ML18082A915
| ML18082A915 | |
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| Site: | Salem  |
| Issue date: | 06/30/1980 |
| From: | RADIATION MANAGEMENT CORP. (RMC) |
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Text
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RMC-TR-130-03 1979 RADIOLOGICAL REPORT ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM January 1 to December 31, 1979 Prepared for Public Service Electric and Gas Company
- by Radiation Management Corporation June 1980
TABLE OF CONTENTS PAGE 1
J
- \\
SUMMARY
1 I
INTRODUCTION 2
THE PROGRAM 3
Objectives 3
Sample Collection 3
Data Interpretation 5
RESULTS AND DISCUSSION 6
Airborne 6
Precipitation 6
Direct 9
Water 10 Aquatic 14 Ingestion 14 Fodder Crops 17 CONCLUSIONS 18 REFERENCES 19 APPENDIX A - PROGRAM
SUMMARY
21 APPENDIX B - SAMPLE DESIGNATION & LOCATIONS 29 APPENDIX C - 1979 DATA TABLES 37 APPENDIX D - SYNOPSIS OF ANALYTICAL PROCEDURES 85 APPENDIX E -
SUMMARY
OF INTERLABORATORY COMPARISONS 105 APPENDIX F - SYNOPSIS OF DAIRY AND VEGETABLE GARDEN SURVEY 113 i
LIST OF FIGURES NUMBER
- 1.
Comparison of Average Concentrations of Beta Emitters in Precipitation and in Air Particulates, 1973 through 1979
- 2.
Average Arrbient Radiation Levels from Monthly TLDs in the Vicinity of Artificial Island, 1973 through 19 79 e e e e e
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- 3.
Average Concentrations of Tritium in the Delaware River PAGE 7
8 in the Vicinity of Artificial Island, 1973 through 1979.....
11
- 4.
Average Concentrations of Beta Emitters and Potassium-40 in the Delaware River in the Vicinity of Artificial Island, 1973 through 1979...........................................
13
- 5.
Average Concentrations of Iodine-131 in Milk in the Vicinity of Artificial Island, May 1974 through December 1979.*..*.**
16 ii
SUMMARY
During the period January 1 to December 31, 1979, Radiation Management Corporation participated in the Operational Radiological Environmental Monitoring Program con-ducted by Public Service Electric and Gas Company at Artificial Island, New Jersey.
Salem Nuclear Generating Station (SNGS) Unit #1 became critical on December 11, 1976, thereby initiating the operational phase of the Radiological Environmental Monitoring Program (REMP). This program was designed to identify and quantify con-centrations of radioactivity in various environmental media and to quantify ambient radiation levels in the environs of Artificial Island.
During the operational phase, the program will monitor the operations of SNGS Unit #1, fulfill the requirements of the SNGS Environmental Technical Specifications, and provide background data for SNGS Unit #2 and Hope Creek Generating Station. This report presents the results of thermoluminescent dosimetry and radiochemical analyses of environmental samples collected during 1979.
A total of 2569 analyses were performed on 1579 environmental samples during the period covered by this report. Samples of air particulates, air iodine, surface, ground and drinking wat~r, benthos, sediment, milk, fish, cra5s, vegetables, game, fodder crops, and precipitation were collected. Therrnoluminescent dosimeters were used to measure arrbient radiation levels.
A variety of radionuclides, both naturally occurring and man-made, were found in the above samples.
These nuclides were detected at levels similar to those found during the preoperational phase of this program.
In general, results at indicator stations compared favorably to control stations. It is concluded that the radiological charac-teristics of the environment around Artificial Island were not affected by the operation of SNGS Unit #1 during 1979.
1
INTRODUCTION Radiation Management Corporation (RMC) has participated in the Artificial Island Radiological Environmental Monitoring Program (REMP) since January 1973.
RMC has previously reported results from the preoperational phase of the REMP for 1973(1), 1974(2), 1975{3) and 1976(4).
On December 11, 1976, SNGS Unit #1 first achieved criticality, thereby initiating the operational phase of the REMP.
RMC has also reported results from the initial operating period between December 11 and December 31, 1976 (5), January 1 and December 31, 1977 (6) and January 1 and December 31, 1978 (7). This report summarizes the operational period between January 1 and December 31, 1979.
Artificial Island will eventually be the site of four nuclear power reactors.
Two of the reactors are part of the Salem Nuclear G~nerating Station. Unit #1 is a 1090 MWe pressurized water reactor (PWR), and is presently operational.
Unit #2, now under construction, will consist of an 1115 MWe PWR and is scheduled for operation in the near future.
The remaining two units will be part of the Hope Creek Generating Station.
Artificial Island is actually a man-made peninsula in the Delaware River,
.created by the deposition of dredging spoils. It is located in Lower Alloways Township, Salem County, New Jersey.
The environment around Artificial Island is characterized mainly by the Delaware River and Bay, extensive tidal marshes, and grass lands.
These land types make up approximately 85% of the land area within five miles of the site.
Most of the remaining land is used for agricul-tural production. {8)
More specific information on the demography, hydrology, meteorology, and land use characteristics of the local area may be found in the Environmental Report (8), Environmental Statement (9), and the Final Safety Analyses Report (Units 1 and 2) for SNGS ( 10).
2
THE PROGRAM In the operational phase of the REMP, the program was conducted in accordance with Section 3.2 of the SNGS Environmental Technical Specifications (ETS).
Radioanalytical data were collected and compared with results from the preoperational phase.
Differences between these periods were examined statistically, where applicable, to determine whether any station operational effects exist.
Objectives The objectives of the operational radiological environmental program are:
- 1.
To fulfill the obligations of the Radiological Surveillance-Environmental sections of the Environmental Technical Specifications for SNGS *
- 2.
To determine whether any significant increase occurs in the concentration of radionuclides in critical pathways.
- 3.
To determine if SNGS has caused an increase in the radioactive inventory of long lived radionuclides.
- 4.
To detect any change in ambient gamma radiation levels.
- 5.
To verify that SNGS operations have no detrimental effects on the health and safety of the public or on the environment.
This report as required by Section 5.6 of the Salem ETS summarizes the findings of the 1979 REMP.
Results of the four year preoperational program have been summarized for purposes of comparison with subsequent operational reports. (4)
Sample Collection In order to meet the stated objectives, an appropriate operational REMP was developed by RMC in cooperation with Public Service Electric and Gas Company.
Samples of various media were selected to obtain data for the evaluation of the radiation dose to man and other organisms.
The selection of sample types was based on: (1) established critical pathways for the transfer of radionuclides through the environment to man, and (2)
- experience gained during the preoperational phase.
Sampling locations were determined from site meteorology, Delaware estuarian hydrology, local demograohy, and land uses.
Sampling locations were divided into two classes--indicator and control.
Indicator stations are those which are expected to manifest station effects, if any exist; con-trol samples are collected at locations which are believed to be unaffected by station operations.
Fluctuations in the levels of radionuclides and direct radiation at indi-cator stations are evaluated with respect to analogous fluctuations at control stations, which are unaffected by station operation.
Indicator and control station data are also evaluated relative to preoperational data.
The REMP for the Artificial Island site in-cludes additional samples and analyses not specifically required by the Salem ETS.
The summary tables in this report include these additional samples and analys*es.
3
Air particulates were collected on Hollingsworth and Vose H-70-018 filters with low~volume air samplers (1 cfm) before 9-10-79.
After 9~10-79, air par-ticulates were collected on Schleicher Schuell No. 25 glass "fiber filters with low-volume air samplers.
Iodine was collected from air by absorption on TEDA charcoal cartridges connected in series behind the air particulate filters.
Air sample volumes were measured with calibrated dry-gas meters corrected to standard temperature and pressure.
Precipitation was collected on a 95-square-inch rain gauge.
Samples were collected monthly and transferred to new polyethylene bottles.
The rain gauge was rinsed at collection with distilled water to include residual particulates in the preci-pitation samples.
Results of subsequent analyses were corrected for the increase in volume.
Tritium results were also corrected for the tritium content of the distilled water.
Ambient radiation levels in the environs were measured with energy-compensated Caso4. (Tm) thermal umi nescent dosimeters (TLDs).
Packets containing four TLDs each were placed on and around the Artificial Island site at various distances and were exposed on a monthly and quarterly basis.
Monthly well and potable water samples were taken in new two-gallon polyethylene bottles. Separate raw and treated potable water samples were composited daily by personnel of the Salem Water Company.
The Salem Water Company draws its water from Laurel Lake and adjacent wells, which are not expected to be influenced by SNGS liquid discharge.
Surface water samples were collected by Icthyological Associates and shipped to RMC for analysis in new polyethylene bottles. Sample containers were rinsed twice with the sample medium prior to collection. Edible fish and crabs were taken by net, sealed in a bag or jar and shipped frozen.
Benthos and sediment were taken with a bottom grab sampler.
Milk samples were taken in new polyethylene bottles and shipped fresh.
Food products, fodder crops, game and bovine thyroid samples were taken and sealed in plastic bags or jars. Perishable samples were frozen at the time of sampling without any preservatives.
Appendix A descrtbes and summarizes, in the format of Table 5.6-1-of the Salem ETS, the entire operational program as performed in 1979.
Appendix B describes the RMC coding system, which specifies sample type and relative locations at a glance.
Also in Appendix B, Table B-1 gives the pertinent information on individual sampling locations, while maps B-1 and B-2 show the sampling locations.
4
Data Interpretation Radiation Management Corporation has an extensive quality assurance program designed to maximize confidence in the analytical procedures used.
The analytical methods utilized in this program are summarized in Appendix D.
Approximately 20% of the total analytical effort is spent on quality control, including process quality control, instrument quality control, inter-la5oratory cross-check analyses, and comprehensive data review.
Results of the EPA inter-laboratory comparison program appear in Appendix E.
A full discussion of these results can be found in the Annual QC Report (11).
Several factors are important in the interpretation of the data.
These factors are discussed here to avoid repetition in sections that follow.
Grab sampling is a useful and acceptable procedure for taking environmental samples of a medium in which the concentration of radionuclides is expected to vary slowly with time or where intermittent sampling is deemed sufficient to establish the radiological characteristics of the medium.
This method, however, is only representative of the sampled medium for that specific location and instant of time.
As a result, variation in the radionuclide concentrations of the samples will normally occur. Since these variations will tend to counterbalance one another, the extraction of averages based upon repetitive grab samples is valid.
Within the data tables {Appendix C) an approximate 95% (+/-2 sigma) confidence interval is supplied for those data points above the lower limit of detection (LLD).
These intervals represent the range of values into which 95% of repeated analyses of the same sample would fall.
Results for e*ach type of sample were grouped according to the analysis per-formed.
Means and standard deviations of these results were calculated when applicable.
The calculated standard deviations of grouped data found in Appendix C represent sample and not analytical variability.
When a group of data was composed of mainly (>50%) LLD values, averages were not calculated.
It is characteristic of environmental monitoring data that many results occur at or below the lower limit of detection.
For reporting and calculation of averages, any result occurring at or below the lower limit of detection is considered to be at that limit. Averages. obtained using this method are there-fo.re biased high.
5
RESULTS AND DISCUSSION The analytical results of the 1979 REMP samples are divided into categories bas.ed on exposure pathways: airborne, direct, water, aquatic and ingeslion.
The anal-ytical results for the 1979 REMP samples are summarized in Appendix A.
The data for individual samples are presented in Appendix C.
Airborne Air Particulates Weekly air particulate samples were analyzed for gross beta emitters at eight stations and gross alpha emitters at two stations. Quarterly composites of the weekly samples from each station were analyzed for Sr-89, Sr-90 and gamma emitters.
Of the 106 weekly air particulate samples (two stations) analyzed for gross alpha emitters, 93 showed detectable c~ncentrations. The range o~ gross alpha activity was from <0.0003 to 0.0047 pCi/m and averaged 0.0013 pCi/m
- Weekl~ gross beta analyses showed concentrations ranging from 0.0078 to 0.961 pCi/m, with the average for the eight sampling stations being 0.027 pCi/m
- The last sample of March and the first two samples in April covered a combined sampling period of two weeks.
These four and five day samples were taken at the time of the initial incident at Three Mile Island in order to determine any effects from this event.
No discernable difference in activity was observed.
Figure 1 shows the relation between gross beta activity in air and precipitation for the preoperational versus the operational periods, showing both seasonal and weapons-testing fluctuations.
Results of gamma spectrometry showed detectable levels of several radionuclides, both naturally occurring and man-made (Be-7, Co-60, Ru-106, Sb-125, Cs-137, and Ce-144).
The man-made nuclides detected during the year can f>e attrif>uted to fallout from the March 14, 1978 atroospheric nuclear weapons test. The concentrations of these nuclides have decreased steadily since the test. The fourth quarter results showed LLD values for most of these radionuclides.
The presence of Be-7 throughout the year can be attributed to cosmic ray activity.
The Sr-89. analyses perforrre~ ?n the quarterly composites showed tw? o~t of twenty~ei ~ht samples with detectable act1v1ty.* These were 0.0006 and 0.0009 pC1/m ang fall w1th1n the MDL range.
The MDLs for Sr-89 ranged between <.00~5 and <0.002 pCi/m. Sr-90 conce*~trations ranged between <0.0002 and 0.0008 pCi/m with the average being 0.0005 pCi/m
- Air Iodine Iodine cartridges were connected in series behind each of the air particulate filters for absorption of air iodine.
The absorption media used in these cartridges wa~
11 TEDA 11 impregnated charcoal.
All results for I-131 were below the LLD of 0.0042 pCi/m
- Precipitation Although not specifically required by the Salem ETS, precipitation was sampled continuously and collected monthly at the Salem substation sampling location.
6
/00 10 FIGURE 1 COMPARISON OF AVERAGE CONCENTRATIONS OF BETA EMITTERS !ti PRECIPITATION AND IN AIR PARTICULATES, 1973 THROUGH 1979 i;Ci/l - - - - -.. Pl:ecipitat:.i.on 10-" i;Ci/rn3--
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FIGURE 2 AVERAGE AMBIENT RADIATION LEVELS FROM MONTHLY TLDs IN THE VICINITY OF ARTIFICIAL ISLAND, 1973 THROUGH 1979 3
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Monthly samples were analyzed for tritium, gross alpha emitters and gross beta emitters.
Concentrations of tritium in eleven of the twelve samples were below LLD and ranged from
<102 to <125 pCi/l.
One sample had a concentration of 526 pCi/l.
The concentrations of gross alpha emitters were below LLD (0.4-1.4 pCi/l) in ten of the twelve samples. The other two samples had gross alpha concentrations of 0.7 and 0.9 pCi/l. Gross beta-emitter concentrations ranged from 2.4 to 21 pCi/l and averaged 8 pCi/l.
Quarterly composites of precipitation were analyzed for radiostrontium and gamma emitters.
No gamma emitters were detected.
The Sr-89 *levels were below the MDL which ranged between
<0.6 and <1.7 pCi/l.
The results for two of the four analyses performed for Sr-90 were below the MDL (0.5 and 0.6 pCi/l). The other samples had Sr-90 concentrations of 0.4 and 1.2 pCi /1.
Direct Direct radiation measurements were made at 25 locations using CaSO * (Tm) thermolumi-nescent dosimeters.
During 1979, 300 monthly and 100 quarterly TLfi packets were-collected Each packet included four dosimeters for a total of 1600 analyses. These analyses resulted in an average dose rate of 6.03 mrads/standard month for monthly TLDs and 5. 72 mrads/stan-dard month for quarterly TLDs.
All TLD results presented in this report have been normal-ized to a standard month (30.4 days) to eliminate the apparent differences caused by varia-tions in exposure periods.
When the monthly data is plotted as in Figure 2, a slight peak is observed after June.
This peak is attributed to the elevated readings from two on-site TLD stations which are discussed later in the text. Since the two stations, lOSl and IlSl, are on-site they do not represent any environmental dose to the public.
A comparison of the direct radiation data for 1979 shows a similarity between the average monthly dose for both indicator stations (6.00 mrem/std. month) and control stations 6.17 mrem/std.
month).
In order to better evaluate the variation between TLD results a statistical model has been developed, which is capable of separating a contribution by SNGS from the background component.
The statistical method utilized is a linear regression analysis which involves determining the functions which best describe the background component by the least squares method.
Six models were originally tested and are described in a separate publication (12).
The equation which describes the model selected is:
where:
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= denotes a function of
= predicted value for station j, month m, and year. i
= preoperational mean for station j
= average of the control stations for month m and year i
= average of the control station for year i (a 11 p 11 in place of 11 i 11 represents the preoperational period) 9
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A computer program was developed for multiple regression analysis.
The least squares fit (LSF) line based on all 197~ data was determi~ed along with the statis-tics for.this line.
The data for 1979 was tested against predicted values and prediction limits determined from the model period line.
Differences between predicted and observed values are termed residuals.
Residuals outside the prediction limits of the predicted value are identified as outliers.
For 1979, 28 outliers were predicted from a possible 300.
Six of these outliers occurred at station 2Sl, which was reconstructed in April 1977 after the pre-operational mean was calculated which invalidates the preoperational mean.
If a new mean is used based on data obtained from July 1977 through April 1978 no outliers are obtained.
Six positive outliers occurred at 7Sl. These occurred in February, May, July, September, November and Decerrner. *construction was underway in the area of this station. Since this type of activity has been known to effect the terres-trial component in the past (7), this invalidates the preoperational mean.
Six outliers at station lOSl and seven outliers at station llSl have occurred after May when refueling was in process at Unit #1.
These stations are located in the vicinity of the Refueling Water Storage Tank.
Since these locations are on-site they do not represent a dose to the public.
No TLDs located beyond the plant boundary indicated any additional dose from SNGS opera_tion.
The remaining three outliers were randomly distributed among the stations and can be attributed to statistical fluctuations.
Water Surface-Water Monthly surface water samples were taken at five locations in the Delaware estuary.
One is downstream from the outfall area, one is in the outfall area, and another is directly west of the outfall area at the mouth of the Appoquinimink River.
Two other stations are located upstream--one station is in the river and the other is in the Chesapeake and Delaware Canal.
In addition, one sample from each of two extra stations was collected as replacements for samples which could not be collected.
These stati_ons are located at the water intake area and upstream two miles east of the Augustine Creek.
An extra sample was collected from the Chesapeake and Delaware Canal at the time of the Three Mile Island incident to determine any effects which may have occurred due to that incident.
The station located at the mouth of the Appoquinimink River serves as the operational control. Surface water samples were analyzed for tri-tium, gross alpha emitters, gross beta emitters, strontium-89 and -90, and gamma emit-ters.
Analysis of surface water for tritium yielded an average concentration of 113 pCi/l and ranged from 86 to 218 pCi/l. These levels,are similar to those measured in the preoperational program as shown in Figure 3.
A gradual decrease in tritium activity from 1973 to 1979 can be attributed to general reduction in the world-wide tritium inventory with the cessation of routine atmospheric weapons testing.
Gross alpha concentrations were generally below LLD, which ranged from <0.. 2 to <43 pCi/l. The large variations in LLD are due to the amount of-solids present in the 10 I
FIGURE 3 AVERAGE CONCENTRATIONS OF TRITIUM IN THE DELAWARE RIVER IN THE VICINITY OF ARTIFICIAL ISLAND, 1973 THROUGH 1979
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After July, the analytical method was changed to eliminate the solid content* interference in the gross alpha particle transmission in counting. After the change, the LLDs ranged from <0.2 to <1.0 pCi/l.
Fourteen of the 54 samples analyzed showed detectable gross alpha activity.
The average (1.9 pCi/l) was within the same range as the LLDs for the year.
Gross alpha activity may be expected in suspended solids from naturally occurring radionuclides especially during periods of high surface runoff.
Gross beta concentrations ranged from 3.8 to 107 pCi/l and averaged 25 pCi/l.
Nearly all of the beta activity was contributed by K-40, a natural component of salt and brackish waters, as illustrated in Figure 4, comparing gross beta and K-40 concentrations in the Delaware River.
Due to the flow rate variations and the tidal nature of the estuarine environment, large variations in the gross beta concentrations were observed throughout the year.
Much of this variation can be attributed to the tidal stage at the time of sampling.
Gamma spectrometric analysis of surface water samples showed detectable con-centrations of K-40 in 34 of 54 samples.
The average K-40 concentration was 30 pCi/1 and ranged from <7.8 to 90 pCi/l.
K-40 is a naturally occurring radionuclide which is expected to be found in salt and brackish waters.
Levels of Sr-89 were below MDL (0.6 to 2.5 pCi/l) in nineteen of twenty samples.
Sr-89 was found in one sample.
The concentration (0.5+/-0.4) pCi/l was comparable to the MDL levels found in the samples.
Levels of detectable Sr-90 ranged from 0.4 to 1.0 pCi/1 in five of the twenty samples.
The MDLs values ranged from
<0.4 to <0.9 pCi/l. The maximum level of Sr-90 detected in the preoperational program was 1.6 pCi/1 (4).
Well Water Monthly well water samples were taken from an on-site (indicator) well and two off-site (control) wells. All well water samples were analyzed for tritium, gross alpha and gross beta activity, and K-40 (by atomic absorption). Quarterly composites were analyzed for gamma emitters, and Sr-89 and Sr-90.
No detectable concentrations -0f tritium were observed in any of the samples. The LLDs ranged from <96 pCi/l to <124 pCi/1.
Concentrations of gross alpha emitters were below the LLD (0.7 to 3.7 pCi/l) in all the samples, The concentrations of gross beta emitters averaged 9.2 pCi/l and ranged from 2.1 to 25 pCi/l. The potassium-40 activity as determined by atomic absorption averaged 8.7 pCi/l. This indicates that the gross beta activity observed in these samples is primarily the result of naturally occurring K-40, a beta emitter.
The only nuclide detected by gamma spectrometry was K-40 (9.8 to 19 pCi/1) in six of twelve samples.
All results for Sr-89 and Sr-90 were below the MDL of <0.6 to <2.5 pCi/l and <0.4 to <1.2 pCi/l, respectively.
Potable Water Both raw and treated water samples were taken at the Salem Water Company, the--only drinking water processing plant in the vicinity of Artificial Island.
The raw water source for this plant is Laurel Lake (a tributary of the Delaware River) and several adjacent wells.
Potable water samples were analyzed monthly for tritium, gross alpha and gross beta activity, and K-40 (by atomic absorption); Sr-89 and -90, and garrma emitters were analyzed on a quarterly basis.
12
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Potassiurn-40 FIGURE 4 AVERAGE CONCENTRATIONS OF BETA EMITTERS AND POTASSIUM-40 IN THE DELAWARE RIVER IN THE VICINITY OF ARTIFICIAL ISLAND, 1973 THROUGH 1979
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1-The concentration of tritium averaged 120 pCi/l for all analyses, with no significant differences between the raw an'd treated' samples.
Detectable gross alpha activity was observed in 13 of 24 samples ranging between 0.4 pCi/l and 1.7 pCi/l in all samples.
Gross beta and K-40 concentrations were lower than in the saline surface water, as is usual for fresh water, with K-40 generally contributing less than 50% of the beta acti-vity. The average gross beta concentrations were 4.8 pCi/l (raw) and 3.1 pCi/l (treated).
The average K-40 results were 1.7 pCi/l (raw) and 1.9 pCi/l (treated).
Quarterly composites of raw and treated samples were analyzed for Sr-89 and -90, and gamma emitters. *The concentration of Sr-89 (0.8 pCi/1) found i~ one of seven samples was less than the range of the MDLs (0.6 pCi/l to 1.0 pCi/l). Strontium-90 was observed in five of the eight samples with concentrations ranging f>etween 0.4 pCi/l and 0.7 pCi/l, with three samples below the MDL (0.5 pCi/l and 0.6 pCi/l).
One sample had a detectable activity for K-40 of 54 pCi/l.
Aquatic Benthos Benthic organisms were collected at four locations and analyzed for Sr-89 and Sr-90.
Levels of Sr-89 were below MDL (1.5-609 pCi/g) for seven of eight analyses.
A con-centration of 14 pCi/g was detected in one sample which is within the MDL range.
The wide fluctuations in MDL are due to inconsistencies in sample size {.01-1.79 grams dry).
One of eight samples showed a detectable Sr-90 concentration of 76+/-75 pCi/g-dry. The detectable activity of this sample is within the MDL range (0.06 to 171 pCi/g-dry) of the other seven analyses.
The MDL for radiostrontium as required by the Environmental Technical Specifications for benthic organisms was not met in all of the samples due to the impracticality of obtaining a sufficiently large sample size of benthic organisms.
Sediment Sedinent was collected semiannually at four locations and analyzed for ganma emitters and Sr-90.
Results of gamma spectrometry showed detectable levels of a variety of naturally occurring radionuclides as well as man-made radionuclides.
