 (86.0) g

~

I I

I l

l 84 II.G Sample Crosscheck Program.

To assure the accuracy and precision of the environmental data obtained from the radiation surveillance program provided fcr the Fort St. Vrain reactor, Colorado State University participates in a number of interlaboratory and intralaboratory quality assurance programs.

The U.S. Environmental Protection Agency (EPA) sponsored laboratory intercomparison studies program is the principal crosscheck.

Thi',

involves the analysis of a variety of environmental media containing various levels of radionuclides.

The media, type of analysis and frequency of analysis are summarized below for the E.P.A. program.

Medium Analysis (radionuclide)

Frequency Water H-3 bimonthly Water gross beta, gross alpha bimonthly Water Co-60, 2n-65, Cs-134 triannually I

Cs-137 Water I-131 triannually Air particulate Cs-137, gross beta, triannually filters gross alpha Milk I-131, Cs-137 triannually I

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 calculated.

Table II.G.1 gives the EPA crosscheck data for all of 1985.

The EPA uses the term, Estimated Laboratory Precision (ELP), calculated as 3 c/in as the control parameter, where n = the number of analyses.

I

85 I

i Whenever our mean value falls outside this limit, the sample calculations are rechecked and the sample reanalyzed' if possible.

During 1985 all results except three were within the ELP.

These samples have the notation (1) in Table II.G.1.

The corrected values j

are shown in'the Table.

The recheck process and conclusion is given below for these samples.

(1) The sample counting results were recalculated using corrected spectral regions of interest and corrected counting yields.

The contribution of Bi-214 to the region of interest of Zn-65 had been previously ignored.

The Co-60 region of interest had previously been too narrow.

Samples with the notation (2)-(5) had the following reporting errors. The results in all cases, however, were within the ELP.

(2) The EPA reporting deadline was missed due to administrative error.

(3) The gas-flow counting system was under repair until after the EPA reporting deadline.

(4) The reporting deadline was missed due to clerical error.

(5) The wrong value was reported.

A clerical error resulted in a transposition of the digits in the result.

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.

I I

86 i

Table II.G.3 lists the results of gross beta analyses of the split water samples. The gross beta results show more variance than the tritiun results between laboratories even though identical methods are used. Differences could be due to counter calibration methods and this possibility will be investigated in 1986 by intralaboratory counts on a standard source.

1 I

I I

I

E 87 Table II.G.1 EPA'bross-CheckDataSummary

% deviation Radio CSU EPA 1 S.D., n=1 E.L.P = 3e / /ii from known Date nuclide Value Value

Water, pCi/L 2-15-86 H-3 3,910 3,796 366 634

+ 3.0 4-15-86 2)H-3 3,627 3,559 364 630

+ 1.9 6-14-85 H-3 2,417 2,416 351 608 0

1.1 8-14-85 H-3 4,430 4,480 448 776 10-11-85 H-3 1,420 1,974 345 598

- 28

Water, pCi/L 1-18-85 gross a 4

5 5

8.7

- 20 gross a 15 15 5

8.7 0

3-22-85

3) gross a 5

6 5

8.7

- 11 8.7

- 46 gross a 11 15 5

5-24-85 gross a 4

12 5

8.7

- 66 gross s 9

11 5

8.7

- 18 7-19-85 gross a 11 11 5

8.7 0

gross s 7

8 5

8.7

- 13 9-20-85 gross a 6

8 5

8.7

- 25 gross a 6

8 5

8.7

- 25 11-25-85 gross a 6

8 5

8.7

- 25

+ 25 gross s 10 8

5 8.7

Water, pCi/L 4-5-85 I-131 7.7 7.5 0.75 1.3

+ 1.3 8-9-85 I-131 35 33 6

10.4

+ 6.1 2.2 12-10-85 I-131 46 45 6

10.4

Water, pCi/L 2-8-85 Co-60 15 20 5

8.7

- 25

1) Zn-65 52 55 5

8.7

- 6.5 Cs-134 35 35 5

8.7 0

Cs-137 24 25 5

8.7

- 4.0 6-7-85

1) Co-60 13 14 5

8.7

- 7.1 6.4

1) Zn-65 44 47 5

8.7 Cs-134 30 35 5

8.7

- 14 Cs-137 22 20 5

8.7

+ 10 10-4-85 Co-60 17 20 5

8.7

- 25 Zn-65 15 19 5

8.7

- 21 Cs-134 17 20 5

8.7

- 15 Cs-137 25 20 5

8.7

+ 25 1

S.D(StandardDeviation)

- E.L.P.' '(Expected Laboratory Precision)

88 Table II.G.1 EPA ' Cross-Check Data Summary Radio CSU EPA I

1 S.D.

n=1 E

L

P = 3 e / /F*

from known Date nuclide Value Value 1

Air, pCi/ Filter 5.5 3-29-85 4)Grosss 34 36 5

8.7 Cs-137 6

9 5

8.7

- 34 9.1 5

8.7 8-30-85 Gross s 40 44 Cs-137 12 8

5 8.7

+ 50 Milk, pCi/L 1.6

- 11 2-29-85 I-131 8

9 0.92 6-28-85 5)I-131 15 11 6

10.4

+ 36 9.1 Cs-137 10 11 5

8.7 10-25-85 I-131 41 42 6

10.4

- 2.4 1.8 Cs-137 55 56 5

8.7 ll

~

S.D (Standard Deviation)

- E.L.P.(Expected Laboratory Precision)

I 89 Table II.G.E Tritium Crosscheck Analyses on Split Water Samples Determined by Colorado State University, Colorado Department of Health, and Public Service Company.

