ML20210A299

Radiological Environ Monitoring Program Summary Rept for 1986

ML20210A299
Person / Time
Site:	Fort Saint Vrain
Issue date:	12/31/1986
From:	Jerrica Johnson, Miller D, Robert Williams COLORADO STATE UNIV., FORT COLLINS, CO
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
P-87152, NUDOCS 8705050057
Download: ML20210A299 (145)

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PROGRAM SUMN ARY RE3 ORT ma 1986 RER"2888K8%$$8567 ~

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l l RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM j

l Sumary Report for the Period January 1,1986 - December 31, 1986

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Prepared by: St4 d b}

James E. John (son, Professor, Date Colorado Statb University Reviewed by: d m ,3 ,( h , w , t ) ,,, _ oq. o 7_ y 7 Radiocheinistry Supervisor Date 1 Approved by: M //,tj([( h jy [Dpfq/ e[//h/g7 Support Servicts Manager ~Date l-l

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Acknowledgements Many persons have contributed to this project during 1986 and it is important to acknowledge their effort. We also wish to thank the citizens from whose fams, homes, and ranches we collect the environmental samples. Without their cooperation the project would not be possible.

The persons working directly on the project have been:

Sheri Chambers Laboratory Technician Sharon Clow Chemist Laura Gonsalves Research Associate Ken Johnson Graduate Research Assistant Joy Matthews Graduate Research Assistant Scott Maxey Graduate Research Assistant Marion Mcdonald Laboratory Coordinator Art Rood Graduate Research Assistant Mathew Trump Laboratory Assistant Charles Sampier Chief Electronics Technician j ]Lqr, kr U '

James E. Johnson, Professor and Project Director

TABLE OF CONTENTS Page No.

List of Tables iii List of Figures v I. INTRODUCTION 1 ,

II. SURVEILLANCE DATA FOR 1986 AND INTERPRETATION OF RESULTS A. External Gamma Exposure Rates 6 B. Air Sampling Data 9 C. Water Sampling Data 35 D. Milk Data 72

E. Food Products 82 F. Aquatic Pathways 84 4

G. Sample Cross Check Data 88 H. Conclusion and Summary 101 III. ENVIRONMENTAL RADIATION SURVEILLANCE PROGRAM AND SCHEDULE A. Collection and Analysis Schedule 120 B. Sampling Locations 124 C. Land-Use Census 135 l

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LIST OF TABLES Page No.

II.A.1 Gamma Exposure Rates. 8 II.B.1 Concentrations of Long-Lived Gross Beta Activity in Airborne Particles.

a. First Quarter, 1986 11

b. Second Quarter, 1986 12

c. Third Quarter, 1986 13

d. Fourth Quarter, 1986 14 II.B.2 Tritium Concentrations in Atmospheric Water Yapor, pCi/L.

a. First Quarter,1986 19

b. Second Quarter,1986 20

c. Third Quarter, 1986 21

d. Fourth Quarter, 1986 22 II.B.3 Tritium Concentrations in Air, pCi/m3 ,

a. First Quarter, 1986 23

b. Second Quarter,1986 24

c. Third Quarter, 1986 25

d. Fourth Quarter, 1986 26 II.B.4 Tritium Released in Reactor Effluents. 27 II.B.5 I-131 Concentrations in Air.

a. First Quarter, 1986 30

b. Second Quarter, 1986 31

c. Third Quarter, 1986 32

d. Fourth Quarter, 1986 33 II.B.6. Radiocesium Concentrations in Ambient Air. 34 II.C.1 Gross Beta Concentrations in Bi-weekly Composites 38 of Drinking Water.

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

II.C.3 Radionuclide Concentrations in Bi-weekly Composites 42 of Drinking Water.

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LIST OF TABLES (continued)

Page No.

II.C.4 Tritium Concentrations in Surface Water. 55 II.C.5 Radionuclide Concentrations in Surface Water. 56 II.C.6 Radionuclide Concentrations in Effluent Water. 68

-II.C.7 Radionuclide Concentrations in Ground Water. 70 II.C.8 Maximum Permissible Concentrations in Water. 71 II.D.1 Radionuclide Concentrations in Milk. 75 II.E.1 Radionuclide Concentrations in Food Products. 83.

II.F.1 Radionuclide Concentrations in Fish. 86 i II.F.2 Radionuclide Concentrations in Sediment. 87 II.G.1 EPA Crosscheck Data. 91 II.G.2 Tritium Concentrations in Crosscheck Data, 93

, CSU-Fort St. Vrain-Colorado Dept. of Health.

II.G.3 Gross Beta Concentrations in Crosscheck Data, 95 CSU-Fort St. Vrain-Colorado Dept. of l'ealth.

II.G.4 Intralaboratory Crosscheck Results 97 II.H.1 Data Summary. 109 II.H.2 Geometric Means of Selected Sample Typi 1982-1985. 117 III.A.1 Radiological Environmental Monitoring /rogram. 120 III.A.2 Lower Limit of Detection. 122 III.A.3 Reporting Levels. 123 III.B.1 Sampling Locations for Environmental Samples. 124 III.C.1 Land-use Census, 1986. 135 iv

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LIST OF FIGURES Page No.

II.B.1 Gross Beta Concentration in Air, 1986. 15

. II.B.2 Gross Beta Concentration in Air, 1973-1986. 16 II.C.1 Tritium Concentration in Water, 1974-1986. 41 II.D.1 Cs-137 Concentration-in Milk, 1986. 81 III.B.1 On-site Sampling Locations 133 III.B.2 Off-site Sampling Locations 134 III.C.1 Land Use Census, 1986 136 i

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1 I. Introduction to Radiological Environmental Monitoring Data for the Period January 1,1986 - December 31, 1986.

During 1986 the Fort St. Vrain Nuclear Generating Station produced electrical energy as follows:

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

Jan-March 0 0 April 1-30 30,177 May 1-30 55,225 4

Jun-December 0 0 A complete and detailed listing of radioactivity released by all effluent routes may be found in the Public Service Company of Colorado Semi-annual Effluent Release Reports for 1986 to the U.S. Nuclear Regulatory Commission. When possible in this report, any correlation of radioactivity in environmental samples with the effluent release data is discussed. These discussions are presented in the appropriate sample type section and in the summary section, II.H.

Table III.A.2 lists the LLD values achievable by the counting systems used during 1986 on project samples.. These values are given for typical sample sizes, counting times and decay times. The LLD is, therefore, an a priori parameter to indicate the capability of the detection system used. The LLD values in Table III.A.2 were calculated as suggested in NUREG-0472.

Throughout the report, however, when a sample result is listed as less than a specified value, that value is the calculated MDC (minimum detectable concentration). This approach is analogous to that of

2 Currie (N11 REG /CR-4007): the MDC is the same as S , the critical c

signal, and the LLD is equal to SD, the detectable signal. The MDC value applies to the actual sample size, counting time and decay time appitcable to that individual sample. It is calculated as:

-At MDC = 2.33 B

/E Y V e Where:

B

= Standard deviation of background count rate E = Counting efficiency, c s-1 pCi-1 Y = Chemical yield V = Sample mass or volume A = 0.693/ Half-life t = Decay time between sample collection and l analysis This calculation method assumes that E and Y are constants and makes no allowance for systematic error.

It should be noted that we have not used the notation < MDC for values less than MDC. Rather, we report the result as less than the I

actual MDC value. Because the MDC is dependent upon variables such as )

l the background count time and sample size, the value will be different for cach sample type and even within sample type.

Essentially all radioactivity values measured on this project are near background levels and, more importantly, near the MDC values for l 1

each radionuclide and sample type. It has been well-documented that environmental radioactivity values exhibit great inherent variability.

This is partly due to sampling and analytical variability, but most importantly due to true environmental or biological variability. As a result, the overall variability of the surveillance data is quite

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I 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. .

l Environmental radiation surveillance data also commonly exhibit

. non-normal frequency distributions. Usually the data can be

satisfactorily treated using log-normal statistics. However, when the l number of observations is small, i.e., less than 10, log-normal treatment is tentative.

L The geometric means-and geometric standard deviations are calculated for each sample set. If any data paint measured resulted in a negative value, the corresponding MDC is used in the calculation '

of the log-normal statistics. (Negative values are possible due to the -

statistical natu're of radioactivity counting.) In Section II.H.

Conclusions and Summary, the geometric means and geometric standard '

i deviations for the reporting period of 1986 are . listed in Table

II.H.2.

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The arithmetic mean for each sample set is also listed in Table

! II.H.2. All measured values, both positive. and negative, are used in

! the calculations of the arithmetic mean. This is the suggested i

practice by Gilbert (Health Physics 40:377, 1984) e.nd the NRC j (NUREG/CR-4007).

Many sets of data were compared in this report. The statistical test used was either a "t"-test or a paired "t"-test. If data sets are noted to be significantly different or not significantly different, the confidence for the statement is at the 95% level ( a =

! 0.05).

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In this report we have footnoted appropriate tables with the

) maximum permissible concentration applicable to each radionuclide. We I

have chosen to list the maximum pemissible concentrations as found in

Appendix B Table II of 10CFR20. This is the concentration in water or l air of each radionuclide which if ingested or inhaled continuously 4

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, i

cannot be solely due to reactor effluent. As stated in 10CFR20 these

are the maximum concentrations above natural background that a i

j licensee may release to an unrestricted area.. It is assumed that no j

direct ingestion or inhalation of effluents can occur at the I

restricted area boundary and that dilution and dispersion decreases j the concentration before it reaches nearby residents. This is

certainly the case for the Fort St. Vrain environs.

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- There is no specified maximum permissible dose rate or dose f comitment for residents near the Fort St. Vrain reactor from the j reactor effluents. Such limits for water cooled reactors are found in

10CFR50 Appendix I. These are judged the "As Low as Reasonably I

Achievable" dose rates from such reactor types and, although not 4

directly applicable to the Fort St. Vrain gas cooled reactor, can be 4

used for comparison purposes.

A limit that does apply is the independent maximum permissible F

dose commitment rate set by the E.P.A. (40CFR190) for any specified i member of the general public from any part of the nuclear fuel cycle.

i l This value is 25 mrem / year, the dose rate to the whole body from all i

5 contributing radionuclides excluding background and medical radiation dose rate.

Dose commitments are calculated for hypothetical individuals for any mean concentrations noted in unrestricted areas that are significantly above control mean values.

The following is the footnote system used in this report.

a. Sample lost prior to analysis.

b. Sample missing at site.

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c. Instrument malfunction.

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d. Sample lost during analysis.

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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.

6 II. Surveillance Data for January Through December 1986 and

. Interpretation of Results.

A.- External Gamma-ray Exposure Rates The average measured galuna-ray exposure rates expressed in mR/ day are given in Table II. A.I. The values were determined by CaF2:Dy (TLD-200) dosimeters at each of 41 locations. (see Table III.B.1). Two l q

TLD chips per package are installed at each site and the mean value is 1 reported for that site. The mean calculated total exposure is then j divided by the number of days that elapsed between pre-exposure and post-exposure annealing to obtain the average daily exposure rate.  !

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.: 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 1986 was 0.43 mR/de . The mean

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j exposure rate was 0.43 mR/ day for the adjacent area and 0.42 mR/ day i for the reference area. These mean values were not significantly different from the values measured during any quarter of 1985.

The mean exposure rate for all sites during the 2nd quarter was

indeed statistically higher than the 1st . quarter of 1986. This is l attributed to deposition of fission products from the Chernobyl reactor fire occurring in late April of 1986. The fission product debris arrived in the FSV environs during the first week of M g . (See Figure II.B.1) The highest air concentrations were observed during the second week of May. The results for the third quarter were lower again for all sites but were elevated for the fourth quarter of 1986.

There is no reasonable explanation for the third and fourth quarter results at this time.

7 s.

The exposure rate measured at all sites is due to a combination of exposure from cosmic rays, from natural gamma-ray emitters in the earth's crust and from ground surface deposition of fission products due to previous world-wide fallout. The variation in measured values is due to true variation of the above sources plus the variation due to the measurement method. The purpose of the two TLD rings around the reactor is not. to measure gamma-rays generated from the reactor facility itself, but to document the presence or absence of gamma-ray emitters deposited upon the ground from the reactor effluents. Since the inception of power production by the reactor there has been no detectable increase in the external exposure rate due to reactor releases.

The TLD system was calibrated by exposing chips to a scattered gamma-ray flux 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 I

control program includes calibration before readout of each quarterly I

batch of TLD devices.

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' TABLE II.A.1 Gamma Exposura Rates.- (mR/ day) 1986 1st Quarter 3rd Quarter 4th Quarter Facility Area 2nd Quarter s-F-1 0.52 0.49 0.37 0.43 F-2 0.41 0.46 0.40 0.43' F-3 0.46 0.45 0.40 0.45

. F-4 0.42 0.44 0.45 0.44 F-5 0.43 0.48 0.40- 0.49 F-6 0.42, 0.46 0.38 0.52-

. F-7 0.40' O.49 0.41 0.50 ,.

F 0.45 0.46 0.40 0.45

-F-9 0.41 0.41 0.39 0.48 ,,

F-10 0.38 0.38 0.40 0.49 F-11 0.41 0.52 0.41 0.49 F-12 0.41 0.42 0.39 0.41

, F-13 0.40 0.40 0.35 0.45 - '

F-14 0.39 0.42 0.36 0.39 .

F-15 0.40 0.45. 0.38 0.44 ci, F-16 0.40 0.45 0.39 0.40 ^.

F-17 0.41 0.45 0.38 0.45 F-18 0.48 0.47 0.40 '0.50 X (1.96o) 0.42 (0.035) 0.45 (0.035) 0.39 (0.022) 0.46 (0.037)

Adjacent Area ,

A-1 0.43 0.48 0.37 0.48 A-2 0.45 0.50 0.41 0.49 A-3 0.44 0.44 0.40 0.46 A-4 0.31 0.44 0.31 h A-5 0.41 0.40 0.32 0.42 A-6 0.38 0.41 0.35 0.43 A-7 0.41 0.44 0.40 0.46-A-8 0.42 0.47 0.43 0.45 A-9 0.42 0.43 0.38 0.44 A-10 0.45 0.55 0.45 0.50 A-11 0.42 0.46 0.39 0.51-A-12 0.41 0.44 0.43 0.39 A-13 0.36 0.42 0.36 0.38 A-14 0.37 0.45 0.33 0.42 A-15 0.40 0.49 0.38 0.43 A-16 0.41 0.52 0.40 0.45-A-17 0.44 0.53 0.39 -0.49 A-20 0.43 0.59 0.43 0.48 i (1.96o) 0.40 (0.042) 0.47 (0.051) 0.39 (0.040) 0.45 (0.037)

Reference Area R-1 0.40 0.48 0.40 0.45  :

R-2 0.41 0.49 0.43 0.48  !

0.34 "

R-3 0.43 0.35 0.39 t

R-4 0.39 0.44 0.40 0.45 R-7 0.35 0.45 0.35 0.44 X (1.960) 0.38 (0.031) 0.46 (0.026) 0.39 (0.035) 0.44 (0.033):

h. - Utility pole replaced. TLD lost.

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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 1986. A-19, while s technically in the adjacent zone, is only a few meters from the facility boundary and logically should be considered a facility site.

1 It has been termed a facility site since the inception of the

' = monitoring program. The reference sites R-3, R-4, and R-11 are all

- new locations as of January 1,1984 and sufficiently distant to be considered reference (control) locations. (See Table III.B.1).

The reported concentrations are listed in units of femtocuries per cubic meter of ambient air, although the measured activity is due to a mixture of radionuclides. It should be also noted that the current technical specifications no longer require measurement of gross alpha activity. All filters, however, are saved indefinitely for later alpha particle analysis if needed.

No statistically significant difference was found in the arithmetic mean values between the facility and reference sites during 1986. However, the mean gross beta particulate activity was significantly elevated in both facility and reference sites during the second quarter. This was due to fission product cebris from the reactor fire at Chernobyl in the Ukraine region of the U.S.S.R.. The accident occurred on April 26, 1986 and the fallout cloud reached the western coast of the U.S.A. on approximately May 5. We began collecting daily air filters from the R-3 site and noted elevated gross beta particulate on May 7. The major debris cloud reached the

10 FSV vicinity during the week of May 10-17, however. Figure II.B.1 shows the weekly mean values for the facility sites and the reference sites for all of 1986. The peak due to Chernobyl fallout is clearly evident although of short duration. The mean value for the facility sites during the third quarter, for example, was not different from the mean of the third qarter in 1985. This surface deposition of the fission products did not cause elevated air concentrations later in the year due to resuspension. Certain radionuclides however were observed in food chain samples and this is discussed in subsequent sections.

The gross beta data for 1986 have been added to the plot of air concentrations since 1973 (Figure II.B.2). In this figure the half-yearly mean values for the facility sites are plotted with the values from the reference sites. The contribution from Chernobyl is clearly evident. 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- I facility and reference sites. Thus, it can be again concluded that reactor air effluents of particulate fission products or activation products is not a source of dose commitment for the Fort St. Vrain environs population.

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

• a.) Collection Period: First Quarter,1986.

b Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 Jan 4 29 (1.9)* 19 (1.5) 30 (1.8) 26-(1.7) 24 (1.9) 30 (2.2) 36 (2.6)

Jan 11 20 (1.6) 15 (1.3) 24 (2.2) 21 (1.7) 10 (1.5) 22 (2.2) 23 (1.9) i Jan 18 29 (2.4) 23 (1.7) 17 (1.8) . 22 (1.9) 20 (1.9) 24-(2.3) 27 (2.1)

Jan 25 19 (1.4) -20 (1.4) 18 (1.6) 18 (1.3) 8.6 (1.2) 20 (2.2) 27 (2.0) i Feb 1 f 23 (1.4) 26 (1.4) 26 (1.8) 24 (2.2)- 22 (2.0) 31 (2.4) i Feb 9 20 (1.2) 23 (1.3) 23 (1.4) 24 (1.2)' 16 (1.5) 24 (1.8) 27 (1.6)

Feb 15 31 (1.7) 62 (3.0) 33 (1.5) 29 (1.6) 41 (2.8) 36 (2.2) 30 (2.0) >J Feb 22 15 (1.4) 21 (1.4) 16 (1.3) 18 (1.2) 7.2 (1.2) 18 (1.7) 19 (1.4)

! Mar 1 14 (1.5) 16 (1.4) 13 (1.2) 33 (1.9) 16 (2.3)' 16 (1.9) 16 (1.9) i

! Mar 8 (j) 2.9 (0.71) 27 (1.7) 30 (2.0) 43 (3.7)- 18 (2.1) 21L(1.7) 29 (1.8)  ;

Mar 15 11 (1.3) 20 (1.9) 12.(2.1) 8.0 (1.0) , 12 (1.8) 12 (2.2). 16 (2.0)

Mar 21 13 (1.2)- 15-(1.3) 16 (2.2) 14 (1.4) 10 (1.4) 16 (1.9) 15 (1.4) 1 l Mar 29 ;29 (1.6) 30 (1.8) 29 (2.3) 15 (1.2) 39 (2.1) 33 (2.0) 31 (1.7) 5 20 24 22 23 ' 19 l 23 25 1.96o '17 24 14 18 21 14 13 I

MAX: 62 X: 22 MAX: 41~ X: 22 MIN: 3 -n: 51 MIN: 7: :n: 39  ;

1.96 a : 18 1.96 c: 17:

• 1.96o (Due to. counting statistics.);

f; Sample unavailable due to vandalism.

j Value suspect due to filter damage.

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

b.) Collection Period: Second Quarter, 1986 j

Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 Apr 5 9.5 (1.3)* c1 7.6 (1.7) 5.8 (1.2) 20 (1.5) c2 22 (2.5)

Apr 12 24 (1.6) c1 c1 23 (2.4) 22 (1.6) 36 (2.2) 26 (1.8)

Apr 19 24 (1.7) 22 (1.3) c1 6.0 (2.3) 22 (1.5) 24 (3.8) 22 (2.2)

Apr 26 15 (1.5) 17 (1.4) 24 (1.5) 15 (2.1) 21 (2.1) c3 c3 May 3 23 (1.7) 26 (1.6) 22 (1.7) 16 (2.4) 31 (2.0) 26 (1.7) 23 (1.9)

May 1'O 50 (2.3) 50 (2.3) 54 (2.2) 39 (1.9) 39 (1.6) 50 (2.0) 50 (2.4)

May 17 570 (6.3) 300 (4.7) 480 (6.3) 620 (5.5) 710 (7.0) 690 (6.4) 520 (6.4) -

May 24 210 (4.4) 380 (5.3) 370 (5.0) 240 (4.3) 420 (6.2) 620 (8.8) 380 (5.4)

May 30 98 (3.1) 49 (2.4) 80 (3.3)- 110 (2.9) 75.(3.1) 91 (2.4) 96 (3.4)

Jun 7 23 (1.6) 31 (1.6) 27 (1.5) 34 (2.3) 30 (1.8) 27 (1.3) 27 (1.8)

Jun 14 36 (7.8) 34 (1.6) 36 (2.1) 35 (1.6) 34 (1.8) 37 (1.6) 28 (2.7)

Jun 22 14 (1.9) 36 (1.8) 67 (3.7) 16 (1.4) 29 (1.5) 33 (1.5) 26 (2.3)

Jun 28 35 (2.5) 37 (2.6) 30 (2.1) 34 (2.0) 48 (2.9) 36 (1.8) 25 (3.2) 1 X 87 89 110 92 120 150 100 1.96o 300 250 310 340 410 490 320 MAX: 620 X: 94 MAX: 710 X: 120 MIN: 5.8 n: 48 MIN: 20 n: 36 1.96 c: 290 1.96 0: 400

• 1.96 a(Due to counting statistics.)

c1 Pump inoperative for major fraction of sampling period.

c2 Heavy moisture from storm caused particulate to run off filter.

c3 Pumps inoperative at site. All replacement pumps were under repair.

Table II.B.1 Concentrations of Long-lived Gross Beta Particulate Activity in Air. (fCi/m3) c.) Collection Period: Third Quarter, 1986.

Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 Jul 5 38 (2.6)* 38 (2.2) 39 (1.8) 23 (1.9) 50 (2.9) 43 (2.1) 32 (3.1)

Jul 12 18 (1.7) 18 (1.3) 20 (1.6) 19 (1.4) 27 (2.1) 19 (1.4) 15 (2.5)

Jul 19 22 (2.0) 43 (3.7) 25 (1.4) 19 (1.8) 27 (1.9) 13 (1.1) 18 (2.7)

Jul 26 17 (3.0) 8.4 (1.1) 18 (1.6) 22 (1.5) 25 (1.7) 22 (1.5) 20 (1.7)

, Aug 2 c6 32 (2.0) 36 (1.8) 20 (1.8) 37 (2.6) 37 (2.3) 28 (2.0)

Aug 9 41 (1.3) 21 (1.5) 31 (1.9) 23 (1.7) 35 (1.8) 27 (1.7) 33 (2.2)

Aug 16 27 (1.7) 38 (2.1) 42 (1.8) 22 (2.0) 36 (2.1) 25 (1.5) 30 (2.2) ,_.

Aug 23 52 (2.4) 44 (2.1) 39 (2.1) 39 (2.2) 42 (2.3) 27 (1.4) 42 (2.4) w Aug 30 36 (2.0) 37 (2.1) 45 (2.0) 27 (1.9) 44 (2.3) 35 (1.9) 38 (2.0)

Sep 6 29 (1.4) 21 (1.6) 32 (2.2) 27 (1.6) 31 (1.9) 29 (1.7) 29 (2.0)

Sep 13 16 (1.5) 37 (3.6) 24 (1.5) 12 (1.3) 16 (1.4) 19 (1.4) 22 (1.5)

Sep 20 40 (1.8) 14 (2.9) 28 (3.0) 41 (4.4) 41 (2.2) 38 (2.0) 35 (2.2)

Sep 27 36 (2.4) 29 (1.7) c4 c5 29 (1.9) 29 (1.5) 27 (1.7)

X 31 29 32 25 34 28 28 1.96 o 22 23 17 16 18 17 16 MAX: 52 X: 29 MAX: 50 X: 30 MIN: 8.4 n: 49 MIN: 15 n: 39 1.96c: 20 1.96 c: 17

• 1.96 o (Due to counting statistics.)

c4 Filter missing from sample site. c6 Sample volume insufficient .

c5 Pump inoperative during sample period.

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

d.) Collection Period: Fourth Quarter, 1986.

Collection Facjlity_ Sites Referenc_eJJ1es F-9 F-16 A-19 R-3 R-4 R-11 I

Date F-7 Oct 4 23 (1.3) 14 (1.6) 24 (7.4) 22 (1.2) 22 (1.4) 22 (1.3) 26 (2.0)

Oct 11 36 (2.1) 22 (1.8) 46 (3.3) 30 (1.9) 33 (2.5) 23 (1.6) 30 (2.0)

Oct 18 40 (1.8) c7 41 (2.1) 34 (1.5) 41 (2.1) 33 (1.8) 35 (2.1)

Oct 25 25 (1.5) 26 (1.7) 25 (1.8) 22 (1.5) 32 (1.8) 22 (1.5) 27 (1.6)

Nov 1 37 (1.6) 34 (1.7) 38 (1.9) 27 (1.3) 40 (2.0) 43 (2.9) 40 (2.4)

Nov 8 21 (1.5) 20 (1.7) 22 (1.7) 22 (2.2) 21 (1.6) 16 (1.6) 27 (1.7)

Nov 15 31 (1.9) 30 (1.9) 27 (1.7) 30 (1.6) 35 (2.0) 30 (1.5) 35 (2.3) i Nov 22 25 (1.9) 32 (2.4) 16 (2.0) 20 (1.7) 23 (1.6) 32 (2.0) 30 (1.9)

Nov 29 34 (2.1) 34 (2.6) 29 (2.1) 26 (2.1) 31 (2.2) 22 (1.6) 30 (2.5)

Dec 6 34 (2.3) 30 (2.3) 32 (2.2) 32 (2.7) c7 29 (1.7) 34 (2.1) 30 Dec 13 63 (3.2) 42 (2.6) 43 (2.3) 35 (1.9) 41 (2.5) 40 (1.8) 40 (2.4)

Dec 20 47 (2.8) c7 c7 37 (2.4) 32 (1.9) 41 (2.0) 54 (2.7)

Dec 27 55 (2.7) 45 (2.4) , 45 (2.4) 39 (2.0) 41 (2.6) 45 (2.0) 49 (2.7) 36 30 32 29 33 31 35 i X 18 20 12 15 18 17 1.96 o 25 MAX

63 X: 32 MAX: 54 X: 33.

MIN: 14 n: 49 MIN: 16 n: 38 i

1.96 c: 19 1.96 c: 17

• 1.96 o (Due to counting statistics.)

c7 Pump inoperative during sample period.

1 i

Figure II.B.1 2000 ~

Gross Beta Concentrations in Air - 1986 900 800 :

700 . t 600 _

500 400 4

l'\

1 300 -

~

e a Facility Sampling Stations X = 43 e = 75 fCl/m8 e-* Reference Sampling Stations 100 -

90 -

% = 50 o = 100 fCi/m3 80 '

70 .

60 _

50 n 40

') .

N k 30 h /V d /

\ s <

G 20 , N f 10 9 -

8 :

7 -

6 .

5 ~

4 3 -

2-j - .

Jan Feb Mar Apr May Jun Jul AuG Sep Oct Nov Dec Months

.-m

Figure II.B.2 10* -

Gross Beta Concentrations in Air 900 -

800 -

700 -

e o Facility Sampling Stations 600 -

X = 59 e = 59 500 -

,__ Re_ference Sampling Stations 400 . X = 60 e = 59 300 -

200 -

\ /

\ / \

\ 1 cn \ T E \ / \

N 100 -

\ g U 90 - \ l l

80 -

f 1

70 -

I  ;

60 \I \ g

\ j\

50 -E \ \ I!

I\

\ f 1 \

I 40 -

h

{ g

\ \

30 -

\ \

\

\i

\

20 -

N  ;

\ \

\/\ / \

\'

\ \

/

10 ' ' ' f i t i i i i_ ie i  !

1973 '74 '75 '76 '77 '78 '79 '80 '81 '82 '83 '84 '85 '86 '87 Time (year)

17

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 1986 is listed in Tables II.B.2a-2d. The corresponding tritium concentration in air (pCi/m3 ) is calculated from the specific activity data using weekly mean temperatures and dew points measured at the FSV meteorological tower. The measuring point is at a height of 2 m from the surface. The tritium air concentrations are shown in Table II.B.3a-3d.

The principle release mode of tritium from the reactor is batch liquid releases from holding tanks. The tank water is first analyzed and then released with sufficient additional dilution, if necessary, in order not to exceed 10CFR20 concentration limits. The summary of tritium release by all modes is shown in Table II.B.4. The summary indicates that tritium released in 1986 was greater than in 1985. (See previous annual reports to the USNRC).

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

Tables II.B.2a-2d indicate a strong correlation of elevated atmospheric tritium concentrations corresponding to the batch release of tritium in water along the ditch. Due to evaporation while in transit, elevated tritium concentrations in air have been observed for these two lo

:ations often in past years.

On two occasions, the week ending August 9 and the week ending September 13, there appears to be significant tritium activity in the

18 reference samples as well as the facility samples. The source of these results is not known. While cross-contamination of samples is a possible explanation of the results, it is not a probable one as the laboratory takes all known steps to prevent cross-contamination.

However, it also seems improbable that water vapor evaporating from FSV effluent could be detected at the reference sites as far as 30 miles away at near the same concentration, even if the wind were in

, that direction during the collection period.

The mean value for sites F-16 and A-19 were significantly greater than for all other sites during the year. When all four facility sites are averaged, however, the total mean value is less than the MDC value of 250 pCi/L. Radiation dose commitment values are not warranted on the basis of elevated air concentration values alone.

Inhalation is not a significant pathway for dose to humans. The milk and food product pathway is the only significant source of radiation dose to humans from environmental tritium.

Since the same relative humidity is assumed for all sites, Table II.D.3 shows the same site dependence on reactor effluent as Table II.B.2.

l l

1

Table II.B.2 Tritium Concentrations in Atmospheric Water Vapor. (pCi/L) a.) Collection Period: First Quarter,1986 Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 Jan 4 300 (270)* 300 (280) < 230 < 230 < 230 e < 230 Jan 11 < 240 < 240 < 240 < 240 < 240 < 240 < 240 Jan 18 < 240 < 240 < 240 < 240 e < 240 < 240 Jan 25 < 240 < 240 < 240 240'(280) < 240 < 240 < 240 Feb 1 < 240 < 240 < 240 < 240 ' < 240 < 240 < 240 Feb 9 < 240 < 240 < 240 <.240 < 240 -< 240 '< 240 Feb 15 < 240 < 240 < 240 < 240 < 240

< 240 250 (290).

Feb 22 '430 (300) < 250 < 250 < 250 < 250 < 250 < 250~

Mar 1 < 240 < 240 < 240 < 240 < 240 < 240 < 240 Mar 8 < 240 < 240 < 240 < 240 < 240 < 240 < 240 Mar 15 < 240 < 240 <-240 < 240 <.240- < 240 < 240 Mar 21 < 240 < 240 < 240- 240 (280) < 240 < 240 < 240 Mar 29 < 240 < 240 640 (290) 1000 (290) < 240 < 240 <-240

• 1.960 (Due to counting statistics.)

e Insufficient sample. volume for analysis. .

Table II.B.2 Tritium Concentrations in Atmospheric Water Vapor. (pCi/L) b.) Collection Period: Second Quarter, 1986.

Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 Apr 5 < 240 < 240 < 240 < 240 < 240 < 240 < 230 Apr 12 < 240 < 240 < 240 < 240 < 240 < 240 320 (280)*

Apr 19 < 240 < 240 < 240 < 240 < 240 < 240 < 240 l

l Apr 26 < 240 < 240 250 (280) < 240 < 240 < 240 < 240 May 3 < 240 < 240 < 240 < 240 < 240 < 240 < 240 May 10 < 240 < 240 < 240 300 (280) < 240 < 240 < 240 May 17 < 240 -< 240 < 240 < 240 < 240 < 240 < 240 May 24 < 240 < 240 430 (290) 280-(290) < 240 < 240 < 240 May 30 < 230 < 230 700 (280) 400 (280) e < 230 < 230 Jun 7 < 230 < 230 340 (280) < 230 < 230 < 230 < 230 Jun 14 < 230 < 230 < 230 < 230 < 230 < 230 < 230 Jun 22 < 230 < 230 520 (280) 720 (280) < 230 240 (280) 290 (280)

Jun 28 < 240 < 240 320 (290) 310-(290) < 240 < 240 < 240

• 1.96 a(Due to counting statistics.)

e Insufficient sample volume for analysis.

l Table II.B.2 Tritium Concentrations in Atmospheric Water Vapor. (pCi/L) c.) Collection Period: Third Quarter, 1986.

Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 Jul 5 < 230 < 230 320 (280)* 870 (290) < 230 < 230 < 230 Jul 12 < 230 < 230 < 230 560 (280) < 230 < 230 < 230 l

Jul 19 < 230 < 230 < 230 510 (280) < 230 270 (280) < 230 Jul 26 < 240 < 240 290 (280) 420 (290) < 240 < 240 < 240 Aug 2 < 230 < 230 1200 (290) 890 (280) < 230 250 (280) 330 (280) i Aug 9 < 230 < 230 350 (280) 290 (280) 640 (290) 760 (300) 670 (290)

Aug 16 < 230 < 230 < 230 720 (290) < 230 < 230 < 230 Aug 23 < 230 < 230 < 230 370 (280) < 230 < 230 < 230 Aug 30 < 240 < 240 1100 (290) 610 (290) < 240 < 240 < 240 Sep 6 e < 230 380 (280) < 230 e < 230 < 230 Sep 13 540 (280) 660 (280) 1300 (290) 1100 (290) 350 (280) 480 (280) < 230 Sep 20 < 240 < 240 480 (290) e < 240 < 240 < 240 Sep 27 < 230 < 230 330 (280) 590 (280) < 230 < 230 < 230 1 *1.96 o(Due to counting statistics.)

l e Insufficient sample volume for analysis.

l

l Table II.B.2 Tritium Concentrations in Atmospheric Water Vapor. (pCi/L) d.) Collection Period: Fourth Quarter 1986 Collection Facility Sites Reference Sites l Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 l Oct 4 < 230 < 230 < 230 < 230 < 230 < 230 < 230 Oct 11 < 230 < 230 < 230 < 230 < 230 e. < 230 Oct 18 < 230 < 230 < 230 270 (280)* < 230 < 230 270 (280)

Oct 25 < 230 < 230 < 230 < 230 e < 230 < 230 3 Nov 1 < 230 < 230 < 230 < 230 < 230 < 230 < 230 Nov 8 < 230 < 230 < 230 < 230 < 230 < 230 < 230 Nov 15 < 230 < 230 < 230 < 230 < 230 < 230 260 (280)

Nov 22 < 230 < 230 < 230 < 230 < 230 < 230 < 230 Nov 29 < 240 < 240 < 240 < 240 < 240 < 240 < 240 Dec 6 < 230 < 230 < 230 < 230 < 230 < 230 < 230 Dec 13 < 230 < 230 < 230 < 230 < 230 < 230 < 230 Dec 20 < 230 < 230 < 230 < 230 < 230 < 230 < 230 Dec 27 < 230 < 230 < 230 < 230 < 230 < 230 < 230

• 1.96 c(Due to counting statistics.)

e Insufficient sample volume for analysis.

Table II.B.3 Tritium Concentrations in Atmospheric Water Vapor. (pCi/m3) a.) Collection Period: First Quarter,1986.

Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 Jan 4 0.96 (0.88)* 0.96 (0.91) < 0.75 < 0.75 < 0.75 e < 0.75 Jan 11 < 0.78 < 0.78 < 0.78 < 0.78 < 0.78 < 0.78 < 0.78 Jan 18 < 0.77 < 0.77 < 0.77 < 0.77 e < 0.77 < 0.77 Jan 25 < 0.77 < 0.77 < 0.77 0.78 (0.92) < 0.77 < 0.77 < 0.77 E$

Feb 1 < 0.93 < 0.93 < 0.93 < 0.93 < 0.93 < 0.93 < 0.93 Feb 9 < 0.92 < 0.92 < 0.92 < 0.92 < 0.92 < 0.92 < 0.92 Feb 15 < 1.2 < 1.2 < 1.2 < 1.2 < 1.2 < 1.2 1.2 (1.4)

Feb 22 1.7 (1.2) < 0.98 < 0.98 < 0.98 < 0.98 < 0.98 < 0.98 Mar 1 < 0.95 < 0.95 < 0.95 < 0.95 < 0.95 < 0.95 < 0.95 Mar 8 < 0.96 < 0.96 < 0.96 < 0.96 < 0.96 < 0.96 < 0.96 Mar 15 < 1.0 < 1.0 < 1.0 < 1.0 < 1.0 < 1.0 < 1.0 Mar 21 < 0.97 < 0.97 < 0.97 0.99 (1.1) < 0.97 < 0.97 < 0.97 Mar 29 < 1.0 < 1.0 2.7 (1.2) 4.4 (1.2) < 1.0 < 1.0 < 1.0 l

• 1.96o (Due to counting statistics.)

e Insufficient sample volume for analysis.

I

.._- - - . - . -_... . - - _ _ - _ - _ - . .~.-_. - .- - -.

- . - ~ . - -

t 6

Table II.B.3 Tritium Concentrations in Atmospheric Water Vapor. (pCi/m h ,

b.) Collection Period: Second Quarter, 1986.

Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 Apr 5 < 0.68 < 0.68 < 0.68 < 0.68 < 0.68 < 0.68 < 0.68 Apr 12 < 1. 6 < 1.6 < 1. 6 < 1. 6 < 1. 6 < 1.6 2.1 (1.9)*

Apr 19 < 1.0 < 1.0 < 1.0 < 1.0 < 1.0 < 1.0 < 1.0 l Apr 26 < 1. 6 < 1.6 1.7 (1.9) < 1. 6 < 1. 6 < 1. 6 < 1.6 SS May 3 < 1.5 < 1.5 < 1.5 < 1.5 < 1.5 < 1.5 < 1.5 May 10 < 2.1 < 2.1 < 2.1 2.6 (2.5) < 2.1 < 2.1 < 2.1 May 17 < 0.72 < 0.72 < 0.72 < 0.72 < 0.72 < 0.72 < 0.72 May 24 < 1.5 < 1.5 2.6 (1.8) 1.8 (1.8) < 1. 5 < 1. 5 < 1. 5 May 30 < 2.3 < 2.3 7.0 (2.8) 4.0 (2.8) e < 2.3 < 2.3 Jun 7 < 2.2 < 2.2 3.2 (2.7) < 2.2 < 2.2 < 2.2 < 2.2 ,

Jun 14 < 2.4 < 2.4 < 2.4 < 2.4 < 2.4 < 2.4 < 2.4 Jun 22 < 2.0 < 2.0 4'.5 (2.4) 6.2 (2.4) < 2.0 2.0 (2.4) ~ 2.5 (2.4) 1 Jun 28 < 2.3 < 2.3 3.0 (2.7) 3.0 (2.7) < 2.3 < 2.3 < 2.3 l

• 1.96 c(Due to counting statistics.)

e Insufficient sample volume for analysis.

i

!i

! Table II.B.3 Tritium Concentrations in Atmospheric Water Vapor. (pCi/m 3) i

c.) Collection Period

Third Quarter, 1986. .4 i

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

Jul 5 < 2.1 < 2.1 3.0 (2.6)* 8.2 (2.7) < 2.1 < 2.1 < 2'.1 Jul 12 < 2.1 < 2.1 < 2.1 5.1 (2.6) < 2.1 < 2.1 < 2.1

Jul 19 < 2.5 < 2.5 < 2.5 5.5 (3.1) < 2.5 2.9 (3.0) < 2.5

{ Jul 26 < 2.2 < 2.2 2.6 (2.6) 3.8 (2.6) < 2.2 < 2.2 < 2.2 :m i ui  ;

Aug 2 < 1.6 < 1.6 8.4 (2.0) 6.3 (2.0) < 1.6 1.7 (2.0) 2.3-(2.0) i ,

l Aug 9 < 1.9 < 1.9 2.8 (2.3) 2.4 (2.3) 5.2 (2.4) 6.2 (2.5) 5.5 (2.4)

{ Aug 16 < 1.8 < 1.8 < 1.8 -5.6 (2.2) < 1.8 ' < 1.8 < 1.8 i

j. Aug 23 < 1.9 < 1.9 < 1.9 3.0 (2.3) < 1.9 < 1.9 < 1. 9 .

Aug 30 < 1.9 < 1.9 8.4 (2.3) 4.9 (2.3) < 1.9 < 1.9 < 1.9' Sep 6 e < 1.7 2.8 (2.1) < 1. 7 e < 1. 7 < 1.7 i Sep 13 3.2 (1.7)' 4.0 (1.7) 8.0 (1.8) 6.6 (1.8) 2.1 (1.7) 2.9 (1.7), < 1.4 ,

j Sep 20 < 1.7 < 1.7 -3.4 (2.1) e < 1.7 < 1.7 < 1.7 l

Sep 27 < 1.3 < 1.3 1.9 (1.6)' 3.4 (1.6) < 1.3 < 1.3 < 1.3 II i *1.96 o(Due to counting statistics.)

i

e Insufficient sample volume for analysis.

(

Table II.B.3 Tritium Concentrations in Atmospheric Water Vapor. (pCi/m')

d.) Collection Period: Fourth Quarter, 1986.

Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 Oct 4 < 1.3 < 1.3 < 1.3 < 1.3 < 1.3 < 1.3 < 1.3 Oct 11 < 1.1 < 1.1 < 1.1 < 1.1 < 1.1 e < 1.1 Oct 18 < 0.82 < 0.82 < 0.82 0.97 (0.98)* < 0.82 < 0.82 0.98 (0.98)

Oct 25 < 1.3 < 1.3 < 1.3 < 1. 3 e < 1.3 < 1.3 n3 cn Nov 1 < 1.0 < 1.0 < 1.0 < 1.0 < 1.0 < 1.0 < 1.0 Nov 8 < 0.74 < 0.74 < 0.74 < 0.74 < 0.74 < 0.74 < 0.74 Nov 15 < 0.62 < 0.62 < 0.62 < 0.62 < 0.62 < 0.62 0.70 (0.76)

Nov 22 < 0.89 < 0.89 < 0.89 < 0.89 < 0.89 < 0.89 < 0.89 Nov 29 < 0.85 < 0.85 < 0.85 < 0.85 < 0.85 < 0.85 < 0.85 Dec 6 < 0.75 < 0.75 < 0.75 < 0.75 < 0.75 < 0.75 < 0.75 Dec 13 < 0.54 < 0.54 < 0.54 < 0.54 < 0.54 < 0.54 < 0.54 Dec 20 < 0.73 < 0.73 < 0.73 < 0.73 < 0.73 < 0.73 < 0.73 Dec 27 < 0.68 < 0.68 < 0.68 < 0.68 < 0.68 < 0.68 < 0.68

• 1.96 o (Due to counting statistics.)

e Insufficient sample volume for analysis.

. - . _ _ _ - _ - . - - ~ . . _ . -- -- - ._ ,_. - . - -.-. - __ _ _ _ _ . _-- . . . - .-.. . . - ~ - ,

n Table II.B.4 Tritium Released (Ci) in Reactor Effluents, 1986.

l I

4 i TRITIUM RELEASED (Cl) IN REACTOR EFFLUENTS, 1986 l

l l l l l 1 Mo0E I JAN FEB MAR APR MAY I JUN JUL AUG SEP OCT l NOV DEC TOTAL ll t l

Continuous I .0121 I .0107 .0123 .0526 .117 .0853 .270 .415 .123 .0523 .0603 .0940 1.30

( Tu rb i ne I I  ! l l Building i i Sump) l

• l I (1) (1) (1) (1) l Batch Release .0200 I .00937 .00659h .0373 .187 .116 .209 .257 .119 .155 1.10' .0793 2.30 1 1 Reactor I 1 ,  !

L Building i I (

, Sump) l l U 4

I I i 1 1 I If Il l

l Batch I l l I l Release 1 3.32 1 4.31 ,12.1 17.3 24.8 30.2 .

10.1 1 8.32 '

11.0 .152 1.74 .374 124 l (System 62) i I i i 1 I

, I i

1. Caseous l ll l l 1 1 Stack l .0104 I .009871 2.68 1 .271 .0323 I .0355 .539 I .00243 .00461 .00359 .00140 000313 3.59 1 I I i i i i 2 1 TOTAL i 3.36 I 4.34 14.80 ,17.7 25.1  : 30.4 11.1 8.99 .

