Text

Artificial Island Radiological Environ Monitoring Program.
	ML18078B179
Person / Time
Site:	Salem
Issue date:	03/31/1978
From:	; Public Service Enterprise Group
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ML18078B178	List: ML18078B177; ML18078B179;
References
	RMC-TR-79-03, RMC-TR-79-3, NUDOCS 7904120302
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RMC-TR-79-03 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1978 RADIOLOGICAL REPORT JANUARY 1 TO DECEMBER 31, 1978 Prepared For PUBLIC SERVICE ELECTR IC AND GAS COMPANY By RADIATION MANAGEMENT CORPORATION MARCH 1978 7 9 0 4 I 2 0 3 02.

RMC-TR-79-03 1978 RADIOLOGICAL REPORT ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM January 1 to December 31, 1978 E\Ju1ro So12-:t-2.

Prepared for UY' \L\ .. i, .., ,

~()\l\-Z:ot1-s--~

Public Service Electric and'~GGCompany by Radiation Management Corporation March 1978

TABLE OF CONTENTS PAGE

SUMMARY

1 INTRODUCTION 2 THE PROGRAM 3 Objectives 3 Sample Collection 3 Data Interpretation 5 RESULTS AND DISCUSSION 6 Airborne 6 Precipitation 9 Direct 9

)

Water 10 Aquatic 14 Ingestion

15 Fodder Crops 18 19 CONCLUSIONS 20 REFERENCES 21 APPENDIX A - PROGRAM

SUMMARY

29 APPENDIX B - SAMPLE DESIGNATION &LOCATIONS 37 APPENDIX C - 1978 DATA TABLES APPENDIX D - SYNOPSIS OF ANALYTICAL PROCEDURES 83 APPENDIX E -

SUMMARY

OF INTERLABORATORY COMPARISQNS 99 APPENDIX F - SYNOPSIS OF DAIRY AND VEGETABLE GARDEN SURVEY 107 i

LIST OF FIGURES NUMBER PAGE

1. Comparison of Average Concentrations of Beta Emitters in Precipitation and in Air Particulates, 1973 through 1978 7

2. Average Ambient Radiation Levels from Monthly TLDs in the Vicinity of Artificial Island, 1973 through 1978......................................................... 8

3. Average Concentrations of Tritium in the Delaware River in the Vicinity of Artificial Island, 1973 through 1978 ***** 11

4. Average Concentrations of Beta Emitters and Potassium-40 in the Delaware River in the Vicinity of Artificial Island, 1973 through 1978 ************************************!****** 12

5. Average Concentrations of Iodine-131 in Milk in the Vicinity of Artificial Island, May 1974 through December 1978 ******** 16 ii

SUMMARY

During the period January 1 to December 31, 1978, Radiation Management Corporation participdted in the Operational Radiological Environmental Monitoring Program conducted 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 concentrations 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 1978.

A total of 3472 analyses were performed on 2688 environmental samples during the period covered by this report. Samples of air particulates, air iodine, surface, ground and drinking water, benthos, sediment, milk, fish, vegetables, game, fodder crops, and precipitation were collected. Thermoluminescent dosimeters were used to measure ambient radiation levels.

A wide 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 no significant differences were observed between indicator and control stations.

It is concluded that the radiological characteristics of the environment around Artificial Island were not affected by SNGS Unit #1 during 1978.

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) and January 1 and December 31, 1977 (6).

This report summarizes the operational period between January 1 and December 31, 1978.

Artificial Island will eventually be the site of four nuclear power reactors.

Two of the reactors are part of the Salem Nuclear Generating 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 1979. 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 agricultural production. (7)

More specific information on the demography, hydrology, meteorology, and land use characteristics of the local area may be found in the Environmental Report (7), Environmental Statement (8), and the Final Safety Analyses Report {Units 1 and 2) for SNGS (9).

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. Radio-analytical data were collected and compared with results from the preoperational phase. Differences between these periods were examined statistically to determine whether any station 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 1978 REMP. Results of the four year preoperational program have been surrmarized 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 demography, 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; control samples are collected at locations which are believed 3

to be unaffected by station operations. Fluctuations in the levels of radionuclides and direct radiation at indicator stations are evaluated with respect to analogous fluctuations at control stations, which are unrelated to station operation. Indicator and background station data are also evaluated relative to preoperational data. The REMP for the Artificial Island site includes additional samples and analyses not specifically required by the Salem ETS *.The summary tables in this report include these additional samples and analyses.

Air particulates were collected on Hollingsworth and Vose H-70-018 filters with low-volume air samplers (1 cfm). 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 caso 4 (Tm) thermoluminescent 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 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 describes and summarizes, in the format of table 5.6-1 of the Salem ETS, the entire operational program as performed in 1978. 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 and quality control procedures utilized in this program are sunmarized in Appendix D. Approximately 20% of the total analytical effort is spent on quality control, including process quality control, instrument quality control, inter-laboratory 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 reference 10. Several factors are important in the interpre-tation 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 minimum detectable level.

These intervals represent the range of values into which 95% of repeated analyses of the same sample would fall.

Results for each type of sample were grouped according to the analysis performed. 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%) MDL values, averages were not calculated.

It is characteristic of environmental monitoring data that many results occur at or below the minimum detectable level (MDL). For reporting and calculation of averages, any result occurring at or below the minimum detectable level is considered to be at that level. Averages obtained using this method are there-fore biased high.