Collection.

__Sampl e Tritium Concentrations oCi/L Date Location CSU CDH PSC 1-12-85 A-25 1,120 (300)*

1,131 (204) 541 (461) 1-12-d5 A-21

< 242

< 350

< 378 1-17-85 E-41

< 242

< 350

< 378 2-16-85 A-25 395 (297) 664(118)

< 374 2-16-85 A-21

< 247

< 350

< 374 2-18-85 E-41

< 235

< 350

< 374 3-9-85 A-25 319 (294) 835(199)

< 356 3-9-85 A-21

< 232

< 350

< 356

~

3-9-85 E-41

< 234

< 350

< 356 4-13-85 A-25

< 238

< 350

< 343 4-13-85 A-21

< 238

< 350

< 343 4-15,-85 E-41

< 231

< 350

< 343 5-11-85 A-25

< 241

< 359

< 344 5-11-85 A-21

< 233

< 350

< 344 5-11-d5 E-41 310 (271) 484(189)

< 344 6-8-85 A-25

< 276

< 350

< 335 6-8-85 A-21

< 232 520 (189)

< 335 6-17-85 E-41 809 (284)'

< 350

< 335 7-20-85 A-25 2,860 (315) 2,940 (233) 3,410 (428)

I 7-13-85 A-21

< 237 420(218) 725(385) 7-15-83 E-41

< 237 1,570(218) 528(381)

1.96c (Due to conting statistics'.)

I O

90 Table IX.G.2 Tritium Crosscheck Analyses on Split Water Samples Detennined by Colorado State University, Colorado Department of Health, and Public Service Company. (continued)

Collection

.. Sample Tritium Concentrations DCi/L Date-Location CSU CDH PSC d-10-85 A-25 2,120 (305)*

2,079.(2041 1,500 (414) 8-10-85 A-21

< 235

<<350

< 326 d-19-85 E-41

< 238

< 350

< 326 9-14-85 A-25 551 (296) 1,236 (193) 1,050(.437) 9-14-85 A-21 244

< 350

< 351 9-16-85 E-41 237

< 350 445(427) 10-12-85 A-25 2,620 (237) 2,264 (205) 2,740 (707) 10-12-85 A-21

< 250-

< 350

< 559 10-17-85 E-41

< 250

< 350

< 559 11-2-85 A-25 1,660 (297) 1,646 (220) 1,220(428) 11-2-85 A-21

< 233

< 350

< 341 11-7-85 E-41 4,490 (323)

< 350 3,790(465) 12-14-85 A-25 5,910 (342) 5,397 (252) 6.170-(503) 12-14-95 A-21

< 232

< 350

< 347 12-23-85 E-41

< 276

< 350

< 347 I

I' I

1.96o (Due to counting statistics.)

I I

91 l

Table II.G.3 Gross Beta Crosscheck Analyses on Split Water Samples Detennined by Colorado State University, Colorado Department of Health, and Public Service Company of Colorado.

1

. Collection __ ____Sampl e Gross Beta Concentrations oCi/L Date Location CSU CDH PSC 1-12-85 A-25 8.64 (2.21)*

14 (4)

< 8.28 1-12-85 A-21 8.06(2.21) 10(4)

. < 8. 29. ;

1-17-85 E-41 10.9 (2.53) 8 (4) 11.9 (10.8) 2-16-85 A-25 9.70 (2.27) 13 (4) 10.9 (9.27) 2-16-85 A-21 9.51 (2.29) 14 (4) 9.72 (9.19) 2-18-85 E-41 7.11 (2.20) 6 (4) 17.3 (9.83) 3-9-85 A-25 7.58 (2.16) 13 (4)

< 7.60 3-9-85 A-21 14.2 (2.43) 15 (4)

< 7.66 3-18-85 E-41 6.34 (2.16) 9 (4)

< 7.71 4-13-85 A-25 10.5 (2.22) 10 (4) 16.8 (10.1) 4-13-85 A-21 5.68 (2.01) 8 (4)

< 7.23-4-15-85 E-41 8.57 (2.15) 7 (4) 13.4 (9.87)

I 5-11-85 A-25 7.01 (2.03) 7 (4) 11.2 (9.78) 5-11-85 A-21 3.17 (1.85) 5 (3) 18.6 (10.4).

5-11-85 E-41 4.26 (1.92) 8 (4) 9.49 (9.62) 6-8-85 A-25 7.24 (2.04) 6 (4)

< 7.55 6-8-85 A-21 6.58 (2.01) 7 (4)

< 7.64 i

6-17-8,5

.E-41 9.27 (2.22) 10 (4)

< 7.86 i

7-20-85 A-25 9.80 (2.18) 10(7) 19.1 (10.0) 7-13-85 A-21 15.4 (2.48) 12 (4) 15.1(10.2).

7-15-85 E-41 5.51 (2.03) 6 (4) 13.4 (9.72) i

1.96 o (Due to counting statistics.)