Some fallout nuclides (Cs-137, Ce-141) were observed intermittently at control stations as well as indicator stations.
Sr-90 was not observed in any of the eight samples analyzed.
The MDL range was <0.03 pCi/g-dry to <0.09 pCi/g-dry.
Ingestion Milk Milk samples were taken twice a month from ~ix local farms during 1979 and analyzed for I-131; gamma emitters, Sr-89 and Sr-90 were analyzed monthly.
Following the nuclear incident at Three Mile Island on March 28, detectable concentrations of I-131 were observed.
These concentrations were found in four of six samples collected from all 14
-stations between April 15 and April 17.
The I-131 observed ranged between 0.14 and 0.66 pCi/J and was attributed to the Three Mile Island incident since the highest activity occurred at the control location.
Samples taken between March 30 and March 31 had no detectable activity because atmospheric conditions had not yet caused fallout from released activity at Three Mile Island.
Figure 5 shows the average I-131 concen-trations in milk samp~es resulting from atmospheric nuclear weapons tests by the Peoples Republic of China between June 1974 and March 1978 and the Three Mile Island incident.
No other I-131 was observed in any of the samples.
Gamma spectrometry showed detectable concentrations of K-40 in all samples and Cs-137 in all but 29 of the 72 samples analyzed.
The annual average concentrations were 1230 pCi/l for K-40 and 2.1 pCi/l for Cs-137.
These levels were not significantly different between control and indicator stations.
Strontium-89 was detected in three of the seventy-two samples analyzed with results ranging between 1.7 pCi/l and 5.9 pCi/l.
The range of MDL values for Sr-89 was <1.3 pCi/l to <4.4 pCi/l.
The wide range of values for the MDL was due to low chemical yields in some of the* analyses.
All of the positive results detected were within the MDL range.
The concentration of Sr-90 was positive in 58 of the 72 samples analyzed and averaged 3.7 pCi/l.
The MDL range was <1.5 pCi/l to <6.7 pCi/l. Sr-90 concentrations were similar at indicator and control stations, indicating no contri-bution from SNGS.
Due to the 28 year half-life and biological assimilation, Sr-90 can be expected to remain long after routine atmospheric testing has ceased.
All Sr-89 and -90 analyses have been chemical yield verified by atomic absorption to determine calcium interference.
Fish Edible fish samples (American Eel, White Perch, Channel Catfish, Spot, etc.) were collected at three locations and analyzed for garrana emitters and tritium. Fish bones were analyzed for Sr-89 and Sr-90.
Gamma spectrometry of these samples showed K-40 in all six samples analyzed at an average concentration of 2.6 pCi/g-wet with a range of 0.6-4.4 pCi/g-wet.
Tritium analyses were performed on both aqueous and organic fractions of the flesh portions of these samples.
The average concentration of tritium was 98 pCi/l with a range of 68-148 pCi/1 for the aqueous fraction and 338 pCi/l for the organic fraction with a range of 176-529 pCi/l.
Of the six samples analyzed, three results are essentially the same as those found in surface water for the same period.
The remaining three results were slightly higher (381-529 pCi/l) than the highest result detected in surface water (218 pCi/l). Since these samples were too small for reanalysis verification of the slightly higher activity was not possible.
All the bone samples analyzed for Sr-89.were below the MDL (0.1 to 1.l*pCi/g-dry).
Four of the six samples analyzed for Sr-90 had detectable concentrations of 0.07-1.4 pCi/g-dry.
The maximum level detected during the preoperational period was 0.94 pCi/g-dry.
Blue Crab Blue crab samples were collected at two locations and the flesh was analyzed for tritium in the aqueous fraction, gamma emitters and Sr-89 and -90.
The shells 15
Feb.
to I~~ r Joo*
Aug.
Ckt.
N~.
~
- ~
~1~*
Oct.
N~.
~
I 1;;;14 Mar.
~I,,, r ~:.
Aug.
Oct.
Nov.
~
Jan.
Feb.
11~
July Aug.
Ckt.
Nov.
~
Jan.
Feb.
~ i"' r
~.:.
July Aug.,
Nov.
°"'*
I-'
at.rrospheric weap:ms test
---+
June 17,1974 at:JTospheric weapons test sept. 26, 1976 at:nosJ;:heric \\oJ0ap::llS test sept. 17, 1977 atJTospheric weap::m.s test
---+
March 14, 1978 9T i;Ci/l
~
I-'
0 I-'
- o 0
I
-+
n z
~)>
-I<
-<IT!
- o Ol>
IT!
)>
- on
-10
~z
-,,n
~IT!
nz
~-1
"';o r- )>
-I
~~
V>O r-z
"'(/)
z 00 "'
c ;o
- ~
IT!
)>0
-<8 °'
~z
'°IT!
'-J'
,,.~
w
-1~
- c
"'~
oz c
G>3:*
- c~
r-07' IT!
n~
ITIZ
""-I IT! :c
- o IT!
'-J
'°
were analyzed for Sr-89 and Sr-90.
Tritium concentrations were found in all of the samples analyzed with an average of 163 pCi/l. This is comparable to tritium values found in surface water for this same period.
K-40 was the only gamma emitter detected with an average of 1.7 pCi/g-wet.
All results for Sr-89 in both the flesh and the shells were MDL with that value being
<0.03 pCi/g-wet for flesh and <0.2 pCi/g-dry for shells. There was no detectable acti-vity of Sr-90 in flesh with the MDL value at <0.01 pCi/g-wet.
All of the shells had Sr-90 detectable activity with an average of 0.43 pCi/g-dry.
The range of activities was 0.32 to 0.49 pCi/g-dry with no difference observed between indicator and control stations.
Food Products A wide variety of other human food products was sampled and analyzed for gamma emitters, and Sr-89 and -90.
These included cucumbers, asparagus, peppers, cabbage, corn and to-matoes.
All samples contained K-40 at concentrations from 1.2 to 6.6 pCi/g-wet.
No other gamma emitters were detected in these food products. Sr-89 concentrations were all below MDL, which ranged from <0.005 to <0.3 pCi/g-wet.
Six of the seventeen samples analyzed showed detectable Sr-90 activity (0.002-0.24 pCi/g-wet). The detectable Sr-90 concentrations were generally within the range of the MDL, which ranged from <0.003 to
<0.02 pCi/g-wet.
Game Five samples of muskrats and on~ sample of venison were taken during this period.
Flesh from all six samples was analyzed for gamma emitters while muskrat bones were analyzed for Sr-89 and Sr-90.
Naturally occurring K-40 was detected in all six samples ranging from',1.1 to 3.6 pCi/g.
Cs-137 was detected in one muskrat with a concentration of 0.008+/-0.006 pCi/g-wet.
This concentration fell within the MDL range of <0.008 pCi/g-wet to <0.01 pCi/g-wet.
Muskrat bones showed detectable Sr-89, with concentrations ranging between 0.1 and 0.2 pCi/g-dry.
The range of the MDLs was <0.009 pCi/g-dry to <O. l pCi/g-dry.
Detectable Sr-90 concentrations were observed in all.samples ranging from 0.29 to 1.0 pCi/g-dry_.
Beef Two beef samples were collected during this reporting perioq.
Only naturally occurring K-4p was detected in these samples at a concentration of 1.9' and 2.4 pCi/g-wet.
Beef Thyroid Two beef thyroids were taken during this period and analyzed for garrma emitters.
One sample showed a detectable concentration of naturally occurring K-40 at a concentration of 1.1 pCi/g-wet.
The other sample had an LLD for K-40 of 1.6 pCi/g-wet.
No I-131 was detected in either sample with LLDs of <0.084 and <0.11 pCi/g-wet.
Fodder Crops Twelve fodder crop samples were taken at eight 1 ocal farms and analyzed for gamma emitters. Of the naturally occurring gamma emitters present, only K-40 was observed in all samples, with an average of 12 pCi/g-dry.
The other detected naturally occur-ring nuclide was Be-7 which occurred in one grass sample.
The result was 2.0 pCi/g-dry.
17
CONCLUSIONS The Radiological Environmental Monitoring Program for Salem Nuclear Generating Station at Artificial Island was conducted during 1979 in accordance with the SNGS Environmental Technical Specifications.
The objectives of the program were met during this period. The data collected shows that SNGS unit #1 was operated in compliance with Environmental Technical Specifications.
From the results obtained, it can be concluded that the levels and fluctuations of radioactivity in environmental samples were as expected for an estuarine environment.
In addition no increases were observed in either radionuclide concentrations in critical pathways or with respect to radionuclide build up.
Ambient radiation levels were relatively low, averaging about 6.17 mrem/std.
month.
I-131 detected in a few samples was attributed to atmospheric fallout from the incident at Three Mile Island in March 1979.
No other unusual radio-logical characteristics were observed in the environs of Artificial Island.
The operation of SNGS Unit #1 had no discernable effect on the radiological characteristics of the environs of Artificial Island.
18
REFERENCES (1)
Radiation Management Corporation.
11Salem Nuclear Generating Station -
Radiological Environmental Monitoring Program - 1973.
11 RMC-TR-74-09, 1974.
(2)
Radiation Management Corporation.
11Artificial Island Radiological Environmental Monitoring Program - 1974 Annual Report.
11 RMC-TR-75-04, 1975.
(3)
Radiation Management Corporation 11Artificial Island Radiological Environmental Monitoring Program - 1975 Annual Report}
1 RMC-TR-76-04, 1976.
(4)
Radiation Management Corporation.
11Artificial Isla~d Radiological Environmental Monitoring Program - Preoperational Surrrnary - 1973 through 1976. II RMC-TR-77-03, 1978.
( 5)
Radiation Management Corporation.
11Artificial Island Radiological Environmental Monitoring Program - December 11 to December 31, 1976.
11 RMC-TR-77-02, 1977.
(6)
Radiation Management Corporation.
11Artificial Island Radiologfcal' Environmental Monitoring Program -
1~77 Annual Report 11
. RMC-TR-78-04A, 1977.
(7)
Radiation Management Corporation.
11 Arti fi ci a 1 Island Radiological Environmental Monitoring Program - 1978 Annual Report 11 RMC-TR-79-03, 1978.
(8)
Public Service Electric and Gas Company.
11 Environmental Report, Operating License Stage - Salem Nuclear Generating Station Units 1 and 2.
11 1971.
(9)
United States Atomic Energy Commission.
11 Final Environmental Statement -
Salem Nuclear Generating Station, Units 1 and 2.
11 Docket No. 50-272 and 50-311, 1973.
(10) Public ServiCe Electric and Gas Company.
11 Final Safety Analysis Report -
Salem Nuclear Generating Station, Units 1 and 2.
11 1972.
( 11) Radiation Management Corpora ti on.
11Qual ity Control Data 1979 - Annual Report 11
, 1980.
(12) Radiation Management Corporation.
11Artificial Island Radiological Environmental Interpretation of Results of the Thermoluminescent Dosi me try Program 11 RMC-TR-78-11, 1978.
19
APPENDIX A PROGRAM
SUMMARY
21
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 SALEM COUNTY, NEW JERSEY JANUARY 1, 1979 TO DECEMBER 31, 1979 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NON ROUTINE SAMPLED OF ANALYSES DETECTION MEAN**
NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT)
PERFORMED (LLD)*
(RANGE)
DISTANCE AND DIRECTION (RANGE)
(RANGE)
MEASUREMENTS Air Particulates Alpha 106 0.3 1.2 (47/53) 3H3 llO m"i NE 1.4 (46/53) 1.4 (46/53) 0 (lo-3 pCi/m3)
(0.5-3.0)
(0.6-4.7 (0.6-4.7)
Beta 422 27 (369/369) 251 1575 ft NNE 28 (53/53) 27 (53/53) 0 (7.8-54)
(13-54)
(13-61) 5Dl 3.5 mi E 28 (52/52) 27 (53/53) 0 (13-51)
(13-61) 2F2 8. 7 mi NNE 28 (53/53) 27 (53/53) 0 (14-53)
(13-61)
Sr-89 32 0.5 0.8 (2/28) 5Sl 1.0 mi E 0.9 (1/4)
- (0/4) 0 (0.6-0.9)
Sr-.90 32 0.2 0.5 (21/28) 251 1575 ft NNE 0.6 (3/4) 0.5 (4/4) 0 (0.2-0.8)
(0.3-0.8)
(0.2-0.7)
Gamma 32 Be-7 94 (28/28) 2F2 8. 7 mi NNE 102 (4/4) 60 (4/4) 0 (70-130)
(73-130)
(58-99)
Co-60 0.3
- (0/28) 3H3 llO m"i NE 0.7 (1/4) 0.7 (1/4) 0 Ru-106 0.6
-3. 7 (1/28) 3H3 110 mi NE 4.6 (1/4) 4.6 (1/4) 0 Sb-125 0.8 1.5 (6/28) lFl 5.8 mi N 2.0 (1/4)
- (0/4) 0 (0.8-2.3)
Cs-137 0.5 1.3 (25/28) 16El 4.1 mi NNW 1.6 (3/4) 1.2 (4/4) 0 (0.6-2.3)
(1.0-2.1)
(0.4-1.6)
Ce-144 1.6 5.0 (19/28) lODl 3.9 mi SSW 6.5 (2/4) 4.2 (2/4) 0 (1.8-8.4)
(4.5-8.4)
(3.7-4.6)
Air Iodine 1-131 423 4.2
- (0/370)
None Detected
- (0/53) 0 (10-3 pCi/m3)
Precipitation Alpha 12 0.4 0.8 (2/12) 2F2 8.7 mi NNE 0.8 (2/12)
No Control 0
(pCi/l)
(0.7-0".9)
(0.7-0.9)
Location Beta 12 3.4 8 (10/12) 2F2 8.7 mi NNE 8 (10/12)
No Control (2.4-21) 0 (2. 4-21)
Location H-3 12 102 526 (1/12) 2F2 8.7 mi NNE 526 (1/12)
No Control 0
Sr-89 4
0.6
- (d/4)
Location None Detected No Control 0
Sr-90 4
0.8 (2/4)
Location 0.5 2F2 8.7 mi NNE 0.8 (2/4)
No Control 0
(0.4-1.2)-
(0.4-1.2)
Location Gamma 4
- (0/4)
None Detected No Control 0
Location
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORfNG PROGRAM
SUMMARY
SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 SALEM COUNTY, NEW JERSEY JANUARY 1, 1979 TO DECEMBER 31, 1979 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATIONS NON ROUTINE SAMPLED OF ANALYSES DETECTION MEAN**
NAME MEAN MEAN REPORTED
{UNIT OF MEASUREMENT)
PERFORMED (LLD)*
(RANGE)
DISTANCE AND DIRECTION (RANGE}
(RANGE)
MEASUREMENTS Direct Radiation Gamma 300 6.00 (252/252) llSl 0.09 mi SW
- 13. 66 (12/12) 6.17 (48/48) 0 (mrem/sta. month)
Dose (monthly)
(3.63-26.05)
(4.24-26.05)
(5.33-7.62)
Gamma 100 5.69 (84/84) llSl 0.09 mi SW 13.00 (4/4) 5.88 (16/16) 0 Dose (quarterly)
(3.66-22.53)
(4.02-22.53)
(5.05-6.77)
Surface Water Alpha 54 0.2
- 1. 9 (11/44) llAl 0.2 mi SW 2.9 (2/11) 1.1 (3/10) 0 (pCi/l)
(0.2-4.5)
(2. 0-3. 7)
(0.5-1.7)
Beta 54 3.2 27 (42/44)
?El 4.5 mi SW 39 (10/10) 22 (10/10) 0 (2.3-107)
(8.1-107)
(3.8-59)
H-3 54 96 lll (8/44)
?El 4.5 mi SW 123 (1/10) 163 ( 1/10) 0 (73-218)
Sr-89 20 0.6 0.5 (1/16) 1F2 7.1 mi N
- 0. 5 (1/4)
- (0/ 4) 0 Sr-90 20 0.4 0.4 (3/i6) 12Cl 2.5 mi WSW 0.7 (2/4) 0.7 (2/4) 0 N
(0.4-0.5)
(0.4-1.0)
(0. 4-1.0)
+::>
Gamma 54 K-40 7.8 41 (28/44)
?El 4.5 mi SW 55 (9/ 10) 30 (6/10) 0 (15-90)
(25-78)
(22-54)
Well Water (pCi/l)
Alpha 36 0.7
- (0/24)
None Detected
- (0/12) 0 Beta 36 3.4 9.5 (22/24) 4Sl Site Well 14 (12/12) 9.9 (12/12) 0 (2.1-25)
(9.3-25)
(6. 9-16)
H-3 36 96
- (0/24)
None Detected
- (0/12) 0 K-40 36 8.0 (24/24) 4Sl Site Well 14 (12/12) 9.9 (12/12) 0 (2.1-18)
(ll-18)
(7.9-14)
Sr-89 12 0.6
- (0/8)
None Detected
- (0/ 4) 0 Sr-90 12 0.4
- (0/8)
None Detected
- (0/4) 0 Gamma 12 K-40 7.8 13 (5/8) 4Sl Site Well 14 (4/4) 9.1 (1/4) 0 (10-19)
(10-19)
Potable Water Alpha 24 0.4 0.9 (13/24) 2F3 8 mi NNE 0.9 (13/24)
No Control 0
Raw-Treated (0. 4-1. 7)
(0.4-1. 7)
Location (pCi/l)
Beta 24 4.0 (24/24) 2F3 8 mi NNE 4.0 (24/24)
No Control 0
(2.3-12)
(2.3-12)
Location H-3 24 113 135 (3/24) 2F3 8 mi NNE 135 (3/24)
No Control 0
(84-198)
(84-198)
Location
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 SALEM COUNTY, NEW JERSEY JANUARY 1, 1979 TO DECEMBER 31, 1979 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST'MEAN CONTROL LOCATIONS NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN**
NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT)
PERFORMED (LLD)*
(RANGE)
DISTANCE AND DIRECTION (RANGE)
(RANGE)
MEASUREMENTS Potable Water (cont.)
Sr-89 8
0.6 0.8 (1/8) 2F3 8 mi NNE 0.8 (1/8)
No Control 0
Raw-Treated Lo ca ti on (pCi/l)
Sr-90 8
0.5
.0.5 (5/8) 2F3 8 mi NNE 0.5 (5/8~
tJo Control 0
(0.4-0. 7)
(0.4-0.7 Location K-40 24 1.8 (24/24) 2F3 8 mi NNE 1.8 (24/24)
No Control 0
(0.72-3.1)
(0.72-3.1)
Location Gamma 8
K-40 7.8 54 (1/8) 2F3 8 mi NNE 54 (1/8)
No Control 0
Location Bent hos Sr-89 8
1.5 14 (1/6) llAl 0.2 mi SW 14 (1/2)
- (0/2) 0 (pCi/g-dry)
Sr-90 8
0.6 76 (1/6) 16Fl 6.9 mi NW 76 (1/2)
- (0/2) 0 N
Ul Sediment Sr-90 8
(pCi/g-dry) 0.03
- (0/6)
None Detected
- (0/2) 0 Gamma 8
K-40 14 (6/6) 12Cl 2.5 mi WSW 17 (2/2) 17 (2/2) 0 (12-17)
(15-i8)
(15-18)
Mn-54 0.02 0.04 (1/6) llAl 0.2 mi SW 0.04 (1/2)
- ( 0/2) 0 Co-60 0.03 0.06 (3/6) llAl 0. 2 mi SW 0.09 (1/2)
- (O/i) 0 (0.03-0.09)
Cs-137 0.02 0.15 (4/6) llAl 0.2 mi SW 0.22 (2/2) 0.04 (1/2) 0 (0.08-0.28)
(0.16-0.28) ce-141 0.08 0.11 (1/6) 16Fl 6.9 mi NW 0.11 (1/2)
- (0/2) 0 Ra-226 0.61 (6/6) 12Cl 2.5 mi WSW
- 0. 78 (2/2)
- 0. 78 (2/2) 0 (0.40-0.85)
(0.62-0.93)
(0.62-0.93)
Th-232 0.72 (6/6) 12Cl 2.5 mi WSW 0.96 (2/2) 0.96 (2/2) 0 (0.40-1.0)
(0.81-1.1)
(0.81-1.1)
Milk I-131 144 0.04 0.15 (3/120) 3Gl 17 mi NE 0.66 (1/24) 0.66 (1/24) 0 (pCi/l)
(0.14-0.18)
Sr-89 72 1.3 3.4 (3/60) 14Fl 5.5 mi WNW 5.9 (l/12) 3.3 (2/12) 0 (1. 7-5.9)
(2.2-4.4)
Sr-90 72 1.5 3.6 (49/60) 5F2 7 mi E
- 6. 3 (10/12) 4.3 (9/12) 0 (0.9-12)
(1.5-12)
(2.4-6.1)
L___
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 SALEM COUNTY, NEW JERSEY JANUARY 1, 1979 TO DECEMBER 31, 1979 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATIONS NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN**
NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT)
PERFORMED (LLD)*
(RANGE)
DISTANCE AND DIRECTION (RANGE)
(RANGE)
MEASUREMENTS Milk (cont.)
Gamma 72 K-40 1242 (60/60) 2F4 6.3 mi NNE 1290 ( 11/11) 1168 (12/12) 0 (630-1900)
(880-1800)
(770-1500)
Cs-137 0.6 2.2 (37/60) 5F2 7 mi E
- 2. 8 ( 10/12) 2.0 (6/12) 0 (0.7-4.5)
( 1.8-4. 5)
( 1. 4-3. 2)
Edible Fish H-3 6
91 74 (3/4) llAl 0.2 mi SW 108 (2/2) 82 (1/2) 0 (pCi/l)
(aqueous)
(68-148)
{68-148)
H-3 5
327 (4/4) 12Cl 2.5 mi WSW 381 (1/1) 381 (1/1).
0 (organic)
( 176-529)
(pCi/ g-dry)
Sr-89 6
0.1
- (0/4)
None Detected
- (0/2) 0 (bones) 0.49 (3/4)
Sr-90 6
0.06 llAl 0.2 mi SW 1.2 (1/2) 0.79 (2/2) 0 N
(bones)
(0.07-1.2)
(0.18-1.4) m
{pCi/ g-wet)
Gamma 6
K-40 2.6 (4/4) 12Cl 2.5 mi WSW 2.5 (2/2) 2.5 (2/2) 0 (1.5-3.7)
(0.6-4.4)
(0.6-4.4)
Blue Crab Sr-89 4
0.2
- (0/4)
None Detected 0
(pCi/g-dry)
(shells)
Sr-90 4
0.38 (2/2) 12Cl 2.5 mi WSW
- 0. 48 (2/2) 0.48 (2/2) 0 (shells)
(0.32-0.43)
(0.46-0.49)
(0.46-0.49)
(pCi/l)
H-3 (flesh) 2 248 (1/1) 12Cl 2.5 mi WSW 248 (1/1) 248 (1/1) 0
( pCi I g-wet)
Sr-89 (flesh) 0.03
- (0/1)
None Detected Sample lost 0
Sr-90 1
0.01 (flesh)
- (0/1)
None Detected Sample lost 0
Gamma 2
- 1. 7 (1/1) llAl 0.2 mi SW
- 1. 7 {1/1) 1.6 (1/1) 0 Fruits & Vegetables Sr-89 17 0.005
- (0/8)
None Detected
- (0/9) 0
( pCi I g-wet)
Sr-90 17 0.003 0.063 (4/8) 1F3 mi 0.24 (1/2) 0.006 (2/9) 0 (0.002-0.24)
(0.005-0.007)
Gamma 17 K-40 3.3 (8/8) 3El 4.1 mi NE 6.6 (1/1) 1.9 (9/9) 0 (1. 9-6. 6)
(1.0-2.6)
N
'1 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 SALEM-COUNTY, NEW JERSEY JANUARY 1, 1979 TO DECEMBER 31, 1979 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOT AL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATIONS NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN**
NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT)
PERFORMED (LLD)*
(RANGE)
DISTANCE AND DIRECTION (RANGE)
(RANGE)
MEASUREMENTS Game Sr-89 5
0.009 0.2 (2/3) 4El mi 0.2 (1/1)
- (0/2) 0 (pCi/g-dry)
(bones)
(0.1-0.2)
Sr-90 5
0.55 (3/3) 4El mi 1.0 (1/1) 0.18 (2/2) 0 (bones)
(0.17-1.0)
(0.029-0.33)
(pCi/g-wet)
Gamma 6
(flesh)
K-40 2.7 (4/4) 4El mi 3.6 (1/1) 2.6 (2/2) 0 (1.9-3.6)
(2.0-3.2)
Cs-137 0.008 0.008 (1/4) 3El 4.1 mi NE 0.008 ( 1/2)
- (0/2) 0 Beef Gamma 2
(pCi/g-wet)
K-40 2.2 (2/2) 14Fl 5.5 mi WNW 2.4 (1/1)
No Control 0
( 1. 9-2. 4)
Sample Available Beef Thyroid Gamma 2
(pCi/g-wet)
K-40 1.6 1.1 (1/2) 14Fl 5.5 mi WNW 1.1 (1/2)
No Control 0
Sample Available Fodder Crops Gamma 12 (pCi/g-dry)
Be-7 2.0 (1/10) 15Fl mi 2.0 (1/2)
- (0/2) 0 K-40 12 (10/10) 13E3 mi 21 (2/2) 13 (2/2) 0 (1.3-35)
(7.1-35)
(5.2-20)
LLD listed is the lowest calculated LLD during reporting period. Strontium-89 and -90 detection levels are Minimum Detectable Levels (MDL).