5

RESULTS AND DISCUSSION The analytical results of the 1978 REMP samples are divided into the categories based on exposure pathways: airborne, direct, water, aquatic and ingestion.

The analytical results for the 1978 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 beta emitters at eight stations and 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 105 weekly air particulate samples (2 stations) analyzed for alpha emitters, 71 showed detectable concentrations. The range o! alpha activity was from <0.0003 to 0.0038 pCi/m3 and averaged 0.0010 pCi/m

Weekly gross beta analyses showed concentrations ranging from 0.019 to 1.03 pCi/m3, with the average for the 8 sampling stations being 0.093 pCi/m3

In addition to normal seasonal fluctuations, increased activity was noted in late March and was directly attributed to fallout from the March 14 atmosheric nuclear weapons test by the Peoples Republic of China. 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 radio-nuclides, both naturally occurring and man-made (Be-7, Mn-54, ZrNb-95, Ru-103, Ru-106, Sb-125, I-131, I-132, Te-132, Cs-137, Bala-140, Ce-141 and Ce-144).

Concentrations of man-made nuclides detected during the first quarter composite can be attributed to fallout from the March 14 atmospheric nuclear weapons test. All nuclides detected were observed at the control station as well as indicator stations and at similar concentrations. The results of second, third, and fourth quarter composites showed generally decreasing levels of most nuclides. The presence of Be-7 throughout the year can be attributed to cosmic ray activity.

The radiostrontium analyses performed on the quarterly composites showed levels of Sr-89 rangin~ between <.0005 and 0.050 pCi/m3, with the average being 0.0017 pCi/m3 while Sr-90 ranged between 0.0002 and 0.0032 pCi/m3 with the average being .0015 pCi/m3. The activities noted during the first and second quarters are the result of atmospheric nuclear weapons testing on March 14 and are not related to the operation of SNGS since results were the same at indicator and control stations.

Air Iodine Iodine cartridges were connected in series behind each of the air particulate filters for absorption of gaseous iodine. The absorption media used in these cartridges was 11 TEDA 11 impregnated charcoal. Ten of 369 cartridges analyzed had detectable concentrations of I-131 ranging between OoOlO and 0.051 pCi/m3.

The detectable I-131 was observed in late March and early April at both con-trol and indicator stations, and can therefore be attributed to the world-wide fallout from the nuclear weapons testing on March 14. No additional I-131 activity wa? observed throughout the reporting period.

6

FIGURE 1 COMPARISON OF AVERAGE CONCENTRATIONS OF BETA EMITTERS IN PRECIPITATION AND IN AIR PARTICULATES, 1973 THROUGH 1978 p:i/l - - - - -

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FIGURE 2 AVERAGE AMBIENT RADIATION LEVELS FROM MONTHLY TLDs IN THE VICINITY OF ARTIFICIAL ISLAND, 1973 THROUGH 1978 3

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.Dec. 11, 1976

Preci pi ta ti on Although not specifically required by the Salem ETS, precipitation was sampled continuously and collected monthly at the Salem substation sampling location.

Monthly samples were analyzed for tritium, alpha emitters and beta emitters.

Concentrations of H-3 in these samples were all below MDL and ranged from <50 to <147 pCi/l. The concentrations of alpha emitters were below MDL (0.4-1.4 pCi/l) in nine of the twelve samples. The other three samples had alpha concentrations ranging between 1.4 and 2.0 pCi/l. Beta-emitter concentrations ranged from 3.8 to 565 pCi/l and averaged 75 pCi/l. The highest activity (565 pCi/l was found in the March sample and can be attributed to -fallout from atmospheric nuclear weapons testing.

Quarterly composites of precipitation were analyzed for radiostrontium and gamma emitters. The gamma emitters detected were naturally occurring Be-7 and Ra-226 while the man-made nuclides observed were ZrNb-95, Ru-103, Ru-106, I-131, Cs-137, BaLa-140, Ce-141 and Ce-144. Most of the nuclides were de-tected in the first quarter sample, which included samples that were affected by the March atmospheric nuclear weapons test. The Sr-89 levels ranged between 0.7 and 26 pCi/l, while those for Sr-90 ranged from 0.3 to 1.7 pCi/l. The highest results for Sr-89 occurred during the first quarter and reflect fall-out from atmospheric nuclear weapons testing._

Direct Direct radiation measurements were made at 24 locations using Caso 4 (Tm) thermo-luminescent dosimeters. A new location was added in July and continued through December. During 1978, 294 monthly and 98 quarterly TLD packets were collected.

Each packet included four dosimeters for a total of 1568 analyses. These analyses resulted in an average dose rate of 5.05 mrads/standard month for monthly TLDs and 4.73 mrads/standard month for quarterly TLDs. All TLD results presented in this report have been normalized to a standard month (30.4 days) to eliminate the apparent differences caused by variations in exposure periods. A comparison of the direct radiation data for 1978 shows a similarity between the average monthly dose for both indicator stations (4.96 mrem/std. month) and control stations (5.47 mrem/std. month). These results compare favorably to the preopera-tional results as shown in figure 2, therefore, indicating no effect from SNGS operation.

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 componeht. 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 (11). The equation which describes the model selected is:

CON;m COT*

= f (Xj * - - -

__1_)

COT; where:

f = denotes a function of Yjmi = predicted value for station j, month m, and year i 9

x.J = preoperational mean for station j CONim = average of the control stations for month m and year i COT*1 = average of the control station for year i (a 11 p11 in place of 11 i 11 represents the preoperational period)

A computer program was developed for multiple regression analysis. The least squares fit (LSF) line based on all 1978 data was determined along with the statis-tics for this line. The data for 1978 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 1978, eighteen outliers were predicted from a possible 294. Eight of these outliers occurred at station 2Sl, which was reconstructed in April 1977 after the preoperational 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.