'I

92 Table II.G.3 Gross Beta Crosscheck Analyses on Split Water Samples Detemined by Colorado State University, Colorado Department of Health, and Public Service Company of Colorado. (continued)

. Collection _

Sample Gross Beta Concentrations DCi/L Date Location CSU CDH PSC 8-10-85 A-25 6.15 (2.04)*

17 (4) 8.46 (8.90) 8-10-85 A-21 5.52 (2.07) 12 (4) 32.0 (11.3) 8-10-85 E-41 3.85 (1.99) 6 (4) 14.1 (9.61) 9-14-85 A-25 9.50 (2.20) 15 (4)

< 7.51 9-14-85 A-21 5.87 (2.06) l'1 (4)

< 7.63 9-14-85 E-41 8.46 (2.21) 11 (7)

< 7.67 10-12-85 A-25 4.98 (4.97) 17 (4)

< 7.56 10-12-85 A-21 2.18 (2.47) 8 (4) 9.29 (9.95) 10-12-85 E-41 8.75 (5.18) 19 (8) 16.5 (10.6) 11-2-85 A-25 20.5 (5.83) 14 (4) 7.72 (9.26) 11-2-85 A-21 10.9 (5.44) 13 (4) 11.1 (9.69) 11-2-85 E-41 10.9 (5.42) 15 (4) 13.8 (9.79) 12-14-85 A-25 5.93 ( 5.23) 9 (4) 13.7 (9.57) 12-14-85 A-21

< 4.13 10(4) 12.7 (9.59) 12-23-85 E-41 5.02 (5.1 0.

10(4)

< 6.97 I

I

=

.g I

ee

~

I 1.96 o(Due to counting statistics.)

I I

i 93 II.H.

Sumary and Conclu! ions Table II.H.1 sumarizes the radiat on and environmental radioactivity measurements conducted during 1985 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 U.S. reactor monitoring programs.

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 rang 2 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.

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

(See Table III.A.3).

For the category of gross beta concentrations in drinking water, the mean. for the Gilcrest well was again significantly greater t5an for the reference supply located in Fort Collins.

This difference cannot be due to reactor effluent activity for the following reasons:

a.

Hone of the individual fission product or activation product radionuclides

, measured were significantly higher f r. the Gilcrest drinking water.

b.

Tritium concentrations measured at Gilcrest were statistically the same as those in Fort Collins.

94 Tritium is the only significant radionuclide measured 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 corcentrations in Gilcrest water are due to elevated concentrations of the naturally occurring U-238, and Th-232 decay products.

The suspended solids are higher in Gilcrest water samples due to less filtration of the water.

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

This, of course, is directly in the principal effluent route and should be expected.

Elevated concentrations of tritium have never been observed, however, in any human food source in direct or indirect contact with the farm pond water. Downstream surface water concentrations of tritium have occasionally been elevated, but there is sufficient dilution before any human use of this water.

I l

lI 95 During 1985, the activation product Fe-59 was observed for the first time in fish collected at A-25, the farm pond.

This observatica is of no consequence with regards to human dose commitment possibilities (See Section II.F.),

but signaled the 4

need for further investigation of that effluent pathway.

1-131 was also observed for the first time in milk samples and, also, in fish collected at upstream, effluent and downstream sites.

The source of the I-131 was clearly not due to the reactor, but due to releases from nuclear medicine uses upstream of the reactor.

It was an important observation and it i

l stimulated increased monitoring for I-131. This radionuclide is certainly critical with regard to human dose commitment possibilities and the general public is aware of this. To avoid j

misinterpretation of these environmental monitoring data, more knowledge of I-131 in the upstream surface water must be obtained. It is planned to encourage better communication with the Denver and Boulder hospitals that release I-131, and to install a continuous water sampler on the Platte River and on the St. Vrain creek, upstream of the reactor.

For all other categories of sample types and radionuclides, therr: 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 a=

8 values (Type 1 error, when using hypothesis testing, 0.05).

In fact, most of the positive values reported were actually less than the MDC.

96 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 significant radioactivity release from FSV occurred.

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, al so, 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 calculated values less than zero or less than the minimum detectable concentration (MDC) are listed as less than the actual MDC for that sample analysis.

However, the actual result in all cases was used in the calculation for the arithmetic mean values for the period. Therefore, all values, negative as well as positive, were included.

This procedure is now generally accepted and gives a proper estimate of the true mean value. Because of this procedure, however, the values listed in Table II.H.2 cannot be calculated directly from the tabular values in the report.

It must be emphasized that 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

E 97 is equally true that marty 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 distribution of analytical results, all positive results must be averaged with all negative results. If the negative results were omitted, the resulting arithmetic mean would be falsely biased high.

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 of the log ordinate.

The geometric mean value, i,

is determined directly from the g

l 50th percentile point.

The geometric standard deviation is simply the slope of the line which can be calculated from the ratio between 84.1 percentile point and the 50th percentile.

In a normal distribution, the arithmetic standard deviation is an additive parameter to the arithmetic mean; i.e. (i+o),.whereas, in the log-normal distribution the geometric standard deviation, c.is a multiplicat'ive parameter to the geometric mean (i i o ).

g g

g The area between R multiplied by o and R divided by o should g

g g

g contain 687, of the frequency values.

With the log-normal analysis, no bias results from using either actual values or less than MDC values in estimating the geometric mean. The geometric mean is identical to the median.

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

98 4

1.

Tritium was the only radionuclide that was detected in significant concentrations in any of the effluent

- I pathways that could be attributed to reactor operation.

j Since the tritium is released as tritiated water, the dilution by the surrounding hydrosphere is great.

Although in previous years elevated concehtrations of tritiated water could be detected in downstream surface water samples, such concentrations were not observed in 1985. The mean values 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 l

comitment to humans can be calculated for the effluent' tritium in any pathway.

2.

The fallout from the October 1980 Chinese atmospheric l

nuclear weapon test was no longer detectable'in air samples. Only the previous deposition as observed in soil and food chain samples was still observed.

