ML19259A590
| ML19259A590 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 03/31/1978 |
| From: | PORTLAND GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19259A591 | List: |
| References | |
| PGE-1006-77-2, NUDOCS 7901080148 | |
| Download: ML19259A590 (31) | |
Text
. _ _ _ _
TROJAN NUCLEAR PLANT OPERATIONAL ENVIRONMENTAL RADIOLOGICAL SURVEILLANCE PROGRAM 1977 ANNUAL REPORT July through Decenber Prepared for PORTLAND GENERAL ELECTRIC COMPAIN By MIDWEST FACILITY OF EBERLINE INSTRUMENT CORPORATION AS A CONTRACTOR TO PORTLAND GENERAL ELECTRIC COMPANY MARCH 1978 790108019%
0
TABLE OF CONTENTS PAGE SECTION 1--PREFACE Abstract....................................................
1 Introduction................................................
2 Summary and Conclusions.....................................
2 SECTION 2--SAMPLING PROGRAM Sampling Program and Procedures.............................
3 Table I-Sampling Locations and Sample Collections By Type...
4 SECTION 3--ANALYSIS PROGRAM Analytical Procedures and Counting Meth9ds..................
7 Table II-Technical Specification Required Limics and Reported Detection Levels...
8 Quality Assurance.................
11 Table III-Results of EPA Interlaboratory Comparisons........ 13 SECTION 4-RESULTS AND DISCUSSION Samples from the Terrestrial Environment....................
16 Table A-Mean Ambient Radiation Dose Rate....................
19 Samples from the Aquatic Environment........................
20 SECTION 5-DATA TABLES Commen ts On, and Terms Us ed in Da ta Tables.................. 21 Table IV-Radioactivity in Air Samples.......................
22 Table V-Gross Beta, Gamma Emitters, and Tritium Concentrations in Rainwater Samples...............
23 Table VI-Iodine-131, Gamma Emitters, Sr-89, and Sr-90 Concentrations in Milk Samp1cs......................
23 Table VII-Radionuclides in Soil Samples....................
24 Table VIII-Well Water Samples.........
24 Table IX-Radioisotopes in Grass Samples.....................
25 Table X-Radioisotopes in Terrestrial Animal Samples.........
25 Table XI-Radionuclides in Produce Samples................... 26 Table XII-Radionuclides in Surface Water Samples............
27 Table XIII-Gross Beta and Gamma Emitter Concentrations in Shoreline Soil Samples.......................
28 Table XIV-Gross Beta and Gamma Emitter Concentrations in Sediment Samples................................
28 Table XV-Radionuclides in Aquatic Vegetation Samples.......
28
_ - - - =.
SECTION 1 PREFACE
ABSTRACT This report presents the data obtained through the analyses of environmental samples collected through the Portland General Electric Trojan Nuclear Plant Environmental Radiological Surveillance Program for the period July 1, 1977 through December 31, 1977.
The activity present above detection limits in the routinely collected sample media was observed to be of natural, atmospheric fallout and possibly Trojan origin. The Trojan originating radionuclide Cobalt-58 was observed in samples of aquatic vegetatinn and sediment collected from the Columbia River in low concentration.
Th a radionuclide is released into the Columbia River in low concentrations well within their Technical Specification limits and highly concentrated on the species of aquatic media collected.
1
INTRODUCTION The Trojan Nuclear Plant, a 1130 Mwe pressurized water reactor, first achieved criticality on 15 December 1975, approximately one month after receiving its operating license from the Nuclear Regulatory Commission.
This report presents the analytical data from the Environmental Radiological Surveillance Program with appropriate interpretation for the last six months of 1977.
The analytical contractor during this period has been Eberline Instrument Corporation.
In comparing data obtained during this period with those from previous periods, care should be taken to ensure that differences in procedures between the several contractors are considered.
This is particularly true for
" gross beta" measurements for which the use of different reference nuclides may produce apparently significant differences in gross beta concentrations.
Information concerning environmental radiological surveillance programs prior to this period may be found in earlier reports.
SUMMARY
AND CONCLUSIONS Radioactivity of natural, fission product and neutron act'vation origin was observed in the Trojan on-site and off-site, Oregon. and Washington terrestrial and aquatic environments.
The levels of radioactivity and specific radionuclides observed during this period were generally comparable to the preoperational baseline and operational data accumulated since the Trojan Nuclear Plant achieved criticality in December 1975.
On 17 September 197 7 a nuclear device was exploded at the Lop Nor test site of the People's Republic of China.
Radioactive debris from this explosion (reported yield: 20kt) reached the western coast of the U. S. on 21 September.
Samples collected for several weeks subsequent to this con-tained traces of radioactivity attributed to this debris.
Detectable con-centrations of I-131 were observed in milk samples from most sampling locations during November.
Detectable concentrations of strontium-89 were measured in a number of media.
It is uncertain if this nuclide is attributable to the September explosion or earlier similar tests.
Concentrations of fall-out nuclides measured in samples from the Trojan area were generally consider-ably lower than similar measurements for environmental media in the midwest and eastern U.
S.
Cobalt-58 was the only radionuclide detected which could be specifically identified as probably originating from the Trojan Nuclear Plant.
This activation product radionuclide which was detected at very low levels only in shoreline silt and aquatic vegetation samples originated from the reactor's primary coolone.
2
SECTION 2 SAMPLING PROGRAM
SAMPLING PROGRAM AND PROCEDURES The sampling program which is essentially the same as for previous periods is given in Table I.
Samples are collected by station personnel and forwarded to the analytical contractor's laboratory for assay. Collection procedures remain the same as those given in previous reports with the following exceptions:
1.
Milk:
Iodide is removed from milk samples prior to shipment by standard procedures (see section 3).
This minimizes the loss of iodide due to protein binding which is accelernted by the addition of preservntives, and increases with time even without preservatives.
2.
TLD's: While all procedures for emplacing, collecting and handling TLD's remain essentially unchanged, the processing of the dosimeters is done by PGE personnel rather than a contractor.
3
ea to SAMPLING LOCATIONS AND SAMPLE. COLLECTION FREQUENCY BY TYPE
_ - _ _ _ _ _ _. _ =. _ _ _ _ _ _
SAMPLE LOCATION TERRESTRIAL AQUATIC Air Air Well Surf.
Shore Partic.
Ania. Milk Water Water Sed.
Soil Veg. Anim.
On-Site 1A - U.S. 30 6 E-N Road to Prescott QA S/A S/A M
S/A S/A S/A IB - U.S. 30 W of Containment QA M
S/A 1C - Cemetery on Hill W. of plant QA Q
ID - Recreation Lake M
S/A S/A S/A IE - S. Site boundary, U.S. 30 at R.R.
QA 1F - Meteorology Tower N
W MQA M
S/A S/A IG - So. of Containment Q
1H - Plant Outfall W
W QA II - N. Site boundary, at Col. River W
W QA S/A S/A S/A IJ - RR G E-N Rd. to Prescott QA Oregon Stations 2 - Rainier W
QA M
3 - Lindberg (Ke'ly Res.)