Four positive outliers occurred at 7Sl, three occurred in the beginning of the year while construction was going on in the area of this station which could effect the terrestrial component. The fourth occurred in December, along with outliers at 2Sl and 11Sl. Construction activities at the site may have contri-buted to the appearance of these outliers. If it is conservatively assumed that these were due to station activity, the other on site locations lOSl and 6Sl should have shown positive outliers also. Since no positive outliers were observed at any other location in December, it can be concluded that there were no environmental effects from stntion activity.

Two positive outliers occurred at station 5Fl in April and September. Since no stations, other than two previously mentioned, were outliers during those months it can be concluded that they do not reflect station activity. The remaining 3 outliers were randomly distributed among the stations and are probably the result of statistical fluctuations.

Water Surface Water Monthly surface water samples were taken at five locations tn 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 Appoquin-imink River. Two other stations are located upstream--one station is in the river and the other is in the Chesapeake and Delaware Canal. The station located at the mouth of the Appoquinimink River serves as the operational control. Surface water samples were analyzed for tritium, alpha emitters, beta emitters, strontium-89 and -90, and gamna emitters.

Analysis of surface water for H-3 yielded an average concentration of 106 pCi/l and ranged from <64 to 314 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 1978 can be attributed to general reduction in the world-wide tritium inventory with the cessation of routine atmospheric weapons testing. To test whether there are differences in tritium concentration between the closest indicator location (llAl) and the control location (12Cl) a 11 t 11 test was performed. The 11 t 11 value obtained was 0.97, which shows there is no difference between means at the 95% confidence level.

10

FIGURE 3 AVERAGE CONCENTRATIONS OF TRITIUM IN THE DELAWARE RIVER IN THE VICINITY OF ARTIFICIAL ISLAND, 1973 THROUGH 1978

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FIGURE 4 AVERAGE CONCENTRATIONS OF BETA EMITTERS AND POTASSIUM-40 IN THE DELAWARE RIVER IN THE VICINITY OF ARTIFICIAL ISLAND, 1973 THROUGH 1978

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Gross alpha concentrations were generally below MDL, which ranged from 1.0 to 51 pCi/l. The large variations in MDL are due to the amount of solids present in the sample. Only 1 of the 55 samples analyzed showed detectable gross alpha activity. The result (27+/-23 pCi/l) was within the same range as the MDLs. Alpha activity may be expected in suspended solids from naturally occurring radionuclides especially during periods of high surface runoff.

Gross beta concentrations ranged from 8.0 to 118 pCi/l and averaged 42 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 concentrations of K-40 in 44 of 55 samples. The average K-40 concentration was 42 pCi/l and ranged from <6 to 120 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 (0.4 to 1.6 pCi/l) in all samples. Levels of detectable Sr-90 ranged from 0.3 to 0.7 pCi/l in 9 of the 20 samples. The MDLs values ranged from 0;3 to 0.9 pCi/l. The maximum level of Sr-90 detected in the preoperational program was 1.6 pCi/l.

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 H-3, alpha and beta activity, and K-40 (by atomic absorption). Quarterly composites were analyzed for gamma emitters, and Sr-89 and Sr-90.

Detectable concentrations of H-3 were observed in three of 36 samples ranging between <62 pCi/l to 225 pCi/l. Concentrations of alpha emitters were below the MDL (0.4 to 2.2 pCi/l) in all but one sample, and that sample had a detectable concentration of 2.4 pCi/l. The concentrations of beta emitters averaged 8.2 pCi/l and ranged from <1.8 to 16 pCi/l. The potassium-40 activity as determined by atomic absorption averaged 8.7 pCi/l. This indicates that the 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 16 pCi/l) in four of twelve samples. All results for Sr-89 and Sr-90 were below the MDL of 0.5-1.1 pCi/l and 0.3-0.7 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 trib~tary of the Delaware River) and several adjacent wells. Potable water samples were analyzed monthly for H-3, alpha and beta activity, and K-40 (by atomic absorption); Sr-89 and

-90, and gamma emitters were analyzed on a quarterly basis.

13

The concentration of H-3 averaged 110 pCi/l for all analyses, with no significant differences between the raw and treated samples. Detectable alpha activity was observed in 18 of 24 samples ranging between 0.3 pCi/l and 2.8 pCi/l in all samples. 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 activity. The average gross beta concentrations were 5.0 pCi/l (raw) and 3.4 pCi/l (treated). The average K-40 results were 1.0 pCi/l (raw) and 1.0 pCi/l (treated).

Quarterly composites of raw and treated samples were analyzed for Sr-89 and -90, and gamma emitters. All concentrations of Sr-89 were less than the MDL which ranged 0.8 pCi/l to 1.4 pCi/l. Strontium-90 was observed in four of the eight samples with concentrations ranging between 0.5 pCi/l and 0.9 pCi/l, with four samples below the MDL (0.5 pCi/l and 0.8 pCi/l). No gamma emitters were detected in any of these samples.

Aquatic Benthos Benthic organisms were collected at four locations and analyzed for Sr-89 and -90. Levels of Sr-89 were below MDL (0.2-1100 pCi/l). The wide fluctu-ations in MDL are due to inconsistencies in sample volume (32-.002 grams dry).