Milk I

samples often showed detectable, but extremely low concentrations 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 project been noted to be the predominant contribution to background.

It is the variation in fallout deposition, in addition to the variation in naturally occurring radionuclides, i

99 that mandates the large number of environmental samples to detect any possible radioactivity due to reactor effluents.

A simple comparison of pre-operational and post-operational values is of little value for most sample types because the fallout deposition was considerably greater during the preoperational period.

3.

Figure II.C.1 is a plot of tritium measured in surface water samples over the period 1974-1985.

During the period the predominant source term is that of fallout I

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, an increase can be observed in the downstream locations 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 and decreased to control levels in 1985.

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 ~ 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.

I t

100-5.

I-131 was observed in 1985 for the first time in milk l

samples, a.11 from a single dairy. The reactor did not release any I-131 during the year, and the source was traced to hospital use in cities upstream.

The observation, however,. confirmed the need for turther monitoffng.

6.

'it can be concluded again that the radiation dose commitments calculated for the closest inhabitants or other parts of the nearby ecosystems from current reactor effluents are negligible compared to natural background radiation dose rate and the dose comitment from atmospheric weapon usting f allout.

It can be concluded that the existing environmental monitoring is adequate 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 compreh'ensive emergency response.

I I

I cI I

M M

M Table II.H.1 Environmental Radiological Monitoring Program Annual Summary Fort St. Vrain Nuclear Generating Facility, Platteville Colorado Medium or Pathway Type and Facility Adjacent Locations with Highest Reference Number of Location Nonroutine Sampled (Unit of Total Number Locations Location Annual Mean measurement) of Analysis Mean(f)D Mean (f)s D

Name

. Mean(f)D Mean(f)g Reported Perfonned range range lifstance &

Range Range Measurements Direction Direct Radiation TLD (154) 0.42 (68/68) 0.42 (67/67) A-10 Old FSV 0.49 (2/2) 0.41 (19/19)

(mR/ day)

(0.36-0.50) (0.33-0.52)

School 7.8 km (0.46-0.52)

(0.36-0.46) 2150 Air, Particulates Gross 8 (354) 28.2 (199/199)

F-9, Farm 1.5 28.1 (51/51) 27.1 (155/155) 3 (7.84-56.5) km 180 (8.04-46.2)

(3.29-53.5)

(fCi/m )

Gamma Spectrometry Cs-134 (28)

< 4.43

< 4.43 6.07 (1/12)

(6.07-6.07)

Cs-137 (28) 4.59 (1/16)

F-7 Farm 1.5 4.59 (1/16) < 4.83 0

(4.59-4.59) km 160 (4.59-4.59)

Air, Charcoal I-131 (357) 22.3 (3/204)

F-16 3 Bar 33.4 (1/50) 15.1(1/153) 3 (16.3-33 4)

Rn 1.2 (33.4-33.4)

(15.1-15.1)

(pCi/m )

Air, Atmospheric H-3 (362) 357 (46/206)

A-19 Hunting 380 (19/52) 411 (23/156)

Watcr Vapor (232-825)'

Cabin-(245-825)

(241-650)

Goosequigl (pCi/L)

~

1.7 km 5 bMean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses. (f) g

~

i i" - i q;-

i.'

i

. t.

1.

e i

.i+ 4

.s.5 6

I i

t s

p

m m

m mm m

m m

m Table 11.11.1 1985 Environmental Radiological Monitoring Program Annual Summary Fort St. Vrain Nuclear Generating Facility, Plattevilie Colorado (continued)

Medium or Pathway Type and Facility Adjacent locations with liighest Reference Number of Name Mean(f)b Locationg Honroutine Sampled (Unit of Total Number Locations loca tion Annual Mean measurement) of Analysis Hean (f)b Hean(f)g Mean (f)

Reported Perfonned range range liistance &

Range Range fleasurements Direction Drinking Water (pCi/L)

Gross 8 (52) 5.17 (26/26)

R-6, Gilcrest 5.17 (26/26) 1.24 (25/26)

(1.91-8.74)

CityWate5 (1 91-8.74)

(0.484-3.82) 9.3 km 60 H-3 (52) 390 (11/26)

R-6, Gilcrest 390 (11/26) 401 (3/26)

(274-533)

CityWate5 (274-533)

(270-631) 9.3 km 60 Gamma Spectrometry I-131 (52) 0.589 (1/26)

R-6, Gilcrest 0.589 (1/26) < 0.496 (0.589-0.589)

CityWateg (0.589-0.589) 9.3 km 60

< 4.79 3.40 (1/26)

Cs-134 (52)

< 4.79 (3.40-3.40)

Cs-137 (52) 4.72 (4/26)

R-6, Gilcrest 4.72 (4/26) 4.74 (4/26)

(3.51-6.14)

CityWateg (3.51-6.14)

(3.56-6.72) 9.3 km 60 Zr-95 (52)

< 6.97

< 13.5 D

,., ', ' ', ( 2. 60-2. 60 ),,,2.60 (1/26)" "' ' ' ' '

R-6 Gil' rest

,'2.60 (1/26) 3.73 (1/26)

Nb-95(52) e

.(2.60-2.60)

(3.73-3.73)

, i ci ty. Wa ter, bMean and range base.d upon detectable,meaqurements.op,1y.,, Fraction, of detectable measurements a.t specified locations is indicated in par,eri,th,esis. (,f) i..... ( i d