Mean calculated using values above LLD or MDL only.
Fraction of measurements above LLD or MDL are in parentheses.
APPENDIX B SAMPLE DESIGNATION AND LOCATIONS 29
I'.
APPENDIX B Sample Designation RMC identifies samples by a three part code.
The first two letters are the power station identification code, in this case 11 SA 11 The next three letters are for the media sampled.
AIO
= Air Iodine GAM = Game APT = Air Particulates GAD = Deer ECH
= Hard Shell Blue Crab IDM = Immersion Dose (TLD)
ESB
= Benthos MLK = Milk ESF = Edible Fish PWA = Potable Water; (PWR = raw, P~~T = treated)
ESS
= Sediment RWA = Rain Water FPB
= Beef S~~A = Surface ~~ater FPV
= Food Products, Various THB
= Bovine Thyroid FPG
= Corn VGT = Fodder Crops FPL = Green Leafy Vegetables WWA = Well Water The last four syni:>ols are a location code based on direction and distance from the site. Of these, the first two represent each of the sixteen angular sectors of 22.5 degrees centered about the reactor site. Sector one is divided evenly by the north axis and other sectors are numbered in a clockwise direction; i.e., 2=NNE, 3=NE, 4=ENE, etc.
The next digit is a letter which represents the radial distance from the plant:
s =On-site location E = 4-5 miles off-site A = 0-1 miles off-site F = 5-10 miles off-site B = 1-2 miles off-site G = 10-20 miles off-site c = 2-3 miles off-site H = >20 miles off-site D = 3-4 miles off-site The last number is the station numerical designation within each sector and zone; e.g., 1,2,3,..* For example, the designation SA-WWA-5Dl would indicate a sample in the SNGS program SA, consisting of well water (WWA), which had been collected in the 22.5 degree sector centered on east axis (5), at a distance of 3 to 4 miles off-site (D).
The number 1 indicates that this is sampling station #1 in the designated area.
31
Sampling Locations All Sampling locations and specific information about the individual locations are given in Table B-1.
Maps B-1 and B-2 show the locations of sampling stations with respect to the site.
TABLE B-1 STATION STATION CODE LOCATION 2Sl 1575 ft. NNE of vent 4Sl Site well #5 ENE of Vent 5Sl 1.0 mi. E of vent; site access road 6Sl 0.2 mi. ESE of vent; observation platform 6S2 0.2 mi. ESE of vent; observation bldg.
7Sl 0.12 mi. SE of vent; station personnel gate lOSl 0.14 mi. SSW of vent; site shoreline llSl 0.09 mi. SW of vent; site shoreline llAl 0.2 mi. SW of vent; outfall area 11A2 0.2 mi.
si~ of vent; water intake 12Cl 2.5 mi. WSW of vent; west bank of Delaware river 16Cl 2.5 mi. NNW of vent; 2 mi. E of Augustine Creek 4Dl 3-4 mi. ENE of vent 5Dl 3.5 mi. E of vent; local farm lODl 3~9 mi. SSW of vent; Taylor 1s Bridge Spur llDl 3.5 mi. SW of vent 14Dl 3.4 mi. WNW of vent; Bay View, Delaware 2El 4.4 mi. NNE of vent; local farm 3El 4.1 mi. NE of vent; local farm 4El 4-5 mi. ENE of vent 7El 4.5 mi SE of vent; 1 mi W of Mad Horse Creek 32 SAMPLE TYPES APT,AIO, IDM W~JA IDM,APT,AIO IDM IDM IDM IDM IDM SWA,ESF,ECH, ESB,ESS SWA SWA,ESF,ECH, ESB,ESS SWA GAD IDM,VGT,WWA, APT,AIO, FPG IDM,APT,AIO GAM IDM IDM,FPV IDM,THB,WWA, GAM,FPB 9 FPV,VGT GAM Si~A, ES F, ESB, ESS
llEl 13El 13E3 16El 1Fl 1F2 1F3 2Fl 2F2 2F3 2F4 5Fl 5F2 6Fl 7F2 llFl 13Fl 14Fl 15Fl 15F2 16Fl lGl 3Gl 2Hl 3Hl 3H3 3H4 TABLE B-1 (CONT.)
4-5 mi. SW of vent 4.2 mi. W of vent; Diehl House Lab 4.9 mi W of vent; local farm 4.1 mi. NNW of vent; Port Penn 5.8 mi. N of vent; Fort Elfsborg 7.1 mi. N of vent; midpoint of Delaware River 5.9 mi. N of vent; local farm 5.0 mi. NNE of vent; local farm 8.7 mi. NNE of vent; Salem substation 8.0 mi. NNE of vent; Salem Water Company 6.3 mi NNE of vent; local farm 8.0 mi. E of vent 7.0 mi. E of vent; local farm 6.4 mi. ESE of vent; Stow Neck Road 9.1 mi. SE of vent; Bayside, New Jersey 5.2 mi. SW of vent; Taylor's Bridge, Delaware 9.8 mi. W of vent; Middletown, Delaware 5.5 mi. WNW of vent; local farm 5.2 mi. NW of vent; local farm 8.7 mi. NW of vent; C & D Canal 6.9 mi. NNW of vent; C & D Canal 13 mi. N of vent; local farm 17 mi. NE of vent; local farm 34 mi. NNE of vent; RMC, Phila.
32 mi. NE of vent; National Park, N.J.
110 mi. NE of vent; Maplewood Laboratories 18 mi. NE of vent; local farm 33 GAM IDM MLK, VGT, FPV IDM,APT,AIO IDM,APT SWA FPL MLK IDM,APT,AIO,m~A PWR,PWT VGT,MLK,FPG,FPV IDM MLK,VGT IDM IDM IDM IDM VGT,MLK,FPB,THB VGT,MLK SWA SWA,ESB,ESS FPV,FPL,FPG IDM, VGT,MLK IDM IDM IDM,APT,AIO FPV,FPL,FPG
- (.
I'
0 I
I i
L:::
L=-::!
SCALE OF MILES MAP B-1 ON SITE SAM PL ING LOCATIONS ARTIFICIAL ISLAND 34
MAP B-2 OFF SITE SAMPLING LOCATIONS ARTIFICIAL ISLAND 0
1 H-H I 2
3 I
I 4 I SCA.LIE Of MILIS 35
APPENDIX C 1979 DATA TABLES 37
DATA TABLES Appendix C presents the analytical results of the 1979 Artificial Island Radiological Environmental Monitoring Program for the period of January 1 to December 31.
TABLE NUMBER C-1 C-2 TABLE TITLE Concentrations of Gross Beta Emitters in Air Particulates Concentrations of Gross Alpha Emitters in Air Particulates C-3 Concentrations of Gamma Emitters in Quarterly Composites of PAGE 41 43 Air Particulate Samples.........................................*
44 C-4 Concentrations of Strontium-89 and -90 in Quarterly Composites of Air Particulate Samples............*..........................
48 C-5 Concentrations of Iodine-131 in Filtered Air.....................
49 C-6 Sampling Dates for Air Samples................................ ~..
51 C-7 Concentrations of Tritium, Gross Alpha and Gross Beta Emitters in Precipitation....................................................
56 C-8 Concentrations of Strontium-89 and -90 and Gamma Emitters in Quarterly Composites of Precipitation...... *................. *...
57 C-9 Direct Radiation Measurements - Monthly TLD Results..............
58 C-10 Direct Radiation Measurements - Quarterly TLD Results.........*..
59 C-11 Concentrations of Tritium in Surface Water.......................
60 C-12 Concentrations of Gross Alpha Emitters in Surface Water..........
61 C-13 Concentrations of Gross Beta Emitters in Surface Water.....***...
62 C-14
- Concentrations of Gamma Emitters in Surface Water................
63 C-15 Concentrations of Strontium-89 and -90 in Surface Water..........
64 C-16 Concentrations of Tritium, Gross Alpha and Gross Beta Emitters, and Potassium-40 in Well Water.......................................
65 C-17 Concentrations of Strontium-89 and -90, and Garrrna Emitters in Quarterly Composites of Well Water...............................
66 C-18 Concentrations of Tritium, Gross Alpha and Gross Beta Emitters, and Potassium-40 in Raw and Treated Potable Water................*...
67 39
I TABLE NUMBER DATA TABLES (cont.)
TABLE TITLE PAGE C-19 Concentrations of Strontium-89 and -90, and Gamma Emitters in Quarterly Composites of Potable Water....................*... 68 C-20 Concentrations of Strontium-89 and -90 in Benthos............ 69 C-21 Concentrations of Stronti um-90 and Gamma Emitters in Sediment.
70 C-22 Concentrations of Iodine-131 in, Milk......................... 71 C-23 Concentrations of Gamma Emitters and Strontium-89 and -90 in Mil k..........
G
- 72 C-24 Sampling Dates for Milk Samples...........**................. 74 C-25 Concentrations of Gamma Emitters in Edible Fish...***........ 77 C-26 Concentrations of Strontium-89 and -90, and Tritium in Edible Fish Samples **....**.....*...*....**................*. 78 C-27 Concentrations of Gamma Emitters in Blue Crab Samples......... 79 C-28 Concentrations of Strontium-89 and -90, and Tritium in B 1 ue Crab S amp l es * *. * *....... *......... *............ * *........
8 o C-29 Concentrations of Strontium-89 and -90, and Gamma Emitters in Food Products.*.*...**.***..*....*.........*....*............ 81 C-30 Concentrations of Strontium-89 and -90, and Ganma Emitters in Meat, Game and Bovine Thyroid....... *... *. *... *. *.. * *. *. *. *..
82 C-31 Concentrations of Gamma Emitters in Fodder Crop Samples...... 83 C-32 Typical LLDs for Gamma Spectrometry 84 40
TABLE C-1 CONCENTRATIONS OF GROSS BETA EMITTERS IN AIR PARTICULATES Results in Units of 10-3 pCi/m3 +/- 2 sigma STATION NO.
MONTH SA-APT-2Sl SA-APT-5Sl SA-APT-501 SA-APT-1001 SA-APT-16El SA-APT-lFl SA-APT-2F2 SA-APT-3H3 AVERAGE JANUARY*
54+/-7 49+/-7 45+/-7 49+/-7 48+/-7 44+/-7 48+/-7 42+/-7 47+/-7 43+/-6 36+/-6 40+/-6 34+/-5 35+/-6 37+/-6 41+/-6 39+/-6 38+/-6 30+/-5 34+/-6 36+/-5 33+/-5 30+/-5 33+/-5 33+/-5 32+/-6 33+/-4 18+/-4 17+/-4 23+/-5 15+/-5 14+/-5 17+/-5 16+/-4 16+/-4 17+/-5 FEBRUARY 31+/-5 28+/-5 30+/-5 29+/-5 33+/-6 31+/-5 31+/-5 20+/-5 29+/-8 46+/-6 42+/-6 44+/-6 37+/-5 39+/-6 47+/-6 40+/-5 38+/-5 42+/-7 36+/-5 41+/-6 34+/-5 (1) 37+/-5 43+/-6 38+/-5 38+/-6 38+/-6
.p,
'20+/-5 15+/-5 21+/-5 22+/-3 14+/-6 12+/-5 17+/-5 26+/-6 18+/-9 I-;
MARCH 13+/-4 21+/-5 18+/-5 16+/-4 19+/-5 14+/-4 17+/-4 22+/-5 18+/-6 31+/-5 26+/-5 27+/-5 30+/-5 26+/-5 30+/-5 33+/-6 28+/-5 29+/-5 37+/-6 34+/-6 33+/-5 33+/-6 32+/-6 37+/-6 37+/-6 33+/-5 35+/-4 21+/-5 20+/-4 21+/-4 22+/-4 18+/-4 20+/-4 16+/-4 19+/-4 20+/-4 47+/-8 42+/-8 47+/-8 40+/-8 52+/-10 40+/-10 39+/-7 46+/-10 44+/-9 APRIL 19+/-5 21+/-6 17+/-5 13+/-5 23+/-6 31+/-11 17+/-5 14+/-5 19+/-12 38+/-7 37+/-7 38+/-7 33+/-6 31+/-6 39+/-7 39+/-7 31+/-6 36+/-7 22+/-5 16+/-5 20+/-5 13+/-4 13+/-5 18+/-5 19+/-5 22+/-5 18+/-7 40+/-6 40+/-6 40+/-6 45+/-6 40+/-6 48+/-7 37+/-6 35+/-6 41+/-8 35+/-6 30+/-5
. 43+/-6 33+/-6 26+/-6 35+/-6 36+/-6 37+/-6 34+/-10 MAY 33+/-5 35+/-6 32+/-5 36+/-5 34+/-5 36+/-5 36+/-5 32+/-5 34+/-4 21+/-5 21+/-5 21+/-5 18+/-5 16+/-5 22+/-5 20+/-5 28+/-5 21+/-7 17+/-4 15+/-4 16+/-4 18+/-4 14+/-4 16+/-4 19+/-4 13+/-4 16+/-4 23+/-4 19+/-4 24+/-4 21+/-4 29+/-5 22+/-4 27+/-5 23+/-4 24+/-6 JUNE 19+/-5 23+/-5 20+/-5 19+/-4 18+/-5 22+/-5 21+/-5 17+/-5 20+/-4 43+/-6 38+/-6 42+/-6 41+/-6 39+/-6 38+/-6 44+/-6 40+/-6 41+/-5 40+/-6 39+/-6 28+/-5 33+/-5 29+/-5 33+/-5 35+/-5 30+/-5 33+/-9 25+/-5 27+/-5 25+/-5 27+/-5 24+/-5 22+/-5 28+/-5 23+/-5 25+/-4
+::>
N TABLE C-1 (cont.)
CONCENTRATIONS OF GROSS BETA EMITTERS IN AIR PARTICULATES Results in Units of 10-3 pCi/m3 +/- 2 sigma MONTH SA-APT-2Sl SA-APT-5Sl SA-APT-501 JULY 29+/-5 31+/-5 28+/-5 25+/-5 25+/-5 23+/-5 31+/-5 26+/-5 13+/-6 30+/-5 23+/-5 31+/-6 18+/-5 19+/-5 (1)
AUGUST 34+/-6 29+/-5 36+/-6 32+/-5 30+/-5 25+/-5 22+/-5 23+/-5 21+/-5 23+/-5 22+/-5 18+/-5 SEPTEMBER 19+/-4 15+/-4 18+/-4 25+/-6 21+/-5 18+/-6 23+/-5 17+/-5 18+/-5 21+/-4 15+/-4 19+/-4 24+/-5 19+/-5 19+/-5 OCTOBER 23+/-4 20+/-4 26+/-5 14+/-5 14+/-5 17+/-5 30+/-5 32+/-5 37+/-6 24+/-5 27+/-5 25+/-5 NOVEMBER 25+/-5 27+/-6 27+/-6 26+/-5 24+/-5 24+/-5 44+/-6 42+/-6 46+/-6 48+/-6 44+/-6 51+/-7 24+/-5 23+/-5 24+/-5 DECEMBER 28+/-5 28+/-5 28+/-6 23+/-4 26+/-5 28+/-5 23+/-4 24+/-4 20+/-4 17+/-4 18+/-4 15+/-4 AVERAGE 28+/-19 27+/-18 28+/-19 Sampling dates can be found on Table C-6.
(1)
Sample was destroyed prior to shipment.
STATION NO.
SA-APT-1001 SA-APT-16El SA-APT-lFl 22+/-4 25+/-5 29+/-5 25+/-5 24+/-5 25+/-5 25+/-5 25+/-5 42+/-10 22+/-5 24+/-5 23+/-5 16+/-5 14+/-5 18+/-5 26+/-4 25+/-5 32+/-6 26+/-5 22+/-5 25+/-5 18+/-4 23+/-5 20+/-5 21+/-5 17+/-5 17+/-5 15+/-4 15+/-4 15+/-4 21+/-5 15+/-5 18+/-6 15+/-5 13+/-5 15+/-5 19+/-4 17+/-4 20+/-5 22+/-5 18+/-5 19+/-5 21+/-4 21+/-4 23+/-5 12+/-5 7.8+/-4.8 11+/-5 31+/-5 29+/-5 29+/-5 20+/-5 17+/-5 23+/-5 23+/-5 24+/-5 22+/-5 26+/-5 21+/-4 21+/-5 44+/-6 38+/-5 46+/-7 45+/-6 34+/-5 49+/-7 24+/-5 24+/-5 26+/-5 27+/-5 23+/-5 27+/-6 24+/-5 23+/-4 24+/-5 20+/-4 17+/-4 21+/-4 19+/-5 19+/-5 17+/-5 26+/-18 25+/-19 27+/-20 SA-APT-2F2 SA-APT-3H3 AVERAGE 30+/-5 25+/-5 27+/-6 20+/-5 26+/-5 24+/-4 30+/-5 30+/-5 28+/-16 25+/-5 32+/-5 26+/-8 20+/-5 20+/-5 18+/-4 30+/-6 30+/-5 30+/-7 27+/-5 26+/-5 27+/-6 25+/-5 21+/-6 22+/-4 19+/-5 24+/-5 20+/-6 20+/-5 20+/-4 17+/-5 22+/-5 19+/-5 20+/-6 19+/-5 16+/-5 17+/-6 22+/-5 15+/-4 19+/-5 21+/-5 21+/-5 20+/-4 23+/-4 26+/-4 23+/-4 14+/-5 13+/-5 13+/-5 35+/-6 33+/-5 32+/-6 23+/-5 24+/-5 23+/-6 21+/-5 18+/-5 23+/-6 22+/-5 21+/-4 23+/-4 51+/-6 37+/-6 44+/-9 53+/-7 61+/-7 48+/-16 34+/-5 21+/-4 25+/-8 27+/-6 22+/-5 26+/-5 30+/-5 23+/-5 25+/-5 27+/-5 31+/-6 23+/-9 19+/-5 18+/-5 18+/-3 28+/-19 27+/-19 27+/-19
STATION NO.
JANUARY*
SA-APT-16El 0.8+/-0.5 0.6+/-0.6
<0.8
<0.7 SA-APT-3H3
- 1. 6+/-0. 7 0.9+/-0.6 1.0+/-0. 7
<0.6
+:>
w STATION NO.
JULY SA-APT-16El 0.5+/-0.5 0.7+/-0.4 1.0+/-0. 7 0.8+/-0.5 0.6+/-0.6 SA-APT-3H3
<0.5
<0.3 1.0+/-0. 7 0.8+/-0.5 0.8+/-0.6 Sampling dates can be TABLE C-2 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN AIR PARTICULATES Results in Units of 10-3 pCi/m3 +/- 2 sigma FEBRUARY MARCH APRIL MAY 1.3+/-0.6 1.0+/-0. 6
<1.1 0.6+/-0.5 1.8+/-0. 7
- 1. 3+/-0. 6 0.5+/-0.4
- 1. 7+/-0. 8 1.6+/-0.6 1.1+/-0. 6 0.7+/-0.5 0.6+/-0.5
- 1. 2+/-0. 7
<0.6 0.7+/-0.5 0.7+/-0.5
<l. 3 0.5+/-0.4 0.9+/-0.5
- 1. 2+/-0.6
<0.9
- 1. 0+/-0. 6
- 1. 8+/-0.6 0.7+/-0.5 0.8+/-0.6 1.8+/-0. 7
- 1. 5+/-0.6 0.9+/-0.5 1.0+/-0. 5
<0.6 0.8+/-0.5 0.6+/-0.5 1.1+/-0.6 1.1+/-0. 5
- 1. 2+/-1.2 1.6+/-0.6 JUNE 0.7+/-0.5 0.7+/-0.5 0.6+/-0.5 0.8+/-0.6 1.1+/-0. 6 1.2+/-0.6 0.9+/-0.5 0.6+/-0.5 AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER 1.0+/-0.6 0.7+/-0.6 1.0+/-0. 5 2.2+/-0.8 2.4+/-0.8 1.1+/-0. 7
- 1. 3+/-0. 8 1.1+/-0.8 2.0+/-0.7
- 1. 7+/-0. 6 1.4+/-0.6 1.1+/-0. 7 3.0+/-0.8 2.4+/-0.9
- 1. 2+/-0. 5 1.1+/-0. 7 0.7+/-0.5 1.9+/-0.9 2.6+/-0.9 1.1+/-0. 7
<1.0 1.4+/-0. 7 1.0+/-0.6 0.8+/-0.6 1.4+/-0.6 2.2+/-0.8 3.3+/-0.8
- 1. 2+/-0. 7
- 1. 4+/-0. 8 1.1+/-0. 7 1.6+/-0.7 1.6+/-0.7 1.9+/-0.9 1.2+/-0.6 4.4+/-1.0 3.6+/-1.1
- 1. 7+/-0. 7 1.0+/-0.6
<0.7 2.9+/-0.9 4.7+/-1.l 0.7+/-0.5
<0.8 1.9+/-0. 7 found on Table C-6.
AVERAGE
- 1. 2+/-1. 2 1.4+/-1.8
NUCLIDES*
Be-7 Co-60 Ru-106 Sb-125
~
~
Ce-144 NUCLIDES*
Be-7 Co-60 Ru-106 Sb-125 Cs-137 Ce-144 TABLE C-3 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES Results in Units of 10-3 pCi/m3 +/- 2 sigma STATION NUMBER AND DATE SA-APT-2Sl 1-02-79 3-31-79 6-25-79 10-01-79 to to to to 3 79 6-25-79 10-01-79 1-02-80 92+/-9 110+/-11 98+/-10 87+/-9
<0.9
<0.5
<0.8
<0.3
<4.9
<5.0
<3.4
<3.2
<1.1 1.3+/-0.8
< 1.1
<0.9
- 1. 2+/-0. 4 2.2+/-0.3 1.1+/-0. 4 0.8+/-0.4
- 3. 7+/-1.4 7.0+/-1.8 2.9+/-1.4
<3.2 STATION NUMBER AND DATE SA-APT-5Sl 1-02-79 3-31-79 6-25-79 10-01-79 to to to to 3-31-79 6-25-79 10-01-79 1-02-80 100+/-10 120+/-12 82+/-8 88+/-9
<0.9
<0.5
<0.5
<0.8
<4.9
<5.0
<3.4
<3.2 0.8+/-0.7
<1.3
<1.0
<1.1 1.1+/-0. 4 1.9+/-0.5 1.4+/-0.4
<0.5
- 4. 8+/-1.3 6.6+/-4.2 3.7+/-1.8
<1.6
NUCLIDES*
Be-7 Co-60 Ru-106 Sb-125 Cs-137 O'I Ce-144 NUCLIDES*
Be-7 Co-60 Ru-106 Sb-125 Cs-137 Ce-144 lt\\DLC. 1,,-..)
~(;U!ll,.J CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES Results in Units of 10-3 pCi/m3 +/- 2 sigma STATION NUMBER AND DATE SA-APT-5Dl 1-02-79 3-31-79 6-25-79
. 10-01-79 to to to to 3-31-79 6-25-79 10-01-79 1-02-80 100+/-10 95+/-10 79+/-8 85+/-9
<0.9
<0.5
<1.0
<0.8
<4.9
<5.0
<3.4
<3.2
<1.3
<1.1
<1. 3
<1.1 1.4+/-0. 5 1.7+/-0.6
- 1. 2+/-0. 4 0.7+/-0.4 4.8+/-1.4 7.3+/-2.5 2.0+/-1.6
<1.6 STATION NUMBER AND DATE SA-APT-lODl 1-02-79 3-31-79 6-26-79 10-01-79 to to to to 3-31-79 6-26-79 10-01-79 1-02-80 85+/-9 100+/-10 70+/-7 74+/-7
<0.9
<0.3
<0.6
<0.5
<4.9
<3.3
<3.4
<3.2
<1.3
<1.1
<1.0
<0.9 1.1+/-0.4 1.8+/-0.5 0.9+/-0.3 0.6+/-0.2 4.5+/-1.4 8.4+/-3.0
<3.5
<1.6
.~
NUCLIDES*
Be-7 Co-60 Ru-106 Sb-125
.+:>
Cs-137 CTI Ce-144 NUCLIDES*
Be-7 Co-60 Ru-106 Sb-125 Cs-137 TABLE C-3 (cont.)
CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES Results in Units of 10-3 pCi/m3 +/- 2 sigma STATION NUMBER AND DATE SA-APT-16El 1-02-79 3-31-79 6-26-79 10-01-79 to to to to 3-31-79 6-26-79 10-01-79 1-02-80 100+/-10 120+/-12 84+/-8 79+/-8
<0.9
<0.8
<0.8
<0.3
<4.9
<4.9
<3.4
<0.6 1.1+/-0.8
<1.4
<10
<0.9
- 1. 6'+/-0. 5 2.1+/-0.6 1.0+/-0. 3
<0.08 4.6+/-1.7 6.8+/-1.8 1.8+/-1.4
<3.2 STATION NUMBER AND DATE SA-APT-lFl 1-02-79 4-01-79 6-25-79 10-01-79 to to to to 4-01-79 6-25-79 10-01-79 1-02-80 89+/-9 110+/-11 90+/-9 78+/-8
<0.9
<0.8
<0.8
<0.5
<4.9
<5.0
<3.4
<3.2
<1.3
<1.3 2.0+/-1.4
<0.9 1.1+/-0.4 2.3+/-0.4 1.0+/-0.4
<0.5 2 O+l 11
- Z+1 i::
2 _, +1
~
- /2- ']
NUCLIDES*
Be-7 Co-60 Ru-106 Sb-125 Cs-137 Ce-144 NUCLIDES*
Be-7 Co-60 Ru-106 Sb-125 Cs-137 Ce-144 TABLE C-3 (cont.)
CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES Results in Units of 10-3 pCi/m3 +/- 2 sigma STATION NUMBER AND DATE SA-APT-2F2 1-02-79 3-31-79 6-25-79 10-01-79 to to to to 3-31-79 6-25-79 10-01-79 1-02-80 110+/-11 130+/-13 73+/-7 93+/-9
<0.8
<0.5
<0.6
<0.5 3.7+/-2.9
<5.0
<3.4
<3.2 2.3+/-2.0
- 1. 2+/-1.0
<LO
<1.1 1.1+/-0.4 2.1+/-0.4 1.2+/-0.3 0.6+/-0.3 4.9+/-1. 5 7.6+/-2.0
<3.5
<3.2 STATION NUMBER AND DATE SA-APT-3H3 1-02-79 3-31-79 6-25-79 10-01-79 to to to to 3-31-79 6-25-79 10-01-79 1-02-80 99+/-10 96+/-10 76+/-8 58+/-6 0.7+/-0.4
<0.5
<0.6
<0.5
<3.3 4.6+/-3.3
<3.4
<3.2
<1.3
<Lo
<1.0
<0.8 1.4+/-0.4 1.6+/-0.5 1.2+/-0.4 0.4+/-0.3 3.7+/-1.4
- 4. 6+/-1. 7
<3.5
<1. 6 All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-32.
.J::::o co STATION NO.
SA-APT-2Sl SA-APT-5Sl SA-APT-501 SA-APT-1001 SA-APT-16El SA-APT-lFl SA-APT-2F2 SA-APT-3H3 TABLE C-4 CONCENTRATIONS OF STRONTIUM-89* AND -90 IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES Results in Units of 10-3 pCi/m3 +/- 2 sigma Jan to March Apri 1 to June July to Sept Oct to Dec Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90
<1. 7 0.6+/-0.4
<1.0 0.8+/-0.2
<1.1 0.3+/-0.3
<0.8
<0.4
<1.1 0.3+/-0.3
<0.6 0.6+/-0.2 0.9+/-0.6
<0.3
<0.5
<0.2
<0.9 0.5+/-0.3
<0.8 0.6+/-0.2.
<1.9
<0.5
<0.5 0.3+/-0.2
<2.0
<0.8
- o. 6+/-0. 6 0.5+/-0.2
<0.8 0.3+/-0.2
<0.7 0.2+/-0.2
<1.6
- 0. 4+/-0. 4
<0.7 0.5+/-0.2
<1.2 0.3+/-0.2
<0.8 0.2+/-0.2
<1.0 0.3+/-0.3
<0.9 0.8+/-0.2
<1.0
<0.4
<1.5
<0.6
<1.6
- 0. 5+/-0. 4
<0.8 0.8+/-0.2
<0.9 0.3+/-0.2
<1.0 0.5+/-0.3
<1.4 0.6+/-0.4
<0.8 0.7+/-0.2
<1.4 0.4+/-0.3
<0.6 0.2+/-0.2 Sr-89 results are corrected for decay to sample stop date.
i
MONTH SA-AI0-2Sl SA-AI0-5Sl JANUARY**
<4.7
<6.0
<4.9
<4.4
<7.0
<6.7
<7.2
<6.6 FEBRUARY
<7.7
<7.2
<6.4
<6.2
<6.6
<7.3
<8.4
<8.8
..p:.
l.O' MARCH
<6.8
<8.0
<7.4
<7.0
<7.0
<7.2
<8.2
<7.7
<11
<11 APRIL
<33
<29
<13
<19
<11
<9.3
<8.2
<8.2
<8.5
<7.1 MAY
<7.6
<11
<7.8
<6.9
<6.8
<8.5
<6.8
<6.4 JUNE
<8.0
<8.0
<7.5
<7.8
<7.2
<8.0
<8.6
<7.5 TABLE C-5 CONCENTRATIONS OF IOOINE-131 IN FILTERED AIR Results* in Units of 10-3 pCi/m3 SA-AI0-501 SA-AI0-1001 SA-AI0-16El
<5.5
<5.0
<5.2
<5.1
<4.2
<4.9
<7.4
<6. 2
<7.5
<7.8
<8.5
<9.0
<8.1
<7.5
<8.6
<7.2
<6.4
<7.5
<7.4 (1)
<6.2
<9.6
<3.7
<12
<7.5
<7.4
<8.5
<8.5
<6.6
<7. 9
<6.9
<7.6
<8.3
<9. 1
<7.2
<7.9
<20
<24
<28
<30
<31
<29
<13
<9.2
<10
<11
<10
<11
<8.5
<7.1
<8.2
<8.7
<8.7
<10
<8.1
<6.8
<7.3
<8.6
<8.1
<9.7
<7.3
<6.6
<7. l*
<7.3
<6.2
<6.5
<8.4
<5.6
<5.9
<8.5
<6.7
<7.3
<6.9
<6.9
<8.3
<8.9
<6.8
<8.1 '
SA-AI0-2F2 SA-AI0-3H3
<5.7
<6.5
<4.9
<4.9
<7.0
<8.1
<7.7
<7.8
<7.5
<8.7 I
<6.3
<6.7
<5.9
<7.0
<9.2
<8.9
<7.4
<8.8
<8.1
<8.2
<7.4
<7.5
<8.3
<8.9
<20
<19
<27
<29
<11
<13
<11
<11
<7.8
<8.0
<8. 7 '
<7.6
<8.5
<9.8
<8.3
<8.1
<7.5
<7.9
<6.2
<6.0
<7.3
<6.9
<7.3
<8.0
<7.4
<7. 9
. <8.8
<8.1
U1 0
MONTH SA-AI0-2Sl SA-AI0-5Sl JULY
<7.2
<7.0
<8.5
<8.3
<6.8
<6.8
<7.9
<7.6
<8.0
<7.8 AUGUST
<8.0
<7.2
<7.0
<6.6
<7.6
<6.8
<6.4
<6.2 SEPTEMBER
<6.9
<7.1
<8.5
<8.5
<7.4
<8.4
<7.2
<7.2
<7.6
<7.3 OCTOBER
<6.8
<6.7
<9.6
<9.1
<7.3
<7.4
<8.3
<7.7 NOVEMBER
<8.9
<8.5
<6.6
<6.2
<8.3
<8.2
<8.8
<8.5
<8.3
<7.4 DECEMBER
<8.1
<6.8
<6.1
<5.5..
<5.9
<6.0
<6.3
<5.8 TABLE C-5 (cont.)
CONCENTRATIONS OF IODINE-131 IN FILTERED AIR Results* in Units of 10-3 pCi/m3 SA-AI0-501
.. SA-AI0-1001 SA-AI0-16El
<7.5
<6.5
<6.3
<9.0
<7.4
<7.6
<122(2)
<6.2
<6.9
<8.7
<7.0
<6.8
<7.7
<8.4
<8.4
<9.9
<6.2
<7.2
<8.2
<6.4
<7.2
<8.8
<6.9
<7.4
<7.5
<7.5
<8.7
<6.8
<5.8
<6.1
<12
<8.5
<9.2
<9.5
<10
<9.9
<9.2
<6.7
<7.1
<9.0
<9.6
<9.0
<9.0
<7.1
<6.1
<12
<12
<12
<9.0
<6.5
<6.7
<10
<12
<12
<7.9
<7.3
<7.3
<8.4
<8.3
<7.6
<12
<8.1
<8.0
<12
<9.3
<9.4
<8.3
<7.3
<7.0
<9.3
<7.4
<8.7
<6.7
<6.1
<6.0
<7.2
<5.3
. <6.0
<7.1
<6.9
<8.9 I-131 results are decay corrected to sample stop date.
Actual sampling dates can be found on Table C-6.
(1)
( 2)
No sample was received.
High LLD due to low sample volume.
SA-AI0-2F2 SA-AI0-3H3
<6.9
<7.2
<8.0
<8.5
<7.3
<7.3
<6.7
<8.0
<8.9
<8.8
<8.6
<8.6
<7.6
<7.9
<8.5
<13
<6.8
<7.7
<8.0
<6.9
<11
<9.9
<11
<8.3
<8.9
<8.0
<7.9
<8.2
<7.3
<7. 9
<12
<10
<8.8
<8.2
<8.4
<9.5
<8.6
<8.9
<6.9
<7.7
<9.9
<9.5
<12
<9.1
<7.1
<8.0
<9.6
<8.0
<6.6
<7.8
<8.4
<9. 9
<6.8
<7.5
TABLE C-6 SAMPLING DATES FOR AIR SAMPLES STATION NO.
MONTH 2Sl 5Sl 501 1001 16El lFl 2F2 3H3 JANUARY 1-02-79 1-02-79 1-02-79 1-02-79 1-02-79 1-02-79 1-02-79 1-02-79 to to to to to to to to 1-08-79 1-08-79 1-08-79 1-09-79 1-09-79 1-08-79 1-08-79 1-08-79 1-08-79 1-08-79 1-08-79 1-09-79 1-09-79 1-08-79 1-08-79 1-08-79 to to to to to to to to 1-15-79 1-15-79 1 79 1 79 1-16-79 l-"15-79 1-15-79 1-15-79 1-15-79 1-15-79 1-15-79 1-16-79 1-16-79 1-15-79 1-15-79 1-15-79 to to to to to to to to 1-22-79 1-22-79 1-22-79 1-23-79 1-23-79 1-22-79 1-22-79 1-22-79 1-22-79 1-22-79 1-22-79 1-23-79 1-23-79 1-22-79 1-22-79 1-22-79 to to to to to to to to 1-29.,.79 1-29-79 1-29-79 1-29-79 1-29-79 1-29-79 1-29-79 1-29-79 FEBRUARY 1 79 1-29-79 1-29-79 1 79 1-29-79 1-29-79 1-29-79 1-29-79 to to to to to to to to 2-05-79 2-05-79 2-05-79 2-05-79 2-05-79 2-05-79 2-05-79 2-05-79 2-05-79 2-05-79 2 79 2-05-79 2-05-79 2-05-79 2-05-79 2-05-79 to to to to to to to to 2-13-79 2-13-79 2-13-79 2-13-79 2-13-79 2-13-79 2 79 2-13-79 2-13-79 2-13-79 2-13-79 2-13-79 2-13-79 2-13-79 2-13-79 to to to (1) to to to to 2-20-79 2-20-79 2-20-79 2-21-79 2-20-79 2-20-79 2-20-79 2-20-79 2-20-79 2-20-79 2-13-79 2-21-79 2-20-79 2-20-79 2-20-79 to to to to to to to to 2-26-79 2-26-79 2-26-79 2 79 2-26-79 2-26-79 2-26-79 2-26-79 MARCH 2-26-79 2-26-79 2-26-79 2-26-79 2-26-79 2-26-79 2-26-79 2-26-79 to to to to to to to to 3-05-79 3-05-79 3-05-79 3-05-79 3-05-79 3-05-79 3-05-79 3-05-79 3-05-79 3-05-79 3-05-79 3-05-79 3-05-79 3-05-79 3-05-79 3-05-79 to to to to to to to to 3-12-79 3-12-79 3-12-79 3-13-79 3-13-79 3-12-79 3-12-79 3-12-79 3-12-79 3-12-79 3-12-79 3-13-79 3-13-79 3-12-79 3-12-79 3-12-79 to to to to to to to to 3-19-79 3-19-79 3-19-79 3-19-79 3-19-79 3-19-79 3-19-79 3-19-79 3-19-79 3-19-79 3-19-79 3-19-79 3-19-79 3-19-79 3-19-79 3-19-79 to to to to to to to to 3-26-79 3-26-79 3-26-79 3-27-79 3-27-79 3-26-79 3-26-79 3-26-79 3-26-79 3-26-79 3-26-79 3-27-79 3-27-79 3-26-79 3-26-79 3-26-79 to to to to to to to to 3-31-79 3-31-79 3-31-79 3-31-79 3-31-79 3-29-79 3-31-79 3-29-79 51
MONTH 2Sl 5Sl APRIL 3-31-79 3-31-79 to to 4-05-79 4-05-79 4-05-79 4-05-79 to to 4-10-79 4-10-79 4-10-79 4-10-79 to to 4-16-79 4-16-79 4-16-79 4-16-79 to to 4-23-79 4-23-79 U1 4-23-79 4-23-79 N
to to 4-30-79 4-30-79 MAY 4-30-79 4-30-79 to to 5-07-79 5-07-79 5-07-79 5-07-79 to to 5-14-79 5-14-79 5-14-79 5-14-79 to to 5-21-79 5-21-79 5-21-79 5-21-79 to to 5-29-79 5-29-79 JUNE 5-29-79 5-29-79 to to 6-04-79 6-04-79 6-04-79 6-04-79 to to 6-11-79 6-11-79 TABLE C-6 (cont.)
SAMPLING DATES FOR AIR SAMPLES STATION NO.
501 1001 16El 3-31-79 3-31-79 3-31-79 to to to 4-05-79 4-05-79 4-05-79 4-05-79 4-05-79 4-05-79 to to to 4-10-79 4-11-79 4-11-79 4-10-79 4-11-79 4-11-79 to to to 4-16-79 4-17-79 4-17-79 4-16-79 4-17-79 4-17-79 to to to 4-23-79 4-24-79 4-24-79 4-23-79 4-24-79 4-24-79 to to to 4-30-79 4-30-79 4-30-79 4-30-79 4-30-79 4-30-79 to to to 5-07-79 5-08-79 5-08-79 5-07-79 5-08-79 5-08-79 to to to 5-14-79 5-14-79 5-14-79 5-14-79 5-14-79 5-14-79 to to to 5-21-79 5-22-79 5-22-79 5-21-79 5-22-79 5-22-79 to to to 5-29-79 5-29-79 5-29-79 5-29-79 5-29-79 5-29-79 to to to 6-04-79 6-05-79 6-05-79 6-04-79 6-05-79 6-05-79 to to to 6-11-79 6 79 6-12-79 lFl 2F2 3H3 4-01-79 3-31-79 3-31-79 to (2) to to 4-03-79 4-05-79 4-05-79 4-05-79 4-05-79 4-05-79 to to to 4-10-79 4-10-79 4-10-79 4-10-79 4-10-79 4-10-79 to to to 4-16-79 4-16-79 4 79 4-16-79 4-16-79 4-16-79 to to to 4-23-79 4-23-79 4-23-79 4-23-79 4-23-79 4-23-79 to to to 4-30-79 4-30-79 4-30-79 4-30-79 4-30-79 4-30-79 to to to 5-07-79 5-07-79 5-07-79 5-07-79 5-07-79 5-07-79 to to to 5-14-79 5-14-79
. 5-14-79 5-14-79 5-14-79 5-14-79 to to to 5-21-79 5-21-79 5-21-79 5-21-79 5-21-79 5-21-79 to to to 5-29-79 5-29-79 5-29-79 5-29-79 5-29-79 5-29-79 to to to 6-04-79 6-04-79 6-04-79 6-04-79 6-04-79 6-04-79 to to to 6-11-79 6-11-79 6-11-79
TABLE C-6 (cont.)
SAMPLING DATES FOR AIR SAMPLES STATION NO.
MONTH 2Sl 5Sl 501 1001 16El lFl 2F2 3H3 JUNE 6-11-79 6-11-79 6-11-79 6-12-79 6-12-79 6-11-79 6-11-79 6-11-79 to to to to to to to to 6-18-79 6-18-79 6-18-79 6-19-79 6-19-79 6-18-79 6 79 6-18-79 6-18-79 6-18-79 6-18-79 6-19-79 6-19-79 6-18-79 6 79 6 79 to to to to to to to to 6 79 6 79 6-25-79 6-26-79 6-26-79 6-25-79 6-25-79 6-25'- 79 JULY 6-25-79 6-25-79 6-25-79 6-26-79 6-26-79 6 79 6-25-79 6 79 to to to to to to to to 7-02-79 7-02-79 7-02-79 7-03-79 7-03-79 7-02-79 7 79 7 79 7-02-79 7-02-79 7-02-79 7-0 3-79 7-03-79 7-02-79 7 79 7-02-79 to to to to to to to to 7-09-79 7-09-79 7-09-79 7-10-79 7-10-79 7-09-79 7-09-79 7-09-79
(.J1 w
7-09-79 7-09-79 7-09-79 7-10-79 7-10-79 7-09-79 7 79 7 79 to to to to to to to to 7 79 7 79 7 79 7-17-79 7-17-79 7-12-79 7 79 7-16-79 7-16-79 7-16-79 7 79 7-17-79 7-17-79 7-16-79 7 79 7 79 to to to to to to to to 7-23-79 7 79 7-23-79 7-24-79 7 79 7-23-79 7 79 7-23-79 7-23-79 7-23-79 7-23-79 7-24-79 7 79 7 79 7 79 7-23-7':)
to to to to to to to to 7-30-79 7-30-79 7-30-79 7-30-79 7-30-79 7-30-79 7-30-79 7-30-79 AUGUST 7 79 7-30-79 7-30-79 7-30-79 7-30-79 7-30-79 7-30-79 7-30-79 to to to to to to to to 8-06-79 8-06-79 8-06-79 8-07-79 8-07-79 8-06-79 8-06-79 8-06-79 8-06-79 8-06-79 8-06-79 8-07-79 8-07-79 8-06-79 8-06-79 8-06-79 to to to to to to to to 8-13-79 8-13-79 8--13-79 8-14-79 8-14-79 8-13-79 8 79 8 79 8 79 8-13-79 8-13-79 8 79 8-14-79 8 79 8 79 8-13-79 to to to to to to to to 8-20-79 8-20-79 8-20-79 8 79 8-21-79 8-20-79 8-20-79 8-20-79 8-20-79 8-20-79 8-20-79 8-21-79 8-21-79 8-20-79 8 79 8-20-79 to to to to to to to to 8-27-79 8 79 8 79 8-27-79 8-27-79 8-27-79 8 79 8-27-79
MONTH 2Sl 551 SEPTEMBER 8-27-79 8-27-79 to to 9-04-79 9-04-79 9-04-79 9-04-79 to to 9-10.:.79 9-10-79 9-10-79 9-10-79 to to 9-17-79 9 79 9 79 9-17-79 to to 9*24-79 9-24'-79 9-24-79 9-24-79 to to c.n 10-01-79 10-01-79
+:>
OCTOBER 10-01-7_9 10-01-79 to to 10-09-79 10-09-79 10-09-79 10-09-79 to to 10-15-79 10-15-79 10-15-79 10-15-79 to to 10-22-79 10-22-79 10-22-79 10-22-79 to to 10-29-79 10-29-79 NOVEMBER 10-29-79 10-29-79 to to 11-05-79 11-05-79 11-05-79 11-05-79 to to 11-13-79 11-13-79 11-13-79 11-13-79 to to 11-19-79 11-19-79 TABLE C-6 (cont.)
SAMPLING DATES FOR AIR SAMPLES STATION rm.
5Dl lODl 16El 8-27-79 8-27-79 8-27-79 to to to 9-04-79 9-05-79 9-05-79 9-04-79 9-05-79 9-05-79 to to to 9-10-79 9-11-79 9-11-79 9-10-79 9-11-79 9-11-79 to to to 9-17-79 9-17-79 9-17-79 9-17-79 9.:.17-79 9-17-79 to to to*
9-24-79 9'....25-79 9-25-79 9-24-79 9-25-79 9-25-79 to to to 10-0-1-79 10-01-79 lQ.:.01-79 10-01-79 10-01-79 10-01-79 to to to 10-09-79 10-10-79 10-10-79 10-09-79 10-10-79 10-10-79 to to to 10-15-79 10-15-79 10-15-79 10-15-79 10-15-79 10-15-79 to to to 10-22-79 10-23-79.
10-23-79 10-22-79 10-23-79 10-23-79 to to to 10-29-79 10-29-79 10-29-79 10-29-79 10-29-79 10-29-79 to to to 11-05-79 11-05-79 11-05-79 11-05-79 11-05-79 11-05-79 to to to 11-13-79 11-13-79 11-13-79 11-13-79 11-13-79 11-13-79 to to to 11-19-79 11-20-79 11-20-79 lFl 2F2 3H3 8-27-79 8-27-79 8-27-79 to to to 9-04-79 9-04-79 9-04-79 9-04-79 9-04-79 9-04-79 to to to 9-10-79 9-10-79 9 79 9-10-79 9-10-79 9-10-79 to to to 9-17-79 9-17-79 9-17-79 9-17-79 9-17-79 9-17-79 to to ta*
9-24-79 9 79 9-24-79 9-24-79 9-24-79 9-24-79 to to to 10-01-79 10-01-79 10-01-79 10-01-79 10-01-79 10-01-79 to to to 10-09-79 10-09-79 10-09-79 10-09-79 10-09-79 10-09-79 to to to 10-15-79 10-15-79 10-15-79 10-15-79 10-15-79 10-15-79 to to to 10-22-79 10-22-79 10-22-79 10-22-79 10-22-79 10-22-79 to to to 10-29-79 lQ.:.29-79 10-29-79 10-29-79 10-29-79 10-29-79 to to to 11-05-79 11-05-79 11-05-79 11-05-79 11-05-79 11-05-79 to to to 11-13-79 11-13-79 11 79 11-13-79 11-13-79 11-13-79 to to to 11-19-79 11-19-79 11-19-79
(.Jl
(.Jl MONTH 2Sl 5Sl NOVEMBER 11-19-79 11-19-79 to to 11-26-79 11-26-79 11-26-79 11-26-79 to to 12-03-79 12-03-79 DECEMBER 12-03-79 12-03-79 to to 12-10-79 12-10-79 12-10-79 12-10-79 to to 12-18-79 12-18-79 12-18-79 12-18-79 to to 12-26-79 12-26-79 12-26-79 12-26-79 to to 1-02-80 1-02-80 TABLE C-6 (cont.)
SAMPLING DATES FOR AIR SAMPLES STATION NO.
5Dl lODl 16El 11-19-79 11-20-79 11-20-79 to to to 11-26-79 11-27-79 11-27-79 11-26-79 11-27-79 11-27-79 to to to 12-03-79 12-04-79 12-04-79 12-03-79 12-04-79 12-04-79 to to to 12-10-79 12-11-79 12-11-79 12-10-79 12-11-79 12-11-79 to to to 12 79 12-19-79 12-19-79 12-18-79 12 79 12-19-79 to to to 12-26-79 12-27-79 12-27-79 12 79 12-27-79 12-27-79 to to to 1-02-80 1-02-80 1-02-80 lFl 2F2 3H3 11-19-79 11-19-79 11-19-79 to to to 11-26-79 11-26-79 11-26-79 11-26-79 11-26-79 11-26-79 to to to 12-03-79 12 79 12 79 12-03-79 12 79 12-03-79 to to to 12-10-79 12-10-79 12-10-79 12-10-79 12-10-79 12-10-79 to to to 12-18-79 12 79 12-17-79 12 79 12 79 12 79 to to to 12-26-79 12-26-79 12-26-79 12-26-79 12-26-79 12-26-79 to to to 1-02-80 1-02-80 1-02-80 (1)
No sample was received.
(2)
During the TMI incident, one additional sample was taken at SA-APT-lFl.
The dates were 4-03-79 to 4-05-79.