One of six samples showed a detectable Sr-90 concentration of 0.03 pCi/g-dry.

The detectable activity of this sample is below the MDL range (0.04 to 546 pCi/g-dry) of the other four samples. 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 organis*ms.

Sediment Sediment was collected semiannually at four locations and analyzed for gamma 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 (Zr-95, Ru-103, Cs-137, and Ce-141) were observed inter-mittently at control stations as well as indicator stations. A wide variety of radionuclides was detected in the June sample at station llAl which is located at the SNGS discharge. The majority of the nuclides detected were near the MDL. Cs-137 was detected at a concentration 10 times the control value. This was re~orted to the NRC in a nonroutine report.

Some of the activity present in this sample can be attributed to the characteristics of the sediment at this location. During the preopera-tional period concentrations of Cs-137 ranged from (0.04-0.40 pCi/g-dry) at this location. The 30 year half-life and biological assimilation of Cs-137 accounts for the continued appearance of this nuclide in sediment samples many years after atmospheric testing of nuclear weapons.

14

Sr-90 was observed in two of the eight samples analyzed. The detected activities were 0.03 pCi/g-dry and 0.04 pCi/g-dry, which are in the MDL range (0.03 to 0.06 pCi/g-dry) of the other six samples.

Ingestion Milk Milk samples were taken twice a month from six local farms during 1978 and analyzed for I-131; gamma emitters, Sr-89 and Sr-90 were analyzed monthly. Following the nuclear weapons test of March 14, additional milk samples were collected in order to meet the ETS requirements con-cerning collection during time of elevated I-131 concentrations.

Detectable concentrations of I-131 were observed in 20 of 22 samples collected from all stations between the first week of April through the first collection in May. The I-131 observed ranged between 0.09 and 12 pCi/l and was attributed to the world-wide fallout from the March 14 nuclear weapons test. Figure 5 shows the average I-131 concentrations in milk samples resulting from atmospheric nuclear weapons tests by the Peoples Republic of China between June 1974 and March 1978. No other I-131 was observed in any of the samples.

Two incidents concerning I-131 in milk samples were reported in 1978.

In both cases, the I-131 concentrations at the indicator location were a factor of ten greater than was the concentration at the control location.

The first incident occurred with the April 3 and 4 sample collected at station 5F2. It was concluded that the cause of reportable I-131 was world-wide nuclear fallout from the March 1~ nuclear weapons test since SNGS did not release detectable I-131 during this reporting period.

GaITTTia spectrometry showed detectable concentrations of K-40 in all samples and Cs-137 in all but three of the 67 samples analyzed. The annual average concentrations were 1350 pCi/l for K-40 and 3.4 pCi/l for Cs-137. These levels were not significantly different between control and indicator stations.

Strontium-89 was detected in seventeen of the sixty~seven samples analyzed with results ranging between 1.3 pCi/l and 12 pCi/l. The range of MDL values was 1.3 pCi/l to 3.9 pCi/l. Of the seventeen positive results detected fourteen were within the MDL range. The remaining positive values occurred in April and can be attributed to fallout from an atmospheric nuclear weapon test in March. The concentration of Sr-90 was positive in all but one of the 67 samples analyzed and averaged 3.8 pCi/l. Sr-90 concentrations were similar at indicator and control stations, indicating no contribution from SNGS. Due to the 28 year half-life and biological assimilation Sr-90 can be ex-pected to remain long after routine atmospheric testing has ceased.

All Sr-89 *and -90 analyses have been yield verified by atomic absorption to determine Ca interference.

Fish Edible fish samples (American eel, White Perch, Channel Catfish, Spot, etc.) were collected at three locations and analyzed for 15

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gamma emitters and tritium. Fish bones were analyzed for Sr-89 and Sr-90.

Gamna spectrometry of these samples showed K-40 in all 6 samples analyzed at an average concentration of 2.6 pCi/g-wet with a range of 2.2-3.2 pCi/g-wet.

Cs-137 was detected in one of the six samples at a concentration of .007 pCi/g-wet which is close to the range of MDL values (0.005-0.006 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 78 pCi/l with a range of <57-169 pCi/1 for the aqueous fraction and 305 pCi/l for the organic fraction with a range of 227-466 pCi/l. Of the six samples analyzed, four results are essentially the same as those found in surface water for the same period. The remaining two results were slightly higher (403-466 pCi/l) than the highest result detected in surface water (314 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 minimum detectable level (0.1 to 0.3 pCi/g-dry), with two exceptions. The June samples from station llAl and 7El had detectable levels of 0.07 and 0.11 pCi/g-dry, respectively which is below the MDL of the other samples. Three of the four samples analyzed for Sr-90 had detectable concentrations of 0.19-0.29 pCi/g-dry.

The maximum level detected during the preoperational period was 0.94 pCi/g-dry.

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, tomatoes, squash, and eggplant. All samples con-tained K-40 at concentrations from 0.9 to 2.9 pCi/g-wet. No other gamma emitters were detected in these food products. Sr-89 concentrations were generally below MDL, which ranged from 4 to 10 pCi/kg-wet. One of the fourteen samples analyzed showed detectable Sr-89 activity. The result (9+/-7 pCi/kg-wet) was within the same range as the MDLs. Seven of the fourteen samples analyzed showed detectable Sr-90 activity (2-21 pCi/kg-wet).

Sr-90 concentrations were generally below MDL, which ranged from 3 to 7 pCi/kg-wet. Indicator and control locations had similar concentrations.