W QA S/A S/A Q
4A - Prescott (Mun. Nat. Sup. )
Q 4C - Prescott (Jack Falls Residential Area)
e e
n
^
TABLE "I CONT.
SAMPLING LOC'.rIONS AND SAMPLE COLLECTION FREQUENCY BY TYPE TERRESTRIAL AQUATIC SAMPLE LOCATION Well Surf.
Shore Air Air Partic.
1-131 TLD T n Soil Veg. Anim. Milk Water Water Sed.
Soil Veg. Anim.
5 - Neer City (Ball Farm)
N W
QA S/A S/A S/A Q
6A - Goble (Easters Landing)
'e W
QA 6B - Gobic (Neer Res.)
Q 6C - Goble (Mun. Wat. Sup.)
7-Shiloh 31 sin (Kelly Dairy)
QA S/A M
8 - Deer Island QA S/A S/A Washington Stations 9A - Woodland (Cowlitz PUD Sta W
QA M
l 10 - Kalama(Sewage Plant)
W 3QA 11A - Kalama River (at Col. Riv)
QA llB - Kalama River (PUD Substat) b' W
QA S/A S/A S/A Q
12 - Carroll's Bluff QA 13 - Vision Acres QA 14 - Longview (Ocean Beach Substation)
W N
opA M
15 - Kelso(Dudonski Dairy)
S/A M
Q 16 - Smith Dairy M
17 - Palmer Dairy (Goat)
M 18 - Standard Dairy 19 - Portlan'd W
W
.i.
SAf1PLIf1G LOCATIONS AND SAMPLE COLLECTION FREQUENCY BY TYPE SA3tPLE LOCATION AQUATIC Surf.
Shore.
Water Sed.
Soil Veg. Anin Columbia River Samples CR1 - Rainier S/A S/A CR2 - Lindberg M
S/A CR3 - Trojan M
S/A S/A S/A S/A CR4 - Kalama M
S/A CRS - Woodland S/A S/A S/A CRIA - Rainier S/A W - Weekly e
Q - Quarterly QA-Quarterly and Annual M - Monthly S/A-Semi Annual
b O
SECTION 3 ANALYSIS PROGRAM
ANALYTICAL PROCEDURES AND COUNTING METHODS Samples.e eived at the contractor's laboratory are analyzed for the various radioactive components by standard radiochemical methods.
These methods are equal to, and in most cases identical with, those of the U. S. DOE (HASL Procedures Manual, HASL-300, Health and Safety Laboratory, U. S. Atomic Energy Commission, 376 Hudson Street, N.Y.,N.Y.
10014) or those of the Federal E. P. A.
Analyses of indivdual sample types, general methods, and routine analytical sensitivities are discussed below.
Detailed procedures may be found in the Eberline Instrument Carporation-Midwest Facility Analytical Procedures Manual.
The analytical program and sensitivity requirements are given in Table II.
Air Particulates Cross bata concentrations are measured with low background gas flow (propor-tional and/or Geiger) couating systems with anti-coincidence background suppression. The routine detection limit (LLD) is.002 pCi/m3 for gross beta or gross alpha based on 300 m / week, but in practice, the ambient air concen-3 tration is seldom this low for beta, and is usually below this level for alpha.
Camma isotopic analyces are performed with a GeLi detector vith a routine for most gamna emitters for single filters detection limit of about 0.05 pC1/m3 and about 0.01 pCi/m for monthly composite sanples.
3 Air Radiciodine Charcoal cartridges are analyzed for 1-131 using a 4" diameter x 4" thick sodium iodide (thallium activated) detector. The routine LLD is 0.1 pCi/m.
3 Maximum sensitivity by this method under typical conditions is about 0.02 pCi/m.
3 Rainfall, Surface Water, Well Water Gross beta analysis of water samples is performed by evaporation of a measured aliquot of the sample, digestion, planchetting of the processed sample and radiometric assay by low level beta counting, with a LLD of 0.5 pCi/1. Tritium analysis is performed on all water samples to the required LLD of 1000 pCi/1 by liquid scintillation counting. Lower detection limits, to 10 pCi/1, can be provided by isotopic enrichment, if required.
Gamma isotopic analyses is performed using a GeLi detector with a routine LLD of 10 pCL/1 for most gamma emitters.
7
TABLE II TECHNICAL SPECIFICATION REQUIRED LIMITS AND REPORTED DETECTION LEVELS **
Required Analysis Technical Specification Required Limits Reported Detection Levels Air Particulate-gross beta 0.002 pCi/m3 0.002 pCi/m3 Air Particulate-gross alpha 0.002 pC1/m3 0.002 pCi/m3 Air Particulate-gamma scan 0.3 pCi/m /nuclide 0.3 pCi/m /nuclide 3
3 Air Radiciodine 0.1 pCi/m3 0.1 pCi/m3 Precipitation-gross beta 0.5 pCi/ liter 0.5 pCi/ liter Precipitation-tritium 1000 pCi/ liter 1000 pCi/ liter Precipitation-gamma scan 25 pCi/ liter /nuclide 10 pCi/ liter /nuclide 140 25 pCi/1)
(Ba Terrestrial Soil-strontium 89-90 0.1 pCi/g(dry) 0.01 pCi/g(dry)
Terrestrial Soil-gamma scan 0.' pCi/g/nuclide(dry) 0.1 pCi/g/nuclide(dry)
Terrestrial Vegetation-strontium 89-90 5.0 pCi/Kg(wet) 0.04 pCi/g(dry)*
1 pCi/Kg/nuclide(wet)
Terrestrial Vegetation-gamma scan 50 pCi/Kg/nuclide(wet) 0.4 pCi/g(dry)*
50 pCi/Kg/nuclide(wet)
Terrestrial Animal-strontium 89-90 5 pCi/Kg(wet)
.005 pCi/g(wet)
Terrestrial Animal-gamma scan 50 pCi/Kg/nuclide(wet)
.05 pCi/g/nuclide(vet)
Milk-iodine-131 0.5 pCi/ liter 0.2 pCi/ liter Milk-strontium 89-90 1.0 pCi/ liter 1.0 pCi/ liter Milk-gamma scan 50 pCi/ liter /nuclide 50 pCi/ liter /nuclide 140 (Ba 25 pCi/1)
- Surface Water-gross beta 0.5 pCi/ liter 0.5 pCi/ liter Surface Water-tritium 1000 pCi/ liter 1000 pCi/ liter Surface Water-gamma scan' 25 pCi/ liter /nuclide 25 pCi/ liter /nuclide 140 (Ba 25 pCi/1)
Well Water-gross beta 0.5 pCi/ liter 0.5 pCi/ liter Well Water-tritium 1000 pCi/ liter 1000 pCi/ liter Well Water-gamma scan 25 pCi/ liter /nuclide 25 pC1/ liter /nuclide Bottom Sediment-gamma scan 0.1 pCi/g/nuclide(dry) 0.1 pCi/g/nuclide(dry)
Shoreline Soil-gamma scan 0.1 pCi/g/nuclide(dry) 0.1 pCi/g/nuclide(dry)
Aquatic Vegetation-strontium-89-90 5 pCi/Kg(wet) 0.04 pCi/g(dry)*
5 pCi/Kg(wet)
Aquatic Vegetation-gamma scan 100 pCi/Kg-nuclide(vet) 0.9 pClig(dry)*
0.1 pCi/g(wet)
Aquatic Animal-strontium 89-90 5 pCi/Kg(wet) 0.005 pCi/g(wet)
Aquatic Animal-gamma scan 100 pCi/Kg/nuclide(wet) 0.1 pCi/g/nuclide(wet)
Direct Radiation 1.25 mR/ quarter change 1.25 mR/ quarter change ss w c wa e
Soil or Sediment Samples are oven dried and results reported based on dry weight.