11.2 .363 2.90 .548 131

1 I I (1) Calculated f' rom total quantities released rather than total of Individual releases.

l I

28 f

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

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

! within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after collection. A 100 minute count is typically l required to achieve an MDC of 33 fCi/m 3. Radon daughters and Thoron

! daughters are trapped on the particulate filter ahead of the charcoal trap. Radon-222 daughter in-growth on the charcoal does not provide l, interference to the region of interest for I-131 using the Ge(Li) 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 sampling period is appropriate l as any I-131 in air would not arrive at the sampling station at a l

j constant rate, but rather in pulses of short duration compared to the

] collection period. This is the case whether the I-131 source term i ,

would be weapons testing fallout or reactor stack -effluent.

There were no measured results above the MDC value' for any of the seven sampling stations during the first quarter of 1986. There was significant I-131 present in surface air during the period when the I

Chernobyl fallout cloud was in the Northern Colorado region. The highest concentrations were measured during the week of May 10-17.

This corresponded to the peak in gross beta air concentrations.

j . During the third and fourth quarters, air I-131 concentrations 1

1 returned to pre-Chernobyl levels and only a few concentrations above the MDC were noted. These are all assumed to be false positive values j and indeed the 95% confidence level about the result included zero.

_ . _ - . _ , . _ . ~ . _ . - . . _ . . _ _ _ _ _ , . - . . - - . . _ _ _ _ . . _ _ _ . _ . . . _ - . _ _ _ _ - _ . . _ _ , . _ . . . - , . _ _ - , . , . _

29 Table II.B.6 lists measured ambient air concentrations of Cs-134 and Cs-137. These values are from gama-ray spectrum analyses on weekly air filters composited quarterly from each of the seven air sampling stations. Only during the second quarter was there detectable Cs-134 in air. This is due to Chernobyl fallout. Cs-137 has a slightly higher fission yield than Cs-134, and it is possible that the fission product precursors of Cs-137 more easily escaped from the Chernobyl damaged fuel. For these reasons the measured Cs-137 air concentrations were 1.7 times greater than for Cs-134.

Concentrations during the third and fourth quarters dropped to pre-Chernobyl levels. For the entire year, the mean of the Facility

~

stations was not different from the mean of the reference stations.

Although only Cs-134 and Cs-137 are reported, each gama-ray spectrum is scanned for evidence of peaks from other fission products and activation products. Normally only gamma-ray activity due to the naturally occurrir- background radionuclides are observed. During the second quarter of 1986, however, many other radionuclides were observed due to the Chernobyl accident. These included the fission products Cc-141, Ru-103,Ru-106, Zr-Nb-95, and Cs-132.

l l

i Table II.B.5 Iodine-131 concentrations in Air. (fCf/m3) a.) Collection Period: First Quarter, 1986.

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

Jan 4 < 39 < 36 < 27 < 38

< 16 < 36 < 33 l Jan 11 < 40 < 19 < 32 < 21 < 44 < 24 < 9.0 l Jan 18 < 15 < 33 < 26 < 35 < 27 < 8.9 < 25 l Jan 25 < 21 < 29 < 35 < 23 < 18 < 14 < 26 m Feb 1 < 24 < 35 < 16 < 33 < 34 < 34 < 33 o Feb 9 < 23 < 21 < 12 < 23 < 20 < 24 < 26

! Feb 15 < 20 < 25 < 22 < 22 < 34 < 13 < 19-l Feb 22 < 33 < 14 < 29 < 27 < 22 < 34 < 30 l Mar 1 < 21 < 24 < 19 < 32 < 35 < 24 < 31 ,

Mar 8 < 21 < 17 < 34 < 34 < 19 < 34 < 16 ,

Mar 15 < 22 < 24 < 16 < 24 < 28 < 16 < 24 '

Mar 21 < 19 < 22 < 33 < 15 < 16 < 22 < 14 Mar 29 < 13 < 24 < 20 < 23 < 26 < 33 < 24

• 1.96 (Due to counting statistics.)

3 131I MPCa= 105 fCi/m . (10CFR20, Appendix B, Table II)

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

b.) Collection Period: Second Quarter, 1986.

Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 Apr 5 < 24 < 35 < 21 < 12 < 22 < 14 < 32 Apr 12 < 34 c1 c1 < 32 < 26 < 18 < 19 Apr 19 < 22 < 34 cl < 34 < 18 < 12 < 16 Apr 26 < 26 < 18 < 29 < 34 < 28 c2 c2 May 3 < 20 < 31 < 22 < 24 < 34 < 17 < 33 May 10 37 (42)* < 30 43 (40) 63 (50) 39 (10) 65 (34) 60 (38)

May 17 360 (55) 350 (57) 420 (60) 420 (49) 460 (52) 560 (54) 450 (57) m May 24 140 (45) 210 (49) 180 (51) 160 (49) 160 (43) 320 (59) 220 (49) -

May 30 50 (51) < 29 68 (55) 81 (37) 80 (40) 50 (28) 77 (53)

Jun 7 44 (45) 33 (30) < 26 < 23 40 (42) < 22 < 25 Jun 14 < 32 < 29 34 (39) < 30 60 (31) < 18 54 (52)

Jun 22 170 (180) < 20 < 18 < 28 < 22 < 15 < 29 Jun 28 < 30 < 24 < 25 < 20 38 (37) < 15 56 (64)

• 1.96 c(Due to counting statistics.)

I MPCa= 10 fCi/m . (10CFR20, Appendix B, Table II) c1 Pump inoperative for major fraction of sampling period.

c2 Pumps were inoperative at site. All replacement pumps were under repair, i

l l

- - _ - . .. . -- .- - --.- . -.. . . _ _ . _ _ . - ~

Table II.B.5 Iodine-131 Concentrations in Air. (fC1/m3 )

c.) Collection Period: Third Quarter,1986.

Collection Facility Sites Reference Sites l

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

1 Jul 5 < 21 < 27 < 15 < 14 < 22 < 20 < 30 Jul 12 < 25 < 20 < 17 < 27 < 34 < 26 < 19 Jul 19 < 15 < 32 < 24 < 34 < 30 < 20 < 30 Jul 26 < 30 < 24 < 26 < 20 < 35 < 31 < 32 Aug 2 c3 < 34 < 17 < 33 < 30 < 26 < 32 w

~

Aug 9 c3 < 22 < 20 < 24 < 22 < 34 < 31 Aug 16 < 20 < 19 < 31 < 33 < 22 < 20 < 31 Aug 23 < 28 30 (36) < 21 < 26 < 21 < 28 < 24

Aug 30 < 18 < 21 < 14 < 20 < 16 < 33 < 23 Sep 6 < 11 < 21 < 22 < 24 < 19 < 33 < 24 Sep 13 < 26 < 30 < 24 < 22 < 29 c4 < 19 Sep 20 < 16 < 28 c3 < 27 < 25 < 16 < 24 Sep 27 < 32 < 18 < 13 c3 < 31 < 20 < 24

• 1.96o(Due to counting statistics only.)

131 s 3 IEa= 10 fCi/m . (10CFR20 Appendix B Table II) c3 Sample volume too low for adequate counting.

I c4 Charcoal lost from cartridge at sample site due to equipment malfunction.

l l

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

d.) Collection Period: Fourth Quarter,1986.

l l

! Collection Facility Sites Reference Sites Date F-7 F-9 F-16 A-19 R-3 R-4 R-11 Oct 4 < 27 < 27 < 32 < 20 < 28 < 19 < 20 Oct 11 < 33 < 28 < 22 < 22 < 16 < 25 < 27 Oct 18 < 25 < 31 < 33 < 19 < 16 < 21 < 13 Oct 25 < 32 < 31 < 12 < 20 < 19 < 17 < 33 Nov 1 < 16 < 20 < 24 < 15 < 24 < 20 < 23 Nov 8 < 26 < 33 < 33 < 26 < 20 < 32 < 18 Nov 15 < 16 < 22 < 25 < 28 < 29 < 25 < 24 Nov 22 < 19 < 24 < 32 < 26 < 21 < 31 < 31 m Nov 29 < 28 < 30 < 26 < 26 < 31 < 18 < 27 w Dec 6 < 26 < 14 35 (39)* < 17 c5 < 34 < 24 Dec 13 < 32 < 19 < 22 < 27 < 19 < 28 < 18 Dec 20 < 30 < 34 < 30 < 34 < 20 < 29 < 29 Dec 27 < 27 < 34 < 25 < 23 < 32 < 28 < 28

• 1.96 o (Due to counting statistics.)

kMPC = 10 fCi/m . (10CFR20, Appendix B, Table II) c5 Pump inoperative during sample period.

_ . _ _ _ - m. ._ _ _ ._.

i Table II.B.6 Radiocesium Concentrations in Ambient Air. (fCi/m3) l Facility Sites Reference Sites l Radio-I nuc1ide F-7 F-9 F-16 A-19 R-3 R-4 R-11 1st Cs-134 < 2.1 < 1.4 < 1.2 < 1.6 < 1.6 < 1. 5 < 2.1 Quarter j 1986 Cs-137 < 2.0 < 1.5 < 1.2 2.2 (2.0)* < 1.8 < 1.5 < 2.2 2nd Cs-134 5.6 (3.2) 9.8 (3.2) 6.5 (3.5) 9.5 (2.7) 9.6 (2.7) 9.9 (2.4) 10 (3.9)

Quarter 1986 Cs-137 13 (3.6) 13 (3.2) 12 (4.0) 18 ( 2.9) 18 (2.8) 17 (2.6) 13 (4.0) 3rd Cs-134 < 2.3 < 1. 6 < 1.7 2.3 (2.4) < 1.7 < 1.4 < 1.9 Quarter i 1986 Cs-137 < 2.4 < 1.7 2.2 (2.0) < 2.0 2.2 (2.0) < 1.3 < 2.0 l

4th Cs-134 < 1.3 < 2.1 < 2.0 < 1.6 < 1.3 < 1.3 < 2.0 Quarter 1986 Cs-137 1.6 (1.6) < 2.0 < 2.1 2.3 (2.2) < 1.4 < 1.5 2.5 (2.6)

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

= 1 x 106 fCf/m3, Cs-137 MPC a = 2 x 106 fCi/m3

~

Cs-134 MPC a (10CFR20, Appendix B, Table II).

35 1

II.C. Radionuclide Concentrations in Water

1. Drinking Water Drinking water is sampled weekly and composited biweekly at two locations. Location R-6 is the well used for drinking water by the town of Gilcrest, Colorado and R-3 is a water tap located on the CSU dairy farm. The Gilcrest well is the nearest public water supply that could be affected by the reactor effluents. R-3 samples are from the Fort Collins drinking water supply and serve 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 1986 from each water supply. The mean for the Gilcrest site was again 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 concentrations are i

responsible for the higher measured concentrations. As can be observed in Table II.H.2 the mean for the entire year for the Gilcrest site was not greater than in previous years. Chernobyl fallout was not sufficient to elevate drinking water concentrations of gross beta activity.

Table II.C.2 lists measured tritium concentrations in these same two drinking water sources. The yearly arithmetic mean values for l both locations were less than MDC and, therefore, not statistically )

i  :

different from each other. No evidence of the tritium released from ,

l the reactor was observed. Figure II.C.1 shows that tritium  ;

l concentrations in drinking (potable) water sources were less than MDC l

for 1986.  !

v 36 It should be noted that the tritium values shown in Figure II.C.1 for potable water are slightly different than those shown on similar graphs in previous reports. It was observed during the preparation of this report that the potable water values plotted previously were averages of the Gilcrest drinking supply and the control drinking supply, rather than the Gilcrest tritium values alone. This error was corrected and the tritium concentrations in the Gilcrest city water well were plotted in the revised graph.

The Gilcrest well data has been the subject of several previous-special studies. On a few occasions in the past elevated concentrations were noted in Gilcrest city water well samples. In 1983 weekly samples were collected instead of the usual monthly samples. The tritium in these samples showed no correlation with effluent release or concentrations at A-25.

In 1984 a hydrological stu@ of the ground water flow was conducted by the Geohydrology department at CSU. This stu@ concluded that it would be virtually impossible for tritium released at FSV to be detected at the Gilcrest well site. To be conservative, however, if it is assumed that the mean elevated tritium concentrations observed at Gilcrest in the period 1981-1986 were due to FSV effluent, a dose commitment calculation has been performed. Using U.S.N.R.C.

Regulatory Guide 1.109 parameters and methodology the calculation would proceed as follows: '

1. Assume the " maximum" infant to be the critical individual.

2. The annual water intake of an infant is 330 L/ year and the tritium ingestion dose factor is 3.08 x 10-7 mres/pCf.

l

_ ~ . - - - .. . _ _ . - , -,r -,m. .,-, ,,_. .. , . , , , - . , - ,m.m... ., - _m.,m.,..,.- .-,.r. ,,

37 y

s

3. For the period 1981-1986 the mean tritium concentration at

, 5 the Gilcrest site was 240 pCi/L. The mean upstream

'b concentration of 60 pCi/L for the same period can be taken as a control value.

4. Assuming an infant ingested Gilcrest water at a net mean concentration of 180 LC1/L for the 6 year period, the dose commitment would be:

180 pC1/L x 330 L/ year x 3.08 x 10-7 mrem /pCi x 6 yr = 0.11 mrem This dose commitment is negligible with respect to naturally occurring background dose rates and with respect to appropriate standards for the general public.

The two drinking water supplies are also analyzed for fission product and activation product concentrations. A sample of 18 liters is passed through Dowex 1-x8 anion exchange resin and the resin then counted by Ge(Li) spectrometry for I-131. This same method is used for milk samples. A three liter aliquot of the original sample is counted directly for the other gamma-ray emitters.

Inspection of Table II.C.3 reveals occasional positive values of radionuclide concentration, but with the exception of Cs-137, these are interpreted to be random variations. Chernobyl fallout radionuclides were rarely observed. The Co-60 concentrations did appear to be suspiciously high and most of those samples were recounted. The source of the Co-60 has not been determined but it is certainly neither Chernobyl fallout nor FSV effluent.

t

. _ _ , - y -

,- w- - -- ,-

38 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 Date: 1986 (Reference)

Jan 4, 11 6.6 (2.3)* 1.3 (0.54)

Jan 18, 25 4.0 (2.1) 5.1 (0.68)

Feb 1, 9 3.2 (2.1) 3.7 (0.63)

Feb 15, 22 3.0 (2.1) 0.92 (0.52)

Mar 1, 8 2.3 (2.1) 0.78 (0.51)

Mar 15, 22 5.4 (2.2) 1.7 (0.55)

Mar 29, Apr 5 3.8 (2.2) 1.3 (1.0)

Apr 12, 19 4.0 (2.1) 0.83 (0.51)

Apr 26, May 4 4.0 (2.1) 7.3 (0.75)

May 10, 18 6.9 (2.3) 2.3 (0.58)

May 24, 31 4.8 (2.2) 1.4 (0.53)

Jun 7, 14 4.2 (2.2) 1.5 (0.54)

Jun 22, 28 2.1 (2.2) 1.3 (0.55)

Jul 5, 12 3.8 (2.3) 1.2 (0.54)

Jul 19, 26 3.5 (2.2) 0.67 (0.52)

Aug 2, 9 3.0 (2.2) 1.6 (0.56)

Aug 16, 23 6.1 (2.3) 0.89 (0.52)

Aug 30, Sep 6 3.8 (2.2) 0.75 (0.52)

Sep 13, 20 5.5 (2.2) 1.2 (0.54)

• 1.96o (Due to counting statistics only.)

MPCw = 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.

39 4 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 Date: 1986 (Reference)

Sep 27, Oct 4 3.2 (2.2)* 0.71 (0.52)

Oct 11, 18 4.5 (2.2) 1.5 (0.55)

Oct 25, Nov 1 4.5 (2.2) 1.2 (0.54)

Nov 8, 15 2.7 (2.2) 0.58 (0.51)

Nov 22, 29 2.1 (2.1) 0.96 (0.53)

Dec 6,13 3.7 (2.2) 0.69 (0.52)

Dec 22, 27 3.1 (2.2) 0.74 (0.52)

• 1.96 o (Due to counting statistics only.)

MPCy = 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.

I

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

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

-Date: 1986 (Reference)-

Jan 4, 11 < 240 <.240 Jan 18, 25 < 240 < 240 Feb 1, 8 . < 240 < 240-Feb 15, 22 < 240 . < 240 Mar .1, 8 280 (280)* . < 240 Mar 15, 21 < 240 < 240' Mar 29, Apr 5 < 240 <-240 Apr 12, 19 < 240 < 240-Apr 26, May 4 < 240 < 240 May 10, 17 < 240 < 240 May 24, 30 < 230 < 230 Jun 7, 14 < 230 < 230' Jun 22, 28 <-230** < 240 Jul 5,12 < 240 < 240-Jul 19, 26 < 240 < 240 Aug 2, 9 < 230 260 (280)

Aug 16, 23 < 240. < 240 Aug 30, Sep 6 270 (280) < 230-Sep 13, 20 < 240 < 240 Sep 27, Oct 4 < 230 < 230 Oct 11, 18 < 230 < 230 Oct-25, Nov 1 < 230 < 230 Nov 8, 15 < 230 < 230 Nov 22, 29 < 240 < 240 Dec 6, 13 < 240 <-240 Dec 22, 27 < 230 < 230:

• 1.96 o (Due to counting statistics only.)

3 6 H MPC = 3 x 10 pCi/L (10CFR20), Appendix B, Table II.

• • Value is the result of second analysis on sample.

l

)

Figure II.C.1 .

Tritium Concentrations in Water 1974-1986

• -e Surface Upstream 1500 -

o o Potable 1400 - l ',

'\

1300 -

I\ .

1200 -

..A )i - I \

ros I \

1100 -

i ',\

- i .;fit  ; i 1000 - S ,t 'l I.'g t O i

h g I

it:\

.1 N

900 - I

%' \ :!

f i

t

p I. I g i \

U 800 -

\

f  !! f: l1 g a

• \' f'Ih 700 -

(.

I f

\ ff g 600 -

5: i to i.-

ks I

• 2 500 -

d ,.8

.,s .i

. f,' i,  %

• \

. t  : i '\

400 -

g  ; i -

;g

, a 300 -

.\ l

\ ! -

5 E.'h:

200 -

' .I !t

- i  ! 'A 4 A

>  ;  ;  % /Q .* . /'

L 5100 -

I I I I I I i i i I I I I e 1973 '74 '75 '76 '77 '78 '79 '80 '81 '82 '83 '84 '85 '86 '87

' Time (year)

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

Collection Date Jan 4, 11, 1986 Jan 18, 25, 1986 Feb 1, 9 1986 '

Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 -

I-131 < 0.28 < 0.77 < 0.50 < 0.26 < 0.47 < 0.38 1

Cs-134 < 2.6 < 1. 7 < 2.4 < 3.1 < 2.4 < 2.5

. Cs-137 < 2.8 < 3.0 < 2.6 ' < 3.3 < 2.6 < 2.7 i

Zr-95 < 5.3 < 4.5 < 5.1 < 5.8 < 5.4 < 5.7 -

Nb-95 < 2.0 2.7 (2.4)* < 2.1 < 2.6. < 2.5 < 2.5.

Co-58 < 1.8 . < 2.1 - < 1.6 < 1. 9 < 1.6 < 1.6 Mn-54 < 2.3 < 2.1 < 2.2 < 2.7 < 2.2 < 2.3 2n-65 '7.7 (6.3) < 4.9 < 5.2 < 6.2 < 5.2

. 7.3.(6.1) i l Fe-59 < 6.4 4.7 (5.1) 4.9 (5.0) < 5.1 < 3.8 < 4.5 Co-60 3.6 (3.0) < 2.2 4.6 (2.8) < 2.9 4.4'(2.7) '5.0 (2.8)

Ba-140 < 4.7 < 4.3 < 4.2 < 5.6 < 6.4 < 4.3 La-140 < 5.4 < 4.9 < 4.8 < 6.5 < 7.3 < 5.0

• 1.960 (Due to to counting statistics only.)

t

?

, , - - , - ~ ,-

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

Collection Date: Feb 15, 22, 1986 Mar 1, 8, 1986 Mar 15, 21, 1986 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 I-131 < 0.29 < 0.29 < 0.32 < 0.31 < 0.24 0.48 (0.43)

Cs-134 2.8 (2.9)* < 1.4 < 3.1 < 1.9 < 2.0 < 2.0 Cs-137 < 2.7 3.9 (3.0) < 2.8 < 2.3 5.4 (4.2) < 2.5 Zr-95 < 5.4 < 4.0 < 5.8 < 5.1 < 5.5 < 4.7 Nb-95 < 2.4 1.9 (2.1) < 2.3 2.7 (2.6) 6.2 (3.0) < 2.1 Co-58 2.0.( 2.0) < 1.7 2.7 ( 2.1) < 1.9 < 2.3 < 2.0 Mn-54 < 2.2 < 1.7 < 2.3 < 1.9 2.5 (2.8) < 2.0 Zn-65 < 5.2 < 3.8 5.4 (6.4) 11 (5.3) < 5.9 < 4.7 Fe-59 < 4.2 < 4.2 < 4.5 < 5.3 < 4.5 5.0 (4.9)

Co-60 5.4 (2.7) < 1. 6 2.5.(2.9) 2.3 (2.4). < 2.4 2.4 (2.5)

Ba-140 6.5 (6.6) < 5.3 ~< 4.5 < 3.7 < 6.4 < 5.5 La-140 7.4 (7.6) < 6.1 < 5.2 < 4.3 < 7.3 < 6.3 1.96o (Due'to counting statistics.)

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

Collection Date: Mar 29, Apr 5, 1986 Apr 12, 19, 1986 Apr 26, May 3, 1986 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 I-131 < 0.50 < 0.44 < 0.50 < 0.26 < 0.38 < 0.22 Cs-134 < 2.2 < 2.5 < 3.3 < 1.9 < 3.0 < 1. 5 Cs-137 3.7 (3.9)* < 3.0 < 4.9 < 2.3 < 3.7 < 1.9 Zr-95 < 4.9 < 6.1 < 7.3 < 4.4 < 7.0 < 3.5 Nb-95 < 2.0 < 2.2 3.5 (3.6) < 1.8 < 2.7 < 1.5 j:

Co-58 < 2.1 < 2.2 < 3.2 < 1. 7 < 3.0 < 1.6 Mn-54 < 2.2 2.6 (3.0) < 3.3 < 1.9 < 3.0 < 1.6 Zn-65 < 5.1 7.7 (6.8) < 8.1 < 4.5 < 7.3 < 3.5 Fe-59 < 4.4 < 6.0 < 7.3 < 4.5 < 5.2 < 3.6 Co-60 < 2.2 5.0 (3.1) < 3.3 4.0 (2.4) < 3.4 < 1.6 Ba-140 < 3.3 7.4 (6.8) < 4.9 < 3.1 < 4.9 < 2.4 La-140 < 3.8 8.5 (7.9) < 5.6 < 3.5 < 5.6 < 2.8

• 1.96 o (Due to counting statistics.)