Game Four samples of muskrats were taken during this period. Flesh from all four samples was analyzed for gamma emitters while bones were analyzed for Sr-89 and Sr-90. Naturally occurring K-40 was detected in all four samples ranging from 1.7 to 2.7 pCi/g. Muskrat bones showed detectable Sr-89, with concentrations ranging between 0.1 and 0.3 pCi/g-dry. Detectable Sr-90 concentrations were observed in all samples ranging from 0.25 to 1.56 pCi/g-dry. All results were near the MDL and indicator and control stations had similar results.

Beef One beef sample was collected during this reporting period. Only naturally-occurring K-40 was detected in this sample at a concentration of 1.7 pCi/g.

17

Beef Thyroid One beef thyroid was taken during this period and analyzed for garrrna emitters.

This sample showed a detectable concentration of naturally occurring K-40 at a concentration of 0.6 pCi/g-wet.

Fodder Crops Eleven fodder crop samples were taken at 7 local farms and analyzed for gamma emitters. Gamma spectrometry of these samples showed a variety of radionuclides, both man-made and naturally occurring. 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 occurring nuclide was Be-7 with results ranging from 0.8 to 4.3 pCi/g-dry. The man-made nuclides Ru-106, Sb-125, Cs-137 and Ce-144 were observed in one sample at concentrations near the MDL. Cs-137 was also detected in another sample. All of these nuclides with the exception of Sb-125 were detected during the preoperational period at similar concentrations.

All man-made radionuclides are assumed to be from the residual world-wide fallout from the March 1978 nuclear weapons test since all were detected in the air particulate samples collected following the above mentioned test.

18

CONCLUSIONS The Radiological Environmental Monitoring Program for Salem Nuclear Generating Station at Artificial Island was conducted during 1978 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 5.05 mrem/std.

month and we~e similar to preoperational results. I-131 detected in a few samples was attributed to atmospheric fallout from a nuclear weapons test in March 1978. No other unusual radiological 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.

19

REFERENCES (1) Radiation Management Corporation. 11 Salem Nuclear Generating Station -

Radiological Environmental Monitoring Program - 1973. 11 RMC-TR-74-09, 1974.

(2) Radiation Management Corporation. 11 Artificial Island Radiological Environmental Monitoring Program - 1974 Annual Report. 11 RMC-TR-75-04, 1975.

(3) Radiation Management Corporation 11 Artificial Island Radiological Environmental Monitoring Program - 1975 Annual Report. 11 RMC-TR-76-04, 1976.

(4) Radiation Management Corporation. 11 Artificial Island Radiological Environmental Monitoring Program - Preoperational Summary - 1973 through 1976. 11 RMC-TR-77-03, 1978.

( 5) Radiation Management Corpora ti on. 11 Arti fi ci al Is land Radi ol ogi cal Environmental Monitoring Program - December 11 to December 31, 1976. 11 RMC-TR-77-02.

(6) Radiation Management Corporation. 11 Artificial Island Radiological Environmental Monitoring Program - 1977 Annual Report 11 RMC-TR-78-04A, 1977.

(7) Public Service Electric and Gas Company. 11 En'vironmental Report, Operating License Stage - Salem Nuclear Generating Station Units 1 and 2. 11 1971.

(8) United States Atomic Energy Corrrnission. 11 Final Environmental Statement -

Salem Nuclear Generating Station, Units 1 and 2. 11 Docket No. 50-272 and

. 50-311, 1973.

(9) Public Service Electric and Gas Company. 11 Final Safety Analysis Report -

Salem Nuclear Generating Station, Units 1 and 2. 11 1972.

11 (10) Radiation Management Corporation. Quality Control Data 1978 - Annual Report 11 , 1979.

(11) Radiation Management Corporation. 11 Artificial Island Radiological Environmental Interpretation of Results of the Thermoluminescent Dosimetry Program 11 RMC-TR-78-11, 1978.

20

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, 1978 TO DECEMBER 31, 1978 ANALYSIS AND MINIMUM NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER DETECTABLE ALL INDICATOR LOCATIONS LOCATION.WITH HIGHEST.MEAN CONTROL LOCATION NON ROUTINE SAMPLED OF ANALYSES LEVEL MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (MDL)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Air Particulates Alpha 105 0.3 0.9 (34/53) 3H3 110 mi NE 1.1 (37/52) 1.1 (37/52) 0 (0.4-3.8) (0.5-2.8) (0.5-2.8)

(lo- 3 pCi/m 3) Beta 422 3.4 93 (369/370) lFl 5.8 mi N 97 (53/53) 92 (52/52) 0 (19-1030) (23-961) (22-742)

Sr-89 32 0.5 2.4 (15/28) 5Sl 1.0 mi E 3.2 (2/4) 1.9 (3/4) 0 (0.4-5.0) (1.4-5.0) (0.5-3. 7)

Sr-90 32 0.2 1. 5 (28/28) lFl 5.8 mi N 1.7 (4/4) 1.3 (4/4) 0 (0.2-3.2) (0.4-2.8) (0.2-2.4)

Gamma 32 Be-7 2.0 63 (28/28) 2Sl 0.3 mi NNE 70 (4/4) 65 (4/4) 0 (50-82) (63-78) (50-78)

Mn-54 0.2 0.4 (5/28) 3H3 110 mi NE (0.5) (1/4) (0.5) (1/4) 0 (0.3-0.4)

Zr-95 0.3 1.8 (14/28) 3H3 110 mi NE 2.1 (2/4) 2.1 (2/4) 0 (0.8-3.0) ( 1.8-2 .3) ( 1.8-2.3)