. TABLE C-7 CONCENTRATIONS OF TRITIUM, GROSS ALPHA AND GROSS BETA EMITTERS IN PRECIPITATION Station SA-RWA-2F2 Results in Units of pCi/l +/- 2 sigma COLLECTION PERIOD H-3 ALPHA BETA 1-03-79 to 1-30-79
<111
<0.5 7.1+/-2.2 1-30-79 to 2-26-79
<123
<0.4 5.2+/-2.3 2-26-79 to 3-31-79
<113 0.7+/-0.6 8.8+/-2.6 3-31-79 to 5-01-79
<116
<0.8 3.4+/-2.0 5-01-79 to 5-30-79
<102
<0.6 6.4+/-2.3 5-30-79 to 7-02-79
<119
<1.2 21+/-3 7-02-79 to 7-31-79
<124
<1. 4 21+/-3 7-31-79 to. 9-04-79 526+/-73.
<1.2 6.4+/-2.5 9-04-79 to 10-02-79
<119
<0.6
<3.4 10-02-79 to 10-30-79
<120
<0.8 5.9+/-2.3 10-30-79 to 12 79
<125
<0.8
<3.4 12-03-79 to 1-03-80
<108 0.9+/-0.6 2.4+/-2.3 56
TABLE C-8 CONCENTRATIONS OF STRONTI UM-89* AND -90, AND GAMMA EMITTERS**
IN QUARTERLY COMPOSITES OF PRECIPITATION Station SA-RWA-2F2 Results in Units of pCi/l +/- 2 sigma 1-03-79 3-31-79 7-02-79 10-02-79 to to to to NUCLIDE 3-31-79 7-02-79 10-02-79 1-03-80 Sr-89
<0.6
<1.1
<1.1
<1. 7 Sr-90
<0.5
<0.6 0.4+/-0.3
- 1. 2+/-0. 7 Ru-106
<16
<6.6
<16
<13 I-131
<4.4
<8.0
<7.1
<2.6 Cs-137
<1.6
<0.-8
<1.6
<1. 6 BaLa-140
<6.0
<4.7
<4.1
<2.2 Ce-144
<13
<5.0
<6.5
<4.8 Ra-226
<3.1
<1.2
<3.1
<3.1 Sr-89 results are decay corrected to sample stop date.
All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-32.
57
TABLE C-9 DIRECT RADIATION MEASUREMENTS - MONTHLY TLD RESULTS mrad/standard month*
STATION NO.
JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-IDM-2Sl
- 5. 88+/-0. 49 5.41+/-0.32 5.82+/-0.12 6.47+/-0.64 6.11+/-0. 64 5.76+/-0.32 SA-IDM-5Sl 4.60+/-0.35 4.81+/-0.32 4.54+/-0.24 4.97+/-0. 77 4.87+/-0.29 4.75+/-0.51 SA-IDM-6Sl 5.49+/-0.23 4.99+/-0.39 5.66+/-0.72
- 5. 81+/-0.23
- 5. 71+/-0.53 5.53+/-0.43 SA-I DM-6S2 5.29+/-0.76 5.60+/-0.83 5.11+/-0. 17 5.35+/-0.17
- 5. 52+/-1. 08 5.32+/-0.95 SA-IDM-7Sl 6.06+/-0.48 6.32+/-0.68 6.02+/-0.36 6.13+/-0.45 6.34+/-0.78 5.98+/-0.42 SA-I DM-lOS 1 5.77+/-0.38 5.41+/-0.30 5.25+/-0.52 5.60+/-0.45 5.25+/-0.23
- 4. 83+/-0.11 SA-IDM-llS 1
- 4. 75+/-0.17 4.65+/-0.31 4.24+/-0.60 4.75+/-0.27 4.56+/-0.54 5.14+/-0.10 SA-IDM-5Dl
- 5. 08+/-0. 43 4.79+/-0.29 5.10+/-0. 54 5.45+/-0.77 5.12+/-0.38 5.19+/-0.52 SA-IDM-lODl 6.15+/-0.29 5.62+/-0.26 6.09+/-0. 72 5.76+/-0.31 6.48+/-0.53 5.94+/-0.22 SA-IDM-14Dl 5.78+/-0.55 5.43+/-0.52 5.48+/-0.41 5.37+/-0.24 5.82+/-0.66 4.98+/-0.16 SA-IDM-2El 5.70+/-0.18
- 5. 38+/-0. 47 5.41+/-0.52 5.64+/-0.41
- 5. 71+/-0. 76
- 5. 51+/-0. 45 SA-IDM-3El 5.12+/-0.36 5.19+/-0.66 5.11+/-0.21 5.29+/-0.21 5.60+/-0.12 5.05+/-0.46 SA-IDM-13El 5.44+/-0.38 5.14+/-0.13 5.74+/-0.31 5.12+/-0. 36 5.78+/-0.80 5.01+/-0.33 SA-IDM-16El 5.86+/-0.07 5.75+/-0.27
- 5. 70+/-0. 71
- 5. 78+/-1. 02 5.64+/-0.54 5.33+/-0.26 SA-IDM-lFl 5.77+/-0.36 5.55+/-0.25 5.64+/-0.32 6.26+/-0. 79 6.18+/-0. 61 5.27+/-0. 76 SA-IDM-2F2 4.68+/-0.24 4.41+/-0.48 4.51+/-0.18 4.56+/-0.40 4.88+/-0.25 4.56+/-0.49 SA-IDM-5Fl 5.20+/-0.46 4.89+/-0.21 5.41+/-0.18 5.18+/-0.08 5.22+/-0.28 4.97+/-0.61 SA-IDM-6Fl 4.90+/-0.62 4.56+/-0.44 4.67+/-0.31 4.70+/-0.40 4.27+/-0.43
- 4. 80+/-0. 25 SA-IDM-7F2 4.41+/-0.45 3.93+/-0.59 4.18+/-0.19 4.14+/-0.28 4.09+/-0.58 4.39+/-0.21 SA-IDM-llFl
- 6. 39+/-0. 47 5.95+/-0.30 6.04+/-0.28 6.13+/-0.63
- 5. 93+/-0.18 5.95+/-0.77 SA-IDM-13 Fl 5.31+/-0.30 5.60+/-0.48 5.65+/-0.34 5.66+/-0.21 5.37+/-0.50 5.13+/-0.33 SA-IDM-3Gl 6.19+/-0. 84 6.03+/-0.34 6.69+/-1.03
- 6. 31+/-0. 91 5.97+/-0.29 6.06+/-0.60 SA-IDM-2Hl 5.86+/-0.26 5.74+/-0.37 5.95+/-0.27 5.76+/-0.55
- 5. 78+/-0.13 6.64+/-0.31 SA-IDM-3Hl 6.19+/-0.71 5.66+/-0.74 5.90+/-0.22 5.71+/-0.28 5.99+/-0. 30 5.35+/-0.42 SA-IDM-3H3 6.47+/-0.66 6.04+/-0.38 6.40+/-0.33 6.05+/-0.51 6.12+/-0.41 5.33+/-0.32 AVERAGE 5.53+/-1.17 5.31+/-1.15
- 5. 45+/-1. 30 5.52+/-1.17
- 5. 53+/-1. 25 5.31+/-1.05 STATION NO.
JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE SA-IDM-2Sl 5.68+/-0.47 6.24+/-0.29 6.76+/-0.20 6.30+/-0.42 5.86+/-0.49 6.39+/-0.38
- 6. 06+/-0. 77 SA-IDM-5Sl 4.40+/-0.32 4.41+/-0.29 5.28+/-0.10 5.05+/-0.42 5.13+/-0.41 5.58+/-0.45 4.87+/-0.72 SA-IDM-6Sl 5.83+/-0.30 5.69+/-1.35 6.74+/-0.64 6.16+/-0.50
- 6. 01+/-0. 97 6.39+/-0.66 5.83+/-0.91 SA-IDM-6S2 5.13+/-0.19
- 5. 48+/-0.67 5.94+/-0. 71 5.39+/-0.14 5.35+/-0.06
- 5. 58+/-0. 31 5.42+/-0.45 SA-IDM-7S 1 6.14+/-0.19
- 6. 84+/-0. 61 7.12+/-0.63 6.41+/-0.48 6.46+/-0.24 7.11+/-0.24 6.41+/-0.81 SA-IDM-lOS 1
- 7. 21+/-0.15
- 9. 62+/-1.11 10.55+/-0. 76 9.87+/-0.55
- 10. 06+/-1. 50 10.67+/-0.65 7.51+/-4.84 SA-IDM-llS 1 15.34+/-0.64 25.99+/-2.76 26.05+/-2.37
- 23. 13+/-1. 45
- 20. 78+/-1. 04
- 24. 49+/-1. 75 13.66+/-19.54 SA-IDM-5Dl 4.81+/-0.57
- 5. 41+/-0. 61
- 5. 76+/-0. 78 5.29+/-0.60 5.46+/-0.30 5.25+/-0.69 5.23+/-0.55 SA-IDM-lODl 6.34+/-0.20 6.42+/-0.63 6.82+/-0.45 6.28+/-0.47
- 5. 79+/-0.17
- 6. 31+/-1. 09 6.17+/-0.69 SA-IDM-14Dl 5.73+/-0.46
- 5. 82+/-1. 27 6.46+/-0.38 5.86+/-0.60 5.59+/-0.75
- 6. 03+/-0. 42 5.70+/-0.74 SA-IDM-2El 5.54+/-0.55
- 5. 50+/-0. 80 6.20+/-0.31 5.76+/-0.40 5.19+/-0.59 5.98+/-0.71 5.63+/-0.55 SA-IDM-3El 5.48+/-0.34 5.51+/-0.32 5.28+/-0.37 5.45+/-0.56 5.43+/-0.24 5.52+/-0.09 5.34+/-0.37 SA-I DM-13E 1 5.24+/-0.66 6.16+/-0. 45 5.58+/-0.45 5.92+/-0.21 5.35+/-0.22 5.73+/-0.52 5.52+/-0.72 SA-I DM-16El 5.40+/-0.21 6.49+/-0.65
- 6. 58+/-0. 32 5.49+/-0.14 5.75+/-1.01 6.10+/-0.17 5.82+/-0.78 SA-IDM-lFl 6.03+/-0.46 5.78+/-0.35 6.56+/-0.49 5.92+/-0.39 5.85+/-0.53 6.33+/-0.74 5.93+/-0.73 SA-IDM-2F2 4.44+/-0.18 5.07+/-0. 73 5.22+/-0.37 4.79+/-0.38 4.50+/-0. 80 5.02+/-0.21
- 4. 72+/-0.54 SA-IDM-5Fl 4.93+/-0.42 5.97+/-0.48 6.08+/-0.85 5.26+/-0.58 5.38+/-0.48 5.15+/-0.42 5.30+/-0.75 SA-IDM-6Fl 4.40+/-0.56 5.12+/-0. 76 5.53+/-0.33 4.72+/-0.28 4.97+/-0.24 4.95+/-0.41 4.80+/-0.67 SA-I DM-7F2 3.63+/-0.22 4.47+/-0.37 4.78+/-0.43 3.96+/-0.25 4.32+/-0.17 4.13+/-0.46 4.20+/-0.60 SA-IDM-llFl 6.06+/-0.74 6.91+/-0.70 6.65+/-0.45 6.21+/-0.43
- 6. 09+/-0. 30 6.45+/-0.48 6.23+/-0.62 SA-IDM-13Fl 5.76+/-0.22 6.29+/-0.74 6.27+/-0.48
- 5. 73+/-0.14 5.68+/-0.67 5.89+/-0.27 5.70+/-0.69 SA-IDM-3Gl 5.68+/-0.35 6.48+/-0.73
- 6. 64+/-1. 06 6.44+/-0.33 6.41+/-0.95 6.49+/-0.45
- 6. 28+/-0. 60 SA-IDM-2Hl 5.94+/-0.52
- 5. 93+/-0. 39 6.58+/-0.34 6.71+/-0.40 6.11+/-0.97 6.54+/-0.22 6.13+/-0.75 SA-IDM-3Hl 5.66+/-0.59 6.65+/-0.84 6.45+/-0.08 5.93+/-0.33 6.07+/-0.57 6.70+/-0.24 6.02+/-0.83 SA-IDM-3H3 5.84+/-0.48 7.62+/-0. 72 6.90+/-0.80 6.03+/-0.61
- 6. 01+/-0. 87 6.11+/-0.52
- 6. 24+/-1.15 AVERAGE 5.87+/-4.22 6.87+/-8.23 7.15+/-8.16 6.56+/-7.21 6.38+/-6.34 6.84+/-7.71 6.03+/-5.18 The standard month = 30.4 days.
58
TABLE C-10 DIRECT RADIATION MEASUREMENTS - QUARTERLY TLD RESULTS mrad/standard month*
JANUARY APRIL JULY OCTOBER to to to to AVERAGE STATION NO.
MARCH JUNE SEPTEMBER DECEMBER SA-IDM-2Sl 5.41+/-0.48 6.12+/-0.20 6.09+/-0.87 5.62+/-0.73 5.81+/-0.70 SA-IDM-5Sl 4.48+/-0.10 4.95+/-0.34 4.53+/-0.38
- 4. 34+/-0.18 4.58+/-0.53 SA-IDM-6Sl 5.16+/-0.59 6.01+/-0.24
- 6. 02+/-0. 71 5.43+/-0.64 5.66+/-0.86 SA-IDM-6S2 4.79+/-0.14 5.95+/-0.33 4.90+/-0.36 4.89+/-0.76 5.13+/-1. 09 SA-IDM-7Sl 5.56+/-0.15 6.34+/-0.67 6.41+/-1.06 6.11+/-0. 79 6.11+/-0. 77 SA-IDM-lOS 1 4.70+/-0.56 5.56+/-0.36 8.68+/-0.45 9.78+/-0.98 7.18+/-4.87 SA-IDM-llS 1 4.02+/-0.23 4.67+/-0.28 22.53+/-2.20
- 20. 77+/-2.89
- 13. 00+/-20. 04 SA-IOM-5Dl 4.55+/-0.44 5.34+/-0.20 5.12+/-0.25 4.57+/-0.39 4.90+/-0.79 U1 SA-IDM-10D1 5.63+/-0.33 6.03+/-0.61 6.52+/-0.95 5.42+/-0.59 5.90+/-0.97 c..o SA-IDM-14Dl 5.07+/-0.43 5.67+/-0.25 5.50+/-0.68 4.86+/-0.51 5.28+/-0.75 SA-IDM-2El 5.07+/-0.38
- 5. 70+/-0.21 5.89+/-0.60 4.98+/-0.12 5.52+/-4.36 SA-IDM-3El 4.53+/-0.18 5.34+/-0.53 5.55+/-0.62 4.78+/-0.25 5.05+/-0.95 SA-IDM-13E1 4.80+/-0.40 5.18+/-0.25 5.60+/-0.52 5.05+/-0.56 5.16+/-0.67 SA-IDM-16El 5.21+/-0.19 5.47+/-0.47 6.36+/-1.49 5.23+/-0.15
- 5. 57+/-1. 08 SA-IDM-lFl 5.09+/-0.10 5.42+/-0.62 5.93+/-0.21 5.42+/-0.86 5.47+/-0.69 SA-IDM-2F2 4.08+/-0.13 4.41+/-0.15 4.79+/-0.35 3.97+/-0.28 4.31+/-0.74 SA-IDM-5Fl 4.69+/-0.08 5.31+/-0.38 5.28+/-0.12 4.65+/-0.55 4.98+/-0.72 SA-I DM-6Fl 3.94+/-0.67 5.45+/-0.69 4.40+/-0.25 4.17+/-0.43
- 4. 49+/-1. 33 SA-IDM-7F2
- 3. 69+/-0. 25 5.16+/-0.15 3.82+/-0.59 3.66+/-0.40
- 4. 08+/-1. 44 SA-IOM-11 Fl 5.71+/-0.47
- 6. 92+/-0.19 5.81+/-0. 36 5.35+/-0.38 5.95+/-1.36 SA-I DM-13Fl 5.05+/-0.47 6.21+/-0.57 5.41+/-0.49 5.42+/-0.43 5.52+/-0.98 SA-I DM-3G 1 5.62+/-0.22
- 6. 77+/-0. 56 5.95+/-0.21 5.51+/-0. 28 5.96+/-1.14 SA-IDM-2Hl 5.97+/-0.51 6.33+/-0.38 6.54+/-0.47 5.44+/-0.69 6.07+/-0.96 SA-IDM-3Hl 5.29+/-0.25 6.24+/-0.48 5.93+/-0.22 5.59+/-0.42 5.76+/-0.82 SA-IDM-3H3 5.42+/-0.38 6.70+/-0.59
- 5. 71+/-0. 78 5.05+/-0.39
- 5. 72+/-1. 41 AVERAGE
- 4. 94+/-1. 20
- 5. 73+/-1. 28
- 6. 37+/-6. 98 5.84+/-6.60
- 5. 72+/-4. 92 The standard month = 30.4 days.
CJ).
C)
STATION NO.
2-27-79(1)
SA-SWA-llAl 86+/-75 SA-SWA-11A2. ( 2)
<122 SA-SWA-12Cl SA-SWA-16C1(2)
<122 SA-SWA-7El SA-SWA-1F2 SA-SWA-15F2(3)
SA-SWA-16Fl STATION NO.
8-07-79 SA-SWA-llAl 86+/-76 SA-SWA-11A2 ( 2)
SA-SWA-12Cl 163+/-77 SA-SWA-16C1(2)
SA-SWA-7El 218+/-78 SA-SWA-1F2 92+/-76 SA-SWA-15F2(2)
SA-SWA-16Fl 162+/-77 TABLE C-11 CONCENTRATIONS OF TRITIUM IN SURFACE WATER
- Results in Units of pCi/l +/- 2 sigma 3-09-79 4-01-79 5-11-79
<123
<112
<120
<117
<112
<117
<123
<112
<120
<123 88+/-70
<120
<113
<117
<112
<117 9-11-79 10-02-79 11-06-79
<109
<103
<104
<109
<103
<104
<109
<103
<104
<109
<103
<104 73+/-67
<103
<104 6-05-79
<122
<122
<122
<102 80+/-64 12-03-79
<96
<96
<96
<96
<96 (1)
No surface water sample was received for January 1979 due to river icing.
(2)
Single collection because samples were not available at routine locations.
( 3)
Singl e collection followinq Tf'ill iocidenL 7-05-79
<124
<119
<124
<124
<119
TABLE C-12 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN SURFACE WATER Results in Units of pCi/l +/- 2 sigma STATION NO.
2-27-79(l) 3-09-79 4-01-79 5-11-79 6-05-79 7-05-79 SA-SWA-11Al
<11
<l. 9
- 3. 7+/-3.4
<7.9
<8.4
<43 SA-SWA-11A2 ( 2)
<12 SA-SWA-12Cl
<l. 5
- 1. 7+/-1.3
<7.2
<4.3
<19 SA-SWA-16Cl( 2)
<8.8 SA-SWA-7El 3.0+/-2.8
<3.0
<11
<9.5
<33 SA-SWA-1F2
<l.O 1.4+/-1.0
<5.0
<1.8
<15 SA-SWA-15 F2 ( 3) 2.3+/-1.4 SA-SWA-16Fl 4.5+/-2.1 1.3+/-1.0
<4.2
<3.1
<19 O"l I-'
STATION NO.
8-07-79 9-11-79 10-02-79 11-06-79 12-03-79 SA-SWA-llAl
<0.6
<0.3 2.0+/-0.8
<0.7
<0.2 SA-SWA-11A2(2)
SA-SWA-12Cl
<0.9
<0.6
- 1. 2+/-0. 7
<0.8 0.5+/-0.2 SA-SWA-16Cl(2)
SA-SWA-7El
<0.9
<0.3
- 1. 2+/-0. 7
<0.8
<0.2 SA-SWA-1F2
<0.7
<0.5
<0.5
<1.0 0.4+/-0.3 SA-SWA-15F2(3)
SA-SWA-16Fl
<0.8
<0.3 0.8+/-0.4
<0.8 0.2+/-0.2
( 1)
No surface water sample was received for January 1979 due to river icing.
(2)
Single collection because samples were not available at routine locations.
(3)
Single collection following TMI incident.
TABLE C-13 CONCENTRATIONS OF GROSS BETA EMITTERS IN SURFACE WATER Results in Units of pCi/l +/- 2 sigma STATION NO.
2-27-79(l) 3-09-79 4-01-79 5-11-79 6-05-79 7-05-79 SA-SWA-llAl 30+/-4 7.3+/-2.5 14+/-3 27+/-4 15+/-3 54+/-7 SA-SWA-11A2 ( 2) 26+/-4 SA-SWA-12Cl 5.3+/-2.3 3.8+/-2.3 21+/-4 9.3+/-2.8 20+/-4 SA-SWA-16Cl( 2) 17+/-3 SA-SWA-7El 8.9+/-2.6 8.1+/-2.7 27+/-4 17+/-4 34+/-5 SA-SWA-1F2
<3.2
<3.3 15+/-3 2.7+/-2.4 17+/-3 SA-SWA-15F2( 3) 2.9+/-2.2 SA-SWA-16 Fl 7.4+/-2.5 2.3+/-2.2 12+/-3 6.6+/-2.7 17+/-4 O"'>
AVERAGE 24+/-13 6.4+/-4.4 5.7+/-9.1 20+/-14 10+/-12 28+/-32 N
STATION NO.
8-07-79 9-11-79 10-02-79 11-06-79 12-03-79 ANNUAL AVERAGE SA-SWA-llAl 86+/-9 44+/-6 50+/-6 44+/-5 23+/-4 36+/-46 SA-SWA-11A2( 2) 26 SA-SWA-12Cl 59+/-7 31+/-5 31+/-5 23+/-4 14+/-3 22+/-32 SA-SWA-16Cl( 2) 17 SA-SWA-7El 107+/-11 43+/-6 62+/-7 46+/-5 36+/-5 39+/-59 SA-SWA-1F2 40+/-5 20+/-4 16+/-3 13+/-3 12+/-3 14+/-22 SA-SWA-15F2 ( 3) 2.9 SA-SWA-16 Fl 50+/-6 24+/-4 23+/-4 18+/-3 22+/-4 18+/-27 AVERAGE 68+/-55 32+/-22 36+/-38 29+/-30 21+/-19 25+/-42 (1)
No surface water sample was received for January 1979 due to river icing.
(2)
Single collection because samples were not available at routine locations.
(3)
Single collection following TMI incident.
TABLE C-15 CONCENTRATIONS OF STRONTIUM-89* AND -90 IN SURFACE WATER Results in Units of pCi/l +/- 2 sigma 4-01-79 7-05-79 10-02-79 STATION 3-09-79(l) to to to NUMBER 6-05-79 9-11-79 12-03-79 Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 O"l SA-SWA-llAl
<0.6
<0.4
<0.9
- 0. 4+/-0. 3
<1.2
<0.6
<1.4
<0.6
.+>>
SA-SWA-12Cl
<0.6
<0.4
<2.0
<0.9
<1.2 0.4+/-0.4
<2.1
- 1. 0+/-0. 6 SA-SWA-7El
<0.6
<0.4
<0.9 0.4+/-0.3
<1.2
<0.6
<1.3
<0.5 SA-SWA-1F2 0.5+/-0.4
<0.4
<2.5
<1.0
<1.6
<0.7
<1.1
<0.5 SA-SWA-16Fl
<0.6
<0.4
<0.9
<0.4
<1.5
<0.7
<1.2 0.5+/-0.3 (1)
Sr-89 results are corrected for decay to sample stop date.
Since no January samples were received~ quarterly analyses were performed only on March samples.
I_
_____,.,...~-----~----~
~ --
TABLE C-16 CONCENTRATIONS OF TRITIUM, GROSS ALPHA AND GROSS BETA EMITTERS, AND POTASSIUM-40 IN WELL WATER Results in Units of pCi/l +/- 2 sigma STATION NO.
RADIOACTIVITY 1-08-79 2-14-79 3-12-79 4-10-79 5-14-79 6-11-79 SA-WWA-4Sl H-3
<118
<117(1)
<123
<122
<120
<102 Alpha
<0;9
<2.3
<1.3
<1.9
<1. 7
<1.8 Beta 25+/-4 16+/-3 12+/-3 16+/-3 15+/-3 11+/-3 K-40 11+/-1 11+/-1 12+/-1 12+/-1 11+/-1 12+/-1 SA-WWA-5Dl
<123(2)
<118
<117
<122
<120
<102 Alpha
<0.7
<1.8
<1.0
<1.2
<1.0
<1.7 Beta 7.8+/-3.0 4.1+/-2.2 2.2+/-2.1 2.4+/-2.2 3.2+/-2.0
<3.6 K-40 2.2+/-0.2 2.3+/-0.2 2.8+/-0.3 2.5+/-0.3 2.5+/-0.3 2.1+/-0.2 SA-WWA-3El H-3
<118
<117
<123
<122
<120
<102 Alpha
<0.8
<2.1
<1.0
<1.7
<1.6
<1.7 Beta 16+/-3 12+/-3 6.9+/-2.4 10+/-3 9.5+/-2.5 7.3+/-2.7 O'l K-40 8.2+/-0.8 8.1+/-0.8 U1 8.5+/-0.9 9.0+/-0.9 7.9+/-0.8 8.5+/-0.9 STATION NO.