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

Collection Date: May 10, 17, 1986 May 24, 30, 1986 Jun 7, 14 1986 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 I-131 0.61 (0.70)* < 0.49 < 0.50 < 0.24 - < 0.50 0.50 (0.45) 4 Cs-134 < 2.5 < 2.2 4.1 (3.1) 2.6 (2.6) < 2.5 < 2.2 Cs-137 < 3.2 < 3.3 < 3.1 3.8 (4.0) < 3.0 6.5 (4.0)

Zr-95 < 6.0 < 5.3 < 6.0 < 5.2 < 5.9 < 5.0 Nb-95 < 2.3 < 1.9 < 2.4 < 1.9 < 2.2 3.9 (2.4) g Co-58 < 2.5 2.3 (2.7) < 2.5 < 2.1 < 2.3 < 2.2 Mn-54 < 2.5 3.1 (2.6) < 2.6 < 2.2 < 2.5 < 2.2 Zn-65 < 6.2 < 5.0 < 5.8 < 5.1 < 6.1 < 5.2 1 Fe-59 < 4.9 < 4.2 < 6.0 < 4.3 < 4.5 < 4.3 Co-60 < 2.8 < 2.2 4.8 (3.2) < 2.3 < 2.7 < 2.2 I Ba-140 < 6.0 < 4.7 < 6.3 < 3.3 < 5.3 < 3.2 La-140 < 6.9 < 5.4 < 7.2 < 3.8 < 6.1 < 3.7

• 1.96 o (Due to counting statistics.)

1

.. . .J. _

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

Collection Date: Jun 22, 28, 1986 Radionuclide Gilcrest Ft. Collins R-6 R-3 I-131 < 0.42 < 0.42 Cs-134 < 2.3 3.2 (3.1)

Cs-137 4.8 (4.1)* < 3.1 Zr-95 < 5.4 < 6.4 Nb-95 < 2.1 < 2.3 or Co-58 < 2.2 < 2.3 Mn-54 < 2.3 3.0 (3.1)

Zn-65. < 5.6 8.6 (7.1)

Fe-59 4.8 (5.1) < 6.6 Co-60 < 2.3 < 2.7' Ba-140 < 4.7 < 4.1 La-140 < 5.4 < 4.7

• 1.96 a(Due to counting statistics only.)

9 1

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

Collection Date: July 5,121986 July 19, 26 1986 August 2, 9, 1986 1

Radionuclide Gilcrest Ft. Collins Gilcrest Ft.. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 1 i

I-131 < 0.50 < 0.30 < 0.42 < 0.28 < 0.50 < 0.25 f Cs-134 < 2.2 < 2.6 < 2.9 < 3.1 < 3.0 < 2.5 Cs-137 4.0 (3.9)* < 3.0 5.4 (5.1) < 3.8 < 3.6 < 3.0 Zr-95 < 4.9 < 6.4 < 6.5 < 7.4 < 6.9 ' < 5.8 .O Nb-95 < 2.0 < 2.4 < 2.6 < 2.7 4.3 (3.2)'2.9 (2.7)

. Co-58 < 2.1 < 2.5 < 2.7 < 2.8 < 2.7 < 2.4 Mn-54 < 2.2 < 2.5 < 2.8 < 3.1. 3.7 (3.5) < 2.5-Zn-65 < 5.3 < 5.8 < 6.8 < 7.3 < 7.0 6.6 (6.8)

Fe-59 -< 4.3 < 4.5 < 6.7 < 5.7 < 5.1- < 4.3 Co-60 < 2.3- < 2.8 < 3.0 < 3.4- < 3.1 < 2.8-

, Ba-140 < 3.2 < 4.2 .< 5.8 < 5.0 < 4.8 -< 4.1

< 4.7 La-140 < 3.7 < 4.8 < 6.7 < 5.7 < 5.5-

• 1.96 o (Due to counting statistics only.)

1

.i i .

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

, Collection Date: Aug 16, 23, 1986 Aug 30, Sep 6 ,1986 Sep 13, 20,1986 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 I-131 < 0.46 < 0.27 < 0.22 < 0.18 < 0.44 < 0.23 Cs-134 < 0.26 < 2.3 < 2.3 < 2.9 < 2.5 < 2.6 Cs-137 < 3.2 < 3.5 4.9 (4.1) < 3.5 4.3 (3.6) < 3.2 Zr-95 < 6.1 < 5.2 < 5.0 < 7.2 6.9 (7.5) < 6.5 Nb-95 < 2.3 < 2.2 < 2.1 < 2.6 < 2.4 < 2.4 Co-58 < 2.5 < 2.3 < 2.2 < 2.8 < 2.3 < 2.5 Mn-54 2.9 (3.2)* < 2.4 < 2.2 < 2.9 < 2.6 2.6 (3.1)

Zn-65 < 6.2 < 5.5 < 5.5 < 6.6 < 5.9 < 6.0 Fe-59 < 4.9 < 4.2 < 4.1 < 7.1 < 4.8 < 4.8 Co-60 < 2.7 < 2.4 < 2.3 < 3.1 < 2.8 < 2.8 U Ba-140 < 5.9 < 3.5 < 3.4 < 4.7 < 5.7 < 4.2 La-140 < 6.8 < 4.0 < 4.0 < 5.4 < 6.6 < 4.8

• 1.96 o (Due to counting statistics only.)

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

Collection Date: Sep 27, Oct 4, 1986 Oct 11, 18, 1986 Oct 25, Nov 1, 1986 Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 I-131 0.45 (0.54)* 0.38 (0.45) < 0.35 < 0.23 < 0.28 < 0.21 Cs-134 < 2.4 < 2.2 < 2.1 < 2.0 < 2.2 < 1.7 Cs-137 < 3.4 < 2.6 < 2.6 < 2.4 < 2.7 < 2.1 Zr-95 < 5.0 < 4.9 < 0.49 < 4.6 < 5.1 < 4.3 Nb-95 2.3 (2.6) < 1.8 < 2.0 < 1.8 < 1.9 < 1.6 3-Co-58 < 2.2 < 2.0 < 2.1 < 1.8 < 2.0 < 1.6 Mn-54 < 2.2 < 2.2 < 2.1 < 2.0 < 2.2 < 1.7 Zn-65 < 5.5 < 4.9 < 5.0 < 4.5 < 5.2 < 3.9 Fe-59 < 4.3 < 4.3 < 4.1 < 3.6 < 3.8 3.5 (3.9)

Co-60 < 6.9** < 2.3 < 2.3 < 2.1 < 2.4 < 1.8 e Ba-140 < 3.3 < 5.8 < 3.4 < 3.2 < 3.5 < 2.8 La-140 < 3.8 < 6.6 < 3.9 < 3.6 < 4.1 < 3.2

• 1.96 a(Due to counting statistics.)

• • Value is the result of second analysis.

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

Collection Date: Nov 8, 15, 1986 Nov 22, 29, 1986 Dec 6, 13, 1986 s

Radionuclide Gilcrest Ft. Collins Gilcrest Ft. Collins Gilcrest Ft. Collins R-6 R-3 R-6 R-3 R-6 R-3 I-131 < 0.43 < 0.34 < 0.37 < 0.42 < 0.49 < 0.43 ,

Cs-134 < 1. 6 < 1.9 < 2.6 < 2.4- < 1.8 2.5 (2.3)

Cs-137 < 2.0 5.2 (3.4) < 3.0 3.8 (4.2) < 2.2 3.1 (3.4)

Zr-95 < 3.8 4.6 (5.4) < 5.8 < 5.2 < 4.3 < 4.6 Nb-95 2.6 (1.8)* < 1.7 < 2.3 < 2.0 3.0 (2.1) < 1.6 gg

! Co-58 < 1.6 < 1.8 < 2.3 < 2.3 < 1.9 < 1.9

! Mn-54 1.9 (1.9) < 1.9 < 2.5 2.9 (2.8) < 1.9 < 1.9 Zn-65 < 3.9 < 4.5 < 5.9 < 5.4 < 4.3 7.2-(5.3)

Fe-59 < 4.1 < 3.7 < 4.6 <.16 < 3.7- < 3.9

) Co-60 < 1.8 < 10** '< 2.6 < 3.5** < 2.0 < 12**

l Ba-140 < 2.6 < 3.9 < 4.0 < 3.4 < 5.1 < 4.8 j La-140 < 3.0 < 4.5 < 4.6 < 3.9 < 5.8 < 5.5

• -1.96o (Due to counting statistics.)

• • Value is the result of a second analysis on sample.

~_ _

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

Collection Date: Dec 20, 27, 1986 Radionuclide Gilcrest Ft. Collins R-6 R-3 1-131 < 0.36 < 0.24 Cs-134 < 2.4 < 2.8 ,

Cs-137 4.5 (3.6)* < 3.4 Zr-95 < 6.1 < 7.2 Nb-95 < 2.3 < 2.6 og Co-58 < 2.4 < 2.6 Mn-54 < 2.5 < 2.8 Zn-65 < 5.8 < 6.7 Fe-59 < 5.8 < 11 Co-60 < 2.7 < 3.1

, Ba-140 < 4.0 < 4.4 La-140 < 4.6 < 5.1

• 1.96o -(Due to counting statistics.)

52

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 t

surface water sites. Most of the values were less than MDC. The 4

arithmetic mean value for the downstream locations in 1986 was not significantly different from the two upstream locations (Table II.H.2)

, even thougn there were elevated downstream values for the St. Vrain j

j Creek during September, October and November.

i The total liquid effluent release of tritium as tritiated water in 1986 (Table II.B.4) was greater-than in 1985, but nearly the same as in 1984. (The total release in 1986 was 127 Ci as compared to 16.6 Ci in 1985 and 137 Ci in 1984.) However, Figure II.C.1 shows that upstream, downstream and potable water mean values were nearly the same in 1986 as 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.

3 There were occasional positive values, but the mean of the downstream

! sites was not significantly different from the mean of the upstream i

sites during 1986 for any of the gamma-ray emitting radionuclides '

measured. This has been the case -since the inception of reactor operations at the site. _The occasional positive values are either fallout Cs-137 which can be expected, or values close to the uncertainty limits and assumed to be false positives.

53 In addition to the monthly sampling of the South Platte River and St. Vrain Creek, a continuous water sample is collected at station A-25. An aliquot of the farm pond outlet is sampled every 10 minutes and the composite collected weekly. The weekly composites are then combined and analyzed monthly. The results of these samples are shown in Table II.C.6. For every month there was evidence of measurable tritium release. Mean values for the other radionuclides were low and mostly less than MDC. The correlation with the effluent release report is high when the effluent is routed to the St Vrain Creek or to the South Platte River via the farm pond.

Ground water is sampled quarterly at two locations. These are at F-16, a well on the farm immediately north and the closest to the reactor down the hydrological gradient, and at R-5, the Ehrlich feedlot. Table II.C.7 lists the measured concentrations of fission products and activation products in ground water. The Cs-137 results are not surprising due to Chernobyl fallout and the other results above MDC are assumed to be statistically false positive values. The elevated H-3 result for F-16 during the fourth quarter warrants some discussion however. Usually the water sample is taken at the farm house well but the pump was inoperative, so the sample was taken at another well to the north insnediately adjacent to the Goosequill ditch. The tritium measured at this location was likely seepage due to the proximity of the effluent route. This water is not used for drinking purposes, however, and dose commitment calculations are not warranted. ,

l 1

I i

54 4

For comparison purposes, Table II.C.8 lists the Maximum Permissible Concentration values for each of the radionuclides listed in Tables II.C.5-7.

t I

1 4

4 1

i

)

4 y 1

1 I

i i

i t

}

J 4

L

Table II.C.4 Tritium Concentrations in Surface Water. (pC1/L)

Downstream Sites Upstream Sites Collection St. Vrain S. Platte St. Vrain S. Platte Date: 1986 F-20 R-10 A-21 F-19 Jan 11 < 240 < 240 < 240 < 240 Feb 9 < 240 < 240 < 240 < 240 Mar 8 < 240 < 240 < 240 < 240 Apr 12 260 (280) < 240 < 240 < 240 May 10 < 240 < 240 < 240 < 240 Jun 14 < 230 < 230 620 (280) < 230 Jul 12 < 230

< 240 < 240 < 230 i

Aug 9 < 230 < 230 < 230 230 (280)

Sep 14 860 (290) < 230 270 (280) 280 (280)

, Oct 18 380 (280) < 230 <.230 < 230

~

Nov 8 990 (280) < 230 < 230 < 230 Dec 13 < 230 270 ( 280) < 230 < 230

• 1.96o (Due to counting statistics only.)

l Table II.C.5 Radionuclide Concentrations in Surface Water. IpCi/L)

Collection Date: January 11, 1986.

Downstream Sites ' Upstream Sites Radionuclide St. Vrain S. Platte St. Vrain S. Platte F-20 R-10 A-21 F-19 kg Cs-134 < 2.8 < 1.8 < 2.7 2.2 (2.3)*

Cs-137 < 3.4 < 2.6 < 3.7 3.7 (2.8)

Zr-95 < 6.7- <.3.9 < 5.7 < 4.5 Nb-95 < 2.7 < 1.5 < 2.4 < 1. 9 Co-58 < 2.7 < 1.9 < 2.5 < 2.0 Mn-54 < 2.8 ' < 1.8 < 2.5 < 2.0 '

Zn-65 < 6.7 < 4.2 < 5.8 < 4.4 Fe-59 < 7.1 < 4.8 < 6.3 < 5.4 Co-60 < 3.0 < 1.8 < 2.5 < 2.1 Ba-140 < 6.5 < 5.2 < 5.3 < 3.2 La-140 < 7.5- < 6.0 < 6.1 < 3.6 ,

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

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

Collection Date: February 9,1986.

Downstream Sites Upstream Sites Radionuclide St. Vrain S. Platte St. Vrain S. Platte F-20 R-10 A F-19 Cs-134 < 2.3 < 2.9 < 2.4 < 2.1 Cs-137 < 2.9 < 4.2 < 3.1 < 2.6 Zr-95 < 5.6 < 6.4 < 6.3 < 5.0 on Nb-95 < 2.1 < 2.6 4.5 (2.8) < 2.0 Co-58 2.8 (2.7)* < 2.7 4.5L(2.9) < 2.1 Mn-54 < 2.4 < 2.9 < 2.5 < 2.1 Zn-65 < 5.6 < 6.4 < 5.8 < 4.8 Fe-59 < 5.6 < 6.6 < 6.0 < 5.5 -

'Co-60 < 2.5 < 2.9 < 2.7 < 2.3 Ba-140 < 3.9 < 4.9 < 4.1 < 5.4.

La-140 < 4.5 < 5.6 < 4.8 < 6.3

• 1.96 a (Due to counting statistics only.) .

. . .. _ _ - - _ - _ _ _ _ . . . a

1 s

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

Collection Date: March 8,1986.

Downstream Sites Upstream Sites Radionuclide St. Vrain S. Platte St. Vrain S. Platte F-20 R-10 A-21 F-19 Cs-134 < 2.1 <-2.3 < 3.4 < 3.7 .g-Cs-137 < 3.9 < 4.0 < 3.8 < 4.5 Zr-95 < 5.9 < 5.8 < 7.2 < 13' Nb-95. < 2.5 3.0 (3.3)* < 3.1 < 5.9

< 2.5 '3.2 (3.5) < 2.3 < 3.4 Co-58 Mn-54 < 2.5 2.7 (3.2) 3.7 (3.7) < 4.0 .

Zn-65 < 5.7 < 6.3 < 6.9- 21 (11)

Fe-59 < 4.8 < 5.4 < 5.7 < 12 Co-60 < 2.5 4.2 (3.2)- < 3.4 < 4.1:

Ba-140 < 3.7 < 5.2 < 6.2 **

La-140 < 4.3

. < 6.0 < 7.1 **

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

• • Elapsed time too long to achieve required LLD.

2

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

Collection Date: April 12,1986.

Downstream Sites Upstream Sites Radionuclide St. Vrain S. Platte St. Vrain S. Platte F-20 R-10 A-21. F-19 i

Cs-134 < 2.2 < 2.8 < 3.1 < 2.5 m-Cs-137 < 3.7 < 3.5 < 3.7 < 3.8 -

Zr-95 < 5.7 < 6.6 < 7.0 < 5.7 i

Nb-95 < 2.5 3.7-(3.0)* < 2.6 .< 2.2 Co-58 < 2.4 < 2.7 < 2.8 < 2.4 Hn-54 < 2.4 < 2.8 < 3.0 < 2.5 Zn-65 < 5.6 < 6.3 < 6.9 ~< 5.9 Fe-59 < 4.5 < 5.2 < 5.2 < 4.7 Co-60 < 2.6 < 3.0 3.1 (3.8) 3.2 (3.1)

Ba-140 < 3.7 < 5.8 < 5.6 < 3.7 La-140 < 4.2 < 6.7 < 6.4

. < 4.2

• 1.96 c(Due to counting statistics only.).

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

Collection Date: May 10,1986.

Downstream Sites Upstream Sites Radionuclide St. Vrain S. Platte St. Vrain S. Platte '

F-20 R-10 A-21 F-19 j Cs-134 < 3.4 < 2.8 < 3.7 < 3.4.

l Cs-137 < 4.3 4.4 (4.7)* < 4.6 < 4.3-l Zr-95 < 8.1 8.8 (7.1) < 9.3 < 8.2 i Nb-95 < 3.5 < 2.4 < 4.0 - < 3.6

Co-58 < 3.3 < 2.6 < 3.5

_ < 3.2 Mn-54 3.6 (4.0) 2.8 (3.3) < 3.8 < 3.5 g; Zn-65 < 7.2 9.3 (7.2) < 8.2 < 7.7 i Fe-59 < 5.9 < 6.2 < 6.5 < 6.0 i Co-60 < 5.0** < ?.7 < 4.2 < 3.8 j Ba-140 < 5.7 < 4.6- . < 6.1 < 6.4 La-140 < 6.6 < 5.2 < 7.1 < 7.4

• 1.96 o (Due to counting statistics.)

• • Value is the result of second analysis of sample.

l i

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

Collection Date: June 14, 1986.

Downstream Sites ' Upstream Sites

! Radionuclide St. Vrain S. Platte St. Vrain S. Platte F-20 R-10 A-21** F-19' Cs-134 < 2.9 < 3.1 < 3.1 < 2.9 Cs-137 4.6 (5.2)* < 3.6 < 3.7 < 3.5 Zr-95 < 6.8 < 7.3 < 7.3 < 7.0 Nb-95 < 2.6 < 2.7 3.2 (3.2) 4.8 (3.0) - cn .

Co-58 3.8 (3.5) < 2.8 < 2.9

< 2.8 Mn-54 < 3.0 < 3.0 < 3.1 < 2.9 Zn-65 < 6.7 < 6.9 < 7.1 < 6.7 Fe-59 < 5.5 < 5.6 < 5.4 < 7.1 Co-60 < 3.1 < 3.2 < 3.4 < 3.1 l Ba-140 < 4.4 '< 4.9 < 5.8 < 5.7 La-140 < 5.0 < 5.6 < 6.7 < 6.5

• 1.96 o (Due to counting statistics.)

• • Collected June 7,1986.

w

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

Collection Date: July 12, 1986.

Downstream Sites Upstream Sites Radionuclide St. Vrain S. Platte St. Vrain S. Platte F-20 R-10 A-21 F-19 Cs-134 3.2 (3.2)* < 2.4 < 2.5 < 2.7 g Cs-137 < 3.4 < 3.6 < 3.8 3.5 (3.9)

Zr-95 10 (8.3) < 5.3 < 5.6 < 6.3 Nb-95 < 2.6 2.6 (2.6) 2.5 (2.6) < 2.3 Co-58 3.6 (3.1) < 2.3 < 2.4 < 2.5 Mn-54 < 2.8 < 2.5 < 2.5 3.7 (3.2)

Zn-65 < 6.5 6.7 (6.7) < 5.8 < 6.1 Fe-59 < 5.2 5.7 (5.8) < 4.6 < 4.6 Co-60 < 2.9 < 2.4 < 2.6 < 2.8 Ba-140 < 4.5 < 3.5 < 4.8 < 4.3 La-140 < 5.2 < 4.1 < 5.5 < 5.0 1

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

4

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

Collection Date: August 9, 1986.

Downstream Sites Upstream Sites Radionuclide St. Vrain S. Platte St. Vrain S. Platte F-20 R-10 A-21 F Cs-134 < 2.4 < 2.4 < 3.0 < 2.4 Cs-137 < 2.9 < 2.9 < 4.6 < 3.6 Zr-95 < 5.7 < 5.6 < 6.8 < 5.6 Nb-95 < 2.2 3.9 (2.6) < 2.7 7.7 (2.8) . g3 Co-58 < 2.2 < 2.2 < 2.9 < 2.4 Mn-54 < 2.4 , < 2.4 < 3.0 < 2.4 Zn-65 9.9 (6.6) 11 (6.6) < 6.9 < 5.2 Fe-59 < 4.5 < 4.6 < 5.5 <-4.5 Co-60 < 2.6 < 2.6 < 3.0 < 2.3 Ba-140 < 3.8 < 3.8' < 4.6 < 3.7 La-140 < 4.4 < 4.4 < 5.2 < 4.2

• 1.96o (Due to counting statistics only.)

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

Collection Date: September 13, 1986.

Downstream Sites Upstream Sites  ;

Radionuclide St. Vrain S. Platte St. Vrain

. S.'Platte F-20 R-10 A-21 F-19  !