Camma emitters are measured with a GeLi detector with an LLD as specified.
Vegetation, Meat, Poultry, Fish, Food Crops, etc.
Measured anounts of these types of samples are analyzed for gamma emitters by gamma spectrometry with counting times adjusted to provide LLD's at least as sensitive as those required in Table II for the appropriate sample types.
Milk The determination of I-131 in fresh milk is based on anion exchange removal of the I-131 followed by radiochemical purification and low background beta counting.
The LLD is 0.2 pCi/l or better and the overall accuracy at 0.5 pCi/1 is ! 25% or better at the 95% confidence level.
Gamma emitters in milk are measured with a GeLi detector.
Ambient Radiation Measuremen_ts Effective July 1, 1977, responsibility for ambient radiation dose measure-ments was transferred from the Oregon State Health Division to Portland General Electric Company. Except as noted, no changes have been nade in this phase of the program.
Schedules and field locations are the same, and the same thermo-luminescence material is used. However, the dosimeter design has been changed to reduce its size and eliminate the moisture problems encountered in the past.
To further minimize energy dependance, the copper capsule formerly used with CaF,. Dy (TLD-200) chips was replaced with a two element filter of 0.010" tantalum and 0.002" Icad; this filter has been empirically shown to flatten the response of TLD-200 to ! 20% over the photon energy range if 50-1250 kev. (6)
Calibration of the TLD'c is accomplished with a wooden jig which provides re-137 producibic standard geometry and a 2.5 mci Cs source traceable to the U.S.
National Bureau of Standards.
P for this source was calculated by 5
P = 0.156 n E (10 p,) C in which p is the linear absorption coefficient in air = 3.2x10-5
-1 cm a
E is the photon energy in McV = 662 n is the number of photons per disintegration = 1 C is the activity in millicuries as 0.83 mR/hr at 1 meter.
Readout is accomplished with an Eberline Model TLR-5 reader.
For both the TLD-200's and the TLD-700's (7Li enriched LiF),
the same readout cycle is used: a preheat of 140 C for 10 seconds followed by readout at 230 C for 15 seconds.
9
The detection Jimit for the TLD's, as they are currently handled and processed, is dependent upon the standard deviations of the five-chip array.
Typically, detection limits for a particular group of selected TLD chips complies with t'.e technical specification requirements of detecting changes in ambient radia-tion levels of 1.25 mrem / quarter.
Analytical Detection Limits and Count Rate Errors In environmental radiological analyses the dominant known uncertainty is usually the sampic count rate.
Error terms given in this report are based on this factor since all other ana]ytical uncertainties are relatively small.
Uncertainties are calculated by standard methods (sea Ref. 4), and are reported at the 95% confidence level (20).
The lower limit of detection (LLD) is defined here as "that concentration that is three standard deviations above the average concentration in a blank sample." Analytical data for samples for which concentrations are less than or equal to the LLD are preceded by the symbol "<".
REFERENCES FOR ANALYTICAL PROCEDURES 1.
American Public Health Association, American Water Works Association and Water Pollution Control Federation (1971):
Standard Methods for the Examination of Water and Wastewater.
Thirteenth edition, pp. 583-632; 12th edition, pp. 325-352. APHA, 1740 Broadway, New York, N. Y.
10019.
2 Department of Health, Education and Welfare, Public Health Service:
Radioassay Procedures for Environmental Sampics.
National Center for Radiological Health (1967)
Sec. 1, pp.36-115.
3.
Atomic Energy Commission: Regulatory Guide.
4.3 (September 1973) 4.
Health and Safety Laboratory, Atomic Energy Commission: HASL Procedures bbnual (now known as EML of the Departrent of Energy). HASL, 376 Hudson Street, New York, N.Y.
10014.
5.
National Environmental Research Center, Environmental Protection Agency; Handbook _ of_ Radiochemical Analytical Methods. Program Element 1HA 325.
Office of Research and Development, las Vegas, Nevada 89114.
6.
Denham, D.
H., R. L. Kathren, and J. P. Corley, "A CaF Dy Thermoluminescent 2
Dosimeter for Fnvironmental Manitoring", U.S. At. Enc Comm. Rpt. BNWL-SA-4191 (1972) 10
QUALITY ASSURANCE Quality Assurance is an integral part of management of the analytical program.
The Quality Assurance Program for radiological analysis is defined by Eberline Company, Division, and Facility Fbnuals.
Approximately fifteen percent of the analyses performed by the laboratory are for quality control purposes.
T'ae Laboratory participates in EPA, IAEA, NRC, several States', and other intercalibration programs.
Reports of all quality control analyses are reported monthly to the owner.
Results of EPA inter-calibrations (for which "known" data are available) are given in Table III.
In those casus where discrepant values are obtained, an investigation is undertaken to determine the cause, and corrective action taken as required.
Results of a Fall, 1977 inter-comparison program of the Trojan Environmental Radiation Review Committee (TERRC) are given below.
The data are in good general agreement and those differences that do exist are not considered to be significant.
TERRC INTERCOMPARISON ANALYSES Fall - 1977 Cross Beta in Air Particulate Filters pCi/m3 Eberline Eberline Sample Uncorrected Corrected
- Oregon S.H.D.
Washington S.H.D EB-1 0.11 1 0.02 0.07 ! 0.01 0.063 0.055 EB-2 0.25 1 0.03 0.17 0.02 0.14 0.12 EB-3 0.013 0.004 0.009 0.002 0.008 0.006 Blank
<0.002
<0.002 NA NA
- Eberline gross beta data recalculated to reflect differences between counting efficiencies.for Cs-137, Sr-90, Y-90.
Rainwater - Smith Tower, 10/12/77 pCi/l Analysis Eberline*
Oregon S.H.D.
Washington S.H.D.
Gross Beta 19 1 2 37 2
45 Tritium (HTO)
<1000 NA
<200 Cc-144 15 ! 10 NA NA Cc-141 61 3 NA NA Other Gamma 5
NA NA
- Eberline data are as of analysis 11/25/77, and not corrected for decay to time of sampling.
11
TERRC INTERCOMPARISON ANALYSES CONT.
Vegetation Collected 11/01/78 pCi/g (dry)
- Anclysis, Eberline*
Oregon S.H.D.
gashington S.H.D.