N Nb-95 0.2 2.5 (18/28) 3H3 110 mi NE 2.4 (3/4) 2.4 (3/4) 0 w (0.5-5.0) {0.6-4.3) (0.1-4.3)

Ru-103 0.,2 2.4 (15/28) 2F2 8. 7 mi NNE 2.4 (3/4) 2.5 (2/4) 0 (0.3-6.3) (0.3-6.3) (0.9-0.4)

Ru-106 2.0 12 (23/28) 16El 4.1 mi NNW 13 (3/4) 16 (2/4) 0 (3. 9-19) (7.9-19) (13-19)

Sb-125 0.6 1.9 (21/28) 2F2 8.7 mi NNE 2.1 (3/4) 2.1 ( 2/4.) 0 (0.8-3.2) (1.3-3.2) (1.2-2.9)

I-131 0.2 11 (7 /28) 5Sl 1.0 mi E 3.5 (2/4) (8.8) (1/4) 0 (0.9-16) (0.9-16)

I-132 0.3 0.5 4(28) 5Sl 1.0 mi E (0.8) (1/4) - (0/4) 0 (0.3-0.8)

Te-132 0.1 0.5 (3/28) 2F2 8. 7 mi NNE (0.6) (1/4) - (0/4) 0 (0.4-0.6)

Cs-137 1 3.1 (28/28) lODl 3.9 mi SSW 3.6 (4/4) 2.9 (4/4) 0 (0.9-7. 7) (0.9-7 .7) (0.9-5.5)

BaLa-140 0.3 4.0 (10/28) 5Sl 1.0 mi E (8.4) (1/4) (4.9) ( 1/4) 0 (0.6-8.4)

Ce-141 0.2 1.9 (16/28) lFl 5.8 mi N 1.8 (3/4) (2.7) {1/4) 0 (0.43-5.7) (0.3-4.2)

Ce-144 6 19 (28/28) 3H3 110 mi NE 22 (4/4) 22 (4/4) 0 (3.1-35) ( 10-34) (10-34)

Air Iodine I-131 369 3.8 36 (8/317) 2F2 8.7 mi NNE (51) (1/53) 21 (3/52) 0

( 10- 3 pCi /m 3) (8.4-51) (9.8-37)

Precipitation Alpha 12 0.4 1.8 (3/12) 2F2 8.7 mi NNE 1.8 (3/12) No Control 0 (pCi/l) ( 1. 4-2 .0) ( 1.4-2.0) Location

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 SALEM COUNTY, NEW JERSEY JANUARY 1, 1978 TO DECEMBER 31, 1978 ANALYSIS AND MINIMUM NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER DETECTABLE ALL INDICATOR LOCATIONS 'LOCATION WITH HIGHEST MEAN CONTROL LOCATIONS NONROUTINE SAMPLED OF ANALYSES LEVEL MEAN* NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (MDL) (RANGE) DISTANCE AND DIRECTION

..... (RANGE) (RANGE) MEASUREMENTS Precipitation (cont.) Beta 12 *2.2 75 (12/12) 2F2 8.7 mi NNE 75 (12/12) 0 (pCi /1) (3.8-565) (3.8-565)

H-3 *12 50 - (0/12) None Detected 0 Sr-89 4 0.7 (26) ( 1/4) 2F2 8. 7 mi NNE (26)(1/4) 0 (26)

Sr-90 4 0.7 1.2 (3/4) 2F2 8. 7 mi NNE 1.2 (3/4) 0 (0.3-1. 7) (0.3-1.7)

Garrma 4 Be-7 2.0 21 (4/4) 2F2 8. 7 mi NNE 21 (4/4) 0

~9.5-33) (9.5-33)

ZrNb-95 0.2 1.2) (1/4) 2F2 8. 7 mi NNE (1.2) (1/4) 0 Ru-103 0.1 (23) ( 1/4) 2F2 8. 7 mi NNE (23) (1/4) 0 Ru-106 2.0 6.8 (2/4) 2F2 8. 7 mi NNE 6.8 (2/4) 0 (5.0-8.5) (5.0-8.5)

I-131 0.2 (15) (1/4) 2F2 8. 7 mi NNE (15) (1/4) 0 N

+::> Cs-137 0.5 1.6 (3/4) 2Ft 8. 7 mi NNE 1.6 (3/4) 0 (0.5-2.3) (0.5-2.3)

BaLa-140 0.3 (5.6) (1/4) 2F2 8. 7 mi NNE (5.6) (1/4) 0 Ce-141 0.2 (3.0) (1/4) 2F2 8.7 mi NNE (3.0) (1/4) 0 Ce-144 2.0 5.5(2/4) 2F2 8.7 mi NNE 5.5 (2/4) 0 (1.1-9.9) (1.1-9.9)

Ra-226 0.8 (0.8) ( 1/4) 2F2 8.7 mi NNE (0.8) (1/4) 0 Direct Radiation Gamma 1176 4.96 (984/984) lODl 3.9 mi SSW 5.62 (48/48) 5.47 (192/192) 0 (mrem/std. month) Dose (monthly) (3.44-6.33) (5.30-5.99) (4.25-6.42)

Gamma 392 4.64 (328/328) llFl 5.2 mi SW 5.50 (16/16) 5.18 (64/64) 0 Dose (quarterly) (3.30-5.81) (5.21-5.81) (4.53-6.07)