RAOIOACTI VITY 7-09-79 8-13-79 9-10-79 10-09-79 11-13-79 12-10-79 ANNUAL AVERAGE SA-WWA-4Sl H-3
<124
<124.
<116
<103
<104
<96 Alpha
<3.7
<2.6
<3.7
<1.9
<2.0
<2.9 Beta 18+/-3 12+/-3 12+/-3 14+/-3 11+/-3 9.3+/-2.7 14+/-8 K-40 15+/-2 15+/-2 15+/-2 13+/-1 18+/-2 17+/-2 14+/-5 SA-WWA-501 H-3
<124
<124
<116
<103
<104
<96 Alpha
<2.4
<1.9
<2.4
<1.4
<1. 5
<2.0 Beta 2.3+/-2.1 5.4+/-2.6 3.8+/-2.3 3.8+/-2.3 2.1+/-2. 0
<3.4 3.7+/-3.2 K-40 2.9+/-0.3 3.4+/-0.3
- 2. 9+/-0. 3 3.6+/-0.4 2.4+/-0.2 3.0+/-0.3 2.7+/-0.9 SA-WWA-3El H-3
<124
<124
<116
<103
<104
<96 Alpha
<2.9
<2.5
<2.8
<1.6
<2.0
<2.6 Beta 11+/-3 10+/-3 7.7+/-2.6 10+/-3 8.9+/-2.5 9.3+/-2.7 9.9+/-4.9 K-40 11+/-1 11+/-1 11+/-1 9.1+/-0.9 14+/-1 13+/-1 9.9+/-4.1 (1)
Sampling date for SA-WWA-4Sl for February was 2-13-79.
(2)
Sampling date for SA-WWA-501 for March was 3-13-79.
TABLE C-17 CONCENTRATIONS OF STRONTIUM-89* AND -90, AND GAMMA EMITTERS** IN QUARTERLY COMPOSITES OF WELL WATER STATION NUMBER RADIOACTIVITY SA-WWA-4Sl Sr-89 Sr-90 K-40 SA-WWA-501 Sr-89 Sr-90 K-40 SA-WWA-3El Sr-89 Sr-90 K-40 Results in Units of pCi/l +/- 2 sigma 1-08-79 to 3-12-79
<0.6
<0.4 12+/-11
<0.7(l)
<0.5 12+/-8
<0.7
<0.5
<12 4-10-79 to 6-11-79
<0.9
<0.4 14+/-7
<l. 7
<0.8
<9.3
<0.9
<0.4 9.1+/-6.6 7-09-79 to 9-10-79
<2.5
<1.2 9.8+/-7.2
<1.4
<0.6
<9.3
<1.1
<0.5 11+/-7 10-09-79 to 12-10-79
<1.0
<0.5 19+/-8
<1.0
<0.5
<7.8
<1.1
<0.6
<9.3 Sr-89 results are corrected for decay to sample stop date.
All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-32.
(1)
Sampling date for SA-WWA-501 for March was 3-13-79.
66
m
-....J TABLE C-18 CONCENTRATIONS OF TRI TI UM, GROSS ALPHA AND GROSS BETA EMITTERS, AND POTASS I UM-40 IN RAW AND TREATED POTABLE WATER Station SA-PWA-2F3 Results in Units of pCi/l +/- 2 sigma RADIOACTIVITY JANUARY FEBRUARY MARCH APRIL MAY H-3 (Raw)
<115
<122
<113
<116
<124 (Treated)
<ll5
<122
<ll3
<116
<124 Alpha(Raw) 0.5+/-0.4 0.9+/-0.5 0.4+/-0.3
- 1. 0+/-0. 5
<2.8 (Treated) 1.4+/-0.6
<0.6 0.5+/-0.4
<0.6 0.6+/-0.5 Beta (Raw) 4.7+/-0.6 4.3+/-0.6 2.8+/-0.5 2.9+/-0.5 9.6+/-1.0 (Treated) 2.6+/-0.5 2.7+/-0.5 2.5+/-0.5 3.1+/-0.5 2.7+/-0.5 K-40 (Raw) 2.4+/-0.2 1.2+/-0.1 0.94+/-0.09 0.94+/-0.09
- 0. 72+/-0. 07 (Treated) 2.4+/-0.2 1.4+/-0.l 0.85+/-0.09
- 1. 0+/-0. l
- 1. 0+/-0. l RAD IOACTI V ITV JULY AUGUST SEPTEMBER OCTOBER NOVEMBER H-3 (Raw)
<122
<llO
<119
<120
<125 (Treated) 198+/-77 122+/-68
<l19
<120 84+/-77 Alpha (Raw)
<0.4 0.9+/-0.5
<0.6 1.6+/-0. 7 0.7+/-0.5 (Treated)
<0.6 1.0+/-0.6
<0.7 0.7+/-0.6
<0.5 Beta (Raw) 2.8+/-0.5 3.7+/-0.5 2.6+/-0.5 3.6+/-0.5 3.2+/-0.5 (Treated) 2.3+/-0.5 2.5+/-0.4 3.4+/-0.5 2.4+/-0.5 2.9+/-0.5 K-40 (Raw)
- 1. 6+/-0. 2 1.3+/-0.1 2.9+/-0.3 3.0+/-0.3 2.3+/-0.2 (Treated) 1.6+/-0.2 1.5+/-0. 2 2.8+/-0.3 3.1+/-0.3 2.9+/-0.3 JUNE
<121
<ll9
<3.9
<5.1 12+/-3 8.2+/-2.6 0.89+/-0.09 0.94+/-0.09 DECEMBER ANNUAL AVERAGE
<108
<108
- 1. 7+/-0.6
- 1. 3+/-2. 2
<0.5 1.1+/-2.6 5.2+/-0.6 4.8+/-5.9 2.3+/-0.5 3.1+/-3.3 2.1+/-0.2
- 1. 7+/-1.6.
I 2.8+/-0.3 1.9+/-1.8 '
TABLE C-19 CONCENTRATIONS OF STRONTIUM-89* AND -90, AND GAMMA EMITIERS** IN QUARTERLY COMPOSITES OF POTABLE WATER Station SA-PWA-2F3 Results in Units of pCi/1 +/- 2 sigma 1-01-79 4-01-79 7-01-79 10-01-79 to to to to SAMPLE 3-31-79 6-30-79 9-30-79 12-31-79 Raw Sr-89
<0.6
<0.9 0.8+/-0.7
<1.0 Sr-90 0.4+/-0.3
<0.5
<0.6 0.7+/-0.4 Gamma Emitters K-40
<31
<9.3
<9.3
<7.8 Treated Sr-89
<0.6
<0.9
<1.3
<0.9 Sr-90 0.4+/-0.3
<0.5 0.4+/-0.4 0.7+/-0.3 Gamma Emitters K-40 54+/-24
<7.8
<7.8
<7.8 Sr-89 results are corrected for decay to sample stop date.
All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-32.
68 j
TABLE C-20 CONCENTRATIONS OF STRONTIUM-89* AND -90 IN BENTHOS Results in Units of pCi/g(dry) +/- 2 sigma STATION NUMBER SA-ESB-llAl SA-ESB-12C 1 SA-ESB-7El SA-ESB-16Fl DATE 6-12-79 10-23-79 6-12-79 10-23-79 6-12-79 10-23-79 6-12-79 10-23-79 Benthos Sr-89 14+/-6
<l. 7
<609 (1)
<13
<3.7
<1.5
<442(l)
<420(l)
<3.0
<0*. 7
<17l(l)
<5.4
<1.2
<0.6 76+/-75(2)
<167(1)
Sr-89 results are corrected for*decay to sample stop date.
(1)
High MDL due to small sample size.
(2)
High counting error due to small sample size.
69
TABLE C-21 CONCENTRATIONS OF STRONTIUM-90 AND GAMMA EMITTERS* IN SEDIMENT**
Results in Units of pCi/g(dry) +/- 2 sigma STATION NO.
SA-ESS-llAl SA-ESS-12Cl SA-ESS-7El SA-ESS-16Fl DATE 6-12-79 10-23-79 6-12-79 10-23-79 6-12-79 10-23-79 6-12-79 10-23-79 Sr-90
<0.05
<0.03
<0.04
<0.04
<0.04
<0.03
<0.09
<0.04
'-J K-40 14+/-1 17+/-2 18+/-2 15+/-2 14+/-1 13+/-1 13+/-1 12+/-1 0
<0.02 0.04+/-0.02
<0.02
<0.02
<0.02
<0.02
<0.04
<0.03 Co-60
<0.03 0.09+/-0.02
<0.03
<0.03 0.03+/-0.01 0.07+/-0.02
<0.03
<0.03 Cs-137 0.16+/-0.03 0.28+/-0.03
<0.02 0.04+/-0.02 0.08+/-0.02 0.08+/-0.02
<0.03
<0.03 Ce-141
<0.1
<0.08
<O.l
<0.08
<0.1
<0.08
<0.1 0.11+/-0. 08 Ra-226 0.68+/-0.07 0.80+/-0.08 0.62+/-0.06 0.93+/-0.09 0.49+/-0.05 0.85+/-0.09 0.43+/-0.07 0.40+/-0.06 Th-232 0.66+/-0.08 1.0+/-0.1 1.1+/-0.1 0.81+/-0.08 0.40+/-0.04 0.83+/-0.08 0.63+/-0.09 0.80+/-0.10 All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-32.
Sediment samples included associated benthic organisms.
TABLE C-22 CONCENTRATIONS OF IODINE-131 IN MILK Results* in Units of pCi/l STATION NO.
JANUARY**
FEBRUARY MARCH APRIL MAY JUNE SA-MLK-13E3
<0.05
<0.06
<0.06
<0.07
<0.07
<0.08
<0.04
<0.06
<0.07
<0.08
<0.08
<0.06 SA-MLK-2F4
<0.04
<0.07
<0.06
<0.06
<0.07
<0.07
<0.04
<0.06
<0.06 0.18+/-0.05
<0.07
<0.07 SA-MLK-5F2
<0.04
<0.04
<0.07
<0.06
<0.07
<0.08
<0.04
<0.06
<0.06 0.14+/-0.06
<0.06
<0.06 SA-MLK-14Fl
<0.05
<0.08
<0.07
<0.07
<0.06
<0.1
<0.05
<0.06
<0.07 0.14+/-0.04
<0.06
<0.07 SA-MLK-15Fl
<0.05
<0.06
<0.07
<0.06
<0.07
<0.09
<0.04
<0.05
<0.08
<0.09
<0.06
<0.06 SA-MLK-3Gl
<0.04
<0.08
<0.05
<0.06
<0.07
<0.08
<0.04
<0.06
<0.06 0.66+/-0.07
<0.06
<0.08 I-'
STATION NO.
JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER SA-MLK-13E3
<0.09
<0.06
<0.08
<0.1
<0.09
<0.08
<0.07
<0.07
<0.06
<0.2
<0.1
<0.1 SA-MLK-2F4
<0.09
<0.06
<0.06
<O.l
<0.08
<0.08
<0.08
<0.05
<0.06
<0.09
<0.1
<0.08 SA-MLK-5F2
<0.1
<0.07
<0.09
<0.09
<0.08
<0.1
<0.08
<0.05
<0.05
<0.08
<0.1
<0.09 SA-MLK-14Fl
<0.1
<0.05
<0.06
<0.1
<0.07
<0.08
<0.07
<0.06
<0.07
<0.1
<O:l
<0.1 SA-MLK-15Fl
<0.09
<0.07
<0.07
<0.09
<0.08
<0.08
<0.06
<0.06
<0.07
<0.1
<0.1
<0.07 SA-MLK-3Gl
<0.1
<0.06
<0.08
<0.08
<0.07
<0.09
<0.09
<0.05
<0.05
<0.07
<0.1
<0.1 I-131 results are corrected for decay to sample stop date.
Actual sampling dates can be found on Table C-24.
TABLE C-23.
CONCENTRATIONS OF GAMMA EMITTERS* AND STRONTIUM-89** AND -90 IN MILK Results in Units of pCi/l +/- 2 sigma STATION NO.
NUCLIDE JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-MLK-13E3 K-40 1500+/-150 1300+/-130 980+/-98 910+/-91 990+/-99 970+/-97 Cs-137
<0.9 3.0+/-1.2 2.0+/-0.7 1.8+/-0. 7
<3.1 2.4+/-0.7 Sr-89
<2.1
<1.5
<1.3
<1. 7
<3.1
<17(1)
Sr-90 3.8+/-0.8 2.3+/-0.6 2.7+/-0.6 3.1+/-0.7 3.6+/-1.o*
<6.7(1)
SA-MLK-2F4 K-40 1800+/-180 1400+/-140.
1100+/-110 1200+/-120 1200+/-120 910+/-91 Cs-137 2.* 3+/-1. a 2.7+/-1.2 2.6+/-0.7 2.5+/-0.9
<3.1
- 1. 2+/-0. 6 Sr-89
<3.0
<2.2
<1.4
<1.6
<3.9
<:10(1)
- 2. 4+/-1. 0 2.0+/-1.0 2.6+/-0.6 2.9+/-0.7 3.9+/-1.2
<4.4 SA-MLK-5F2 K-40 1400+/-140 1200+/-120 980+/-98 830+/-83 1000+/-100 1300+/-130
-.....J Cs-137 2.3+/-1.1 2.0+/-1.3 1.9+/-0.8 2.2+/-0.7 2.8+/-2.6 4.1+/-1. 2 N
Sr-89
<3.2
<3.3
<3.0
<2.0
<3.7
<3.8 Sr-90 7.2+/-1.2 1.5+/-1.0
<1.5 7.8+/-1.0 6.8+/-1.1
- 5. 9+/-1.0 STATION NO.
NUCLIDE JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER SA-MLK-13E3 K-40 1000+/-100 1100+/-110 1900+/-190 1500+/-150 630+/-63 1600+/-160 Cs-137
- 1. 4+/-0. 7
<0.8(1)
<1.2
<1.2
<1.1
<1.4 Sr-89
<11(1)
<7.0
<2.4
<4.6
<1.8
<2.2 Sr-90 3.8+/-2.2
<3.4(1) 0.9+/-0.7
- 3. 4+/-1.6 2.0+/-0.6 2.3+/-0.6 SA-MLK-2F4 K..:40 880+/-88 1100+/-110 1400+/-140 1100+/-110 1600+/-160 1700+/-170 Cs-137 1.3+/-0.6
- 1. 3+/-0. 6
<1.2
<1.4 1.6+/-1. 2 2.1+/-1.1 Sr-89
<5.4
<7.1(1)
<5.4
<8.5(1)
<3.9
<11(1)
Sr-90 2.5+/-1.7
<3.5 (1) 2.0+/-1.8 5.0+/-2.6
<1.9
<5.8(1)
SA-MLK-5F2 K-40 990+/-99 830+/-83 1400+/-140 1300+/-130 1800+/-180 1300+/-130 Cs-137 3.0+/-0.7 1.8;!:0. 6
- 4. 5+/-1. 2
<1.2 3.7+/-1.2
<1.4 Sr-89
<3.7
<4.3
<4.8
<9. 0 (1)
<10(1)
<21(1)
Sr-90 5.1+/-1.0 5.5+/-1.0
- 2. 7+/-1.4 12+/-2
<3.5(1) 8.7+/-4.2
~ --
'....j w
~..
TABLE C-23 (cont.)
CONCENTRATIONS OF GAMMA EMITTERS** AND STRONTIUM-89* AND -90 IN MILK Results in Units of pCi/l +/- 2 sigma STATION NO.
NUCLIDE JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-MLK-14Fl K-40 1300+/-130 1400+/-140 1000+/-100 1400+/-140 920+/-92 1100+/-110 Cs-137 1.2+/-1. l 1.2+/-1. l 1.8+/-0. 7
<0.6
<1.6
- 1. 9+/-0. 7 Sr-89
<2.4
<2.2
<1.5
<1.7
<2.8 5.9+/-4.9 Sr-90 4.4+/-0.9 2.5+/-1.0 2.5+/-0.6 2.9+/-0.8 2.8+/-0.8
<4.0(l)
SA-MLK-15Fl K-40 1500+/-150 1400+/-140 1000+/-100 960+/-96 950+/-95 1000+/-100 Cs-137 2.3+/-1.l
<1.2 2.5+/-0.7 2.7+/-0.8 2.0+/-1.9
- 1. 7+/-0. 7 Sr-89
- 1. 7+/-1. 5
<3.0
- 2. 7+/-1.5
<1.8
<2.7
<12(1)
Sr-90 3.1+/-0.9 3.0+/-1.l 3.5+/-0.4 3.4+/-0.8 3.3+/-0.9 3.7+/-3.4 SA-MLK-3Gl K-40 1300+/-130 1200+/-120 770+/-77 970+/-97 1000+/-100 1200+/-120 Cs-137 1.6+/-1.l
<1.4
- 1. 7+/-0.5
<0.8
<3.1 1.4+/-0. 6 Sr-89
<2.7
<1.3
<3.3
<1.8
<8.0(1) 4.4+/-2.9 Sr-90 4.9+/-1.0 2.8+/-0.7
<l.6(1) 3.7+/-0.8 5.8+/-2.6
- 2. 4+/-1. 7 STATION NO.
NUCLIDE JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER SA-MLK-14Fl K-40 1400+/-140 730+/-73 1400+/-140 1500+/-150 1500+/-150 1500+/-150 Cs-137 1.9+/-0. 7 0.7+/-0.6
<1.2
<1.4
<1.2
<1.2 Sr-89
<2.7
<5.6(1)
<2.6
<4.4
<1.6
<4.3 Sr-90 3.4+/-0.9 3.2+/-1.2 2.7+/-0.8 3.1+/-1.4
<0.8 3.4+/-0.9 SA-MLK-15Fl K-40 950+/-95 1400+/-140 1900+/-190 1200+/-120 1400+/-140 1600+/-160 Cs-137 2.1+/-0.7
<1.4
<1.2
<1.4
<1.2 2.7+/-1.2 Sr-89
<4.9
<6.2(1)
<2.5
<2.4
<4.3
<2.3 Sr-90 3.6+/-0.7 2.8+/-0.8 0.9+/-0.6 2.2+/-0.8
<2.3(1) 2.7+/-0.7 SA-MLK-3Gl K-40 990+/-99 990+/-99 1300+/-130 1400+/-140 1500+/-150 1400+/-140 Cs-137 2.1+/-0.7
- 1. 8+/-0. 7
<1.4
<1.4
<l. 2 3.2+/-1.3 Sr-89
<4.2 2.2+/-2.0
<2.8
<7.0(1)
<11(1)
<44(1)
Sr-90 6.1+/-1.9
- 4. 8+/-1. l 5.1+/-0.9 3.5+/-2.3
<3.8(1)
< 13 ( 1)
All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-32.
Sr-89 results are corrected for decay to sample stop date.
(1)
High MDL due to low chemical yield.
Sample consumed in reanalysis.
TABLE C-24
. SAMPLING DATES FOR MILK SAMPLES MONTH 2F4 5F2 14Fl 15Fl 3Gl 13E3 JANUARY 1-02-79 1-02-79 1-01-79 1-01-79 1-02-79 1-02-79 to to to to to to 1-03-79 1-03-79 1-02-79 1-02-79 1-03-79 1-02-79 1-14-79 1-14-79 1-15-79 1-15-79 1-14-79 1-15-79 to to to to to to 1-15-79 1-15-79 1-16-79 1-16-79 1-15-79 1-16-79 FEBRUARY 2-05-79 2-05-79 2-04-79 2-04-79 2-05-79 2-05-79 to to to to to to 2-06-79 2-06-79 2-05-79 2-05-79 2-06-79 2-06-79 2-19-79 2-18-79 2-18-79 2-18-79 2-20-79 2-20-79 to to to to to to
-.....i.
2-20-79 2-20-79 2-20-79 2-20-79 2-20-79 2-21-79
.+:::>
MARCH 3-05-79 3-05-79 3-04-79 3-04-79 3-05-79 3-05.,.79 to to to to to to 3-06-79 3-06-79 3-05-79 3-05-79 3-06-79 3-06-79 3-19-79 3-19-79 3-18-79 3-18-79 3-19-79 3-19-79 to to to to to to 3-20-79 3-20-79 3-19-79 3-19-79 3-20-79 3-20-79 APRIL 3-29-79 3-30-79 3-30-79 3-30-79.
3-29-79 3-30-79 to to to to to to 3-31-79 3-31-79 3-31-79 3-31-79 3-31-79 3-31-79 4-16-79 4-16-79 4-15-79 4-15-79 4-16-79 4-16-79 to to to to to to 4-17-79 4-17-79 4-16-79 4-16-79 4-17-79 4-17-79 MAY 5-06-79 5-06-79 5-07-79 5-07-79 5-06-79 5-07-79 to to to to to to 5-07-79 5-07-79 5-08-79 5-08-79 5-07-79 5-08-79 5-20-79 5-21-79 5-21-79 5-21-79 5-20-79 5-21-79 to to to to to to 5-21-79 5-21-79 5-22-79 5-22-79 5-21-79 5-22-79
MONTH 2F4 5F2 JUNE 6-03-79 6-03-79 to to 6-04-79 6-04-79 6-17-79 6-17-79 to to 6-18-79 6-18-79 JULY 7-01-79 7-01-79 to to 7-02-79 7-02-79 7-15-79 7-15-79 to to
'-I 7-16-79 7-16-79 (J1 AUGUST 8-06-79 8-04-79 to to 8-07-79 8-07-79 8-20-79 8-20-79 to to 8-21-79 8-21-79 SEPTEMBER 9-03-79 9-03-79 to to 9-04-79 9-04-79 9-17-79 9-17-79 to to 9-18-79 9-18-79 OCTOBER 10-01-79 10-01-79 to to 10-02-79 10-02-79 10-15-79 10-14-79 to to 10-16-79 10-16-79 TABLE C-24 (cont.)
SAMPLING DATES FOR MILK SAMPLES 14Fl 15Fl 6-04-79 6-04-79 to to 6-05-79 6-05-79 6-18-79 6-18-79 to to 6-19-79 6-19-79 7-02-79 7-02-79 to to 7-03-79 7-03-79 7-16-79 7-16-79 to to 7-17-79
.. 7-17-79 8-05-79 8-05-79 to to 8-06-79 8-06-79 8-19-79 8-19-79 to to 8-20-79 8-20-79 9-04-79 9-04-79 to to 9-05-79 9-05-79 9-16-79 9-16-79 to to 9-17-79 9-17-79 9-30-79 9-30-79 to to 10-01-79 10-01-79 10-14-79 10-14-79 to to 10-15-79 10-15-79 3Gl 13E3 6-03-79 6-04-79 to to 6-04-79 6-05-79 6-17-79 6-18-79 to to 6-18-79 6-19-79 7-01-79 7-02-79 to to 7-02-79 7-03-79 7-15-79 7-16-79 to to 7-16-79 7-17-79 8-06-79 8-06-79 to to 8-07-79 8-07-79 8-20-79 8-20-79 to to 8-21-79 8-21-79 9-03-79 9-04-79 to to 9-04-79 9-05-79 9-17-79 9-17-79 to to 9-18-79 9-18-79 10-01-79 10-01-79 to to 10-02-79 10-02-79 10-15-79 10-15-79 to to 10-16-79 10-16-79
MONTH 2F4 NOVEMBER 11-04-79 to
-...J 11-05-79 O'\\
11-18-79 to 11-19-79 DECEMBER 12-02-79 to 12-03-79 12-16-79 to 12-17-79 TABLE C-24 (cont.)
SAMPLING DATES FOR MILK SAMPLES 5F2 14Fl 15Fl 11-04-79 11-03-79 11-03-7~
to to to 11-05-79 11-05-79 11-05-79 11-19-79 11-19-79 11-19-79 to to to 11-20-79 11-20-79 11-20-79 12-02-79 12-03-79 12-03-79 to to to 12-03-79 12-04-79 12-04-79 12-15-79 12-17-79 12-17-79 to to to 12-17-79 12-18-79 12-18-79 3Gl 13E3 11-04-79 11-04-79 to to 11-05-79 11-05-79 11-18-79 11-19-79 to to 11-19-79 11-20-79 12-02-79 12-03-79 to to 12-03-79 12-04-79 12-16-79 12-17-79 to to 12-17-79 12-18-79
TABLE C-25 CONCENTRATIONS OF GAMMA EMITTERS* IN EDIBLE FISH Results in Units of pCi/g(wet) +/- 2 sigma STATION SAMPLING DATE K-40 SA-ESF... llAl 6-01-79 to
- 1. 5+/-0. 2 7-16-79 9-24-79 to 2.9+/-0.3 10-23-79 SA-ESF-12Cl 6-01-79 to 0.6+/-0.1 7-16-79 9-24-79 to 4.4+/-0.4 10-23-79 SA-ESF-7El 6-01-79 to 2.3+/-0.2 7-16-79 9-24-79 to 3.7+/-0.4 10-23-79 All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-32.