Cross S 36 4
NA NA Cc-144 9
1 10 1 4 NA Cc-141 911 1211 12 BaLa-140 4
1 16 2
18 ZrNb-95 4
1 11 1
5 K-40 (Natural) 30 6
34 1 3 32 Be-7 (Natural) 5 1
3!1 7
Ru-103
<1 713 NA Other Gamma
<0.1 NA NA Sr-89*
3.6 0.3 6.4 0.4 3.0 Sr-90 0.6 ! 0.1 0.9 0.2 0.5
- as of collection date.
NA = not analyzed or data not available.
12
TABLE III RESULTS OF EPA INTERLABORATORY COMPARISOI;S 1977 MoLth_
Agency Value MWF Value Units Gross Alpha in AP Filters January 12 12 pCi/f11ter March 28 25 pCi/ filter June 14 13 pCi/ filter September 13 9
pCi/ filter Gross Beta in AP Filters
- January 40 48
'Ci/ filter March 7/
76 pCi/ filter June 80 79 pCi/ filter September 32 36 pCi/ filter Sr-90 in AP Filters January 10 713 pCi/ filter March 22 16 4
pCi/ filter June 28 23 1 5 pCi/ filter Cs-137 in AP Filters January 20 19 3
pCi/ filter March 33 38 5
pCi/ filter June 24 36 5
pCi/ filter September 32 39 1 5 pCi/ filter Gross Alpha in Water January 12 8
3 pCi/1 March 36 3014 pCi/1 May 15 4i3 pCi/1 July 29 25 8
pCi/1 9eptember 10 9
2 pC1/1 Gross Beta in Water January 37 38 1 5 pCi/1 March 9
3 3
pCi/1 May 15 11 3
pCi/1 Jrly 15 16 2
pCi/1 Septembcr 30 35.
4 pCi/1 H-3 in Water February 1060 1130 1 300 pCi/1 April 1760 1730 1 400 pCi/1 June 1970 1800 ! 400 pCi/1 August 980 950 ! 300 pC1/1 October 1650 1350 1 400 pCi/1
- MWF reference nuclide is Cs-137.
MWF data have been normalized to connect for differences in counting efficiencies.
13
TABLE III (Cont'd)
RESULTS OF EPA INTERLABORATORY COMPARISONS (Cont'd) 1977 Month Agency Value MWF Value Units cr-51 in Water February 202 280 60 pCi/1 April 177 170 ! 40 pC1/1 June 0
<60 pCi/1 October 153 220 1 80 pCi/1 Co-60 in Water February 45 24 ! 5 pC1/1 April 35 40 8
pCi/1 June 29 27 3
pCi/1 October 38 34 8
pCi/1 Zn-65 in Water February 37
<10 pCi/1 April 50 52 1 8 pCi/1 June 74 68 ! 8 pCi/1 October 53 53 ! 8 pCi/1 Ru-106 in Water February 151 85 20 pCi11 April 72 115 25 pCi/1 June 62 58 1 20 pCi/1 Octcber 74 53 20 pCi/1 C_s-134 in Water February 76 20 ! 10 pCi/1 April 27 24 ! 5 pC1/1 June 44 34 ! 6 pCi/1 October 30 21 ! 4 pCi/1 Cs-137 in Water February 39
<5 pCi/1 April 21 23 ! 5 pCi/1 June 33 33 5
pCi/1 October 25 26 7
pCi/1 S_r-89 in Milk January 73 80 15 pCi/1 March 0
<5 pCi/1 May 44 80 ! 20 pCi/1 July 28 23 ! 8 pCi/1 September 54 38 ! 15 pCi/1 14
TABLE III (Cont'd)
RESULTS OF EPA INTERLABORAT03Y COMPARISONS (Cont'd) 1977 Month Agency V,alue MWF Value Units Sr-90 in Milk January 24 32 1 10 pCi/l March 18 15 4
pCi/l May 10 15 1 5 pCi/1 July 25 21 ! 5 pCi/1 September 51 30 ! 10 pCi/1 I-131 in Milk (by gamma spectrometry)
January 69 75 ! 15 pC1/1 March 51 53 10 pCi/1 May 50 54 5
pC1/1 July 38 43 ! 5 pCi/l September 0
<5 pCi/l Ba-140 in Milk January 101 65 ! 30 pCi/1 March 0
<10 pC1/1 May 72 63 ! 20 pCi/1 July 0
.<20 pCi/l September 50 53 20 pCi/l Cs-137 in Milk January 40 45 10 pCi/l March 29 30 10 pCi/l May 10 15 5
pCi/1 July 19 16 5
pCi/l September 51 49 ! 10 pCi/1 Sr-89 in Water August 14 17 ! 6 pCi/l St-90 in Water August 10 11 1 3 pC1/1 15
SECTION 4 RESULTS AND DISCUSSION
SAMPLES FROM THE TERRESTRIAL ENVIRONMENT Air Particulates and Airborne I-131 Gross beta concentrations for air particulates remained at generally low levels throughout the period.
Means and standard deviations of several groups of stations are compared below.
~
1st half 2nd half 1977 Preoperational 1976 1977 Cs-137 Sr-Y-90 Trojan
.02
.02
.02 !.06
.02
.02
.04 !.06
.03
.04 (On Site)
.02
.02
.03
.08
.05
.06
.05
.04
.03 !.03 (Off Site)
.03 2.02
.02
.04
.04
.04
.06
.02
.04
.01 (Off Site)
Portland
.03 !.02
.03
.05
.05
.04 uavai1ab1e It should be noted that the present contractor uses the Cs-137 beta as the reference nuclide rather than Sr-90, Y-90 betas for gross beta measurements.
This practice results in data which are more conservative than those previously reported.
If both groups of measurements are normalized to the same counting efficiency, they are in very good agreement and indicate no statistically significant differences between the groups of stations, and no activity due to Trojan operations.
Gross beta concentrations ranged from <.002 to 0.25 pCi/m 3 with Cs-137 as the reference nuclide.
Some of the higher measurements may be due to fallout from the Chinese nuclear test in September, although effects observed as a renult of this event were much less in the Trojan area than for Eastern and Midwestern areas.
Gamma isotopic analyses of a composite of all filters showing.a gross beta concentration at >0.1 pCi/m for the week ending 10/04/77 revealed the presence 3
of gamma emitters characteristic of radioactive debris from the Chinese nuclear detonation of 17 September 1977.
The table below lists results of this analysis.
Camma isotopic analyscs of other filters during the period revealed the presence of no gamma emitters above the detection limits of 0.3 pCi/m. 3 Gamma Emitters in Composite of Air Particulate Filters Collected 10/04/77 3 as of 10/24/77 pCi/m Cc-144 I-131 Ba-140 La-140 Cs-137
_fr-95 Ce-141 Ru-103
.081.02
.01!.01
.02.01
.01!.01
.01!.01
.03.01
.03.01
.01.01 Gross alpha concentrations for all samples were at or below the detection limit of 0.002 pCi/m.
3 Concentrations of airborne I-131 as measured in charcoal cartridges were below the detection limits of 0.1 p11/m3 in all cases. Data for individual stations are listed in Appendix I, Table IV.
s 16
Terrestrial Animals Samples of various organs from beef cattle from two locations were collected and analyzed for gross beta, radiostrontium and ganma emitters.