4 Cs-134 < 3.1 < 2.5 < 3.0 < 3.2 i '

Cs-137 < 3.8 3.5 (3.7)* < 3.9 < 4.0

~

~~

Zr-95 < 7.4 < 6.5 < 7.3 < 7.5 os y Nb-95 < 2.7 <-2.3 < 2.8 < 2.8 t Co-58 < 2.8 < 2.3 < 2.8 < 3.0 Mn-54 < 3.1 < 2.6 < 3.1 - < 3.2 -

Zn-65 < 7.5 < 5.9 < 7.3 < 7.3 Fe-59 I- < 6.0 < 4.9 < 5.6- < 5.6 Co-60 l < 3.4 . < 2.7 < 3.4 < 6.6**

Ba-140 l e 5.2 < 4.1 < 5.7 < 5.2-La-140 - 6.0' < 4.7 < 6.5 < 6.0 '

I

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

~

• • Value is the result of. second analysis of sample.-

T

. ~ _ _ . - _ ,-

.a

c. _

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

Collection Date: October 18, 1986 s z

Downstream Sites Upstream Sites' ,

ii-Radionuclide St. Vrain. S. Platte St. Vrain S. Platte F-20 R-10 A-21 .F /

Cs-134 < 1.5 < 1.8 <.2.3 < 1.9 Cs-137 2.8 (2.2)* .4.0 ( 3.2)' 4.4 (3.3) 3.0 ( 3.3)

Zr-95 < 3.8 < 4.1 -

< 5.5 ' < 4.2 Nb-95 < 1.4 < 1.6 <.2.1 'e < 1. 6 Co-58 < 1.4. < 1.8 < 2.1 < 1.8 Mn-54 < 1. 5 < 1.8 < 2.3 < 1. 9 e on 2n-65 <-3.5 < 4.2 < 5.2 < 4.3 Fe-59 < 2.9 < 4.4 '

< 5.8 < 4.4 .

Co-60 < 1.6 < 6.9** < 2.5 .< 7.7**

Ba-140 < 3.7 ~ < 2.7 .- < 3.7 < 3.4 La-140' < 4.3 < 3.1 '- '

< 4.3 < 3.9

• 1.96 o (Due to counting statistics.)

• • Value is the result of second analysis ~of sample.

k 4

y 1

1

_- __ _ .__ __ _ _ _ _ . - _ . . . _ . __ _ . _ . _ _ . __ m l

Table II.C.5 Radionuclide Concentrations in Surface Water. (pCi/L) l Collection Date: November 8, 1986 Downstream Sites Upstream Sites Radionuclide St. Vrain S. Platte St. Vrain S. Platte F-20 R-10 A-21 F-19 Cs-134 < 1.5 < 1.8 < 2.1 < 1.5 Cs-137 < 2.2 < 2.2 < 2.6 < 1.9 on Zr-95 < 3.2 < 4.1 < 5.0 < 3.5 Nb-95 < 1.4 2.1 (2.0)* 3.4 (2.2) < 1.4 C0-58 < 1.4 < 1.6 < 2.0 1.5 (1.7)

Mn-54 < 1.5 < 1.8. < 2.1 < 1.5 l Zn-65 < 3.4 < 4.1 < 5.0 < 3.4 Fe-59 < 3.5 < 4.5 < 5.1 < 3.9 Co-60 < 7.8** < 1.9 < 2.3 < 1.6 Ba-140 < 2.2 < 4.0 < 4.0 < 3.4 La-140 < 2.5 < 4.6 < 4.6. < 3.9

• 1.96 a (Due to counting statistics.)

• • Value is the result of second analysis of sample.

\

4 i

i i;

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

J Collection Date: December 13, 1986 I Downstream Sites Upstream Sites Radionuclide St. Vrain S. Platte St. Vrain S. Platte i F-20 R-10 A-21 F-19 i

Cs-134 < 1.9 < 2.8 < 3.1 < 3.0 Cs-137 < 2.8 < 3.4 < 3.7 8.6 (5.3)

• Zr-95 < 4.1 < 6.9 < 7.6 < 6.6 ,

Nb-95 < 1.7 < 2.4 < 2.7 < 2.7 Co-58 < 1.7 < 2.6 < 2.9 < 2.9 l Mn-54 < 1.9 < 2.8 < 3.2 < 3.0- .O Zn-65 < 4.2 < 6.5 < 7.7 < 7.0 Fe-59 < 3.6 < 5.2 < 5.7 < 5.6

. Co-60 < 7.0** < 3.1 < 3.3 < 11**

I Ba-140 - < 2.8 < 5.9 < 5.1 9.4 (6.5)

La-140 < 3.2 < 6.8 < 5.9 11 (7.4) ,

4 .

• 1.96 o-(Due to counting statistics.)

• • Value is the result of second analysis of sample.

t

[

i. .-.

- . _ . - . . -. _ _ _ . - _-. _ _ - _ _ - _ - - - .__ _ - ._ .. - = . .- .-- _.

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

Collection Year: 1986 Radionuclide January February March April May June Cs-134 < 1. 6 < 1. 7 < 1.0 < 2.3 < 1.9 < 1.8 Cs-137 < 2.5 2.8 (2.4) 2.4 (2.1) < 3.2 4.0 (2.8) 2.1 (2.5) ,

Zr-95 < 4.0 < 4.4 3.2 (3.9) < 4.9 < 4.4 < 4.7 Nb-95 < 1.9 2.2 (2.3) 2.9 (1.7) 4.5 (2.8) < 1.9 1.8 (2.1)

Co-58 < 1.8 < 1. 3 < 1. 2 < 2.1 < 1.8 < 1. 6 oS l Mn-54 < 1.7 < 1.7 < 1.2 < 2.2 < 1.9 < 1.8 Zn-65 6.8 (4.7)* < 3.9 < 2.8 5.6 (6.0) < 4.5 < 3.9 Fe-59 < 3.6 < 3.5 < 2.9 < 4.7 < 4.1 < 5.0 Co-60 1.9 (2.0) < 1.8 < 1.2 2.4 (2.6) < 2.0 < 1.9 Ba-140 < 3.2 < 5.4 < 1.7 < 3.1 < 6.5 < 6.2 La-140 < 3.7 < 6.2 < 2.0 < 3.6 < 7.4 < 7.1 I H-3 7,600 (360) 11,000 (400) 10,000 (390) 40,000 (590) 41,000 (600) 31,000 (540)

• 1.96o(Due to counting statistics only.)

l l

i i

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

Collection Year: 1986 Radionuclide July August September October November December Cs-134 < 2.2 < 1.9 < 2.2 < 1.5 < 2.1 < 1.2 Cs-137 5.7 (3.9)* < 2.9 5.8 (3.9) 3.7 (2.6) < 2.5 2.1 (1.8)

Zr-95 < 4.9 < 4.2 < 4.9 < 3.7 < 5.6 < 2.8 Nb-95 < 2.0 < 1.9 < 2.1 < 1.3 < 1.8 < 1.3 Co-58 < 2.1 < 1.8 < 2.3 < 1.4 < 1.9 < 1.4 Mn-54 l < 2.2 3.2 (2.3) < 2.2 < 1.5 3.0 (2.5) 1.3 (1.5) 3 Zn-65 < 5.1 < 4.3 5.1 (6.1) < 3.4 < 4.6 < 2.9 Fe-59 < 4.4 < 4.2 < 4.4- < 4.0 < 5.9 < 2.9 Co-60 < 2.2 < 1.9 < 7.2** < 6.9** < 2.2 < 1.3 l

Ba-140 < 3.2 < 2.8 < 3.2 < 2.2 < 3.2 < 6.1 La-140 -< 3.7 < 3.2 < 3.6 < 2.6 < 3.7 < 7.0 H-3 :L3,000 (410) 7,300 (360) 10,000-(380) 240 (280) 1,700 (300) 2,900 (310)

• 1.96 c(Due to counting statistics only.)

. ** Value is the result of second analysis of sample.

4 Table II.C.7 Radionuclide Concentrations in Ground Water. (pCi/L)

Collection year: 1986.

Radio- 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter nuclide F-16 R-5 F-16 R-5 F-16 R-5 F-16 R-5 Cs-134 < 1.7 < 3.0 < 2.6 < 2.6 < 2.0 < 2.1 < 2.6 < 2.4 Cs-137 < 3.0 < 3.3 5.5 (4.5) 4.6 (3.8) 4.4 (2.9) < 3.1 4.3 (3.8) 6.1 (4.3)

Zr-95 < 4.5 < 6.2 < 5.9 < 6.1 < 4.6 < 4.7 < 6.2 < 5.4 l Nb-95 < 1.8 5.8 (3.3) < 2.3 < 2.6 < 1.9 < 1.8 < 2.5 < 2.2 gj Co-58 < 1.9 < 1.8 < 2.4 < 2.4 < 1.8 < 2.1 < 2.4 < 2.3 Mn-54 < 2.0 < 2.6 < 2.5 < 2.6 < 2.0 < 2.0 4.2 (3.2) < 2.5 Zn-65 10 (5.5)* < 6.1 < 6.4 < 6.9 < 4.9 < 4.9 < 7.7 < 6.8 Fe-59 < 3.8 < 4.8 < 4.8 < 6.2 < 3.7 < 4.1 < 4.8 < 4.4 Co-60 < 2.0 .< 2.9 < 2.6 < 2.9 < 2.1 < 7.8** < 2.8 6.3 (3.1)

Ba-140 < 3.6 < 4.2 < 3.8 < 4.6 < 3.2 < 3.1 < 4.4 < 3.7

~

i La-140 < 4.2 < 4.8 < 4.3 < 5.3 .< 3.6 < 3.5 < 5.0 < 4.2 H-3 < 240 < 240 < 230 < 240 < 240 < 240 2800(310) < 230

• 1.96 o(Due to counting statistics only.)

• • Value is the result of second analysis of sample.

1 4

-71 Table II.C.8 Maximum Permissible Concentrations in Water.

(10CFR20, Appendix B, Table II) 6 H-3 3 x 10 pCf/L 2

'I-131 3 x 10 pCi/L 9 x 103pCi/L'

~

Cs-134 4

Cs-137 2 x 10 pCi/L 4

Zr-95 6 x 10 pCi/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

Zn-65 1 x 10 pCi/L 4

Fe-59 6 x 10 pCi/L 4

Co-60 5 x 10 pCi/L 4

Ba-140 3 x 10 pCi/L La-140 2 x 104 pCi/L

72 4

II.D. Milk i

j The dairy food chain is the critical pathway for possible radiation dose commitment around any nuclear facility. The critical ,

i individual would be an infant consuming milk produced from cows i

j grazing local pastures. Milk is the critical ~ pathway for possible j dose commitment to humans from environmental contamination of H-3,

, I-131, Cs-137 and Sr-90. For this reason milk is sampled extensively to document the presence or absence of radioactivity due to reactor 4

operations.

There are no daf ries (or personal milk cows) in the facility 1

area, 1.6 km radius. The six dairies in the adjacent area,1.6-8 km radius, were selected as they are located-in the highest x/Q areas 3

(Refer to updated FSAR). The description of these locations can be-i 4

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  ;

l,

predominant wind direction. Herd management practices are' virtually

identical at all dairy locations.

1 Table II.D.1 lists the concentrations of all radionuclides that i

j are investigated in milk samples. The major influence of j radioactivity in milk samples during 1986 was the contribution of Chernobyl fallout. 1-131, Cs-134 and Cs-137 were confirmed.in j tropospheric air by the week of May 10-17. I-131 was detected in milk

, samples as early as May 10 at site A-23. Peak milk concentration of

!l I-131 was observed also at A-23 on June 7. Evidently, the feeding '

! i

)

practices at this dairy included' grazing and/or feeding of fresh-cut

! forage. I-131, Cs-134 and Cs-137 was observed in milk samples from i all daf ries during the fallout period and the high variation in

73 1

1 concentrations is certainly due to differences in feeding practices.

Figure II.D.1 shows the mean Cs-137 milk concentrations from the adjacent dairies and the control dairy for 1986. Only the points above MDC are meaningful, however.

The elevated I-131 concentrations at dairy A-22 on August 16 and September 6 are assumed to be from I-131 present in surface water due to effluents from hospitals in Boulder and Denver. A-22 dairy uses j

irrigation ditch water for its herd rather than well water. The ditch (Independence) receives S. Platte water upstream of FSV. This observation was first made in 1985 and discussed at length in the 1985 final report.

K-natural, as measured by K-40, is very constant in milk. The mean literature value is 1.5 g/L. K concentrations are homeostatically controlled and independent of K intake. K-nat is measured in all milk samples as a quality control measure for the other radionuclides determined in the same sample by gama-ray spectrometry, but K-nat concentrations are no longer reported in Table II.D.1.

i Elevated tritium concentrations in milk due to reactor effluents have never been observed in the post-operational period of the reactor. This implies the tritium from reactor effluents is not contributing any radiation dose to humans via the milk pathway.

Tritium concentrations in milk should respond rapidly to changes in tritium concentrations of the forage water intake or drinking water intake to the cow. This is due to the short biological half-life for f, water in the cow (about three days for the lactating cow). As noted in previous reports, the reported tritium concentration in milk is the l

74 tritium in water extracted from the milk. Contamination of milk samples due to reactor effluents has never been observed during the pre-and operational periods of Fort St. Vrain.

l J

l I

i

.I f

l l

1 i

i a

1

....n,. . - ,,-

._..._._ _ _ _ ._._.___ . _ . _ _ . _ ~ . _ . . . _ . _ . _ . _ _ _ . . _ _ _ . . _ _ . . _ _ _ . . ._ _ _ _ . _ _ . _ _ _ _..

i 1

1 i .!

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

Year of Collection

1986 Radionuclide A-6 A-18 A-22 A-23 A-24 A-26 R-8

] Collection Date Jan 4 Jan 4 Jan 11 Jan 11 Jan 11 I-131 < 0.53 ** 0.50 (0.72)$ < 0.17 < 0.59 ** < 0.75 '

Cs-134 < 2.9 < 2.0 < 2.5 < 2.8 < 2.7 Cs-137 < 4.4 4.6 (5.3) < 3.8 < 3.4 < 4.0 Ba-140 < 1.4 < 6.6 < 3.7 < 7.0 < 6.0 La-140 < 1.6 < 7.6 < 4.2 < 8.1 < 6.9

H-3 < 240 < 240 < 240 < 240 < 240 4

Collection Date Feb 1 Feb 1 Feb 9 Feb 9' Feb 11 Feb 22 -y I I-131 < 0.43 ** < 0.39 < 0.48 < 0.26 < 0.34 < 0.28 -

Cs-134 < 2.9

< 2.1 < 2.4 < 2.1 < 3.5 < 3.0 .!

.Cs-137 < 3.5 < 2.5 < 2.8 3.8 (3.1) < 4.3 '7.9 (5.3)

Ba-140 < 4.6 < 3.4 5.3 (6.4) < 3.1 < 5.5 < 4.3 i La-140 < 5.3 < 3.9 6.1 (7.4) < 3.6 < 6.4 < 4.9 H-3 < 240 < 240 < 240 < 240 < 240 .< 240

$ Collection Date Mar 1 Mar 21 Mar 1 Mar 8- Mar 8 Mar 8 Mar 15

} I-131 .< 0.46 < 0.49 < 0.33 < 0.38 -< 0.22 .< 0.33 < 0.26 Cs-134 < 2.9 < 3.0 < 2.6 < 2.1 < 2.8 .< 2.9 3.1 (3.8)

Cs-137 < 3.5 .< 4.2 < 3.2 < 2.4 3.8 (4.3) < 4.3 4.0 (4.5) 4 Ba-140 < 5.4- < 4.3 < 4.2 7.3 (7.3) < 5.2- < 4.5 < 5.0 La-140 < 6.2 < 5.0 < 4.8 8.4 (8.4) < 5.9 < 5.2 < 5.8 H-3 < 240 <-240 .< 240 < 240 < 240 < 240 < 240 i

• 1.96 o(Due to counting statistics only.)

3

• • Sample unavailable, see milk write-up. .

7 l ,

1

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

Year of Collection: 1986 Radionuclide A-6 A-18 A-22 A-23 A-24 A-26 R-8 Collection Date Apr 19 Apr 12 Apr 12 Apr 12 Apr 12 Apr 19 Apr 19 I-131 < 0.27 0.49 (0.74) * < 0.46 < 0.40 < 0.36 < 0.32 < 0.37 Cs-134 < 2.8 < 2.7 < 3.2 < 3.3 < 2.2 < 3.1 < 2.9 Cs-137 < 4.3 < 3.9 < 3.6 < 3.6 9.1 (4.7) 4.3 (4.5) < 3.6 l Ba-140 < 5.2 < 3.8 < 4.7 < 5.2 < 3.8 < 5.8 < 4.6 La-140 < 5.9 < 4.4 < 5.4 < 6.0 < 4.3 < 6.7 < 5.3 H-3 < 240 320 (290) < 240 < 240 < 240 < 240 < 240 Collection Date May 24 May 17 May 3 May 10 May 3 May 3 May 3 gj I-131 8.1 (0.93) 48 (1.2) 0.84 (0.51) 2.8 (0.50) < 0.33 < 0.43 < 0.30 Cs-134 < 3.2 < 3.4 < 2.8 < 3.0 < 3.2 < 3.0 < 2.8-Cs-137 < 4.7 4.1 (4.9) 5.2 (5.0) < 4.4 < 3.8 < 3.8 < 3.4 Ba-140 < 4.8 < 5.3 < 4.1 < 4.3 < 5.7 < 6.4 < 6.0 La-140 < 5.5 < 6.1 < 4.7 < 4.9 < 6.5 < 7.3 < 6.9 l

H-3 < 240 < 240 < 240 < 240 < 240 < 240 < 240' Collection Date May 30 May 30 May 17 May 17 May 24 May 24 May 17 I-131 1.6 (0.70) 11 (1.7) 37 (1.1) 21 (8.7) 5.0 (0.55) 3.7 (0.59) 16 (0.75)

Cs-134 < 2.7 15 (3.6) 3.0 (3.4) < 3.2 < 3.5 < 3.3 3.4 (3.2)

Cs-137 < 4.0 40 (5.3) < 4.2 4.4 (4.4) < 4.3 5.2 (5.5) < 3.9 -!

Ba-140 < 4.6 6.4 (5.3) < 4.0 < 4.9 < 6.0 < 4.8 < 3.9 La-140 < 5.3 7.3 (6.0) < 4.6 < 5.6 < 6.9 < 5.5 < 4.5 H-3 < 230 < 240 < 240 < 240 < 240 < 240 < 240

• 1.96o (Due to counting statistics only.)

Table II.D.1. Radionuclide Concentrations in Milk. (pCi/L) i Year of Collection: 1986 Radionuclide A-6 A-18 A-22 A-23 A-24 A-26 R-8 Collection Date Jun 7 Jun 7 Jun 7 Jun 7 Jun 7 Jun 7 Jun 14 I-131 0.45 (0.45)* 37 (1.0) 43 (1.0) 86 (1.4) 1.4 (0.57) 23 (0.83) 33 (1.1)

Cs-134 < 3.1 12 (3.6) 15 (3.7) 40 (4.6) < 3.1 2.6 (2.9) 8.6 (4.2)

Cs-137 8.6 (5.3) 39 (5.6) 41 (4.5) 100 (7.2) 6.9 (4.4) 8.7 (4.4) 17 (5.0)

Ba-140 < 4.6 < 4.2 8.0 (7.4) < 5.4 < 6.0 < 3.5 < 6.9 La-140 < 5.3 < 4.8 9.1 (8.5) < 6.2 < 6.9 < 4.0 < 7.9 H-3 < 230 < 230 < 230 < 230 < 230 < 230 < 240 Collection Date Jun 22 Jun 22 Jun 22 Jun 28 Jun 22 Jun 22 Jun 28 :j I-131 6.6 (0.54) 12 (0.72) 4.2 (0.60) 3.3 (0.65) 14 (0.75) 1.6 (0.52) 7.3 (0.63)

Cs-134 12 (3.4) 11 (3.8) 2.0 (2.9) 14 (4.1) 4.7 (3.5) 3.1 (3.7) 6.6 (3.5)

Cs-137 26 (4.2) 24 (5.8) 7.1 (4.2) 37 (5.0) 17 (5.1) 7.2 (4.5) 18 (5.2)

Ba-140 < 4.2 < 4.9 < 3.9 < 5.0 < 5.0 < 4.9 < 4.8 La-140 < 4.9 < 5.6 < 4.4 < 5.8 < 5.7 < 5.7 < 5.5 H-3 < 230 < 230 < 230 < 240 < 230 < 230 250 (280)

• 1.96 o (Due to counting statistics only.)

4

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

Year of Collection: 1986.

Radio- A-6 A-18 A-22 A-23 A-24 A-26 'R-8 nuclide Collection Jul 15 Jul 12 Jul 12 Jul 12 Jul 19 Jul 5 Jul 12 Date I-131 < 0.35 1.2 (0.64) < 0.33 < 0.43 1.4 (0.58) < 0.39 2.5 (0.56)

Cs-134 9.6 (3.7)" 3.3 (4.0) 3.0 (3.5) 9.8 (4.5) 5.0 (3.7) < 2.7 7.1 (3.9)

Cs-137 23 (4.5) 18 (5.9) 9.0 (5.1) 26 (5.6) 11 (5.5) < 4.1 19 (4.8)

Ba-140 < 4.8 < 5.2 < 4.0 < 5.9 < 5.1 < 5.1 < 6.1 La-140 < 5.5 < 5.9 < 4.6 < 6.8 < 5.9 < 5.8 < 7.0 H-3 < 230 < 230 < 230 < 230 < 230 < 230' < 230 Collection Jul 26 Jul 26 Jul 26 Jul 26 Jul 26 Jul 19 Jul 26 Date gg I-131 < 0.47 < 0.41 < 0.43 0.58 (0.53) < 0.34 < 0.45 0.86 (0.6)

Cs-134 14 (3.8) 3.6 (3.5) 6.0 (3.7) 42 (4.1) 12 (3.8) < 3.2 8.9 (4.1)

Cs-137 22 (4.6) < 3.5 12 (4.6) 98 (6.2) 27 (5.7) < 3.9 20 (5.1)

Ba-140 < 4.8 < 4.5 .< 5.0 < 4.0 < 4.2 < 5.2 < 5.5 La-140 < 5.5 < 5.1 < 5.7 < 4.6 < 4.8 < 6.0 < 6.3 H-3 < 240 < 240 < 240 < 240 < 240 < 230 < 240 Collection Aug 2 Aug 2 Aug 2 Aug 2 Aug 9 Aug 16 Aug 2 Date I-131 < 0.45 < 0.36 1.8 (0.61) < 0.43 < 0.34 < 0.41 < 0.50 Cs-134 9.2 (4.9) 3.2 (3.6) < 3.4 31 (5.2) 10 (3.2) 5.8 (3.5) 8.4 (3.9).

Cs-137 26 (6.1) 12 (5.2) < 5.1 76 (8.0) 27 (4.8) 9.1 (4.4) 17 (5.0)

Ba-140 < 6.3 < 4.4 < 5.2 < 5.5 - 8.6 (6.8) < 5.9 < 5.2 La-140 < 7.2 < 5.0 < 6.0 < 6.4 9.9 (7.8) < 6.8 < 6.0 H-3 < 280 < 230 < 230 < 230 < 230 < 230 < 230

• 1.96o (Due to counting statistics only.)