Surface Water Alpha 55 1.0 17 (2/44) 11Al 650 ft. SW (27) (1/11) - (0/11) 0 (pCi /1) (7 .9-27)

Beta 55 1.8 43 (44/44) ?El 4.5 mi SW 70 (11/11) 39 (11/11) 0 (4.3-118) (23-118) (9.3-70)

H-3 55 64 153 (21/44) ?El 4.5 mi SW 178 (7/11) 95 (5/11) 0 (72-314) (82-314) (88-110)

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 SALEM COUNTY, NEW JERSEY JANUARY 1, 1978 TO DECEMBER 31, -1978 ANALYSIS AND MINIMUM NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER DETECTABLE ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST.MEAN CONTROL LOCATIONS NONROUTINE SAMPLED OF ANALYSES LEVEL MEAN* NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (MDL) (RANGE) DISTANCE AND DIRECTION .. (RANGE) (RANGE) MEASUREMENTS Surface Water (cont.) Sr-89 20 0.4 - (0/16) None Detected - (0/4) 0 (pCi/l)

Sr-90 20 0.3 0.6 (7/16) 16Fl 6.9 mi NNW 0.5 (3/4) 0.4 (2/4) 0 (0.4-0.7) (0.4-0. 7) (0.3-0.4)

Gamma 55 K-40 5.0 52 (35/44) ?El 4.5 mi SW 71 (11/11) 46 (9/11) 0 (13-120) (13-120) (14-81)

Well Water Alpha 36 0.4 (2.4) (l/~4) 5Dl 3.5 mi E (2.4) (1/12) - (0/12) 0 (pCi/l) Beta 36 1.8 9 (21/24) 4Sl Site Well 13 (12/12) 10 (12/12) 0 N (2.0-16) (9.3-16) (7 .1-12) 01 H-3 36 62 167 (2/24) 4Sl Site Well (225) (1/12) (189) {1/12) 0 (109-225)

K-40 36 0.01 7 (24/24) 4Sl Site Well 12 (12/12) 9 (12/12) 0 (1.1-16) ( 10-16) (8-14)

Sr-89 12 0.5 - (0/8) None Detected - (0/4) 0 Sr-90 12 0.3 - (0/8) None Detected - (0/4) 0 Gamma 12 K-40 5.0 15 (2/8) 4Sl Site Well 15 (2/4) - (2/4) 0 (14-16) (14.:16) (9.8-9.8)

Potable Water Alpha 24 0.3 0.9 (18/24) 2F3 8 mi NNE 0.9 (18/24) No Control 0 Raw-Treated (0.3-2.8) (0.3-2.8) Location (pCi/l) Beta 24 0.5 4.2 (24/24) 2F3 8 mi NNE 4.2 (24/24) 0 (2.0-11) ( 2. 0-11)

H-3 24 62 240 (5/24) 2F3 8 mi NNE 240 (5/24) 0 (84-438) (84-438)

Sr-89 8 0.8 - (0/8) None Detected 0 Sr-90 8 0.5 0.7 (4/8) 2F3 8 mi NNE 0.7 (4/8) 0 (0.5-0.9) (0.5-0.4)

K-40 24 0.01 1.0 (24/24) 2F3 8 mi NNE 1.0 (24/24) 0 (0.43-1.6) (0.43-1.6)

Gamma 8 None Detected

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 SALEM COUNTY, NEW JERSEY JANUARY 1,1978 TO DECEMBER 31, 1978 ANALYSIS AND MINIMUM NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER DETECTABLE ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATIONS NONROUTINE.

SAMPLED OF ANALYSES LEVEL MEAN* NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (MDL) (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Benthos Sr-89 8 0.2 - (0/6) None Detected - (0/2) 0 (pCi/g-dry)

Sr-90 8 0.04 - ( 1/6) llAl 650 ft. SW (0.03) (1/2) - (0/2) 0 (0.03)

Sediment Sr-90 8 0.03 .04 (2/6) 16Fl 6.9 mi NW (0. 04 )(1/2) - (0/2) 0 (pCi/g-dry) (0.03-0.04)

Gamma 8 K-40 0.5 16 (6/6) 16Fl 6.9 mi NW 18 (2/2) 16. (2/2) 0 (14-19) (17-18) (15-16)

Mn-54 0.02 (0.03)(1/6) llAl 650 ft. SW (0.03)(1/2) - (0/2) 0 Co-58 0.01 (0. 09)(1/6) llAl 11 650 ft. SW (0.09)(J./2) - (0/2) 0 Co-60 0.02 (0.13)(1/6) llAl 650 ft. SW (0 .13 )(1/2) - (0/2) 0 N

O"I Nb-95 0.02 (0.12)(1/6) llAl 650 ft. SW (0.12)(1/2) - (0/2) 0 Zr-95 0.03 (0.06)(1/6) llAl 650 ft. SW (0.06)(1/2) (0.05) (1/2) 0 Ru-103 0.01 .06 (2/6) llAl 650 ft. SW (0.09)(1/2) - (0/2) 0 (0.02-0.09) -

Ru-106 0.2 (0.4) (1/6) llAl 650 ft. SW (0.4) (1/2) - (0/2) 0 Sb-125 0.04 (0.09)(1/6) llAl 650 ft. SW (0.09)(1/2) - (0/2) 0 Cs-137 0.02 0.14 (4/6) llAl 650 ft. SW 0.21 (2/2) (0.04) (1/2)

(0.06-0.21) (0.20-0.21)