The oaly radioactivity detected in the samples originated from either fallout or natural sources.
Data are listed in Appendix I, Table X.
Food Crops Samples of food crops were collected from four locations and analyzed for gross beta, radiostrontium, and gamma emitters.
Strontium-90 was detected at low concentrations in most samples and is attributed to worldwide fallout.
Gross beta activity was detected as is to be expected and is due primarily to natural radioactivity.
Other radioactivity was either of natural origin, or below the sensitivity requirements of the program.
Data are listed in Appendix I~,
Table XI.
Well Water Well water samples were collected quarterly from five locations.
Except for low levels of gross beta radioactivity which are to be expected from natural sources, measurements indicated that gamma emitters and tritium were below the sensitivity requirements of the program.
Data are listed in Appendix I, Table VIII.
Terrestrial Vegetation Data for terrestrial vegetation are listed in Table IX of Appendix I.
Samples of grass were taken at six locations and analyzed for gross beta, radiostrontium, and gamma emitters.
The radioactivity observed in these samples was typical in type and concentrations to what is to be expected from natural and fallout ori-gins.
No activity which is attributable to operation of the Trojan Nuclear Sta-tion was detected.
Milk Milk samples are collected on a monthly schedule from five locations.
During this period, however, milk was not available at station 17.
Samples were analyzed for I-131, radiostrontium, and gamma emitters. All samples contained between 2-12 pCi/l Sr-90 which is attributable to long-term fallout, and several samples collected during October and November contained I-131 and Sr-89 as a result of the September nuclear test.
The maximum levels of I-131 detected were 1.2 pCi/1.
Data for individual samples may be found in Appendix I, Table VI.
Soil Soil samples were collected from seven locations and analyzed for gross beta, gamma isotopic and radiostrontium concentrations.
Data listed in Appendix I, Table VII indicate the prcsence of no radioactivity attributable to the operation of Trojan.
Traces of Cs-137 and Sr-90 were found in all samples, and Sr-89 was found in samples from two locations.
There were no significant differences between stations and the presence of these nuclides is attributed to worldwide fallout from atmospheri nuclear tests.
17 I
Radionuclides in Rainwater Monthly samples of rainwater are collected from three locations and analyzed for gross beta and tritium content.
Samples with a gross beta concen-tration of greater than 10 pCi/1 are analyzed for gamma emitters by gamma spectrometry (CcLi).
During the period 12 samples were analyzed for gamma emitters and except for a trace of Zr-95 and Nb-95 attributed to worldwide fallout in the June sample from the Met Tower (1F), gamma emitters were below the detection limits of the program in all samples analyzed. Although numerical differentes in gross beta concentrations were observed in the samples, there were no significant differences between stations based on the gamma data which are much more useful for comparison than are the beta data.
It should be noted that for these samples as for the air particulates, the use of different nuclides as references for gross beta measurements may produce apparent differences between the data in this report and those provided by other contractors.
Since gross beta analyses are " survey" data these differences are not significant.
Data for rainwater analyses may be found in Appendix I, Table V.
Ambient Radiation Levels Mean ambient dose rates, in units of mrem / day were calculated from the dosi-meter data and are shown in Table A.
There is excellent correlation among the data obtained with the monthly, quarterly and annual dosimeters, and the data do not differ significantly from those obtained previously.
The mean daily dose for the latter half of 1977 was 0.121/ mrem for all 8 onsite stations, 0.149/arem for the 7 offsite stations located in Oregon, and 0.134 for the 7 offsite stations located in Washington, based on the data obtained with the annual dosimeters.
Statistically, there is no significant difference between the two groups of offsite stations,'or has there been in previous reporting n
periods.
Hence, it is reasonable to use the combined mean of all offsite stations - 0.146 mrem / day - for comparison rather than dividing them into two groups based on geographic considerations.
Comparing the offsite and onsite data reveals that the mean doses at offsite locations are approximately 20% greater than those onsite.
This has also been the case hiscorically, although the differences were not quite as great prior to 1976.
The data are also internally consistent for individual sites when compared with prior periods.
For example, locations II and lJ have histori-cally had lower lesels than the mean, with the converse true for location 5.
This trend has continued during 1977.
An interesting comparison can be made between the third and fourth quarter data.
The mean dose rate is consistently greater by 14% during the third quarter, sig.tificant at the 99% confidence level.
This variation is attribut-able to the relatively great rainfall during the fourth quarter of 1977 which tends to reduce ambient exposure primarily due to Jowering the so-called pumping action of the soil and increasing the soil self-shielding.
f 10
TABLE A Mean Ambient Radiation Dose Rate mrem / day 3rd 4th Station Quarter Quarter Annual Monthly 1A 0.14 0.11 0.12 1B 0.13 0.12 0.13 1C 0.14 0.13 0.13 IE 0.13 0.11 0.12 IF 0.14 0.14 0.13 0.17 111 0.14 0.12 0.13 II 0.14 0.10 0.11 IJ 0.11 0.11 0.10 2
0.16 0.15 0.18 3
0.17 0.14 0.18 4C 0.16 0.13
' O.13 5
0.18 0.17 0.18 6B 0.14 0.11 0.11 7
0.14 0.14 0.14 8
0.17 0.14 0.14 9B 0.15 0.13 0.15 10 0.16 0.14 0.13 0.15 11A 0.17 0.13 0.13 llB 0.11 0.12 0.13 0.11 0.14 12 0.14 0.14 0.13 13 Lost 0.13 0.13 0.15 14 0.14 19
SAMPLES FROM THE AQUATIC ENVIRONMENT Surface Water Samples Surface water samples are collected from locations near the Trojan site and include samples from the Columbia River ponds, and municipal water supplies.
Analyses are made for gross beta activity, tritium and gamma emitters.
Neither tritium nor gamma emitters were detected at program sensitivities in any of the samples collected during the period.
Cross beta concentrations were at low, but generally detectable levels and ranged from <0.5 to 20 pCi/l with Cs-137 as the reference nuclide.
It is probable that the elevated concentrations in the samples from locations lA, lE, and 1D collected 9/22/77 were the result of fallout from the Chinese nuclear explosion of 17 September, the debris cloud of which was reported to have passed over the West Coast in the Oregon area early on 21 September.
The fallout would be relatively concentrated in samples from these locations where the volume of diluting water would be less than would be the case for the Columbia River samples which had lower gross beta concencrations on that date.
This supposition is supported by data from the TERRC rainwater intercomparison sample (q.v.).
Since the more definitive gamma isotopic analysis indicated the presence of no significant radionuclides in even the samples with the relatively higher gross beta concentrations, the dif ferences are not considered to be significant or due to operations at the Trojan Nuclear Station.
Data are summarized in Table XII.
Sediment and Shoreline Soil Samples Sediment samples are collected from lakes and streams in the Trojan area as well as from the Columbia River. Naturally occurring radionuclides and fallout radioactivity are present in these samples as well as soil samples collected from the shore of the Columbia River.