77
-.....i ex>
TABLE C-26 CONCENTRATIONS OF STRONTIUM-89* AND -90, AND TRITIUM IN EDIBLE FISH SAMPLES Bones (pCi/g(dry} +/- 2 sigma}
STATION DATE Sr-89 Sr-90 SA-ESF-llAl 6-01-79 to
<0.3 1.2+/-0.1 7-16-79 9-24-79 to
<0.1
<0.06 10-23-79 SA-ESF-12Cl 6-01-79 to
<1.1
- 1. 4+/-0. 3 7-16-79 9-24-79 to
<0.2 0.18+/-0.05 10-23-79 SA-ESF-7El 6-01-79 to
<0.2 0.19+/-0.05 7-16-79 9-24-79 to
<0.2 0.07+/-0.05 10-23-79 Sr-89 results are corrected for decay to sample stop date.
(1)
Sample lost in analysis.
Aqueous Fraction (pCi/l +/- 2 sigma}
H-3 68+/-63 148+/-58
<102 82+/-57 95+/-64
<91 Flesh Organic Fraction (pCi/l +/- 2 sigma}
- 529+/-75 221+/-72 381+/-73 (1) 176+/-69 38i+/-69
TABLE C-27 CONCENTRATIONS OF GAMMA EMITTERS* IN BLUE CRAB SAMPLES STATION NUMBER SA-ECH-llAl SA-ECH-12Cl Results in Units of pCi/g(wet) +/- 2 sigma DATE 6-26-79 9-24-79 to 10-23-79 6-26-79 9-24-79 to 10-23-79 SAMPLE TYPE Flesh Flesh Flesh Flesh K-40 (1)
- 1. 7+/-0. 2 (1)
- 1. 6+/-0. 2 All other gamma emitters <LLD; typical LLDs are given in Table C-32..
(1)
Insufficient sample to analyze because of flesh deterioration.
co 0
TABLE C-28 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND TRITIUM IN BLUE CRAB SAMPLES STATION Sr-89 NUMBER DATE SAMPLE pCi/g +/- 2 sigma SA-ECH-llAl 6-26-79 Flesh (wet)
(1)
Shell (dry)
<0.2 9-24-79 Flesh (wet)
<0.03 to 10-23-79 Shell (dry)
<0.2 SA-ECH-12Cl 6-26-79 Flesh (wet)
(1)
Shell (dry)
<0.3 9-24-79 Flesh (wet)
(2) to 10-23-79 Shell (dry)
<0.2 Sr-89 results are corrected for decay to sample stop date.
(1)
Insufficient sample to analyze Because of flesh deterioration.
(2)
Sample lost in analysis.
Sr-90 pCi/g +/- 2 sigma (1) 0.32+/-0.05
<0.01 0.43+/-0.05 (1) 0.46+/-0.06 (2) 0.49+/-0.06 H-3 (Edible Portion) pCi/l +/- 2 sigma (1) 78+/-72 (1) 248+/-91
co 1--'
TABLE C-29 CONCENTRATIONS OF GAMMA EMITTERS* AND STRONTIUM-89** AND -90 IN FOOD PRODUCTS Results in Units of pCi/g(wetl +/- 2 sigma STATION NO.
DATE SAMPLE TYPE K-40 Sr-89 Sr-90 SA-FPV-2El 5-07-79 Asparagus
- 1. 9+/-0. 3
<0.007 0.002+/-0.002 SA-FPV-3H4 7-29-79 Green Peppers 2.0+/-0.2
<0.01 0.005+/-0.004 SA-FPV-3H4 7-29-79 Tomatoes 1.9+/-0.2
<0.01
<0.006 SA-FPV-13E3 7-30-79 Tomatoes 2.3+/-0.2
<0.008 0.004+/-0.002 SA-FPL-3H4 7-30-79 Cabbage 1.0+/-0. l
<0.02
<0.009 SA-FPG-3H4 7-30-79 Corn 2.1+/-0.2
<0.01
<0.005 SA-FPV-3H4 7-30-79 Cucumbers 1.2+/-0.1
<0.005 0.007+/-0.002 SA-FPV-3El 7-30-79 to Tomatoes 6.6+/-0.7
<0.007
<0.003 7-31-79 SA-FPG-5Dl 7-31-79 Corn 3.1+/-0.3
<0.009
<0.005 SA-FPV-2El 7-31-79 Green Peppers 2.2+/-0.2
<0.01
<0.005 SA-FPL-1F3 7-31-79 Cabbage 4.5+/-0.5
<0.3 0.24+/-0.07 SA-FPG-2F4 8-13-79 Corn 2.9+/-0.3
<0.01 0.007+/-0.004 SA-FPV-2F4 8-13-79 Tomatoes 2.8+/-0.3
<0.007
<0.004 SA-FPL-lGl 8-14-79 Cabbage 2.6+/-0.3
<0.04
<0.02 SA-FPG-lGl 8-14-79 Corn 2.1+/-0.2
<0.006
<0.003 SA-FPV-lGl 8-14-79 Green Peppers 2.3+/-0.2
<0.02
<0.009 SA-FPV-lGl 8-14-79 Tomatoes 1.9+/-0.2
<0.01
<0.005 All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-32.
Sr-89 results are corrected for decay to sample stop date.
CXl N
STATION NO.
SA-GAM-3El SA-GAM-llEl SA-GAM-3El SA-GAM-1101 SA-GAD-4Dl SA-GAM-4El SA-FPB-3El SA-THB-3El SA-FPB-14Fl SA-THB-14Fl TABLE C-30 CONCENTRATIONS OF GAMMA EMITTERS* AND STRONTIUM-89 AND -90** IN MEAT, GAME, AND BOVINE THYROID Results in Units of pCi/g(wet) +/- 2 sigma DATE SAMPLE TYPE K-40 Cs-137 Sr-89 Sr-90 pCi/g(dry)+/-2 sigma 3-05-79 Muskrat 1.9+/-0.2 0.008+/-0.006
<0.04 0.17+/-0.02 3-05-79 Muskrat 2.0+/-0.2
<0.008
<0.009 0.029+/-0.004 12-09-79 Muskrat 3.2+/-0.3
<0.01 0.1+/-0.1 0.48+/-0.06 12-10-79 Muskrat 3.2+/-0.3
<0.02
<0.1 0.33+/-0.05 12-13-79 Venison 2.1+/-0.2
<0.01 12-15-79 to Muskrat 3.6+/-0.4
<0.01 0.2+/-0.1
- 1. 0+/-0. 1 12-16-79 3-21-79 Beef
- 1. 9+/-0. 3
<0.03 3-21-79 Bovine Thyroid
<1.6
<0.1 5-15-79 Beef 2.4+/-0.2
<0.009 5-15-79 Bovine Thyroid 1.1+/-0. 7
<0.08 All other garruna emitters searched for were <LLD; typical LLDs are given in Table C-32.
Radiostrontium performed on muskrat bones only.
Sr-89 results are corrected for decay to sample stop date.
00 w
STATION NUMBER SA-VGT-2F4 SA-VGT-13E3 SA-VGT-5Dl SA-VGT-3Gl SA-VGT-3Gl SA-VGT-13E3 SA-VGT-5F2 SA-VGT-14Fl SA-VGT-15Fl SA-FPG-15Fl SA-FPG-5Dl.
SA-FPG-3El TABLE C-31 CONCENTRATIONS OF GAMMA EMITTERS* IN FODDER CROP SAMPLES Results in Units of pCi/g(dry) +/- 2 sigma SAMPLE DATE TYPE Be-7 8-27-79 Corn Sil age 9-03-79 Corn Silage 9-09-79 to Grass 9-10-79 9-10-79 Corn Si 1 age 9-10-79 Green Chop 9-11-79 Alfalfa Hay 10-00-79 Sil age 10-00-79 Sil age 11-03-79 to Grass 2.0+/-0.5 11-06-79 12-10-79 Soybeans 12-06-79 to Soybeans 12-07-79 12-08-79 Soybeans K-40
- 1. 3+/-0. 5 7.1+/-1. 7 14+/-5
- 5. 2+/-1.4
. 20+/-5 35+/-4 7.4+/-0.9 13+/-1 2.2+/-0.5 15+/-2 13+/-1 10+/-1 All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-32.
Those nuclides not routinely reported are indicated by a dash (-).
TABLE C-32 TYPICAL LLDs FOR GAMMA SPECTROMETRY*
SURFACE AIR WELL/POTABLE FOOD FODDER WATER FISH SEDIMENT PART! CU LA TES PRECIPITATION WATER MILK PRODUCTS CROPS GAME SHELLFISH NUCLIDES (pCi/l)
(pCi/g)
(pCi/g)
(lo-3pci /m3)
(pCi/l)
(pCi /1)
(pGi/l)
(pGi I g-wet)
(pCi/g-dry)
(pCi/g-wet)
(pGi/g-wet)
Be-7 0.3 Na-22 0.8 0.01 0.03 0.3 1.0 0.8 0.8 0.005 0.05 0.006 0.1 K-40 7.8 6.2 11 7.8 Cr-51 4.7 0.2 0.5 4.4 9.8 6.2 3.1 0.02 0.3 0.05 0.2 Mn-54 0.7 0.01 0.02 0.3 0.7 0.7 0.6 0.003 0.05 0.006 0.01 Co-58 0.8 0.02 0.02 0.4 0.8 0.9 0.8 0.01 0.05 0.008 0.02 Fe-59 1.2 0.05 0.1 0.6 2.5 1.6 1.6 0.02 0.08 0.01 0.03 Co-60 0.8 0.01 0.03 0.5 0.9 0.8 0.6 0.003 0.05 0.008 0.01 Zn-65
- 1. 7 0.03 0.05 0.8
- 1. 7 1.5 1.6 0.01 0.09 0.02 0.03 co Zr-95 0.05 0.7
+:::>
Nb-95 0.02 0.3 ZrNb-95 0.6 0.01 0.6 0.6 0.6 0.03 0.05 0.006 0.01 Mo-99 4.7 48 6.2 3.1 1.1 0.6 0.05 Ru-103 0.04 0.4 RuRh-106 6.2 0.1 0.2 3.2 6.6 6.4 4.7 0.03 0.3 0.06 0.1 Ag-llOm 0.7 0.01 0.09 1.0 0.7 0.7 0.6 0.003 0.05 0.006 0.01 Sb-125 0.06 0.9 Te-129m 21 0.3 0.8 6.2 20 14 9.3 0.2 0.7 0.1 0.3 I-131 4.0 0.2 0.8 1.0 8.0 0.9 0.5 0.009 0.06 0.006 0.2 Te-132 0.5 5.8 6.0 0.6 0.3 0.02 0.06 0.005 I-133 0.008 Gs-134 0.8 0.01 0.03 0.3 0.6 0.6 0.8 0.01 0.05 0.008 0.01 Cs-136 2.4 0.1 0.4 0.7 4.5 1.8 0.9 0.009 0.05 0.009.
0.1 Gs-137 0.8 0.01 0.8 0.8 1.2 0.003 0.05 0.008 0.01 BaLa-140 2.0 0.08 0.6 1.3 4.7 1.5 0.6 0.02 0.05 0.006 0.07 Ge-141 0.08 0.8 Ce-144 3.1 0.05 0.2 5.0 3.2 1.4 0.* 03 0.2 0.03 0.03 Ra-226 1.2 0.02 D.8 1.2 1.2 0.9 0.02 0.08 0.01 0.02 Th-232 3.1 0.05 1.2 3.1 3.1 3.1 0.03 0.2 0.03 0.05 Dash (-) indicates a positive concentration was measured in all samples analyzed.
APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES 85
GROSS ALPHA ANALYSIS OF SAMPLES Total Water (A0, Al)
A 250 ml (A0) or one 1 (Al) aliquot of the sample is evaporated to dryness on a hot plate in a preweighed, 2 11 X 1/4 11 ringedplanchet, allowed to cool, and re-weighed.
The*planchet is counted in a low-background, gas flow proportional counter.
Self-absorption corrections are made based on the measured sample weight and calculated thickness.
The calibration standard used is Pu-239.
A 250 ml or one 1 sample of distilled water is evaporated in the same manner and used as a blank.
Total Salt Water (AA)
Alpha emitters are concentrated initially from a liter aliquot of water sample by coprecipitation with magnesium hydroxide.
The precipitate is then dissolved in hydrochloric acid and titanium trichloride is added to the solution.
The alpha emitters are coprecipitated by adding birium chloride and sulfuric acid to pre-cipitate barium sulfate.
The precipitate is transferred to a tared stainless steel planchet and dried.
The planchet is reweighed and counted in a low back-ground gas-flow proportional counter.
Self-absorption corri~ctions are made on the basis of the weight of the precipitate.
Calculations are made utilizing the following equations:
Result (pCi/l)
=
((S/T)
(B/t)) I (2.22 VE TF) 2 sigma error (pCi/l)
= 2 ((S/T2) + (B/t2)) 112 / (2.22 V E TF) where:
S
=
Gross counts of sample B = Counts of blank E
=
Fractional Pu-239 counting efficiency T
= Number of minutes sample was counted t
= Number of minutes blank was counted V = Sample aliquot size (liters)
TF = Transmission factor (based on net weight of sample in counting planchet)
Calculation of lower limit of detection (LLD)
The detection limit is assumed to be exceeded when the counting result is different from the blank reading by at least 4.66 times the standard deviation of that back-ground.
LLD (pCi/l)
= 4.66 (B 112) I (2.22 VE TF t) 87
where:
B E
t v TF
=
=
=
=
=
Counts of blank Fractional Pu-239 counting efficiency Number of minutes blank was counted Volume of aliquot (liters)
Transmission factor (based on net weight of sample in counting planchet)
Air Particulates (AD)
After a decay period of three to seven days, to allow for the decay of short lived radium and thorium daughter products, the filters are counted in a gas-flow proportional counter.
The alpht activity per unit volume is calculated from the volume of air filtered.
An unused filter is used as a blank.
Calculations are made utilizing the following equations:
Result (pCi/m3) = ((S/T)
(B/t)) I (2.22 V E) 2 sigma error (pCi/m3) = 2 ((S/T2) + (B/t2)) 112 / (2.22 V E) where:
s
= Gross counts of sample B = Counts of blank E = Fractional Pu-239 counting efficiency T = Number of minutes sample was counted t
= Number of minutes blank was counted v = Volume of aliquot (cubic meters)
Calculation of lower limit of detection (LLD)
The detection limit is assumed to be exceeded when the counting result is different from the blank reading by at least 4.66 times the standard deviation of that back-ground.
LLD {pCi/l)
= 4.66 (B1/ 2) / (2.22 VE t) where:
B E
t v.
=
=
Counts of blank Fractional Pu-239 counting efficiency Number of minutes blank was counted Volume of aliquot (cubic meters)
GROSS BETA ANALYSIS OF SAMPLES Total Water (B0, Bl)
A 250 ml (B0) or one 1 (Bl) aliquot is evaporated to dryness on a hot plate in a preweighed, 2 11 x 1/4 11
, ringed planchet and reweighed.
The planchet is then counted in a low background gas-flow proportional counter. Self-absorption corrections are made based on the measured residue weight and calculated thickness.
The calibration standard used is Sr Y-90.
A 250 ml or one 1 sample of distilled water is evapo-rated in the same manner and used as a blank.
Calculations are made utilizing the following equations:
Result (pCi/l) = ((S/T) - (B/t)) I (2.22 VE TF) 2 sigma error (pCi/l) = 2 ((S/T2) + (B/t2)) 112 / (2.22 VE TF) where: s B
E T
t v TF
=
=
=
=
=
=
=
Gross counts of sample Counts of blank Fractional Sr-90-Y-90 counting efficiency Number of minutes sample was counted Number of minutes blank was counted Volume of aliquot (liters)
Transmission factor (based on net weight of sample in counting planchet)
Calculation of lower limit of detection (LLD)
The detection limit is assumed to be exceeded when the counting result for the sample is different from the blank reading by at least 4.66 times the standard deviation of that background.
LLD (pCi/l) = 4.66 (B 112) I (2.22 VE TF t) where:
B
= Counts of blank E = Fractional Sr-90-Y-90 counting efficiency t
= Number of minutes blank was counted V = Volume of aliquot (liters)
TF = Transmission factor (based on net weight of sample in counting planchet)
Air Particulates (BD)
After a decay period of three to seven days, tq allow for the decay of short lived radium and thorium daughter products, the filters are counted in a gas-flow proportional counter.
The beta activity is calculated from the volume of air filtered.
An unused filter paper is used as a blank.
Calculations are made utilizing the following equations:
Result (pCi/m3) = (S/T) - (B/t)) I (2.22 V E) 89
2 sigma error (pCi/m3) = 2 ((S/T2) + (B/t2)) 112 / (2.22 VE) where:
S = Gross counts of sample B = Counts of blank E
= Fractional Sr-90-Y-90 counting efficiency T
=
Number of minutes sample was counted t
= Number of minutes blank was counted V
= Volume of sample (cubic meters)
Calculation of lower limit of detection (LLD)
The detection 1 imit is assumed to be exceeded when the counting result for the sample is different from the blank reading by at least 4.66 times the standard deviation of that background.
LLD (pCi/m3) = 4.66 (8 112) I (2.22 V E t) where:
B = Counts of blank E = Fractional Sr-90-Y-90 counting efficiency t
= Number of minutes blank was counted V = Volume of sample (cubic meters) 90
GAMMA SPECTROMETRY OF SAMPLES Water (Nl)
Four liters of sample is reduced to 100 ml and sealed in a standard container and counted with a NaI(Tl) detector coupled to a multi-channel pulse-height analyzer.
The counting time is 50,000 seconds.
Milk (N7)
A 4 liter aliquot is dried at 175°C, ashed at 500°C until no carbon residue is present, compressed and sealed in *a standard container, and then counted with a NaI(Tl) detector, coupled to a multi-channel pulse-height analyzer.
The counting time is 50,000 seconds.
Dried Solids (N8, GS)
A large quantity of the sample is dried at a low temperature, less than 100°C.
A 100 gram aliquot (or the total sample if less than 100 grams) is taken, compressed to unit density, sealed in a standard container, and counted with a NaI(Tl) or Ge(Li) detector, coupled to a multi-channel pulse-height analyzer.
The counting time is 50,000 seconds.
Air Dried Solids (NA)
A large quantity of sample is air dried.
A 100 gram aliquot (or the total sample if less than 100 grams) is taken, compressed to unit density, sealed in a standard container and counted with a Nal(Tl) detector, coupled to a multi-channel pulse-height analyzer.
The counting time is 50,000 seconds.
Air Particulate (GB)
All samples received for the month are mixed, compressed, and sealed in the standard container, and counted with the high resolution Ge(Li) detector, coupled to a multi-channel pulse-height analyzer.
Calculation of result and two sigma error The spectrum obtained is smoothed to eliminate spurious statistical noise.
Peaks are identified by changes in the slope of the gross spectrum.
The net.
counting rate above the baseline is calculated. This counting rate is con-verted to activity in curie units, making allowance for counting efficiency and gamma ray abundance.
A PDP-11 computer program was introduced for spectrum analysis.
Calculations are made utilizing the following equations:
Result (pCi/l, g or m3) = ((S/T)
(B/t)) I (2.22 VE F) 2 sigma error (pCi/l, g or m3)
= 2 ((S/T2) + (B/t2)) 112 / (2.22 VE F) 91
where:
s B
T E v F
=
=
=
=
=
=
Sample counts in energy channels for peak being quanti tated Background counts in energy channels for peak being quanti tated Number of minutes sample was counted Detector efficiency for energy of interest Sample aliquot size Fractional gall1l1a abundance Calculation of lower limit of detection (LLD) for G8 and GB LLD (pCi/l, g or m3) = 4.66 (6 S) 112 / (2.22 VE FT) where:
S
= Sample counts in energy channels for peak being quanti tated T
= Number of minutes sample was counted E = Detector efficiency for energy of *interest V = Sample aliquot size F
= Fractional gall1l1a abundance Calculation of lower limit of detection (LLD) for Nl, N7, NB and NA LLD (pCi/l, g or m3) = 4.66 (.63 6 S) 1/ 2 / (2.22 VE FT) where:
s T
E v F
=
=
=
=
=
Sample counts in energy channels for peak being quantitated Number of minutes sample was counted Detector efficiency for energy of interest Sample aliquot size Fractional gall1l1a abundance 92
ANALYSIS OF.WATER SAMPLES FOR POTASSIUM-40 BY AA (E~)
Sample Preparation An aliquot sample sfze of 100 ml is filtered.
The concentration of potassium is determined spectr6photometrically on a Perkin Elmer Model 373 atomic absorption unit.
The. result obtained, in micrograms per milliliter, is multiplied by the specific activity of 0.12% for natural potassium to deter-mine the amount of potassium-40 present in the sample.
The error reported is 10% of KCl are determined with each sample set.
Calculations are made using the following equations:
K-40 (pCi/l)
=
Cs D (C/S) K 103 LLD (pCi/l) = Cs D (.1/S) K 103 where:
Cs c s D
K
=
=
=
=
=
=
Concentration of Standard (µg K/ml)
Sample reading Standard reading Dilution factor Specific activity of K-40 per unit weight of potassium
- 852 pCi /mg 93
ANALYSIS OF SAMPLES FOR TRITIUM Water (H2)
A 15 ml aliquot of the sample is vacuum distilled to eliminate dissolved gasses and non-volatile matter.
The distillate is frozen in a trap cooled with a dry ice-isopropanol mixture.
Eight (8) ml of the distillate are mixed with ten (10) ml of Insta-Gel liquid scintillation solution.
The sample is then counted for tritium in a liquid scintillation counter. A sample of low tritium (<50 pCi/l) water is vacuum distilled as a blank and is counted with each batch of samples.
In the calculation of the result it is assumed that the condensated and original sample are of equivalent volumes.
The volume change associated with the removal of dissolved gases and non-volatile matter is not significant compared to the other errors in the analysis.
Calculations are made utilizing the following equations:
Result (pCi/l) = ((S/T) - (B/t)) I (2.22 VE) 2 sigma error {pCi/l) = 2 ((S/T2) + (B/t2)) 112 / (2.22 VE}
where:
S
= Total gross counts of sample B = Counts of blank E = Fractional H-3 counting efficiency T
= Number of minutes sample was counted t
= Number of minutes blank was counted V
= A 1 i quot vo 1 ume ( l i te rs )
Gross counts of sample may be corrected for the blank activity. If the collection container is rinsed with distilled water and the rinse is added to the sample, the rinse plus sample and a separate aliquot of the distilled water are counted.
The corrected gross counts for the sample only are calculated using the following equa-tions:
S
= ((s-b)v) I G s
=
( c ( G+H ) ) I V b
= (d(H)) I V V = ((G+H) V) I G where:
s G
H s
b v
c d
=
=
=
=
=
=
=
=
Gross counts of sample Volume of sample Volume of rinse Volume corrected gross counts of sample plus rinse Volume corrected gross counts of rinse Corrected aliquot volume Uncorrected gross counts o*f sample plus rinse Uncorrected gross counts of rinse 94
Calculation of lower limit detection (LLD)
The detection limit is assumed to be exceeded when the counting result is different from the blank reading by at least 4.66 times the.standard deviation of that background.
LLD (pCi/l) = 4.66 (B112) I (2.22 VE t) where:
B = Counts of blank E
= Fractional H-3 counting efficiency t
= Number of minutes blank was counted V = Aliquot volume (liters)
Aqueous and Organic Fraction of Milk or Organic Solids (H3, H4, H9)
A carefully measured aliquot of a food produc~, such as milk or fish, is dried in a rotating vacuum flash evaporator.
During the evaporation process, the evaporated water fraction is trapped out by a dry ice isopropanol mixture for counting as in (a) below.
The dried residue is reserved for (b).
The wet sample is analyzed as in (c).
- a.
Aqueous H-3 in Food Products An eight (8) ml aliquot of the cold-trapped water is counted in a liquid scintillation counter in the same manner as surface water samples are counted.
- b.
Organic Bound H-3 in Food Products The dried*residue is combusted in an RMC designed oxidizer.
The collected water - organic fraction is measured and vacuum distilled to remove any impurities.
Permanganate in KOH solution is added to remove impurities which may cause quenching.
An eight (8) ml aliquot is counted in a liquid scintillation counter.