... t i s'-

g 6

i.

ro

6e s,

M M

Table II.H.1 1985 Environmental Radiological Monitoring Program Annual Summary Fort St. Vrain Nuclear Generating Facility, Platteville Colorado (continued)

Medium or Pathway Type and Facility Adjacent locations with Highest Reference Number of L cation Honroutine Sampled (Unit of Total Number Location location Annual Mean Name Mean Q)b Mean(f)g Reported measurement) of Analysis Hean(f)g Hean(f)g Perfonned range range Distance &

Range Range Measurements Direction e

Drinking Water (pCi/L)

Co-58 (52) 2.72 (1/26)

R-6 Gilcrest 2.72 (1/26)

< 5.71 (2.72-2.72)

CityWateg (2.72-2.72) 9.3 km 60 Mn-54 (52)

< 2.99

< 5.10 Zn-65 (52)

< 6.47

< 11.6 Fe-59 (52)

< 7.27

< 11.1 Co-60 (52)

< 3.24

< 5.70 Ba-140 (52)

< 6.80

< 6.77 La-140 (52)

< 7.82

< 9.32 bMean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses. (f) t i

I '

l 6

6 I si e

.4 8

4

$e e

6 l+

3

!6 )

L3 i

e.s, t

9 9

M M

Table II.H.1 1985 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 Annual Mean cadon Nonrou tine measurement) of Analysis Mean(f)g locationg Mean(f_)b Mean(f)g Reported Mean(f)

Name Perfonned range range Distance &

Range Range Measurements Direction Surface Water H-3 (60) 2,275 (15/36)

A-25Goosgquill 3,244 (10/12) 336 (2/24)

(pCi/L)

(270-7020) 2.2 km 20 (465-7020)

(319-353)

Gamma Spectrometry Cs-134 (60)

< 5.07

< 5.07 2.96 (1/24)

(2.96-2.96)

Cs-137 (60) 3.71 (6/36) 5.29 (1/12) 6.63 (3/24)

(2.84-5.29)

(5.29-5.29)

(4.31-7.79)

< 7.29 10.8 (1/24)

Zr-95 (60)

< 7.29 (10.8-10.8)

Nb-95 (60) 3.78 (2/36)

F-20,St. grain 5.12 (1/12) 3.61 (1/24)

(2.44-5.12) 1.5 km 340 (5.12-5.12)

(3.61-3.61)

Co-53 (60)

< 3.25

< 3.36 Mn-54 (60)

< 3.44

< 3.28 Zn-65 (60)

< 7.02

< 6.44 Fe-59 (60)

< 8.04

< 7.39

< 3.52

< 3.44 Co-60 (60)

< 3.52 bMean and range based upon detectable measurements only. ' Fraction of detectable measurements at specified locations is indicated in parenthesis. (f) 4' i e

M M

M Table 11.11.1 1985 Environmental Radiological Monitoring Program Annual Sunnary Fort St. Vrain Nuclear Generating facility, Platteville Colorado (continued)

Medium or Pathway Type and Facility Adjacent locations with Hightest Reference Number of L cation Nonroutine Sampled (Unit of Total Number Locations Location Annual Mean Hame Mean (f)b Mean(f)g measurement) of Analysis Mean (f)b Mean(f)g Reported Perfonned range range Distance &

Range Range Measurements Direction Surface Water (pCi/L)

Gamma Spectrometry Da-140 (60)

< 6.99

< 6.30 La-140 (60)

< 8.04

< 7.24 Ground Water (pCi/L)

H-3 270 (1/4)

F-163BgrRanch 270 (1/4)

< 244 (270-270) 1.2 km 0 (270-270)

Gamma Spectrometry Cs-134 (8)

< 4.49

< 4.28 Cs-137 (8)

< 4.55

< 4.55 5.71 (1/4)

(5.71-5.71)

Zr-95 (8)

< 6.27

< 5.67

< 3.27

< 2.97 Nb-95(8)

< 3.27 A

< 2.83

< 2.57 Co-58 (8)

< 2.83 Mn-54 (8)

< 2.99

< 2.80 Mean and range based upon detectable measurements only.,'.' Fraction of detectable measurements at specified locations b

is indicated in parentheses.

(f)

-g

M M

Table II.H.1 1985 Environmental Radiological Monitoring Program Annual Suninary Fort St. Vrain Nuclear Generating Facility, Platteville Colorado (continued)

Medlum or Pathway Type and

' Facility Adjacent locations with Highest Reference Number of location Nonroutine Sampled (Unit of Total Number Location location Annual Mean Hame Mean (_f.)b Mean(f)g Reported measurement) of Analysis Mean(f)g Hean(f)g f

Perfonned range range Distance &

Range Range Measurements Direction Ground Water (pCi/L)

Gamma Spectrometry

[

Zn-65 (8)

< 6.08

< 5.69 Fe-59 (8)

< 6.34

< 5.90 Co-60 (8) 3.44 (1/4)

F-16, 3 Bar 3.44 (1/4)

< 2.97 (3.44-3.44)

Rancg1.2 (3.44-3.44) km 0 Ba-140(8)

< 56.8

< 5.59

< 65.3

< 6.43 La-140(8)

< 65.3 bMean and range based ~upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses. (f).-

.i 4

ei et I:

.s.I i

.*6.

i..

e

(.

8 l'

i io l a e6e tai t.

16-t i

i 8

. :... 4 i P

i....