Samples from the river may also contain traccs of longer-lived activity from operations at the Hanford Project.
Two samples of sediment f: om lakes and streams contained traces of Zr-95 and Nb-95.
This activity is attributed to fallout from recent atmospheric nuclear tests and not operations at Trojan.
One sample of sediment and one sample of shoreline soil contained low, but detectable concentrations of Co-58.
It is passible that this radioactivity was as a result of Trojan operations.
Tables XIII to XV of Appendix I lists results of analyses for these samples.
i 20 l
SECTION 5 DATA TABLES P
COMMENTS ON, AND TERMS USED IN DATA TABLES Wet Weight a reporting unit used with organic tissue samples such as vegetation and animal samples in which the amount of sample is taken to be the weight as received from the field with no moisture removed.
Dry Weight a reporting unit used for soil and sediment in which the amount of sample is taken to be the weight of the sample after removal of moisture by drying in an oven at about 110 C for about 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />.
pCi/m3 a reporting unit used with air particulate and radioiodine data which refers to the radioactivity content expressed in picoeuries of the volume of air expressed in cubic meters passed through the filter and/or the charcoal trap.
Note that the volumes are not corrected to standard conditions.
Gamma Emitters samples were analyzed by high resolution (GeLi) gamma or spectrometry. The resulting spectrum is analyzed by a Gamma Isotopic computer program which scans from about 50 to 2000 key and lists the energy peaks of any nuclide',present in concentra-tions exceeding the sencitivity limits set for that particular experiment.
NA, NS used in place of a concentration value when a sample was not available (NS), or when a sample was not analyzed for some specific measurement (NA).
Error Terms figures following
"!" are error terms based on counting uncertainties at the 23 (95% confid nce) level.
Values pre-9 ceded by the "<" symbol were below the stated concentration at the 3a (99% confidence) level.
Sensitivitf In general, all analyses meet the sensitivity requirements of the program as given in Table II.
For the few samples that do not (because of inadequate sample quantities, analytical interferences, etc.) the sensitivity actually obtained in the analysis is given.
Comment when all analyses of a particular type during the period resulted in concentrations below the sensitivity limits, a statement is made on the appropriate table rather than presenting a whole page of "<" data.
If all but one or two data points are below the sensitivity limits, the previously mentioned convention is followed and the finite data are given as footnotes.
21
TABLE IV RADIOACTIVITY IN AIR SAMPLES Collection Cross Beta 10 2 pCi/m3 Week TRQJAN ON-SITit STATTQNS OREGON STATI0'IS WASHINGTON STATIONS Endine IH*
II*
IF*
6B*
3 2
5*
9B 10 14
- 11B*
St. Helen s*
07/06/77 2.9 2 1.2 5.6 1.0 7.7 2 1.2 14 2 (', 4.3 2 0.9 8.521.4 4.4 2 0.A 4.0 2 0.9 iA 2 0.5 1.1 2 0.5 8.7 2 1.4 NS 07/14/77 1.2 2 0.5 1.3 2 0.5 1.2 2 0.5 3.5 2 0.7 2.7 2 0.7 1.9 2 0.6 1.7 2 0.6 3.1 2 0.7 3.7 2 0.9
<0.2 1.8 2 0.6 NS 07/19/77 0.4 0.3 1.6 2 0.9 1.7 2 0.9 8.0 2 1.6 1.1 2 0.9 7.8 2 1.6 3.2 1.0 1.5 1 0.9 4.7 2 1.1 0.3 2 0.3 5.7 t 1.3 NS 07/28/77 3.6 2 0.7 7.2 2 0.8 5.3 1 0.8 10 2 1(b) 9.4 2 0.9 4.5 t 0.7 3.1 0.6 4.0 2 0.7 8.7 2 0.9 2.8 2 0.6 11 2 1(b)
NS 08/02/77 2.2 2 0.9 3.3 2 1.0 (0.2 4.1 1 1.0 1.0 0.8
<0.2 4.8 2 1.1 4.8 2 1.1 4.8 2 1.1 1.0 2 0.8 4.8 2 1.1 NS 08/11/77 1.2 t 0.2 3.2 2 0.7 1.2 2 0.5 16 2 2(b) 5.1 2 1.0 14 2 2(b) 11 2 2(b) 3.3 2 0.8 8.3 2 1.5 1.4 2 0.6 11 2 2(b)
NS bo 08/16/77 1.7 2 0.8 11 2 1(b) 2.6 2 0.9 12 t 2(b) 12 2 2 (b) 19 2 2(b) 11 t 1(b) 5.3 2 1.2 16 2 2(b) 3.9 2 1.1 5.1 2 1.2 NS 08/23/77 NS 4.6 2 0.8 4.0 2 0.7 18 2 3(b) 9.5 2 1.5 30 2 4(b) 6.9 2 1.1 NS 6.5 2 1.1 2.4 2 0.6 11 2 2(b)
NS b#
08/31/77 2.4 2 0.5 3.220.7 3.9 2 0.8 9.2 2 1.6 1.9 t 0.4 NS 2.6 1 0.5 1.1 2 0.4 6.4 2 1.2 1.4 2 0.6 1.7 2 0.6 NS
~~~~
09/08/77 7.0 2 1.2 1.3 2 0.6 4.7 2 0.9 12 2 2(b) 5.3 2 1.0 NS 1.9 2 0.6 1.4 2 0.6 4.1 2 0.9 6.3 2 1.2 1.2 2 0.6 NS 09/14/77 2.1 2 0.8 11 2 2(b) 1.3 2 0.7 3.7 2 0.9 28 2 4(b) 4.7 i 0.8 1.1 2 0.7 7.2 1 1.3 13 2 2(b) 1.520.7 12 2 2(b)
NS 09/22/77 0.3 2 0.3 5.8 1.?
0.2 2 0.2 12 2 2(b) 4.1 2 0.8 5.5 2 1.0 6.5 2 1.2 1.8 2 0.6 t.3 2 0.9 0.3 2 0.3 4.8 2 0.9 NS 09/26/77 NS 5.3 t a.1 4.4 2 0.9 9.3 2 1.3 16 2 2(b) 14 2 1(b) 1.8 2 0.9 8.8 t 1.3 20 2 2(b) 1.1 2 0.8 25 2 3(b)
NS 10/04/77 NS 2.620.8 1.7 2 a.7 4.0 2 0.9 50 2 8(b) 47 2 7(b) 5.4 2 1.1 0.9 2 0.6 14 2 2(b) 4.4 2 1.0 5.0 1.0 NS 10/13/77 2.020.6 9.0 2 1.4 13 2 2(b) 4.1 2 0.7 5.6 2 0.9 13 2 2(b) 0.9 2 0.4 8.3 1 1.3 NS 1.6 2 0.5 8.7 2 1.4 NS 10/20/77 14 2 2(b) 13 2 2(b) 1.7 2 0.4 1.8 1 0.4 9.3 ! 1.5 21 2 3(b) 4.2 2 0.8 16 2 3(b) 0.6 2 0.3 2.2 t 0.6 12 2 2(b) 3.7 2 0.7 10/27/77 0.6 2 0.4 5.8 2 1.2 0.2 2 0.2 13 2 2(b) 10 2 2(b) 1.9 2 0.5 0.8 2 0.3 7.9 2 1.5 2.6 2 0.6 2.6 2 0.6 25 2 4(b) 2.4 2 0.6 11/02/77 10 2 2(b) 5.8 2 1.2 6.0 2 1.2 1.0 2 0.5 0.2 2 0.?