If less than eight (8) ml are collected, the entire portion collected is carefully measured \\'Jith a 10 ml pipette and then counted.
A sample of deep well water is counted as a blank.
- c.
Aqueous and organic Bound H-3 in Food Products A wet weight aliquot is combusted in an RMC designed oxidizer.
The collected water fraction is measured and vacuum distilled to remove any impurities.
Per-manganate in KOH solution is added to remove impurities which may cause quenching.
An eight (8) ml aliquot is counted in a liquid scintillation counter.
If less than eight (8) ml are collected, the entire portion collected is carefully measured with a 10 ml pipette and then counted.
A sample of deep well water is counted as a blank.
Calculations are made utilizing the following equations:
Result (pCi/l)
=
((S/T) - (B/t)) I (2.22 V E) of distillate 2 sigma error (pCi/l)
= 2 ((S/T2) + (B/t2)) 112 / (2.22 VE) of distillate 95
Result (pCi/g of freeze dried sample) = A (YI) 2 sigma error (pCi/g of freeze dried sample) = C (YI)
Result (pCi/g or l of original sample) = A (YF) 2 sigma error (pCi/g or l of original sample) = C (YF) where:
s B
E T
t v YI VF A c
=
=
=
=
=
=
=
=
=
=
Gross counts of sample Counts of blank Fractional H-3 counting efficiency Number of minutes sample was counted Number of minutes blank was counted Volume of distillate counted Liters of water-organic recovered/ g of freeze dried sample Liters of water recovered/ (1 or g) of sample aliquot taken Result in pCi/l of distillate 2 sigma error in pCi/l of distillate Calculation of lower limit detection (LLD)
The detection limit is assumed to be exceeded when the counting result is dif-ferent from the blank reading by at least 4.66 times the standard deviation of that background.
LLD (pCi/l) = 4.66 (8 112) I (2.22 VE t)
LLD (pCi/g of freeze dried sample) = F (YI)
LLD (pCi/l or g) = F (VF) of original sample where:
B = Counts of blank E
= Fractional H-3 counting efficiency t
= Number of minutes blank was counted V
=
Volume of distillate counted YI = Liters of water-organic recovered/g of freeze dried sample VF
= Liters of water recovered/(l or g) of sample aliquot taken F
= LLD in pCi/l of distillate 96
ANALYSIS OF SAMPLES FOR IODINE-131 Milk or Water (!0)
The initial stable iodide concentration in milk is determined with an iodide ion specific electrode. Thirty milligrams of stable iodide carrier is then added to four (4) liters of milk.
The iodide is removed from the milk by passage through ion-exchange resin.
The iodide is eluted from the resin with sodium hypochlorite, and purified by a series of solvent extractions with the final extraction into a toluene phase.
The toluene phase is mixed with a toluene-based liquid scintillation solution.
The sample is then counted in a*
beta-gated gamma coincidence detector, shielded by six inches of steel. Distilled water is used as a blank.
The yield is calculated from stable iodide recovery based on the recovered volume.
Calculations are made utilizing the following equations:
Result = ((S/T) - (B/t)) I (2.22 VE FY)
(pCi/l) 2 sigma error = 2 ((S/T2) + (B/t2)) 112 / (2.22 VE FY)
(pCi/l)
= 4.66 (8 112) I (2.22 V E F Y t)
(pCi/l) where: s B
t E v F
y
=
=
=
=
=
=
=
Gross counts of sample in channels containing I-131 peak Background counts in channels containing I-131 peak Number of minutes background was counted Iodine-131 counting efficiency Sample aliquot size Fractional gamma abundance Chemical yield of iodine Air Cartridges (Il)
An iodine absorber composed of charcoal is emptied into an aluminum can (6 ems high by 8 ems in diameter) and counted with a Na! (Tl) detector, coupled to a multi-channel pulse-height analyzer.
Calculation of results and two sigma error Peaks are identified by changes in-the slope of the spectrum.
If peaks are iden-tified the spectrum obtained is srooothed to elimin'ate spurious statistical noise.
The presence of iodine-131 is identified by the presence of a 364 Kev peak.
The net counting rate above the baseline is calculated. This counting rate is con-verted to activity in curie units, making allowance for counting efficiency and gamma ray abundance.
A PDP-11 computer program is used for spectrum analysis.
Results are corrected for decay from the sampling time to the middle of the counting period, using a half-life value for I-131 of 8.06 days.
Calculations are made *utilizing the following equations:
Result = ((S/T) ~ (B/t)) / (2.22 VE F Y)
(pCi/m3) 97
2 sigm~ error = 2 ({S/T2) + (B/t2)) 112 / (2.22 VE F. Y)
(pCi/m )
= 4.66 (8 112) I (2.22 V E F Y t)
{pCi/m3) where: s
=
B =
t
=
E
=
v =
F
=
Gross counts of sample in channels containing I-131 peak Background counts in channels containing I-131 peak Number of minutes background was counted Iodine-131 counting efficiency Sample aliquot size Fractional gamma.abundance 98
ANALYSIS OF SAMPLES FOR STRONTIUM-89 AND -90 Total Water (S~, T0).
A two liter aliquot of sample is used.
Stable strontium carrier is added to the liquid to facilitate chemical separation of Sr-89 and -90, and to determine the strontium recovery.
Strontium concentration and purification is ultimately real-*
ized by at least two precipitations of strontium nitrate in concentrated nitric acid. Additional iron rare earth scavenging and barium chromate separations are performed to remove suspected interfering nuclides.
The purified strontium is converted to a carbonate for weighing and counting.
Soon after 'the separation, the sample is counted in a low-background gas-flow proportional counter. After about 14 days, the sample is recounted, then Sr-89 and -90 activities are calcu-lated on the basis of Y-90 ingrowth and Sr-89 decay.
A sample of distilled water is used as a blank.
Milk (S4, T4)
A one and half liter aliquot of milk is ashed to destroy organic material *and then dissolved in concentrated mineral acid. Stable strontium is added to the dissolved ash to facilitate chemical separation of Sr-89 and -90, and to determine the strontium recovery.
Strontium concentrations and* purification is ultimately realized by at least two precipitations of strontium nitrate in concentrated nitric acid. Additional iron rare earth scavenging and barium chromate separations are performed to remove su£;pected interfering nuclides.
The purified strontium is* converted to a carbonate for weighing and counting.
Soon after the separation, the sample is counted in a low background gas-flow proportional counter. After about 14 days, the sample is recounted, then Sr-89 and -90 activities are calculated on the basis of Y-90 ingrowth and Sr-89 decay.
A sample of distilled water is used as a blank.
Bones antl Shells (S5, T5)
A large quantity of the sample is dried, ashed and a 25 g portion is then dissolved in concentrated acid. Stable strontium carrier is added to the dissolved sample to facilitate chemical separations of Sr-89 and -90, and to determine the strontium recovery.
Strontium concentration and purification is ultimately realized by at least two precipitations of strontium nitrate in concentrated nitric acid.
Addi-tional iron rare earth hydroxide scavenging and barium chromate separations are per-formed to remove suspected interfering nuclides.
The purified strontium is converted to a carbonate for weighing and counting.
Soon after the separation, the sample is counted in a low-background gas-flow proportional counter. After about 14 days, the sample is recounted, then Sr-89 and -90 activities are calculated on the basis of Y-90 ingrowth and Sr-89 decay.
A sample of distilled water is used as a blank.
Soil and Sediment (S6, T6) -
A large quantity of sample is dried, and a 25 g portion is then leached with concen-trated HCl before drying.
Stable strontium carrier is added to the sample to facili-tate isolation of the strontium and to determine the strontium recovery.
Strontium concentrations and purification is ultimately realized by at least two precipitations of strontium nitrate in concentrated nitric acid. Additional iron rare earth scavenging and barium chromate separations are performed to remove suspected interfering nuclides.
The purified strontium is converted to a carbonate for weighing and counting. Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after the separation, the sample is counted in a low-background gas-flow pro-portional counter. After about 14 days, the sample is recounted, then Sr-89 and -90 99
activities are calculated on the basis of Y-90 ingrowth and Sr-89 decay.
A sample of distilled water is processed with each batch of samples.
Organic Solids (SB, T8)
A 250 g portion of the sample is ashed and then dissolved in concentrated acid.
Stable strontium carrier is added to the dissolved sample to facilitate chemical separation of Sr-89 and -90, and to determine the strontium recovery.
Strontium concentration and purification is ultimately realized by at least two precipitations of strontium nitrate in concentrated nitric acid. Additional iron rare earth hydrox-ide scavenging and barium chromate separations are performed to remove suspected inter-fering nuclides.
The purified strontium is converted to a carbonate for weighing and counting.
Soon after the separation, the salllJle is counted in a low-background gas-flow proportional counter.
After about 14 days, the sample is recounted, then Sr-89 and -90 activities are calculated on the basis of Y-90 ingrowth and Sr-89 decay.
A sample of distilled water is used as a blank.
Air Particulates {SA, TA)
Stable strontium carrier is added to facilitate chemical isolation of Sr-89 and
-90 and for determination of the strontium recovery in the procedure~
Strontium concentrations and purification is ultimately realized by at least two precipitations of strontium nitrate in concentrated nitric acid. Additional hydrox-ide precipitations and barium chromate separations are performed.
The purified strontium is converted to a carbonate for weighing and counting.
Gross beta counts are made soon after the strontium isolation and again after a 7-14 day interval and Sr-90 and Sr-89 activities are calculated on the basis of appropriate Sr-89 decay and Y-90 ingrowth equations.
Calculations are made using the following equations:
Result Sr-90 =3((Z{Sl-Bl)) - (S2-B2)) / (2.22 K V E9 Y T)
{pCi/l, g or m) 2 sigma error ~r-90 = 2 (Z2{Sl+Bl) + S2+B2) 112 / (2.22 (K2)112 V E9 YT)
(pCi/l, g or m )
MDL = (-9 -6(2 82+Z(Sl-B1)) 1/ 2 + 2.25 + z2(Sl+Bl))/(4.44 V E9 YT)
(pCi/l, g or m3)
Result Sr-89 =3(F(Sl-Bl) + H(S2-82)) I (2.22 V E8 Y T exp (-.693t4/52.7))
(pCi/l, g or m )
2 sigma error Sr-89 = 2(F2(Sl+Bl) + H2(S2+82)) 112 / (2.22 V EBY T exp(-.693t4/52.7))
(pCi/l, g or m3)
MDL = (F(X-Bj) + H (S2-B2)) / (2.22 V E8 Y T exp (-.693t4/52.7))
(pCi/l, g or m )
100
where:
Sr-89(1)
Y-90(2)
Sl S2 Bl B2 tl t2 t3 t4 El E2 z R
H K
F c B x E9 EV E8 T
y v
= Sr-89 counts on first count
= Counts of Sr-90
= Counts of Y-90 on first count
= Counts of Y-90 on second (after equil.)
= Sr-89(1) + Sr-90 + Y-90(1) + 8(1) *
= Sr-89(2) + Sr-90 + Y-90(2) + B(2)
= Blank counts in first count
= Blank counts in second count
= Time in hours from separation time to Sl
= Ti me in days from separation ti me to S2
= Time in days from Sl to S2
= Time an days from sampling date to separation date
= 1 - exp (-. 693tl/64 hours)
= 1 - exp (-. 693t2/2.667 days)
= exp (-.693t3/52.7 days)
= E9/EY
= (1 + E l/R)/K Z (El/R + 1) (E2/R)
- t-g ~~/~i)--Z9(~~/~~£+B2)+(F B1) 2-2 F H B2 S2+2 F H Bl B2 2
+ (H(S2-B2))
= 2 F H ( 52-82) - 2 F2 81 - 9 F2
- = ((82 - 4 F2 c)l/2 - 8) / (2 F2)
= Counting eff. of Sr-90 =.3590 -.* 7082 X. (Wt. in g of strontium carbonate)
= Counting eff. of Y-90
=.4380 -.1337 X (Wt. in g of strontium carbonate)
= Counting eff~ of Sr-89 =.4568 -.2060 X (Wt. in g of strontium carbonate)
= Number of minutes sample and blank were counted
= Yield
= Sample aliquot size Calculatfon of minimum detectable levels (MDLs)
Due to the method of ca lcul ati ng the activity of Sr-90 in the presence of Sr-89, the form used in the NBS Handbook 80 for calculating minimum detectable activities is not applicable.
101
ENVIRONMENTAL.DOSIMETRY (00)
Measurement Techniques Each dosimeter utilized is a capillary tube containing calcium sulfate. (Tm) powder as the thermal uminescent dosimeter (TLD) material. This was chosen primarily for its high light output, minimal thermally induced signal loss (fading), and lack of self-dosing.
The energy response curve has been flattened by a complex multiple element energy compensation shield supplied by Panasonic Corporation, manufacturer of the TLD reader.
The four dosimeters per station are sealed in a polyethylene bag to demonstrate integrity at time of measurement.
Visible through the bag are the sample placement instructions.
One set of TLDs is placed in a lead shield at.RMC and represents a zero dose.
The TLDs are then taken and placed in the field stations; one field TLD set is placed in a field lead shield at station 18 and is used in calculating the in-transit dose.
Following the pre-designated exposure period the TLD is heated with hot gas and the luminescence measured with a TLD reader.
Data are normalized to standard machine conditions by correcting machine settings to zero before readout.
Data are corrected for in-transit dose using a set of TLDs which is kept in a lead shield in the field and only exposed during transit.
Average dose per exposure period, and its error, are calculated.
The basic calibration is in mR exposure to a standard Cs-137 source. This is converted to absorbed dose in tissue by the factor : 0.955 rad/Roentgen and to dose equivalent by using a quality factor of 1.
Calculation of results and two sigma error gross TLD(i) = (TLD(i) -
D~(i)) (CF (ins)) (CF(i)) 0.955 mrad/mRoentgen
.ITO = NET(si te~) - (NET(RMC0) (D(sta) I D(RMC0))).
NET TLD(i) = gross TLD{i) - ITO n
AVG
= ((sigma NET TLD)/n){D{STD) I D(EX))
i=l ERROR {95% CL) = t(n-1) sigma NET TLD(i) / n) (D(STD)/D(EX))
102
ENVIRONMENTAL DOSIMETRY (cont.)
where:
Gross TLD(i)
= Individual TLD reading corrected to standard instrument con di ti ons TLD( i)
= Gross reading of dosimeter i NET TLD(i)
= Net dose obtained during exposure period in the field CF( ins)
= Correction factor of reader= (6.21) (ELs-0.95)
ELS
= External light source D~ (i)
= Zero for dosimeter, i CF(i)
= Calibration factor for dosimeter i ITO
= In-Transit dose NET( site )0
= Mean of n dosimeters in site lead shield NET(RMC)0
= Mean of n dosimeters in RMC lead shield D(sta)
= Exposure period of station D(RMC0)
= Exposure period of RMC0 AVG
= Mean exposure per standard exposure period at a given station n
= Number of readings D(EX)
= Days exposed D(STD)
= Days in standard exposure period t( n-1)
= t-distribution (student) factor for 95% CL sigma NET TLD(i)
= Standard deviation of n readings of NET TLD(i)
ERROR
= The 95% confidence limit error of AVG 103
APPENDIX E
SUMMARY
OF INTERLABORATORY COMPARISONS 105
TABLE E-1 INTER-LABORATORY COMPARISONS: ALPHA & BETA DATE RMC #
SAMPLE RMC EPA ALL PARTICIPANTS UNITS TYPE MEAN+/-s.d.
MEAN+/-s.d.
MEAN+/-s.d.
Sept 1978 96793 Water 2+/-1 5+/-5 6+/-2 pCi/l 13+/-1 10+/-5 11+/-2 pCi /1 Oct 1978 98135 Water 17+/-1 19+/-5 19+/-8 pCi/l 41+/-1 34+/-5 35+/-8 pCi/l Nov 1978 98577 Water 12+/-1 11+/-5 11+/-3 pCi/l 29+/-1 26+/-5.
26+/-4 pCi/l Jan 1979 99915 APT 4+/-1 5+/-5 5+/-2 pCi/fil ter 21+/-1 18+/-5 20+/-3 pCi /fi 1 ter Jan 1979 100511 Water 7+/-1 6+/-5 7+/-2 pCi/ 1 13+/-2 16+/-5 16+/-3.
pCi/l Apr 1979 2323 Water 8+/-1 10+/-5 10+/-4 pCi/l 17+/-1 16+/-5 16+/-3 pCi/l Apr 1979 2546 APT 13+/-1 14+/-5 14+/-3 pCi/fi 1 ter 61+/-3 63+/-5 65+/-6 pCi /fi 1 ter May 1979 4650 Water 22+/-1 22+/-6 25+/-8 pCi/l 36+/-3 44+/-5 43+/-6 pCi/l June 1979 6446 Water 19+/-2 18+/-5 16+/-6 pCi/l 25+/-3 22+/-5 23+/-5 pCi/l July 1979 8393 APT 9+/-1 9+/-5 10+/-2 pCi/fi lter 39+/-2 30+/-5 33+/-4 pCi /fi 1 ter July 1979 8672 Water 8+/-2 9+/-5 pCi/l 15+/-1.
12+/-5 pCi/l Oct 1979 19885 Water 5+/-1 5+/-5 8+/-2 pCi/l 43+/-2 40+/-5 41+/-6 pCi/l Results are not available at this time.
107
DATE Dec 1978 Feb 1979 Apr 1979 June 1979 Aug 1979 Oct 1979 TABLE E-2 INTER-LABORATORY COMPARISON TRITIUM IN WATER AND URINE UNIT : pCi /l RMC #
SAMPLE RMC EPA ALL PARTICIPANTS TYPE MEAN+/-s.d.
MEAN+/-s.d.
MEAN+/-s.d.
99262 Water 1894+/-64 2030+/-346 1995+/-249 100914 Water 1158+/-30 1280+/-331 1293+/-224 3729 Water 2057+/-232 2270+/-349 2292+/-257 7054 Water 1367+/-140 1540+/-337 1573+/-231 9937 Water 1054+/-140 1480+/-335 1508+/-214 20368 Water 1498+/-63 1560+/-370 Results are not available at this time.
108
TABLE E-3 INTER-LABORATORY COMPARISON: STRONTIUM-89 AND -90 DATE RMC #
SAMPLE ISOTOPE RMC EPA ALL PARTICIPANTS.
UNITS TYPE MEAN+/-s.d.
MEAN+/-s.d.
MEAN+/-s.d.
Oct 1978 98135 Water Sr-89 5+/-1 10+/-5 10+/-3 pCi/l Sr-90 5+/-1 5+/-2 5+/-1 pCi/l Jan 1979 99915 APT Sr-90 5+/-0 6+/-2 6+/-1 pCi/filter (N=3)
Jan 1979 100557 Mi 1 k Sr-89 23+/-1 33+/-5 29+/-4 pCi/l Sr-90 24+/-1 19+/-2 17+/-3 pCi/l Mar 1979 1604 Food Sr-89 36+/-4.
48+/-5 43+/-8 pCi/kg Sr-90 15+/-2 22+/-2 22+/-4 pCi/kg Apr 1979 2546 APT Sr-90 20+/-1 21+/-2 19+/-3 pCi/fil ter Apr 1979 4606 Mi 1 k Sr-89 29+/-6 42+/-5 34+/-1 pCi/l Sr-90 41+/-2 54+/-3 48+/-7 pCi/l May 1979 4650 Water Sr-89 9+/-3 9+/-5 10+/-4 pCi I 1 Sr-90 8+/-2 8+/-2 8+/-1 pCi/l July 1979 8393 APT Sr-90 7+/-1 10+/-2 10+/-2 pCi /fi 1 ter July 1979 9937 Milk Sr-89
<3 5+/-5 6+/-3 pCi/l Sr-90 7+/-2 11+/-2 12+/-2 pCi/l Oct 1979 20468 APT Sr-90 6+/-1 10+/-2 pCi/filter Nov 1979 22079 Milk Sr-89 23+/-2 25+/-5 pCi/l Sr-90 14+/-1 17+/-2 pCi/l Results are not available at this tirre.
109
TABLE E-4 INTER-LABORATORY COMPARISON GAMMA DATE RMC #
SAMPLE NUCLIDE RMC EPA ALL PARTICIPANTS UNITS TYPE MEAN+/-s.d. MEAN+/-s.d.
MEAN+/-s.d.
Oct.1978 97770 Water Cr-51 152+/-18 117+/-6 126+/-32 pCi/l Co-60 29+/-1 23+/-5 23+/-4 pCi /1 Zn-65 85+/-2 82+/-5 82+/-10 pCi/l Ru-106 42+/-3 46+/-5 47+/-14 pCi/l Cs-134 25+/-1 25+/-5 25+/-4 pCi /1 Cs-137 131+/-1 125+/-6 127+/-11 pCi /1 Oct 1978 98135
- Water Co-60
<2 0
0 pCi /1 Cs-134 9+/-1 10+/-5 10+/-4 pCi/l Cs-137 13+/-1 13+/-5 13+/-4 pCi/l Jan 1979 99915 APT Cs-137 7+/-1 6+/-5 8+/-2 pCi/fil ter Jan 1979 100057 Milk I-131 102+/-3 105+/-5 106+/-8 pCi/l Cs-137 51+/-1 49+/-5 51+/-4 pCi/l Ba-140
<6 0
0 pCi/l K
1516+/-44 1560+/-78 1499+/-113 mg/l Mar 1979 101060 Water Cr-51
<14 0
0 pCi/l Co-60 12+/-1 9+/-5 10+/-3 pCi/l Zn-65 25+/-3 21:t5 22+/-5 pCi/l Ru-106
<9 0
0 pCi/l Cs-134 6+/-1 6+/-5 7+/-2 pCi/l I
Cs-137 13+/-1 12+/-5 13+/-3 pCi/l Mar 1979 1604 Food I-131 140+/-17 90+/-5 90+/-6 pCi/kg Cs-137 92+/-3 74+/-5 75+/-6 pCi/kg Ba-140
<70 0
0 pCi/kg K
3189+/-71 2700+/-135 2798+/-236 mg/kg Apr 1979 2546 APT Cs-137 24+/-2 21+/-5 23+/-5 pCi/fil ter Apr 1979 3577 Water I-131 43+/-4 40+/-4 41+/-7 pCi/l Apr 1979 4606 Milk I-131 73+/-11 96+/-5 100+/-10 pCi/l Cs-137 182+/-10 154+/-8 156+/-13 pCi/l Ba-140
<22 0
0 pCi/l K
1702+/-31 1560+/-78 1504+/-110 mg/l May 1979 4650 Water Co-60 13+/-1 15+/-5 16+/-4 pCi/l Cs-134 10+/-1 19+/-5 20+/-5 pCi/l Cs-137
<2 0
0 pCi/l Jun 1979 7025 Water Cr-51
<35 0
0 pCi/l Co-60 44+/-6 47+/-5 47+/-6 pCi /1 Zn-65
<3 0
0 pCi/l Ru-106
<12 0
0 pCi/l Cs-134 62+/-5 71+/-5 68+/-7 pCi/l Cs-137
<2 0
0 pCi/l 110
TABLE E-4 (cont.)
INTER-LABORATORY COMPARISON GAMMA DATE RMC #
SAMPLE NUCLIDE RMC EPA ALL PARTICIPANTS UNITS TYPE MEAN+/-s.d.
MEAN+/-s.d.
MEAN+/-s.d.
July 1979 8393 APT Cs-137 13+/-1 10+/-5 12+/-4 pCi/fil ter July 1979 8837 Milk I-131 17+/-3 17+/-5 18+/-4 pCi/ 1 Cs-137 15+/-3 12+/-5 13+/-3 pCi/l Ba-140
<6 0
0 pCi/l K
1629+/-7T 1630+/-81 1567+/-17 mg/l Aug 1979 9208 Water I-131 21+/-1 26+/-5 25+/-4 pCi/l Oct 1979 20468 APT Cs-137 18+/-0 12+/-3 pCi/filter Nov 1979 22079 Milk Cs-137 52+/-2 49+/-5 pCi/l I-131 632+/-32 637+/-32 pCi /1 K
1509+/-67 1470+/-73 mg/l Dec.1979 23288 Water I-131 52+/-2 53+/-5 pCi/ 1 Results are not available at this time.
111
APPENDIX F SYNOPSIS OF DAIRY & VEGETABLE GARDEN SURVEY 113
APPENDIX F SYNOPSIS OF DAIRY & VEGETABLE GARDEN SURVEY A door-to-door survey of dairy farms within 5 miles of SNGS was performed in April and July.
The results of the April survey v1ere as follows:
One dairy farm, located 4.9 miles from SNGS in the west sector was located.
The results of the July survey were as follows:
No change from April survey.
Since a dairy farm was located within 5 miles of the site, the vegetable garden survey vrns performed to a distance of one mile.
No vegetable gardens were found in this area.
115