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

Year of Collection: 1986.

Radionuclide A-6 A-18 A-22 A-23 A-24 A-26 R-8 Collection Aug 16 Aug 16 Aug 16 Aug 9 Aug 23 Aug 30 Aug 16 Date I-131 < 0.36 < 0.50 0.76 (0.59) < 0.46 < 0.36 < 0.36 < 0.33 Cs-134 16 (4.2)* < 3.3 5.6 (4.1) 3.6 (3.3) 8.4 (4.3) 5.6 (3.3) 8.2 (3.7)

Cs-137 33 (5.2) 6.5 (5.7) 22 (6.2) 18 (4.1) 24 (6.6) 16 (5.0) 23 (4.6)

Ba-140 < 5.4 < 4.8 < 4.8 < 4.4 < 5.6 < 3.8 < 5.7 La-140 < 6.2 < 5.5 < 5.5 < 5.0 < 6.5 < 4.4 < 6.5 H-3 < 230 < 230 < 230 < 230 < 240 < 240 < 230 Collection Sep 6 Sep 6 Sep 6 Sep 13 Sep 13 Sep 13 Sep 13 Date ,a e

I-131 0.54 (0.56) < 0.44 5.6 (0.58) < 0.27 < 0.46 < 0.29 < 0.45 Cs-134 6.3 (3.7) < 3.3 15 (3.7) < 2.9 9.9 (3.8) < 3.1 9.6 (3.4)

Cs-137 8.5 (4.5) < 4.0 42 (5.8) < 3.5 22 (4.8) 4.7 (4.4) 16 (5.1)

Ba-140 6.0 (7.1) < 5.8 < 4.2 < 4.7 < 4.9 < 6.3 < 4.0 La-140 6.9 (8.1) < 6.7 < 4.8 < 5.4 < 5.6 < 7.2 < 4.6 H-3 < 230 270 (280) 260 (280) 250 (280) 390 (280) < 240 < 230 Collection Sep 20 Sep 20 Sep 20 Sep 20 Sep 27 Sep 27 Sep 27 Date I-131 < 0.34 < 0.032 < 0.47 < 0.31 < 0.32 < 0.34 < 0.45 Cs-134 < 2.1 < 3.0 4.2 (2.6) < 3.3 11 (3.3) 2.6 (2.9) 9.2 (3.1)

Cs-137 12 (3.6) < 4.6 3.9 (3.3) < 4.0 16 (4.0) < 3.6 23 (4.6)

Ba-140 < 4.2 < 5.7 < 3.5 < 5.3 < 4.3 < 3.4 < 4.1 La-140 < 4.9 < 6.6 < 4.0 < 6.1 < 4.9 '

< 4.0 < 4.7 H-3 < 240 < 240 < 240 < 240 < 230 < 230 360 (280)

• 1.96 o (Due to counting statistics only.)

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

Year of Collection: 1986 Radionucli de A-6 A-18 A-22 A-23 A-24 A-26 R-8 Collection Date Oct 25 Oct 25 Oct 25 Oct 11 Oct 18 Oct 25 Oct 11 I-131 < 0.44 < 0.35 < 0.26 < 0.40 < 0.45 < 0.32 < 0.40 Cs-134 < 2.4 < 2.4 < 2.6 < 2.2 5.8 (2.8) < 2.6 6.2 (2.9)

Cs-137 6.3 (4.3)* < 3.0 4.4 (3.7) 3.8 (3.2) 17 (4.1) < 3.1 22 (4.4)

Ba-140 < 3.5 < 3.8 < 4.2 < 3.5 < 4.3 < 5.0 < 4.0 La-140 < 4.0 < 4.4 < 4.8 < 4.0 < 4.9 < 5.7 < 4.6 H-3 < 230 < 230 < 230 < 230 .< 230 < 230 < 230 Collection Date Nov 1 Nov 30 Nov 29 Nov 8 Nov 22 Nov 22 Nov 1 .g I-131 0.63 (0.53) < 0.34 < 0.40 < 0.35 < 0.23 < 0.20 < 0.46 Cs-134 < 2.4 5.1 (2.9) < 2.5 < 2.2 4.6 (3.6) < 2.6 8.4 (3.1)

Cs-137 7.8 (4.3) 3.8 (3.7) < 3.1 < 3.3 3.9 (4.5) 3.2 (3.8) 27 (4.7)

Ba-140 < 3.5 < 3.9 < 4.0 < 3.2 < 4.9 < 4.2 < 3.6 La-140 < 4.1 < 4.5 < 4.6 < 3.6 < 5.7 < 4.8 < 4.2 H-3 < 230 < 240 < 240 < 230 < 230 < 230 < 230 Collection,Date Dec 6 Dec 20 Dec 20 Dec 13 Dec 28 Dec 28 Dec 6 I-131 < 0.33 < 0.29 < 0.43 < 0.32 < 0.41 < 0.29 < 0.40 Cs-134 < 2.2 < 2.2 < 2.2 < 2.8 < 2.9 < 1.2 5.1 (3.0)

Cs-137 < 2.6 4.0 (3.9) < 2.8 6.5 (4.9) 8.1 (4.2) < 1.8 9.2 (3.8)

Ba-140 < 4.2 < 3.2 < 3.5 < 5.1 5.4 (6.1) < 1.7 < 4.6 La-140 < 4.9 < 3.6 < 4.0 < 5.8 6.2 (7.1) < 2.0 < 5.3 H-3 < 230 250 (280) < 230 < 230 < 230 < 230 < 230

• 1.96 o(Due to counting statistics only.)

Figure II.D.1  ?

81

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Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Months

82-I II.E. Food Products Food sampling locations were selected from areas possibly l irrigated by surface water downstream of the FSV discharge point or by-well water from the aquifer most likely to be contaminated.by seepage from the farm pond. The locations of these food product collection sites are described in Table III.B.1. One sample of each principal class of food products was collected from these locations. Locations 4 and available produce often change due to owner needs, harvest time,  !

i j harvest size, etc.

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

Table II.E.1 lists the results for the 1986 harvest. No significant l activity of any of the principal radionuclides was observed. The l gama-ray spectra were scanned for other radionuclides, but only the l naturally occurring were observed, presumably due to surface soil deposits. Since the harvest collection was approximately 120 days

] after the Chernobyl fallout first appeared in the area, all the I-131 i

j had decayed. It is somewhat surprising, however, that only Cs-137 was l detected and only in one food product.

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

Collection Date: September 16, 1986.

Location Food Type I-131 Cs-134 Cs-137 A-27 Green Beans < 21 < 21 < 34 R-14 Tomato < 25 < 21 35 (30)*

A-9 Watermelon < 7.5 < 7.8 < 11 R-13 Potatoes < 15 < 13 < 15 A-28 Yellow < 19 < 18 < 23 Squash A-8 Potatoes < 15 < 12 < 18 A-29 Spaghetti < 14 < 13 < 17 Squash R-16 Corn < 14 < 11 < 12 A-8 Pinto Beans < 12 < 12 < 13 R-13 Onions < 21 < 14 < 17

• 1.96 o (Due to counting statistics only.)

84 II.F. Aquatic Pathways Table II.F.1 1. hows radionuclide concentrations measured in fish samples collected it F-19, A-25 and R-10 on two dates in 1986. The fish were collected by electro-shocking and the composite sample was homogenized without cleaning and analyzed on a wet weight basis. The only significant radionuclide concentrations measured were of Cs-137.

This can be attributed to the Chernobyl fallout, as downstream or effluent concentrations were no different than upstream. The fallout Cs-134 concentrations were less than MDC levels. The other occasional positive values are considered to be methodological fluctuation (false positives). No positive I-131 concentrations were detected.

Table II.F.2 shows results for analysis of the cesium radioisotopes in surface sediment collected at R-10, a downstream location. No Cs-134 or 137 detectable concentracions were observed in the June 14 collection even though this was one month after the arrival of the Chernobyl fallout. The fallout was clearly demonstrable, however, in the sediment sample collected in October.

This delay is likely due to the time required for surface runoff to concentrate in stream sediment.

Monitoring for Corbicula Fluminea, a species of freshwater clam, was conducted at all fish sampling sites. These monitoring dates coincided with the fish collection dates. Corbicula have been introduced to North America from Asia. The freshwater clams are now found in large river systems in the U.S. from coast to coast. The Colorado Division of Wild 1tfe 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

85 samplings have indicated no evidence of Corbicula in any of the -

sampling sites of the reactor surface water courses.

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Table II.F.1 Radionuclide concentrations in Fish (pCi/g).

Collection Date First Half Jun 7, 1986 Second Half Aug 15, 1986 i

j Radionuclide Upstream Effluent Downstream Upstream Effluent Downstream l

F-19 A-25 R-10 F-19 A-25 R-10 l Cs-134 < 2.5 < 2.1 < 5.0 < 2.2 < 6.7 < 2.7 Cs-137 6.1 (3.6)* 8.2 (3.7) 15 (7.1) 8.9 (3.8) < 7.8 < 3.2 Co-58 < 2.3 < 2.0 < 4.4 < 2.0 < 6.0 < 2.5 Mn-54 < 2.5 < 2.0 < 4.9 < 2.1 < 6.5 < 2.8 l

Zn-65 < 6.0 < 5.1 < 12 10 (6.6) < 17 7.6 (8.1) i Fe-59 5.0 (5.8) < 4.2 < 9.9 < 4.0 < 12 < 5.0 Co-60 8.4 (3.4) < 2.4 < 5.2 < 2.5 9.1 (8.5) < 3.3

• 1.96 o (Due to counting statistics only)

[

'87 i 1 t Table II.F.2 Radionuclide Concentrations in Sediment from Location R-10. (pCi/kg)

I i

} Radionuclide First Half 'Jun 14, 1986 ,

1 Cs-134 < 0.039 Cs-137 < 0.037 i

Second Half Oct 18,1986

.1 i *

'j Cs-134 70 (41) i Cs-137 250 (44)

• i I

• 1.96 o (Due to counting statistics.)

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1

l 88 II.G Sample Crosscheck Program.

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

The U.S. Environmental Protection Agency (EPA) sponsored laboratory intercomparison studies program is the principal crosscheck. This involves the analysis of a variety of environmental media containing various levels of radionuclides. The media, type of analysis and frequency of analysis for the E.P.A. program are sununarized below .

Medium Analysis (radionuclide) Frequency Water H-3 triannually i

Water gross beta, gross alpha bimonthly Water Co-60, 2n-65, Cs-134 triannually Cs-137 Water I-131 semiannually

Air particulate Cs-137, gross beta, semiannually 4 filters gross alpha Milk I-131, Cs-137 triannually For each radionuclide analysis of a particular medium, three independent measurements are performed and all results are reported to the EPA.

Table II.G.1 gives the EPA crosscheck data for 1986. The EPA l uses the term, Estimated Laboratory Precision (ELP), calculated as one l

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89 i

standard deviation for one determination. The normalized deviation from the mean is calculated as:

CSU mean value - EPA known value a En~

Where: a = standard deviation of the mean of all participating laboratory results n = number of analyses by our laboratory, normally n=3 The control limit is determined by the mean range of all results

+ two standard deviations of the range. This is termed the warning level by EPA. If any result exceeds 2 standard deviations from the

mean the result is unacceptable. Whenever our mean value falls outside this limit the calculations are rechecked and the sample reanalyzed if possible. During 1986 all results except nine were within the warning level. The results exceeding the warning level have the notation (n) in Table II.G.I. The corrected values are shown in the Table. The recheck process and conclusion is given below for these samples.

(1) The analytical results were misrecorded on EPA form. A decimal point was misplaced.

(2) The error was due to improper correction of the contribution of 81-214 (a naturally cccurring radionuclide in background) to the Zn-65 spectrum region of interest. The 1.7632 MeV Ifne of Bi-214 was used instead to calculate the 4

contribution of Bi-214. The proper result was then obtained.

(3) The analytical results were misrecorded. The original analysis was correct.

90 (4) The June sample result was recalculated but the problem could not be identified. Due to I-131 decay the sample could not be reanalyzed. Both the February and October results were acceptable.

(5,6) Count yield for K-40 was in error. The count yield was redetermined from a new KC1 standard and this corrected the results to within control limits.

(7) Computer program for EPA results only was in error. This was corrected.

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 (except for one result) was acceptable.

Table II.G.3 lists the results of gross beta analyses of the split water samples. These results are acceptable.

Table II.G.4 shows results of an intralaboratory cross-check program. Replicate samples are independently analyzed. The replicate results are not statistically different and imply that the precision of the methods is acceptable.

~1 9

' Table II.G.'1. EPA Cross-Ch:ck Data Summary.- 1986 Radio- CSU. ' EPA 1 E.L.P.* ' ' Normalized Deviation -

Date nucli de - .Value .Value .from known**

-Water pCi/1 Feb 14 H-3' 5,500 5,227 '523 0.79-

.Jun 13 H-3 2,600 3,125 '360: - 2.72 Oct 17 H-3 5,400 5,973 597 - 1.50 Water'pCi/l Jan 24 Gross alpha 2.7 3.00 5.00 - 0.11.

Gross beta -7.0 7.00 5.00 0.0 Mar 21 Gross alpha 11 15.0- 5.00 - 1.27 Gross beta 6.3 8.00 5.00 - 0.58-May 23 Gross alpha 5.0 8.00 5.00 - 1.03 Gross beta 14 15.0 5.00 - 0.23 Jul 18 Gross alpha 4.0 6.00 5.00 - 0.69 Gross beta 14 (1) 18.0 5.00 - 1.38~

Sep 19 Gross alpha 13 (7) 15.0 5.00' - 0.69 Gross beta 7.0 8.00 5.00 - 0.34 Nov 21 Gross alpha 23 (7) 20.0 5.00 1.03 Gross beta 18 (7) 20.0 '5.00 - 0.69 Water pC1/1 Feb 7 Co-60 18 18.0 5.00 0.11 Zn-65 49 40.0 5.00 3.00 Cs-134 30 30.0 5.00 0.0 Cs-137 22 22.0 5.00 0.0 Jun 6 Co-60 63 66.0 5.00 - 0.92 Zn-65 83(2) 86.0 5.00 - 1.15 Cs-134 55 49.0 5.00 1.96 Cs-137 11 10.0 5.00 0.34 Oct 10 Co-60 31 31.0 5.00 0.11 Zn-65 83 85.0 5.00 - 0.81 Cs-134 24 28.0 5.00 - 1.5- ,

Cs-137 45 (3) 44.0 5.00 '0.46

• E.L.P. = Expected Laboratory Precision

• • Normalized Deviation = CSU Value - EPA Value , if this value falls a/(M1 between upper a lower warning levels', the accuracy is acceptable.

l 92

. Table II.G.1 EPA Cross-Check Data Sumary. 1986 l Radio- CSU EPA 1 E.L.P.* Normalized Deviation Date nuclide Value Value from known**

Water pCi/1 Apr 4 I-131 7.7 9.00 6.00 - 0.38 Aug 8 I-131 38 45.0 6.00 - 1.92 Milk pCi/1 Feb 28 I-131 8.7 9.00 6.00 - 0.~ 10 Jun 27 I-131 64 (4) 41 6.00 6.74 Cs-137 28 31 5.00 - 1.15 K-40 1,600 (5) 1,600 80.00 - 0.59 Oct 31 I-131 42 49 6.00 - 2.11 Cs-137 41 39 5.00 0.69 K-40 1,600 (6) 1,565 78.0 - 0.10-Air pCi/ Filter Apr 25 Gross alpha 13 15 5.00 - 0.58 Gross beta 42 47 5.00 - 1.73 Cs-137 14 10 5.00 1.50 Sep 12 Gross alpha 19 22 5.00 - 1.03 Gross beta 59 66 5.00 - 2.31 Cs-137 24 22 5.00 0.58 Blind Sample Oct 22 Gross alpha 33 40 5.00 - 2.54 Gross beta 50 (7) 51 5.00 - 0.23 i Co-60 26 24 5.00 0.81 Cs-134 9.0 12 5.00 - 1.03 Cs-137 11 8.0 5.00 1.15

• E.L.P. = Expected Laboratory Precision.

• • Normalized Deviation = CSU Value - EPA Value , if this value falls between upper & lower warning leve , the accuracy is acceptable.

i i

93 Table II.G.2 Tritium Crosscheck Analyses on Split-Water Samples Determined by Colorado State University, Colorado Department of Health, and Public Service Company. 1986

^

t Collection Sample Tritium Concentrations pCi/L Date Location CSU CDH PSC Jan 11 A-25 6,300 i 350 5,036 1 241 5,390 t 490 Jan 11 A-21 < 240 < 350 495 t 419~

Jan 13 E-41 < 240 < 350 461 t 418 Feb 8 A-25 8,000 1 300 5,893 1 226 12,300 1 571 Feb 8 A-21 < 280 < 350 < 348 Feb 3 E-41 < 240 < 350 3,130 1.456 Mar 8 A-25 4,100 t 300 4,284 i 412 4,260 i 746 Mar 8 A-21 < 280 t < 350 < 576 Mar 8 E-41 < 280 . < 350 < 576 Apr 12 A-25 57,000 t 690 52,320 i 507 55,400 1 855 Apr 12 A-21 < 240 885 1175 < 348 Apr 14 E-41 < 240 < 350 < 344 May 10 A-25 16,000 1 440 14,520 1 294 15,700 607 May 10 A-21 < 240 < 350 < 348 May 19 E-41 < 240 < 350 < 348 Jun 7 A-25 31,000 540 30,161 1.395 31,000 1 754 Jun 7 A-21 620 1 290 < 350 717 i 441 Jun 2 E-41 < 240 385 i 169 < 341 1

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\

la 1 - -

94 Table II.G.2 Tritium Crosscheck Analyses on Split Water Samples Determined by Colorado State University, Colorado Department of Health, and Pubite Service Company. 1986 Collection Sample- Tritium Concentrations pCi/L Date Location CSU CDH PSC Jul 12 A-25 -7,400 1 360 7,923 1 247 8,380 1 529 Jul 12 A-21 < 230 < 350 2,110 445 Jul 14 E-41 . < 230 < 350 < 345 Aug 9 A-25 9,300 1 370 9,152 1 258 10,5001 Aug 9 A-21 350 i 281 < 350 < 331 Aug 5 E-41 288 1 279 < 350 < 331 Sep 13 A-25 19,000 t 460 17,236 1 308 18,900 t 644 Sep 13 A-21 < 240 417 t 160 < 341 Sep 8 E-41 < 240 438 1 161 < 341 Oct 18 A-25 360 1 280 < 350 < 349 Oct 18 A-21 < 230 < 350 < 333 Oct 27 E-41 < 230 < 350 < 333 Nov 8 A-25 320 280 < 350 < 339 Nov 8 A-21 < 230 < 350 < 339 Nov 10 E-41 < 230 < 350 < 339 Dec 13 A-23 1,600 1 290 < 350 1,660 + 441 Dec 13 A-21 < 230 < 350 <345 Dec 8 E-41 < 230 < 350 < 346

d 95 Table II.G.3 Gross Beta Crosscheck Analyses on Split Water Samples Determined by Colorado State University, Colorado Department of Health, and

Public Service Company. 1986 Collection Sample Gross Beta Concentrations pCi/L Date Location CSU CDH PSC

~

~~Jan"11 A-25 13 t 5.4 40 t 6 8.83 t 9.32 Jan 11 A-21 6.5 i 5.2 12 4 < 7.10 Jan 13 E-41 19 i 5.7 11 t 4 7.17 t 9.11 Feb 8 A-25 11 1 5.2 10 4 < 6.86 Feb 8 A-21 16 i 5.5 14 t 11 18.3 i 10.1 Feb 3 E-41 10 t 5.2 11 t 4 10.6 t 9.37 Mar 8 A-25 7.7 i 5.2 13 t 4 < 7.72 Mar 8 A-21 6.9 t 5.1 8t4 9.73 t 10.2 Mar 8 E-41 7.5 t 5.1 10 t 4 < 7.79 Apr 12 A-25 33 t 6.3 21 t 5 30.3 i 10.3 Apr 12 A-21 14 i 5.4 7i4 11.2 1 8.96 Apr 14 E-41 9.7 5.2 6 4 13.6 t 9.16

, May 10 A-25 12

• 5.3 11 1 4 21.3 i 9.46 May 10 A-21 6.4 i 5.0 116 8 17.2 t 9.06 May 19 E-41 11 5.3 14 i 4 22.2 1 9.71 Jun 7 A-25 15 5.4 92 f.8 11.2 1 9.55 Jun 7 A-21 11 i 5.2 23 5 19.9 i 10.2 Jun 2 E-41 5.8 i 5.0 12 4 10.5 t 9.63 l

l l

96 Table II.G.3 Gross Beta Crosscheck Analyses on Split Water Samples Determined by Colorado State University, Colorado Department of Health, and Public Service Company. 1986 Collection Sample Gross Beta Concentrations pCi/L Date Location CSU CDH PSC Jul 12 A-25 9.2 5.2 6i4 11.1 8.88 Jul 12 A-21 10 t 5.4 13 i 4 13.6 t.9.37 Jul 14 E-41 5.0 t 5.1 814 10.4 1 8.84 Aug 9 A-25 9.4 t 5.3 9i4- < 7.57 Aug 9 A-21 17 i 5.8 12 i 4 18.4 i 10.9 Aug 5 E-41 12 5.5 7t4 15.9 1.10.2 Sep 13 A-25 11 i 5.4 10 i 4 14.9 i 9.47 Sep 13 A-21 5.9 i 5.2 - 8i4 15.9 i 9.64 Sep 8 E-41 8.0 5.3 <6 9.73 1 9.07 Oct 18 A-25 5.3 i 5.2 11 1 4 13.9 i 9.49 Oct 18 A-21 18 i 5.8 13 1 4 12.5 9.49 Oct 27 E-41 9.6 . 5.4 8i4 11.7 i 9.73 Nov 8 A-25 24 i 6.0 15 4 12.2 i 9.73 Nov 8 A-21 11 t 5.4 9t4 12.3 9.73 Nov 10 E-41 7.5 5.3 9 4 < 7.25 Dec 13 A-25 7.5 t 5.3 <6 < 6.75 l Dec 13 A-21 5.9 t 5.2 11 t 4 < 6.75 Dec 8 E-41 9.5 1 5.4 12 4 < 6.74 l

f I

l J

. 97 Table II.G.4- Intralaboratory Crosscheck Results. (pCi/L)

Collection Date: March 15, 22, 1986.