2.7 0.8 0.4 2 0.4 0.9 2 0.4
<0.2 2.5 2 0.7 11 2 2(b) 3.5 2 0.9 11/10/77 1.820.6 1.2 2 0.4 1.7 2 0.4 10 2 2(b) 2.1 2 0.5
<0.2 NS
<0.2 NS NS 4.3 2 0.9 N$
!!/17/77 8.4 2 1.4 1.4 2 0.4 1.7 2 0.3 21 2 3(b) 2.5 2 0.6 1.3 2 0.4 2.3 2 0.4 (0.2 11 2 2(b) 6.6 2 1.3 7.4 2 1.4 NS 11/21/77 2.8 2 1.1 0.2 2 0.2 0.3 2 0.2 3.9 2 1.1 1.5 2 0.6 5.1 2 0.9 NS
<0.2 4.7 2 0.7 5.3 2 1.2 1.0 2 0.3 NS 11/30/77 4.2 2 0.7 2.2 2 0.4 6.4 2 1.1 5.0 2 0.9 6.2 2 1.1 0.8 2 0.2 0.6 2 0.4
<0.2 4.3 2 0.8 3.9 2 0.8 3.3 2 0.7 NS 12/07/77
- 0. 6 ! 0. 2 0.2 2 0.2 3.7 2 0.9 0.9 2 0.3 0.7 2 0.2 5.4 2 1.0
<0.2 0.7 2 0.3 7.2 2 1.0 3.6 2 0.8 3.3 2 0.8
7 12/14/77 NS 1.7 1 0.3 3.3 2 0.7 3.6 2 0 7 0.9 2 0.3 1.1 2 0.4
<0. 2.
1.3 2 0.3 5.3 2 t?.8 3.7 2 0.7 2.9 2 0.7 NS 12/21/77 12 2 1(b)
NS 1.6 2 0.6 1.2 2 0.4 2.1 2 0.7 5.2 2 0.9 NS 3.1 2 0.7 0.9 + 0.6 1.2 2 0.6 4.3 2 0.7 NS 12/23/77 0.3 2 0.1 1.4 2 0.3 4.0 2 0.7 5.0 ! 0.5 5.0 t 0.8 3.7 0.7 NS 4.5 2 0.8 2.7 2 0.7 5.7 2 0.9 B.1 + 1.0 N S___
Average 3.7 4.4 3.3 7.9 8.0 9.1 3.7 4.3 7.0 2.8 7.7 3.2 Maximum 14 13 13 21 50 47 11 16 20 6.6 21 3.7 Minirum 0.3 0.2 0.2 0.9 0.2 0.8 0.4 0.7 0.6 0.3 1.0 2.4
- I-131 sanpled weekly. Concentrations are (10 10-2 pCi/m3 unless otherwise noted.
(a) Portland station 19 collected only 10/04/77. Cross bota concentrations: 17. 2 3 lo-a pC1/m. Camma Emitters:
<30 10-2 pCi/m?. I-131:
<10 10-2 pC1/m3 3
(b) Additional analysis = Camma Emitters:
<30 10-2 pC1/m.
2 NS: Station not sampled.
TABLE V Gross Beta, Gamma Emitters, and Tritium (a) Concentrations in Rainwater Samples
~
pCi/l 1F 9B 2
Collection Date Gross 6 Gamma Gross S Gamma Cross B Gamma 07/06/77 67 7
<25 (b) 84 8
<25 34 1 3
~<25 08/02/77 SAMPLES NOT AVAILABLE THIS DATE 09/06/77 7!2
<25 11 ! 2
<25 9!2
<25 10/04/77 30 3
<23 20 2
<25 25 3
<25 11/01/77 14 ! 2
<25 23 ! 3
<25 18 ! 2
<25 12/05/77 8
1 NR 9
1 NR 6t1 NR (a) Tritium was measured to be <1000 pCi/1 in all samples.
(b)Zr-Nb-95 = 21 14 pCi/1.
O TABLE VI Iodine-131, Gamma Emitters (c), Sr-89 and Sr-90 Concentrations in Milk Samples (d) pCi/l Collection 15 7
16 18 Date I-131 Sr-89 Sr-90 I-131 Sr-89 Sr-90 I-131 Sr-89 Sr-90 I-131 Sr-89 Sr-90 07/28/77
<0.5
<1 2! 1
<0.5
<1 3
3
<0.5
<1 2
1
<0.5
<1 7
2 08/23/77
<0.5
<2 1! 1
<0.5
<1 2t2
<0.5
<1 2
1
<0.5
<2 2
2 09/22/77
<0.5
<2 2
2
<0.5
<1 10 3
<0.5
<2 10 3
<0.5
<1 2
1 10/26,27/77
<0.5
<4 12 5
<0.5 4
3 3!2
<0.5
<2 8
2 0.4 0.2 4
2 2
2 11/16,17/77 1.2!0.2
<1 3
2 0.5!0.2 7
3 2
2 0.4!0.2
<2 2
2
<0.5
<1 3!2 12/07/77
<0.5
<2 5
3
<0.5
<2 3
1
<0.5
<3 7!4
<0.5
<2 3!2 (c) Gamma Emitters were measured to be <50 pCi/1 in all snmples.
(d) Station 17 was not available during this sampling period.
TABLE VII Radionuclides in Soil Samples Collected 29 July 1977 pCi/g (dry) 1A 1F 17 3
5 8
11B Wt. Ratio Wet - Dry 1.1 1.1 1.2 1.2 1.3 1.2 1.2 Gross Beta 4
1 4
1 4
1 411 4
1 32 1 5
1 Sr-89
.06
.05
<0.01
.02
.02
<0.01
<0.01
<0.01
<0.02 Sr-90
.16
.04
.06 !.01
.11
.02
.01
.01
.09
.02
.07 !.01
.08 !.02 Cs-137 (a) 1.0 1 0.2
.7
.1
.9
.2
.7
!.1 1.3
!.2
.2
.1
.8 1.1 (a)All stations other ganma emitters:
<0.1 pCi/g.
TABLE VIII WELL WATER SAMPLES (Gross Beta, Tritium and Gamma Isotopic
- Analysis)
Collection Collection Gross S Tritium Gamma Isotopic
- Date Site (pC1/1)
,(pCi/1)
(pCi/1)
'7/20/77 1B 4!l
<1000
<25 v7/20/77 3
4!1
<1000
<25 07/20/77 6A 2!1
<1000
<75 07/20/77 11B
< 0.5
<1000
<2.