4if i.

e

.i

}

6 sei I

l

.i.e I

i-i.')<

t 46'l-il )

a.g l'6e t ti..

m

Table 11.11.1 1985 Environmental Radiological Monitoring Program Annual Suninary Fort St. Vrain Nuclear Generating Facility, Platteville Colorado (continued)

Medium or Pathway Type and facility Adjacent Locations with liighest Reference Number of Location Honrou tine Sampled (Unit of Total Number loca tions Location Annual Mean Mean(f_)b Mean(f)f' Reported measurement) of Analysis Mean (f)6 Mean (f)s D

Name Perfonned range range Distance &

Range Range Measurements Direction Sediment Gamma Spectrometry (pCi/kg, dry)

Cs-134 (2)

< 68.8 Cs-137 (2) 174 (2/2)

(125-222)

Milk (pCi/L)

H-3 (114) 329 (7/97)

A-26. Cotton-373 (2/15) 310 (2/17)

(241-389) wood Dairy (359-389)

(250-310) g 7.8.km 108 Gamma Spectrometry I-131 (114) 1.21 (6/ 97)

A-22, Odenbaugh 1.21 (6/17) < 0.487 (0.674-2.13) Dairy 3.2 km (0.674-2.13) 900 Cs-134 (114) 4.54 (1/97)'

A-26, Cotton-m 4.54 (1/15) < 4.91

.(4. 54-4. 54 ).

wood Dairy (4.54-4.54) 0 7.8 km 108 Cs-137 (114) 4.65 (13/97)

A-6, Henderick-5.19 (5/17)

'4.80 (3/17)

' (2.84-6.92)-

son Dairy 'o.

(4.34-6.92)

(3.61-5.53) 7.1 kn),115 Ba-140 (114)

< 6.91

< 6.37 La-140 (114)

< 7.95

< 7.32 bMean and range based upon detectable men urements only. Fraction of detectable measurements at specified locations g

is indicated in parentheses. (f) o.

m m

m M

m W

m Table II.H.1 1985 Environmental Radiological Monitoring Program Annual Suninary Fort St. Vrain Nuclear Generating Facility, Platteville Colorado (continued)

~

Medium or Pathway Type and Facility Adjacent locations with liighest Reference Number of L cation Nonrou tine Sampled (Unit of Total Number location Location Annual Mean Mean(_f)b Mean(f)g Reported measurement) of Analysis Hean(f)g Mean(f)g f

Name Perfonned range range Fistance &

Range Range Measurements Direction Food Products Gamma Spectrometry (pCi/kg, wet) 1-131 (10)

< 15.9

< 16.0

< 23.4

< 24.1 Cs-134 (10)

< 23.4

< 24.1

< 20.8 Cs-137 (10)

< 24.1 Fish Gamma Spectrometry (pCi/kg, wet)

Cs-134 (6)

< 6.80

< 6.58 Cs-137 (6)

< 5.96

< 6.98

< 6.41 Co-58 (6) 3.70 (1/6)

< 4.40 F-19So.glatteDam

< 4.00 (3.70-3.70) 0.9 km 90 Mn-54 (6)

< 5.25

< 4.89

< 4.71 Zn-65 (6) 15.5 (1/6)

< 5.80 F-19So.glatteDam

< 9.20 (15.5-15.5).

0.9 km 90 Fe-59 (6)

< 8.97 30.6,(1/6),A-25Gooseguill

< 10.3 (30.6-30.6) 2.2 km 20 Co-60 (6)

< 5.32

< 6.54

< 4.61 bMean and range based upon detectable meass ements only. Fraction of detectable measurements at specified locations is indicated in parentheses. (f)

- i

'3 I

,e m

M M

M Table 11.11.2 Summary Table of Geometric Means, Geometric Standard Deviations and Arithmetic Means for Selected Sample Types, 1982-1985.

1982 1983 1984 1985 Sample X_

X_

X X

X_

Type X

o o

X o

o X

g g

Atmospheric Water Vapor (pCi/L)

H-3 Facility 316 2.81 157 249 2.52 137 252 2.23 296 197 1.01

< 249 Reference 259 1.78 277 208 2.46 52.6 313 2.36 263 192 1.06

< 249 3

Air (fCi/m )

Gross Beta Facility 19.4 1.48 20.8 13.6 1.81 15.8 15.1 1.70 17.4 26.7 1.02 28.2

, Reference 18.7 1.46 1,46 13.1 1.94 16.1 15.9 1.58 17.6 24.8 1.01 27.1 3

I-131 (fCi/m )

22.5 3.65

< 35.0 10.5 1.05

< 43.0 Facility Reference 22.3 3.43 1.06 12.7 1.09

< 35.7 3

Cs-137 (fCi/m )

5.96 2.59 0.674 1.68 1.30

< 4.39 Facility Reference 5.94 3.01

< 30.0 2.05 1.15

< 4.41 00 In prior reports I-131 and Cs-137 means were composite.

I o"

M M

M Table 11.11.2 Summary Table of Geometric Means, Geometric Standard Deviations and Arithmetic Means for Selected Sample Types, 1982-1985.

(continued)

Sample 1982 1983.