Drinking Water R-6 Radio-nuclide Analysis 1 -Analysis 2 Cs-134- < 2.0 < 2.4 Cs-137 5.4 (4.2)* < 4.3 Zr-95 < 5.5 7.2 (8.2)

Nb-95 6.2 (3.0) 4.9 (3.7)

Co-58 < 2.3 < 2.9 Mn-54 2.5 (2.8) < 2.8

< 7.3 Zn-65 < 5.9 Fe-59 < 4.5 < 5.6 Co-60 <-2.4 < 2.9 Ba-140 < 6.4 < 5.4

~

La-140 < 7.3 < 6.2 Gross Beta 5.4 (2.2) 2.5 (2.2)

H-3 < 240 290 (280)

Collection Date: March 8, 1986.

Milk A-23 Radio-nuclide Analysis 1 Analysis 2 Cs-134 < 2.3 < 2.2 Cs-137- < 3.9' < 2.4 Ba-140 6.6 (6.8) < 6.4 La-140 7.6 (7.8) < 7.3 H-3 < 240 < 240

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

4 y - - - - _ m--. - - --,y .-, - - . - - -,

98 Table II.G.4 Intralaboratory Crosscheck Results. (pCi/L)

Collection Date: June 7, 14, 1986.

Drinking Water R-6 Radio-nuclide Analysis 1 . Analysis 2 Cs-134 < 2.1 < 2.5 Cs-137 < 3.1 < 3.0

-Zr-95 < 4.8 < 5.9 )

Nb-95 < 2.0 < 2.2 Co-58 <-2.0 < 2.3 Mn-54 < 2.1 < 2.5 Zn-65 < 5.0 < 6.1 Fe-59 < 4.3 < 4.5 Co-60 < 2.2 < 2.7 Ba-140 < 5.1 < 5.3-La-140 < 5.9 < 6.1 ,

Gross Beta 4.2 (2.2)* 3.8 (2.2)

H-3 < 230 < 240 Collection Date: June 7. 1986.

Milk A-23 Radio-nuclide Analysis 1 Analysis 2 Cs-134 39 (3.9) 40 (4.6)

Cs-137 110 (6.1) 100 (7.2)

Ba-140 < 3.9 < 5.4 La-140 < 4.5 < 6.2 H-3 < 230 < 240 1 I

• 1.96 c(Due to counting statistics only.)

_ m q

99 Table II.G.4 Intralabirat:ry Crossch:ck R:;sults. (pCi/L)'

Collection Date: Srp 13 & 20. 1986.

Drinking Water R-6 Radio-nuclide Analysis 1 Analysis 2 Cs-134 < 2.5 < 2.4 Cs-137 4.3 (3.6)* 4.2 (4.2)

Zr-95 6.9 (7.5) < 5.5 Nb-95 < 2.4 < 2.2 Co-58 < 2.3 < 2.2 Mn-54 < 2.6 < 2.4 Zn-65 < 5.9 < 5.6 l

l Fe-59 < 4.8 < 4.5 Co-60 < 2.8 6.8 (2.9)  !

Ba-140 < 5.7 < 3.5 La-140 < 6.6 < 4.0 Gross Beta 11 (2.5) 4.7 (2.2)

H-3 < 240 < 240 Collection Date: Sep 13. 1986 Milk A-23 Radio-nuclide Analysis 1 Analysis 2 l Cs-134 < 2.9 < 2.5 l Cs-137 < 3.5 5.0 (4.4)

Ba-140 < 4.7 < 3.5 La-140 < 5.4 < 4.1 H-3 250 (280) < 240

• 1.96o Due to counting statistics only.

l i

100 Table II.G.4 Intralaboratory Crosscheck Results. (pCi/Li Collection Date: December 27, 1987 Drinking Water R Ka Gl o-nuclide Analysis 1 Analysis '2 Cs-134 < 2.4 < 2.9 Cs-137 4.5 (3.6) < 4.2 Zr-95 < 6.1 < 6.4' Nb-95 < 2.3 < 2.6 Co-58 < 2.4 < 2.7 Mn-54 < 2.5 < 2.8 Zn-65 < 5.8 j < 6.8 Fe-59 6.5 (5.6) I < 5.4 Co-60 < 2.7 3.7 (3.6)

Ba-140 < 4.0 < 4.3 La-140 < 4.6 < 5.0 Gross Beta 3.1 (2.2) 4.7 (2.2)

H-3 < 230 < 230 i

Collection Date: December 27, 1987 Milk A-24 Radlo-nuclide Analysis 1 Analysis 2 Cs-134 < 2.9 2.3 (2.5)

Cs-137 3.4 (2.3) < 2.6 Ba-140 5.4 (6.1) < 3.3 i

La-140 6.3 (7.1) < 3.8 H-3 < 230 < 230

• 1.96 cDue to counting statistics only.

i

101 II.H. Summary and Conclusions Table II.H.1 summarizes the radiation and environmental radioactivity measurements conducted during 1986 in the environs of the Fort St. Vrain Nuclear Generating Station, owned and operated by Public Service Company of Colorado. The values for each sample type may be compared to pre-operational and operational periods for this reactor, as well as to the values from other U.S. reactor monitoring programs. It must be emphasized, however, that the mean values in Table II.H.1 are only the means of the values greater than MDC, the statistically minimum detectable concentration. The range also is given only for detectable measurements. The mean and range values, therefore, are not the true means or ranges if any of the values in the sample population were less than MDC. The format of Table II.H.1 is a requirement of the NRC.

Inspection of Table II.H.1 reveals that there were no individual measurements except those due to Chernobyl fallout that exceeded the Reporting Level (RL) (See Table III.A.3). The Chernobyl fallout data was reported weekly to the NRC during the entire period.

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

a. None of the individual fission product or activation product radionuclides measured were significantly higher in the Gilcrest drinking water.

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

102 the only significant radionuclide measured in the air or water effluent from FSV. Since it is far more mobile than any of the specific radionuclides, if in the unlikely event that effluent activity were reaching the Gilcrest aquifer, elevated tritium concentrations would be the first and most sensitive indicator.

c. The city of Gilcrest does not filter and treat its water to the same degree as Fort Collins. This has been verified and evidenced by the fact that the gama-ray spectra of the suspended solids from Gilcrest water samples show elevated natural radionuclides. It has been concluded in previous reports that the elevated gross beta concentrations in Gilcrest water are due to elevated concentrations of the naturally occurring U-238, and Th-232 decay products. The suspended solids are higher in Gilcrest water samples due to less filtration of the water.

For the category of tritium in surface water, as has been the case since reactor operation, elevated concentrations were noted at station A-25, the outlet of the (Goosequill) farm pond. 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 fann pond water. Downstream surface water concentrations of tritium have occasionally been elevated, but there I is significant dilution before any human use of this water. During 1986 elevated tritium concentrations were observed downstream on

103 several occasions but the mean values for the first and second half of 1986 were not significantly greater'than in upstream surface water.

An historical summary of tritium concentration in upstream, downstream and potable surface water for six month periods from 1974 to 1986 is depicted in Figure II.C.1. The potable water concentrations plotted are those for the Gilcrest city water well.

I-131 was observed again in milk samples. Because the reactor did not' release any significant fission products during 1986, the source of the I-131 concentrations in afik could not be reactor effluent. It was noted in the 1985 annual report that the source of

. the I-131 concentrations during that year was not due to the reactor but due to nuclear medicine use and release upstream of the reactor.

This was an important observation as I-131 is certainly a critical radionuclide in human dose commitment possiblilties, a fact of which -

I the general public is aware. This discovery prompted increased monitoring for I-131. Upstream nuclear medicine releases of- I-131 is, therefore, a possible source of the I-131 observed again in milk samples during 1986. But this source was totally overshadowed in late

, spring and early summer by the Chernobyl source term. There was a significant input of I-131 to the FSV environs due to Chernobyl fallout during 1986. This produced elevated milk concentrations of I-131 which were very dependent upon herd grazing and feeding practices. There was, however, an indication of a small input of i I-131 due to nuclear medicine releases from the Denver and Boulder hospitals, i.e., I-131 concentration in A-22 late in the summer when the I-131 from Chernobyl had decayed.

i

104 Cs-137 and Cs-134 and other fission products were also observed in nearly all environmental samples due to the Chernobyl fallout.

Table II.H.2 presents an additional summary of mean values for selected sample types. The sample types and radionuclides were chosen 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.

The arithmetic means in Table II.H.2 were calculated for all sample results. It should be noted that the tabular data presented in the body of this report contain only positive calculated values. Any calculated 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 is equally true that many sample types do in fact have zero concentrations of certain radionuclides. Therefore, to obtain

105 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 j- be falsely biased high.

From log-nomal analysis of each data set for each 12 month period, the geometric mean and geometric standard deviations are also presented in Table II.H.2. The log-nomal probability treatment is to plot all data for each sample _ type over th'e year on log-probit l 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,gi , is detemined directly from the 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, og, is a multiplicative parameter to the geometric mean (i ig g). The area betweenig multiplied by og andi gdivided by o g should contain 68% 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

i i

. -- ..-. - ... . - . -.- _. . .- - -. .- . - - . - . , . . ~ .

106 ,

l

1. Tritium was the only radionuclide that was detected in significant concentrations in any of the effluent pathways that could be attributed to reactor operation. Since the tritium is released as tritiated water, the dilution by the surrounding hydrosphere is great.- Although in 1986 elevated concentration of tritiated water could be detected in

< downstream surface water samples, the mean values of downstream surface and Gilcrest drinking water 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.

2. Figure II.C.1 is a plot of tritium measured in surface water samples over the period 1974-1986. During the period the predominant source term is that of fallout deposition. There is some delay period in the peaks due to the mean residence time of tritium in the hydrosphere and input from other areas. Beginning in 1981, an increase can be observed in the downstream locations relative to upstream. This small

, increase is statistically significant, and slightly elevated mean3 H concentrations in the potable water at Gilcrest were noted in the period of 1981-1986. The dose commitment calculated as a result of possible ingestion of this drinking water was found to be negligible. This is discussed in

. Section II.C.1.

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

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

4. The fallout of fission products from the tropospheric debris produced by the Chernobyl reactor explosion and fire was evident in the FSV environs within 12 days after the accident. This was immediately detected as particulate radioactivity on the air sampler filters and as I-131 on the activated charcoal cartridges at all seven sampling stations.

Although the fission product activity ratios were slightly different than observed in the past from nuclear weapon testing, it was again documented that only I-131, Cs-134 and Cs-137 were transported to humans via the food chain. Milk was the most significant pathway for radiation dose to humans from the Chernobyl fallout.

The Chernobyl fallout has totally obscured what fission product debris has remained in the FSV environs from the October 1980 Chinese atmospheric nuclear weapon test. The biosphere will contain the Chernobyl fallout for an equally long period. Nuclear weapon test fallout has since the inception of the project been noted to be the predominant source tenn above natural background. It is the variation in fallout deposition, in addition to the variation in naturally occurring radionuclides, that mandates the large number of environmental samples to detect any possible radioactivity due to reactor effluents. A simple comparison of

108 pre-operational and operational values is of little value for most sample types because the fallout deposition was considerably greater during the pre-operational period.

5. The immediate detection of the critical fission products in the air and resulting deposition from the Chernobyl fallout assures that the environmental monitoring program is of adequate scope and sensitivity to detect any accidental releases from the FSV reactor operation. It can be concluded from the data collected by the environmental monitoring program that the radiation dose 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 rates and the dose commitment from atmospheric fallout.

1 i

Table II.H.1 Environmental Radiolo9 ical Monitoring Program Annual Sunnuary Fort St. Vrain Nuclear Generating Facility, Platteville Colorado Medium or Pathway Type and Facility Adjacent Locations with Highest Reference Number of .

Sampled (Unit of Total Number Locations Locations Annual Mean Locations Nonroutine measurement) of Analysis Mean (f)D Mean (f)b Name Mean (f)b Mean (f)b Reported Perfonned range range Distance & Range Range Measurements Direction Direct Radiation TLD (163) 0.43 (72/72) 0.43 (71/72) A-10 Old FSV 0.49~(4/4) 0.42 (20/20)

(mR/ day) (0.35-0.52) (0.31-0.59) Schgol7.8km (0.45-0.55) (0.34-0.49) 215 Air o Particulates Grosss(349) 44 (197/208) R-4 Dairy 54 (50/50) 51 (152/156)

(2.9-620) Store 20.5 km (12-690) (7.2-710) 3 2500 (fCi/m )

Gamma Spectrometry E$

Cs-134 (28) 6.7 (5/16) R-11 PSC 10(1/4) 9.8 (3/12)

(2.3-9.8) Garage 10.5 (9.6-10) km 3400 Cs-137 (28) 10 (6/16) A-19 Hunting 18 (1/4) 11 (5/12)

(1.6-18) Cabin (2.2-18)

Goosequill 1.7 km 50 Air, Charcoal I-131 (353) 150 (20/201) A-19 Hunting 180 (4/51) 160 (17/152)

(30-420) Cabin (63-420)

(pCi/m3 ) , ,

Goosequ111 1.7 km 50 Airo Atmospheric H-3 (356) 530 (41/206) F-16 3 Bar 560 (16/52) 380 (14/150)

(240-1300) Ranch 1.2-km (250-1300) (240-760)

WaterVgpor 00 (pCi/m )

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

Tabic 11.11.1 Enviroiimental lladiological Monitoring Program Annual Sunmiary Fort St. Vrain Nuclear Generating Facility, Platteville Colorado Medium or Pathway Type and Facility Adjacent Locations with liighest Reference flumber of Sampled (Unit of Total Number Locations Annual Mean Locations lionrou tine Locationg Reported measurement) of Analysis Mean (f) Mean (f)b Name Mean_(_f_)bMean (f)b Performed range range Distance & Range Range Measurements Direction Drinking Water R-6, Gilcrest 4.0 (26/26). 1.6 (26/26)

(pCi/L) Gross 8 (52) 4.0 (26/26)

(2.1-6.9) CityWateg (2.1-6.9) (0.58-7.3) 9.3 km 60 H-3 (52) 280 (2/26) R-6 Gilcrest 280 (2/26) 260 (1/26)

(270-280) City Water (270-280) 9.3 km 600 Gamma Spectrometry I-131 (52) 0.53 (2/26) R-6 Gilcrest 0.53 (2/26) 0.45 (3/26)

(0.45-0.61) City Water (0.45-0.61) (0.38-0.50) 9.3 km 600 Cs-134 (52) 3.4 (2/26) R-6 Gilcrest 3.4 (2/26) 2.8 (3/26)

(2.8-4.1) City Water (2.8-4.1) (2.5-3.2) 9.3 km 600 Cs-137 (52) 4.6 (8/26) R-6 Gilcrest 4.6 (8/26) 4.4 (6/26)

(3.7-5.4) City Water (3.7-5.4) (3.1-6.5) 9.3 km 60 0 Zr-95 (52) 6.9 (1/26)

R-6 Gilcrest 6.9 (1/26) 4.6 (1/26)

City Water 9.3 km 600 Nb-95 (52) 3.7 (6/26) R-6 Gilcrest 3.7 (6/26) 2.8 (5/26)

(2.3-6.2) CityWateg (2.3-6.2) (1.9-3.9) 9.3 km 60 b Fraction of detectable measurements at specified locations Mean and range based upon detectable measurements only.

is indicated in parenthesis. (f)

Table I1.11.1 Envirodmental Radiological Monitoring Program Annual Sunmary Fort St. Vrain Nuclear Generating Facility, Platteville Colorado Medium or Pathway Type and Facili ty Adjacent Locations with flighest Reference Number of Sampled (Unit of Total Number Location Locations Annual Mean Locations Nonroutine measurement) of Analysis Mean(f)g Mean (f)b Name Mean (f)b Mean (f)b Reported Perfonned range range Distance & Range Range Measurements Direction Drinkino Water Co-58 (52) 2.4 (2/26) R-6 Gilcrest 2.4 (2/26) 2.3 (1/26)

(2.0-2.7) City Water (2.0-2.7) 9.3 kn 600 Mn-54'(52) 2.8 (4/26) R-6 Gilcrest 2.8 (4/26) 2.8 (5/26)

(1.9-3.7) City Water (1.9-3.7) (2.6-3.1) 9.3 km 600 Zn-65 (52) 6.6 (2/26) R-3 Ft Collins 8.1 (6/26) 8.1 (6/26)

(5.4-7.7) CityWateg (6.6-11) (6.6-11) 45 km 330 Fe-59 (52) 4.9 (2/26) R-6 Gilcrest 4.9 (2/26) 4.4 (3/26) ll

~

(4.8-4.9) City Water (4.8-4.9) (3.5-5.0) 9.3 km 600 Co-60 (52) 4.2 (6/26) R-6 Gilcrest 4.2 (6/26) 3.7 (5/26)

(2.5-5.4) City Water (2.5-5.4) (2.3-5.0) 9.3 km 600 Ba-140 (52) 6.5 (1/26) R-3 Ft Collins 7.4 (1/26) 7.4 (1/26)

City Water 45 km 330 U La-140 (52) 7.4 (1/26) -

R-3 Ft Collins 8.5 (1/26) 8.5 (1/26)

City Water 45 km 3300 b Fraction of detectable measurements at specified locations.

Mean and range cased upon detectable measurements only.

is indicated in parentheses. (f)

0 Table 11.11.1 Enviroiimental Radiological Monitoring Program Annual Summary Fort St. Vrain Nuclear Generating Facility, Platteville Colorado Medium or Pathway Type and Facility Adjacent Locations with liighest Reference Number of Sampled (Unit of Total Number Location;; Locations Annual Mean Locations Nonroutine measurement) of Analysis Mean (f)D Mean (f)b Name Mean(f_)b Mean (f)b. Reported Performed range range Distance & Range Range Measurements Direction Surface Water H-3 (60) 10,000 (17/36) A-25 Goosequill 15,000 (12/12) 350 (4/24)

(240-41,000) 2.2 km 200 (240-41,000) (230-620)

(pCi/L) .

Gamma Spectrometry Cs-134 (60) 3.2 (1/36) F-20 St Vrain 3.2 (1/12) 2.2_(1/24) 1.5 km 3400 Cs-137 (60) 3.7 (13/36) F-19 S. Platte 2.2 (1/12) 4.6 (5/24)

, (2.1-5.7) 1.2 km 900 (3.0-8.6)

Zr-95 (60) 7.3 (3/36) F-20 St Vrain 10(1/12) < 13 (3.2-10) 1.5 km 3400 0 Nb-95 (60) 3.0 (9/36) F-19 S. Platte 6.2 (2/12) 4.4 (6/24)

(1.8-4.5) 1.2 km 900 (4.8-7.7) (2.5-7.7)

Co-58 (60) 3.4 (4/36) A St Vrain 4.5 (1/12) 3.0 (2/24)

(2.8-3.8) Bridge 2.4 km (1.5-4.5) 2200 Mn-54 (60) 2.8 (6/36) A-21 St Vrain 3.7 (1/12) 3.7 (2/24)

(1.3-3.6) Bridge 2.4 km (3.7-3.7)

.. 220 Zn-65 (60) 7.8 (7/36) F-19S.Pfatte 21 (1/12) 21 (1/24)

(5.1-11) 1.2 km 90 Fe-59 (60) 5.7 (1/36) A-21 St Vrain 5.7 (1/12) < 12 bridge 2.4 km 2200 b F'raction of detectable measurements at specified locations Mean and range based upon detectable measuremunts only.

is indicated in parentheses. (f)

. . -_.4m... 6.i-, e

-.-L.'4 . -4h e -Ah4A -4,4 4,&. h+A42i e & *e+w u. ii. as e a -. 4.- - _.,4

-- L *E.ee.W Table 11.11.1 Environmental Radiological Monitoring Program Annual Sunmary Fort St. Vrain Nuclear Generating Facility, Platteville Colorado Medium or Pathway. Type and Facility Adjacent Locations with Highest Reference Number of Sampled (Unit of Total Number Locations Locations Annual Mean Locations Nonroutine measurement) of Analysis Mean (f)D Mean (f)b Name Mean (f)b Mean (f)b Reported Performed range range Distance & Range Range Measurements Direction Surface Water Gamma Spectrometry (pCi/L)

Co-60 (60) 2.8 (3/36) R-10 S. Platte 4.2 (1/12) 3.2 (2/24)

(1.9-4.2) atg06010km (3.1-3.2) 290 Ba-140 (60) < 6.5 F-19 S. Platte 9.4 (1/12) 9.4 (1/24) at dam 1.1 km 90 0 La-140 (60) < 7.5 F-19 S..Platte 11 (1/12) 11 (1/24) b at dam 1.1 km 900

' Ground Water H-3 (8) 2,800(1/4) F-16 3 Bar 2,800 (1/4) < 240 (pCi/L) Ranch 1.2 km 00 Gamma Spectrometry Cs-134 (8) < 2.6 -- -- .

< 3.0 Cs-137 (8) 4.7 (3/4)

R-5 Erlich 5.4 (2/4) 5.4 (2/4)

(4.3-5.5) Feedlot (4.6-6.1)- (4.6-6.1) 8.7 km 25 0 Zr-95 (8) < 6.2 -- --

< 6.2 Nb-95 (8) < 2.5 R-5 Erlich 5.8(1/4) 5.8 (1/4)

Feedlot

~~

. 8.7 km 25 Mean and range based upon' detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis. (f)

Table 11.11.1 Environmental Itadiological Monitoring Program Annual Sunniary-Fort St. Vrain Nuclear Generating Facility, PlaLLeville Colorado i Medium or Pathway Type and l'acili ty Adjacent Locations with liighest Reference. Ilumber of. ,

Sampled (Unit of Total Number Locations Locations Annual Mean Locations Nonrou tine measurement) of Analysis Mean (f)U Mean (f)b Name Meaii (f)b Mean (f)b Reported Perfonned range range Distance & Range Range Measurements Direction Ground Water (pCi/L) '

Gamma Spectrometry i Co-58 (8) <2d -- -. < 2.4 Mn-54 (8) 4.2 (1/4) F-16 3 Bar 4.2 (1/4) < 2.6 Ranch 1.2 km ,

00 -

Zn-65 (8) 10 (1/4) F-16 3 Bar 10 (1/4) < 6.9 5 i Ranch 1.2;km 00 Fe-59 (8) < 4.8 - - --

< 6.2 Co-60 (8) < 7.8 R-5 Erlich 6.3 (1/4)' 6.3 (1/4)

Feedlot 8.7 km 25

< 4.4 < 4.6

~

Ba-140 (8) -- -- .

La-140 (8) < 5.0 . -- .