07/20/77 16 8!2
<1000
<25 10/27/77 1G 4-1
<1000
<25 10/24/77 3
2?~
<1000
<25 10/24/77 6A 2_l
<1000
<25 10/24/77 11B 1!1
<1000
<25 10/24/77 16 2
1
<1000
<25
TABLE IX Radioisotopes in Crass Samples Collected 29 July 1977 pCi/g wet weight Analysis IF lI 3
5 8
11B Gross S 721 711 8! 1 10 ! 1 21 2
14 ! 1 Cr-89
.02 !
.01
<0.03
.10
.05
.04
.04
.22 2
.12
<0.01 Sr-90
.03
.03
.03
.03
.05
.03
.03
.03
.08
.07
.07
.03 Ce-144 1.0
! 0.1
.62
.09 47
.11
<0.85 2.7 2 0.3
<0.4 Zr-95
.16 !.04
.08
.02
.18
.02
.5
.1
.4
.1
.11 !.03 Nb-95
.16
.04
.08
.02
.18
.02
.5
!.1
.4 2
.J
.11 !.03 Cs-137
<0.05
<0.05
.09 !.02
<0.1
<0.1
<0.05 Other Gamma
<0.05
<0.05
<0.05
<0.1
<0.1
<0.05 U
TABLE X Radioisotopes in Terrestrial Animal (Beef) Samples Collected 23 August 1977 pCi/c wet weight 3
16 Anal / sis Liver Muscle Bone Thyroid Liver Muscle Bone Thyroid Gross B 0.8 ! 0.A 2.1 t 0.4 8.0 2.0 1.2 0.3 0.8 ! 0.3 3.1 t 0.5 1.3 0.4 (a)
Sr-89
<.010
<0.005
<0.005
<0.005
<0.005
<0.005
<0.006 (a)
.017
.015
<0.005
.40 !.P3
<0.005
<0.005
<0.005
.017 !.007 (a)
Gamma Emitters
<0.1
<0.1
<0.1
<0.1
<0.1
<0.1
<0.1 (a)
(a) Sample lost prier to shipment.
TABLE XI Radianuclides in Produce Samples Collected 8/24/77, Location IA Sample pCi/g (wet wt.)
Type Gross B Sr-89 Sr-90 Gamma Emitters Cucumbers 1.4 ! 0.1
<0.008 0.014 0.009
<0.05 Reuban 2.9 0.3
<0.005 0.013 ! 0.005
<0.05 Tomatoes 1.1 1 0.1
<0.001
<.001
<0.05 Carrots 4.3 0.4
<0.007 0.023 2 0.009
<0.05 Onions 3.2 ! 0.3
<0.005 0.045 ! 0.013
<0.05 Cabbage 1.6 ! 0.2
<0.006 0.099 0.056
<0.05 Cress 4.9 i C.5
<0.008 0.014 0.007
<0.05 Collected 8/24/77, Location 16 Strawberries 0.9 ! 0.1
<0.009 0.022 0.015
<0.05 Raspberries 1.6 ! 0.2
<0.005 0.015 ! 0.013
<0.05 Collected 11/18/77, Location 1C Apples 0.3 0.1
<0.01 0.034' ! 0.009
<0.05 Collected 11/18/77, Location 5 Plums 0.3 0.1
<0.005
<.005
<0.05 26
TABLE XII Radionuclides in Surface Water Samples (Gross Beta, Tritium (a), and Gamma Isotopic (b) Analyses)
Gross Beta pCi/l Collection On-Site Locations Gregon Stations Columbia River Date 1A 1B 1C 1D 4A 6C CR2 CR3 CR4 07/21/77 NS NS NS NS US NS 2! 1 1! 1 1
1 07/29/77
<0.5 4!2 1! 1 2
2 1
1
<0.5 NS NS NS 08/23/77 NS NS NS NS NS NS 2!2 2!2 3! 1 08/25/77 5
1 3! 1 NS 2!2 NS MS NS NS MS 09/22/77 14 2
20 3
NS 16 t 2 NS NS 3
2 3!2 6
2 10/04/77 NS NS NS NS NS NS 4
2 4
2 2
2 10/25/77 5
2 4
2 2
2 4
2 3
2 2!2 NS NS K'
S 11/07/77 NS NS NS NS NS NS 3
2 4! 2 5
2 11/15/77 3
2 2
1 NS 3
2 NS
.N S NS NS NS 12/05/77 7
1 7
1 NS 10 1
NS NS 4
~1 4
1 4
1 sican 6
5 7
7 2
1 6
6 2t1 1
2 3
1 3t 1 4!2 Maximum 14 2
20 3
2! 1 16 1 2 3
2 2
2 4
1 4! 1 6
2 Minimum
<0.3 2
1 1
1 2
2 1
1
<0,5 2
1 1
1 1
1 NOTE:
Special sample collected 07/29/77 from location 2: Gross beta = 1 1 pCi/1.
NS = Not sampled that date.
(a) Tritium measured to bc <1000 pCi/l in all samples.
(b)Camma emitters measured to be <25 pCi/l in all samples.
TABLE XIII Gross Beta and Gamma Emitter Concentrations in Shoreline Soil Samples Collection Collection Wt. Ratio pCi/g (dry)
Date Site Wet - Dry Gross Beta Gamma Emitters 07/21/77 CRl 1.0 1
1 Cs-137: 0.1
0.1 Others
<0.1 07/21/77 CR3 1.2 2! 1 Co-58 : 0.3 ! 0.1 Others:
<0.1 07/21/77 CR5 1.2
<C5
<0.1
-~
TABLE XIV Cross Beta and Gamma Emittaz Concent ntions in Sediment Samples Collection Collection Wt. Ratic pCi/g (dry)
Date Site Wet - Dry Gross Beta Gamma Emitters 07/21/77 CR2 1.2 0.7 _
'.6 Co-58: 0.1
0.1 Others
<0.1 07/21/77 CR3 1.3 2.4 1 3
<0.1 07/21/77 CR4 1.3 1.0 0.6
<0.1 07/29/77 1A 1.4 5.4
1.2 Zr-Nb-95
0.15 ! 0.08 others:
<0.1 07/29/77 1B 1.5 3.1 0.9
<0.1 07/29/77 1D 1.3 3.7
1.0 Zr-Nb-95
0.1
0.1 Others
<0.1 TABLE XV Radionuclides in Aquatic Vegetation Samples pCi/g (wet)
Collection Collection Gamma Date Site Cross 6-Sr-89 Sr-90 Zr-Nb-95 Co-58 Co-60 Cs-137 Emitters 07/21/77 CR1 5
1
.02
.02
.02
.02
<0.05 1.3 0.2
.50
.13
<0.05
<0.05 07/21/77 CR3 3!1
<.02
<.02
.25
.12 3.4 ! 0.3
.91
.21
<0.05
<0.05 07/21/77 CR5 3
1
<.03
.015
<0.05
<0.05
<0.05
<0.05
<0.05 07/29/77 1A 7
1
<.02
.050 !.019
<0.05
<0.05
<0.05
<0.05
<0.05 07/29/77 1D 10 ! 1
<.02
.026 !.018
.3
.1
<0.1
<0.1
.07
.02
<0.1