X o

X_

1985 1984 X

E o

X X

X Type X

og g

g g

Drinking Water (pCi/L)

N~domposite 273 2.95 186 354 1.90 311 Gilcrest 305 1.60 201 190 1.14 164 251 2.25 75.5 182 1.05

< 249 Ft. Collins Gross Beta Composite 6.11 1.91 7.32 6.43 1.46 6.23 Gilcrest 7.70 1.37 8.05 4.84 1.03 5.17 1.71 2.32 2.26 1.03 1.06 1.20 Ft. Collins I-131 0.426 3.70 0.500 0.170 1.33 0.0042 Gilcrest 0.340 4.12 0.500 0.182 1.01 0.0767 Ft. Collins Cs-137 Composite 0.545 2.58 0.162 0.898 3.13 1.27 Gilcrest 2.54 2.99 1.63 1.83 1.09 1.54 i

Ft. Collins 4,14 2.33 2.80 1.40 1.06 1.73 r

Co Not available.

O o

i

0 Table II.H. 2 Summary Table of Geometric Means, Geometric Standard Deviations and Arithmetic Means for Selected Sample Types, 1982-1985. (continued)

I Sample

'1982 1983 1984

i. 1985 i

R j

g i

Type i

i i

o o

o g

g g

?.

h i

Surface Water (pCi/L)

H-3 l

Effluent 273 2.95 14,000 563 4.54 4,620 8,270 4.45 13,317 1,340\\1.26 2,670 Downstream 471 3.06 1,070 319 3.37 528 339 1.84 219 188

(,1.08 90.6 Upstream 281 1.54 15.0 254 2.01 229 278 2.35 139 142

'l 1.98

< 246 i

[

Cs-137 7

Effluent 0.981 3.21 1.32 1.58 2.34 0.631 3.39 2.49 0.830 2.24 1.20 1.43 j

Downstream.

0.908 2.77 0.115 1.02 3.27 0.976 2.84-2.50 0.570 2.24 f 1.07 2.06

~

)1.32 1.34 Upstream 0.676 3.61 0.356 1.44 2.66 2.03 3.23 2.87 1.84 1.92 Milk (pC1/L)

J' H-3 Adjacent 170 4.36

< 284 183 2.84

< 300 196 2.07

< 296 171 J'1.06

< 250 Reference 259 1.78

< 284 h7 1.72 < 300 199 1.66

< 296 190 1.09

< 246 r.

I-131 hi Adjacent 0.243 4.35

< 0.115 0.626 4.49 < 0.116 0.753' 2.33

< 0.500 0.224 p 1.05 0.0167 R ference 0.262

, n4.29.< 0.117.n, 0.528

.4.40...s 0.141.

,,.0.604, 2.94

. < 0.500 0.207.i 1.09

< 0.469 Cs-137

i. >

..,.3 i, p.

i Adjacent O.285 4.29

< 0.117 0.251 2.33 < 0.720 1.28 3.58

< 9.00 2.10 i 1.01 1.73 h1.25 R:ference 0.168

'2.13

< 0.101 0.204 1.64

< 0.132 1.06

'5.28

< 9.00 1.86 1.56 t

l 112 III.

Radiological Environmental Monitoring Program III.A. Sample Collection and Analysis Schedule.

Tabic 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 the same objective.

That objective is to document the radiation and i

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 I

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 identified 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 September of 1985, 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 i

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. From the 1985 census it was verified that the closest permanent residence in Sector 16 is still the critical receptor with regards to mean annual dose commitment.

A new TLD I

113 i

station will be assigned to this site in 1986.

In 1986 the land use census will be performed in the Spring rather than the Fall.

No resident in the sampling sectors up to a distance of 8 km from the plant has a cow used for personal milk consumption. One lactating goat was observed, but the owners stated that the milk was not consumed. All milk produced is transported to commercial processors.

The milk produced locally is diluted by a large milk shed, processed and distributed over a large area for consumption.

Therefore, the dairy food chain would not be the critical dose pathway for any of the local residents. Inhalation or ingestion of produce contaminated by effluents would instead be the critical pathway. This is true for chronic releases or releases under accidental conditions.

Table III.A.2 lists the LLD concentration values for each sample I

type and radionuclide measured in this report. These LLD values are the actual values pertinent to the sample sizes, counting yields, and counting times used in the project.

Typical decay periods were used in the calculations.

It should be noted that the LLD values are in all cases equal to or less than those required by the technical specifications.

Table III.A.3 lists the USNRC reporting level for each sample type and radionuclide.

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61 Table Ill A.2. Detection Capabilities For nv'ironmental Sample Analysis Lower Limit of Detection (LLD)*

'fo'dProducts Sediment Analysis Water Airborne' Particulate '

F'I sh '

Milk '

o (pC1/L) or Gas (fCl/m3)

(pCl/kg, wet) (pCl/L)

(pCl/kg, wet)

(pCi/kg, dry)

Gross Beta 3.86 3.25 11-3 494 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 Hb-95 4.24 00-58 3.66 12.8 Hn-54 3.64 12.7 0

c.

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

As suggested in NUREG-0472.

All values are at or below values listed in Table 8.2-2. of Technical Specifications.

.... i..i..........i i,.. 4 e,

a-i.

.i......g..i.iii..

i..... i....... o.,

i 4 -,

r.:.ei.i,s....

i...

iii s i s..is...i..

f i.'.i

( &I l / sie I)

((.i if a if,. I J lj4 esi )

g g.' e ' l,

4.