< 5.3 b

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

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 Sampled (Unit of Total Number Location Locations Annual Mean Locations Nonroutine measurement) of Analysis Mean(f)g Mean (f)b Name Mean (f)b Mean (f)b Reported Perfonned range range Distance & Range Range Measurements Directio:

Sediment (pCi/kg, dry) Cs-134 (2) R-10 S. Platte at- 70 (1/2) 70 (1/2)

C0-60 10 km 2900 Cs-137 (2) R-10 S. Platte at 250 (1/2) 250 (1/2)

C0-60 10 km 2900 Milk (pCi/L)

H-3 (120) 290 (6/99) A-24, Marostica 390 (1/17) 310 (2/17) -

(250-390) Dgiry 6.9 km (250-360) 0; 0

Gamma Spectrometry I-131 (120) 12 (31/99) A-23 Leroy Oden- 23 (5/17) 12 (5/17)

(0.45-86) baugh Dai5 y ( .58-86) (0.86-33) 4.1 km 90 Cs-134 (120) 9.9 (41/99) A-23 Leroy Oden- 23 (6/17) 7.1 (13/17)

(2.6-42) baughDaigy (3.6-42) (3.1-9.6) 4.1 km 90 Cs-137 (120) 18 (60/99) A-23 Leroy Oden- 46 (8/17) 17 (13/17)

(3.2-100) baugh Dai y (3.8-100) (3.4-27)

S 4.1 km 90 Ba-140 (120) 6.7 (7/19) A-18 Boos Dairy 6.4 (1/15) < 6.9 (5.3-8.6) 4.7 km 20 La-140 (120) 7.7 (7/99) A-18 Boosg Dairy. 7.3 (1/15) < 7.9 (6.1-9.9) 4.7 km 20 Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses. (f)

Table II.ll.1 Enviro'dmental Radiological Monitoring Program Annual Summary Fort St. Vrain Nuclear Generating Facility, Platteville Colorado Medium or Pathway Type and Facility Adjacent Loc'a tions with Highest Reference Humber of Sampled (Unit of Total Number Locations Locations Annual Mean Locations Nonrou tine measurement) of Analysis Mean(f)b Mean (f)b Name Meaii (f)b Mean (f)b Reported Performed range range Dis tance & Range Range Measurements Direction Food Products Gamma $pectrometry (pCi/kg, wet)

I-131 (10) < 21 --

< 25 Cs-134 (10) < 21 --

< 21 Cs-137 (10) < 34 R-14 S. Ibarra 35(1/5) 35 (1/5)

Garden 12 km 350 _

Fish Gamma Spectrometry -

(pCi/kg, wet) 5; .

Cs-134 (6) < 2.5 < 6.7 --

< 5.0 Cs-137 (6) 7.5 (2/2) 8.2 (1/2) R-10 S. Platte 15 (1/2) 15 (1/2)

(6.1-8.9) at C060 10 km 290U Cs-58 (6) < 2.3 < 6.0 --

< 4.4 Mn-54 (6) < 2.5 < 6.5 --

< 4.9 Zn-65(6) 10 (1/2) < 17 F-19S.Plattelg(1/2) 7.6 (1/2) at dam 1.1 km 90 Fe-59 (6) 5.0 (1/2) < 12 F-19 SA Platte 5.0 0

(1/2) < 9,9 at dam 1.1 km 90 Co-60 (6) 8.4 (1/2) 9.1 (1/2) A-25 9.1 (1/2) ' < 5.2 GgosequillPond2.2km 0

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

Table II.H.2 Summary Table of Geometric Means, Geometric Standard Deviations and Arithmetic Means for Selected Sample Types.

1983 _ _

1984 _ _ 1985 _ _ 1986 _

X o X X o X X o X X o X g g g g g g Atmospheric Water Vapor (pCi/L)

H-3 Facility 250 2.5 140 250 2.2 300 200 1.0 < 250 220 2.1- < 240 Reference 210 2.5 53 310 2.4 260 190 1.1 < 250 180 ~2.4 < 240 Air (fCi/m3)

Gross Beta i Facility 14 1.8 16 15 1.7 17 27 1.0 28 29 2.0 44 Reference 13 1.9 16 16 1.6 18 25 1.0 27 31 2.0 51 1-131 Facility ** ** ** 22 3.7 < 35 11 1.1 < 43 18 2.5 la Reference ** ** ** 22 3.4~ 1.1 13 1.1 < 36 16 5.5 19 Cs-137 Facility ** ** ** 6.0 2.6 0.67 1.7- 1.3 < 4.4 2.5 3.3 4.1 Reference ** ** ' ** 5.9 '3.0 < 30 2.1 1.2- < 4.4 2.0 4.7 4.5

• • Not available.

Table II.H.2 Summary Table of Geometric Means, Geometric Standard Deviations and Arithmetic Means for Selected Sample Types.

1983 _ _

1984 _ _

1985 _ _

1986 _

X a X X og X X o X X g g g g g Kg og Sample Type Drinking Water (pCi/L)

H-3 Composite 350 1.9 310 ** ** ** **- ** ** ** ** **

Gilcrest ** ** ** 300 1.6 200 190 1.1 160 130 2.9 < 240 ::

• • ** ** 250 2.2 76 180 1.0 <250 1.4 Ft. Collins 210 < 240 03 Gross Beta Composite 6.4 1.5 6.2 ** ** ** ** ** ** ** . ** **

Gilcrest ** ** ** 7.7 1.4 8.0 4.8- 1.0 5.2 3.8 1.4 4.0 Ft. Collins ** ** ** 1.7 2.3 2.3 1.0 1.1 1.2 1.3 1.9 1.6 I-131 Gilcrest ** ** ** 0.43 3.7 0.50 0.17- 1.3 0.0042 0.19 2.4 0.14 Ft. Collins ** ** ** 0.34 4.1 0.50 0.18 1.0 0.077 0.25 1.7 < 0.49 Cs-137 Composite 0.90 3.1 1.3 ** ** ** **- ** ** ** ** **

Gilcrest ** ** ** 2.5 3.0 1.6L 1.8 1.1 1.5 2.6 2.1 1.4 Ft. Collins ** ** ** 4.1 2.3 2.8~ 1.4 1.1 1.7 2.0 -3.3 1.3

• • Not available.

Table II.H.2 Summary Table of Geometric Means, Geometric Standard Deviations and Arithmetric Means for Selected Sample Types 1983 1984 1985 1986 i o i i o i Rg o R- S g o i g g g g g Surface Water-(pCi/L)

H-3 Effluent 560 4.5 4,600 8,300 4.4 13,000 1,300 1.3 2,700 7,800 4.3 15,000 Downstream 320 3.4 530 340 1.8 ~220 190 1.1 91 180 3.3 72 Upstream 250 2.0 230 280 2.4 140 140 2.0 < 250- 230 1.4 < 240 e

Cs-137 U$

Effluent 1.6 2.3 0.63 3.4 2.5 0.83 2.2 1.2 1.4 2.8 1.6 2.8 Downstream 1.0 3.3 0.98 2.8 2.5 0.57 2.2- 1.1 2.1 1.8 2.5 1.7 Upstream 1.4 2.7 2.0 3.2 2.9- 1.8 1.9 1.3- 1.3 1.9 3.1 1.5-Milk (pCi/L) '

H-3.

Adjacent 180 2.8 < 300 200 2.1 < 300 170 1.1 < 250 190- 1.8 < 240 Reference 260 1.7 < 300 200 1.7 < 300 190 1.1 <.250 140 3.6 < 240 I-131 Adjacent ' O.63 4.5 < 0.12- 0.75 2.3 < 0.50 0.22 1.0 0.017 0.46 12 3.9 Reference 0.53 4.4 < 0.14 '0.60 2.9 <-0.50 0.21 1.1' O.47 0.68 5.9- 3.8-

'Cs-137 Adjacent - 0.25 2.3 < 0.72 1.3 3.6 < 9.0 2.1- 1.0 1.7 5.8 3.4 . 11 Reference. 0.20 1.6 < 0.13 1.1 5.3 < 9.0 1.9- 1.2 .1.6 7.6 4.2- 13

• • Not available

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i g i e6 l W U .Ua

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N OO es aE 30 e *

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0 C ==

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es N 7 - O= >= == c= 0c CT C 2 ED M *a *g a

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9

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T 4

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

Analysis Water Airborne Particulate Fish Milk Food Products Sediment (pCi/L) or Gas (fCi/m 3 ) (pCi/kg, wet) (pCi/L) (pCi/kg, wet) (pCi/kg. dry)

Gross Beta 3.86 3.25 H-3 -494 I-131 0.89 66.4 0.89 56.8 Cs'-134 5.58 8.06 19.5 4.98 44.4 90.6 Cs-137 6.68 7.86 18.5 6.14 44.6 100 Zr-95 10.12 Nb-95 4.12 y Co-58 4.60 12.8 m-Mn-54 4.68 12.7 2n-65 10.94 23.6 Fe-59 8.40 31.4 Co-60 4.40 14.5 Ba-140 6.66 8.00 La-140 7.66 9.16

• As. suggested in NUREG-0472. 'All values are at or below values listed in Table 8.2-2 of technical specifications.

t 123 i

a C

a- N m-M

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C>

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c X X X F* w N .

h. .E.

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C.

n 1, O C

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= 8-W C C

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f.

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is N. -

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=h a W O C C O f'% e= w *

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< = C 6 O O N _C - 0 0 C

Table III.B.1 Radiological Environmental Monitoring Program (continued)

Sampling Site Descriptions (F: Facility Area 0-1.6 km. A: Ad.jacent Area 1.6-8km. R: ' Reference Area) ,

Exposure Site No. Location Description (see map) Sector Distance, Pathway km Direct Radiation F-1 Pole by gate to Goosequill road on dirt extension of 1 1.3 CR 21.

F-2 21st pole N of ditch on dirt extension of CR 21 just 2 1.1 before road drops down to river bottom.

F-3 .

17th pole N of ditch on dirt extension of CR 21 or 3 0.7 first pole N of E-W road F-4 15th pole N of ditch on dirt extension of CR 21, S of 4 0.7 pump road, midway between F-3 and F-5.

F-5 lith pole N of ditch on dirt extension of CR 21, near 5 0.6 drive to pump house. ,,

F-6 8th pole .lj of ditch on dirt extension of CR 21, 6 0.8 of E-W concrete ditch, S pf bridge.

F-7 Old dairy _ barn,1st pole N after crossing ditch on 7 1.2' dirt extension of CR.21.

F-8 1st pole W of pump house on N side of road 0.4 km E 8 1.3 of CR 191/2.

F-9 Pole E of first shed at intersection of CR 19.1/2 9 1.5 and CR 34.

F-10 Pole on NW corner of int rsection of dirt extension 10 .1.5 of CR 19 and 34.

n g , ..

Table III.D.1 Radiological Environmental Monitaring Program (continued) ,

Sampling Site Descriptions .

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

Exposure Site No. Location Description (see map) . Sector Distance,

. Pathway km Direct Radiation F-11 7th pole N of intersection of dirt extension of CR 19 11 1.2 4 with CR 34.

F-12 Pole on SE corner of corral across from Aristocrat 12 1.0 Brangus. office.

F-13~ Take first dirt road S of Visitor Center toward W. 13 0.5' M

' On metal staircase going down off dike.

F-14 2nd . pole 0.1 km S intersection CR 361/2 & Rd 19. 14 1.5 F-15 2nd pole 0.7 km S of intersen, tion of CR 38 on CR 19. 15 . 1.5

! F-16 Pole at NE corner of- potato cellar at 3 Bar Ranch 1 1.2

- (Russell 's) . ,,

F-17 Visitor Center, on N end of cross beam over entrance. 13 0.2 F-18 Pole closest to house on SW corner,17250 CR 191/2. 16 0.8 l .

• I'o e

Table 111.0.1 Radiological Environmental Monitoring ~ Program (continued)

Sampling Site Descriptions (F: Facili ty Area 0-1.6 km. A: Adjacent Area 1.6-Okm. R: Reference Area) ,

Exposure Site No. Location Description (see map) Sector Distance, Pathway km Direct Radiation A-1 Pole on NW corner of intersection of CR 44 and CR 21. 1 6.7 A-2 Pole on NE corner intersection of CR 42 and CR 251/2. 2 6.8 A-3 Pole on NE corner of intersection of CR 42 and C0 60. 3 7.5 A-4 .lst pole NE of intersection of CR 29 and CR 38, take 4 7.4 CR 29'E out of Gilcrest to CR 30. -

S$

A-5 SE corner of CR 34 and CR 29. Taped to road sign on 5 7.2 SW corner of intersection.

Pole on S side of CR 32 near drive to dairy 13278 CR A-6 6 7.1

32. ..

A-7 Niles Miller dairy. 0.4 km E of US 85 on CR 30. 7 7.3 A-8 On CO 66 (CR30) farm on S iide of road (address 9476) 8 4.7 Pole in front of house.

A-9 Corner of C0.66 (CR 30) and CR 19, Miller produce 9 4.6 stand, pole on SW corner of intersection.

A-10 Pole on SE corner at intersection CR 261/2 & CR 15. 10 7.8 A-11 At intersection of CO 66 and CR 13, 2nd pole N of 11 7.2 Corner.

6

J .

Tabic III.D.1 Radiological Environmental Monitoring Program (continued)

Sampling Site Descriptions (F: Facility Area 0-1.6 km. A: Adjacent Area 1.6-8km. R: Reference Area)'

s Exposure Site No.

, Pathway Location Description (see map) Sector Distance, km

-Direct Radiation A-12 On CR 34, pole E of house N of Lake Thomas 2 km from - 12

'I-25. 7.2

'A-13' Pole opposite lake, N of silage pits E side of CR 13 13 5.8 2.9 km N of CR 34.

A-14 Intersection of CR 13 and CR 40, NW corner. 14 6.9 A-15 Intersection of CR 42 and CR 15, NW corner.

l -

15 6.7

) A-16 Intersection of CR 44 and CR 19, SW corner.

16 6.8 A-17 - Platteville school (S edge of town on Main St.)

pole on NW corner just outside school, . intramural 5.9 fiel d. -

A-20 1st pole.N of "KS" farm sign on S end of building' 9. 2.5 parallel with CR 19 (turkey farm).

=

7 e*

4 e'

~~

l Radiological Environmental Monitoring Program (continued) ,

Table III.B.1 Sampling Site Descriptions (F: Facility Area 0-1.6 km. A: Adjacent Area l'.6-8km. R: Reference Area)

Sector Distance, km Exposure Site No. Location Description (see map)

Pathway Direct Milliken School, on CR 21 1/2, pole in Lola park 9.3 Radiation R-1 at SW corner of school yard.

Johnstown School (Letford Elementary), pole on S end 10.8 R-2 of drive. School off Idaho St. on W side of town.

CSU dairy farm on W Drake, N of Vet Hospital, Ft. 45.1 R-3 Collins, CO. Pole is E of hay barn next to railroad tracks.

Air sampler corner US 28f and C0 66, Longmont 20.5

! R-4 Dairy Store. .

Dehind Gilcrest School quonset auditorium, pole 9.3

- R-7 on SW end of school property, just before garage.

l i -

9

Table II!-8.1 Radiological Environmental Monitoring Program (continued) ,

-Sampling Site Descriptions ,

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

Exposure- Site No. Location Description (see map) Sector Distance, Pathway km Airborne F-7 Farm at intersection of CR 21 and CR 34. Silica gel 7 1.5

'inside building on N end of workbench.

.F-9 First shed along drive at end of Rd 191/2 9 1.5 intersection with Rd 21. Silica gel is located in shed. Hygrothermograph is located in corral area W of shed.

F-16 Potato cellar at 3 Bar Ranch (Russell's). Silica gel 16 1.2 -

in plastic housing on tree to S of pump. Q!

.A-19 Hunting cabin between Goosequill ditch and Platte 1 1.7 river. Silica gel with hygrothermograph in box on the tree.

R-3 Colorado State University Dairy, W. Drake Rd, Ft. 45.1 Collins, CO.. W side of shed directly N of main dairy building. Silica gel inside pump ' housing.

R-4 Intersection of US 66 and US 287, E side of dairy 20.5 store, north edge of Longmont. Silica gel in plastic housing attached to utility pole.

R-11 W side of garage at PSC office in Johnstown (Main St). 10.5 Silica gel in plastic housing on post.

Table III.B.1 Radiological Environmental Monitoring Program (continued)

Sampling Site Descriptions '

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

I' Exposure Site No. Location Description (see map) Sector Distance, Pathway km Waterborne Surface F-19 S. Platte at dam located on dirt road E of pump house 4 1.2

1. 3 directly E of reactor.

F-20 St. Vrain creek on Rd 19 1/2 0.3 km .from discharge 16 1.5 ~

into St. Vrain crcck. Directly N of reactor.

A-21 St. Vrain crcck at bridge on Rd 34, E of Rd 19. 11 2.4 s

A- 25 Goosequill Pond outlet. Continuous sampler located in 1 2.2 g green box adjacent to the green shed on the N end of a the pond R-10 S. Platte river at bridge, on C0 60 where highway 10.1 has just turned and headed South.

Ground ~

F-16 Well behind residence at 3 Bar Ranch (Russell's) 1 1.2 R-5 Erlich feed lot,1.0 km W of CO 66 on WCR 46 8.7 near intersection of Rd 19. .

Drinking R-3 CSU dairy W Drake.Rd, Ft. Collins, CO, N of Vet 45.1 ,

Hospital

.- .R-6 Gilcrest U.S.-Post Office-located on Birch St. and '9.3 Rd 40 off of Hwy 85. Water taken from utility sink inside Post Office.

Table 111.0.1 Radiological Environmental Monitoring Program (continued)

Sampling Site Descriptions

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

Exposure Site No. Location Description (see map) Sector Distance, Pathway km Waterborne Sediment R-10 Sediment from S. Platte River at bridge on C0 60. 10.1  ;

from

• Shoreline Ingestion Milk A-6 Hendrickson Daity,13278 Rd 32 (Grand Ave) 1.6 km E 6 7.1 of US 85.

u> ,

~

A-18 Boos Dairy,11258 W Rd 40, W of US 85 behind modular 2 4.7 home.

A-22 Percy Odenbaugh Dairy,.S on dirt rd from "Percy 5 3.2 Odenbaugh Dairy" sign on Rd 36 E of Rd 23.

A-23 Leroyl0.d'enbaugh Dairy,11733 Rd. 36, .W of Rd 25 ~

4 4.1 3

-A-24 . Marostica Dairy, 20718 Rd ;17, 4 miles S of CO 60. 16 6.9 .

-l A-26 L & F Dairy (Ficchtner), E of Rd 13 on Rd 32 8 7.8 R-8 Arlo'Johnston Farm, located off Exit 255 W of I-25 22.5 directly.N of Johnson's Corner restaurant Fish F-19' S. Platte at . dam located on dirt Rd E of pump house 4 1.1

. f3 directly E of reactor.

A-25 Goosequill pond' outlet 1- 2.2 R-10 S. Platte river. at bridge on C0 60. 10.1. -

1

) Table III.B.1 Radiological Environmental Monitoring Program (continued)

Sampling Site Descriptions (F: Facility Area 0-1.6 km. A: Adjacent Area 1.6-8km. R: Reference Area) i

Exposure Site No. Location Description (see map) Sector Distance, km Pathway Food Products A-9 Miller Store Rd 19 & C0 66 9 4.6 A-8 Walter Maier Farm, 9704 CO 66 8 4.7 i

A-27 Walker Fann, .18535 CR 25 3 4.0 A-28 Jerry Miller Farm, CR 34 & CR 25 5 3.8 A-29 Ben Gutfelder Farm,12027.CR 42 2 7.4 R-13 Harry Matashima Farm, 1/3. mile H of Rd 46 13.7 on Rd 33 , 22501 CR 33 R-14 S. Ibarra garden, 16046 CO 256 12.0 R-16 Frank Eckhardt Farm, 21454 CR 33 14.0 l

l 133 Figure III.B.1 On-site scmpling locations I

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'135 Table III.C.1 - 1986 Land'Use Census Sector . Nearest Nearest  : Nearest Residence Garden Milk Animal 21692 Rd 21 **

1 17578 Rd 19h

-2 18311 Rd 23 19277'Rd 25 11248 Rd 40-3 11250 Rd 38 18089 Rd 25h 4 11247 Rd 36 11733 Rd 36 11733 Rd 36 5- 16519 Rd-23 16134 Rd 23 16134 Rd 23 6 16017 Rd 23 11056 Rd 32h 13278 Rd 32 7 9999 Rd 34 9999 Rd 34 8 15883 Rd 21 14605 Rd 21 9867 Rd 26, 9 9434 Rd 34 9434 Rd 34 9033 Rd 26

• • 7388 Co Hwy 66 10 9061 Rd 34 11 8745 Rd 34 6165 Rd 32 6165 Rd 32 12 9053 Rd 34 5660 Rd 34 5492 Rd 34 13 17038 Rd 17 16936 Rd 15 4709 Rd 38 14 8900 Rd 36 8900 Rd 36 6608 Rd 38 19279 Rd 17 **

15 8903 Rd 38 16 17250 Rd 19 18250 Rd 19 20700 Rd 17 Census date: June 10,12,18, 1986 by Clow and Chambers

• • No milk animal or garden available in sector

136 Figure HI.C.1 1906 Land Use Census 1

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$] Residence & Garden T Residence & Milk Animal

h Public Service ~ PA a P.O. Box 840 Denver, CO 80201- 0840 R.O. WILLIAMS, JR.

VICE PRESIDENT NUCLEAR OPERATIONS April 22, 1987 Fort St. Vrain Unit No. 1 P-87152 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Docket No. 50-267

SUBJECT:

Annual Radiological Environmental Monitoring Report Gentlemen:

Enclosed please find a copy of the Fort St. Vrain Nuclear Generating Station Radiological Environmental Monitoring Program Annual Summary Report for 1986. The report is submitted in accordance with section 7.5.1d of the Fort St. Vrain Technical Specifications.

A copy of the Summary Report is also being sent to the Director, Office of Nuclear Reactor Regulation, per the requirements of section 7.5.1d of the Technical Specifications. Please contact Mr. Mike Holmes at (303) 480-6960 if you have any questions regarding the Report.

Sincerely,' ,

R. O. Williams, Jr.

Vice President, Nuclear Operations R0W:FJB/skd Enclosure 19

P-87152 April 22, 1987 cc: Regional Administrator, Region IV Attention: Mr. J. E. Gagliardo, Chief Reactor Projects Branch Mr. R. E. Farrell Senior Resident Inspector Fort St. Vrain Mr. Al Hazie Colorado Department of Health 4210 E. lith Avenue Denver, CO 80200