I

g i

i I

M M

M in t

its i

fis i

i Table III.A.3.gpeporting Levels (RL) For Nonroutine Operating, Reports Reporting Level (RL)

Analysis Water AirbornepargiculateorGas Fish Hilk Broad Leaf' Vegetation (pC1/L)

((Ci/m )

(pC1/kg, wet)

(pC1/L)

(pCf /.kg, wet) 11-3 2 x 10 (a) 4 3

4 Mn-54 1 x 10 3 x 10 2

Fe-59 4 x 10 1 x 10 3

4 Co-58 1 x 10 3 x 10 2

4 Co-60 3 x 10 1 x 10 2

4 Zn-65 3 x 10 2 x 10 2

6 Nb-95, 4 x 10 Zr-95 2

2 I-131 2

9 x 10 3

1 x 10 4

3 3

Cs-134 30 1 x 10 1 x 10 60 1 x 10 4

3 3

Cs-137 50 2 x 10 2 x 10 70 2 x 10 2

2 Da-140, 2 x 10 3 x 10 La-140

.It 6

4.....eis.l 4i..4 (l e ; i..

6 4...... : i a..

.r..

g a for drinking water samples. This is 40CFR Part 141,value.,,,,,,

..o......

c.. i i... i. i...i..

i i 1,

,.6i, t it t /ni 's

c i n.. _,. i u-i 6. i i i.

i 1

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c.

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th.

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in.

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C @

C C * * * *

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w w

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04 to T

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ss

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6 6 =

60

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44

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=

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=

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m

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C C

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= -

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=-C Er E 6 *OC C C e C CN C C

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c.

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6

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TM T **

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=

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= Cm

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C C C N to b

s.

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h=

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>= Q Cf C

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I Table III.B.1 RAolotoclCAI. r.NvlRONHENTA1. HONITORING PROGRAM SAMPl.ING SITE DESCRIPT10NS fr: racility Area 0-1.6 km. A: Art.lREfDt. Area 1.6-A_hal. R: Re fe r.90C!LAEga_1 j

e Exposure rattway Site No.

(Old Site No.)

Location Description (see map)

Sector Distanco, km f

VH9fho_In!!

Surfaco F-19 U-i 3 S.

Platto at dam ased inlet pond 88 1.2 l

k.

A-21 U-i2 St. Vrain crook at bridge on 3es 11 2.88 A-10 D-8so S.

Pla t to a t CO 60 10.1 F-20 D-8 5 st. Vrain crook on 19 1/2 o.3 kan f rom 16 1.5 l

d i sclea rgo into St. Vralte Crook 5-25 E-38 Coosoquill rond outlet 1

2.2 N

1 Cround h-16 Woll lashind residenco at 3 Dar. Ranch 16 1.2 at ( r-16) i:

l t

i l

R-5 Erlich feed lot, 1.0 km West or CO 66 a.7 l

oss Wold Crity Ad 8 6 1

Drinking R-3 CSU dia ry W. Drake Rd, rt. Collins, CO 8:5.1 R-6 Clicrost city water, 688 rnst Orrico 9.3 l

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l Table III.B.1 RAOiOtocicAt EnvinonntnTAi_ Houltonino PnocnAH (Continued)

SAHPLING SITE DESCRIPT10fsS jF: IsCllltyJ tge_Q-L6_hm J : Ad.jpcgnt Atgg i f-l}_kngul}; 'BGL4EDDC_9 3 E9fl Exposisro Pathway Site No.

(Old Sito No.)

Location Description (see map)

Sector Distanco, kre l Lood Prodygn A-9 Hitler Store Rd 19 k Co 66 9

Is. 6 l

A-8 Wal ter Ma ler Fa rm, 9708: CO 66 8

8s. 7 i

A-27 Wi l la rd Wol ra Fa rm, 1303 8 Cnty std 3a 8:

5.n l

A-28 Odie Illndenbrandt Farm, 16506 Cnty Ed 25 8:

8s. 0

{

l A-29 non CastFolder Fa rm, 12027 Cnty Rd 8 2 2

7.4 1

g R-12 Joan Lewis Fa rm, 13255 Cnty Rd 8:6 9.8 ro l

R-13 llarry Ha tashima Farm, 1/3 mile N of 13.7 Rd 8 6 on Rd 33 l

1 l

tt-18:

Kawata Fa rms, E or (Aty Rd 31 on Rd 8e6 12.2 i

R-15 Jian Misslor Farm, 18:36R Cnty Rd 8 2 10.0 1

l A-30 Frank Fram, 12058s Wold Cnty Rd 40 3

5.2

]

l A-31 Oster Ferm, Corner Rd 38 and Rd 25 3

8s. 2

(

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Figure III.C.1 1985 Land Use Census I

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Q Garden Location A Milk Location O Resident :.ocation o Garden & Resident

& Milk & Garden I

l 127 l

Table III.C.1 1985 Land Use Census

Location of:

Sector Nearest Nearest Nearest Residence Garden Milk Animal 1

17578 Rd 19 21692 Rd 21 2

18451 Rd 23 18451 Rd 23 11248 Rd 40 3

11250 Rd 38 18535 Rd 25 4

11247 Rd 36 11733 Rd 36 11733 Rd 36 5

16123 Rd 23 16134 Rd 23 16134 Rd 23 6

16107 Rd 23 621 Reynolds St 13278 Rd 32 (Dairy) 11056 Rd-32h (Goats) 7 9999 Rd 34 11170 Rd 30 8

15883 Rd 21 14500 Rd 21 9867 Rd 26 9

9434 Rd 34 15275 Rd 19 9033 Rd 26 10 9061 Rd 34 15449 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 I

14 8900 Rd 36b 8900 Rd 36h 15 8903 Rd 38 8903 Rd 17 16 17250 Rd 19h 18986 Rd 19 20700 Rd 17

Census date: September 26, 1985.

- No milking animals available.

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