Ce-141 0.02 0.04 (3/6) llAl 650 ft. SW 0.06 (1/2) 0.03 (1/2) 0 (0.03-0.06) - -

Ce-144 0.09 (0.5) ( 1/6) llAl 650 ft. SW (0.5) (1/2) - (0/2) 0 Ra-226 .07 0. 7 ( 6/6) 12Cl 2.5 mi SW 1.0 (2/2) 1.0 (2/2) 0 (0.6-0.86) (0.80-1.1) (0.80-1.1)

Th-232 0.1 1.0 (6/6) 16Fl 6.9 mi NW 1.1 (2/2) 1.0 ( 2/2) 0 (0.83-1.1) (1.1-1.1) (0.9-1.1)

Milk I-131 147 0.03 1.8 (16/121) 5F2 7 mi E 4.6 (4/26) 0.6 (4/26) 2 (pCi/l) (0.09-12) (0.27-12) (0.18-1.3)

Sr-89 67 1.3 3.1 ( 13/67) 5F2 7 mi E 4.4 (5/12) 1.9 (4/12) 0 (1.3-12) ( 1.8-12) ( 1.8-2.8)

Sr-90 67 1.4 3.8 (54/55) 5F2 7 mi E 6.0 (12/12) (4.3 (12/12) 0 (1.4-9 .0) (2.7-9.0) (2.2-5.4)

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 SALEM COUNTY, NEW JERSEY JANUARY 1, 1978 TO DECEMBER 31, 1978 ANALYSIS AND MINIMUM NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER . DETECTABLE ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATIONS NONROUTINE SAMPLED OF ANALYSES LEVEL MEAN* NAME MEAN MEAN REPORTED (UNIT UF MEASUREMENT) PERFORMED (MDL) (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Milk (cont.) Gamma 67 K-40 5.0 1412 (55/55) 2F4 6.3 mi NNE 1482 (11/11) 1400 (12/12) 0 (790-2100) (1200-2100) (850-1600)

Cs-137 0.9 3.6 (54/55) 13E3 4.9 mi W 6.0 (8/8) 2.8 (12/12) 0 (1.2-12) (2.5-12) ( 1.3-4.9)

Edible Fish H-3 6 57 108 (2/4) 12Cl 2.5 mi WSW 119. (2/2) 119 ( 2/2) 0 (pCi/l) (aqueous) (88-127) (69-169) (69-169)

H-3 6 74 282 (4/4) 12Cl 2.5 mi WSW 352 (2/2) 352 ( 2/2) 0

( o.r.gani c) (227-403) (238-466) (238-466)

(pCi/g-dry) Sr-89 6 0.1 .09 (2/4) ?El 4.5 mi SW 0.11 (1/2) - (0/2) 0 (bones) ( 0.07-0 .11)

Sr-90 6 0.1 0.23 (3/4) ?El 4.5 mi SW 0.26 (2/2) 0.24 (2/2) 0 N (Bones) (0.19-0.29) (0.22-0.29) (0.22-0.25)

-....J (pCi/g-wet) Gamma 6 K-40 0.09 2.5 (4/4) llAl 650 ft. SW 2.7 (2/2) 2.7 (2/2) 0 (2.2-3.1) (2.3-3.1) (2.2-3.2)

Fruits & Vegetables Sr-89 14 0.004 0.009 (1/4) 2El 4.5 mi NNE 0.009 (1/2) - (0/10) 0

( pCi I g-wet)

Sr-90 14 0.003 .005 (2/4) lGl 10.2 mi N 0.011 (3/5) .008 (5/10) 0 (0.003-0.007) (0.002-0.021) ( 0. 002-0. 021)

Gamma 15 K-40 0.09 2.3 (4/4) 15Fl 5.4 mi NW 2.5 ( 1/1) 1.4 (11/11) 0 (1. 7-2.9) (0.9-2.2)

Game Sr-89 4 0.08 0.2 (2/2) 4Dl 3.5 mi ENE 0.3 (1/1) .19 (2/2) 0 (pCi I g-dry) (0.1-0.3) (.18-.20)

Bones Sr-90 4 0.05 .43 (2/2) llDl 3.5 mi SW 1.6 (1/1) 0.9 (2/2) 0

( .39- .46) (.25-1.6)

(pCi/g-wet) Gamma 4 flesh K-40 0.09 2.7 (2/2) 3El 4.5 mi NE 2.7 (1/1) 2.3 (2/2) 0 (2.7-2.7) (2;2-2.3)

Beef Gamma (pCi/g-wet) K-40 0.09 1. 7 (1/1) 14Fl 5.5 mi WNW 1. 7 (1/1) No Control 0 Sample Available

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 SALEM COUNTY, NEW JERSEY JANUARY 1, 1978 TO DECEMBER 31,**1978 .

ANALYSIS AND MINIMUM NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER DETECTABLE ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST.MEAN CONTROL LOCATIONS NON ROUTINE SAMPLED OF ANALYSES LEVEL MEAN* NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (MDL) (RANGE) DISTANCE AND DIRECTION . (RANGE) ... (RANGE) MEASUREMENTS Beef Thyroid Gamma 1 (pCi/g-wet) K-40 0.09 0.6 (1/1) 14Fl 5.5 mi WNW 0.6 (1/1) - (0.3) 0 Fodder Crops Gamma 12 N (pCi/g-dry) Be-7 0.3 2.1 (3/9) 14Fl 5.5 mi WNW 4.3 (1/1) 13 (3/3) 0 co (0.8-4.3)

K-40 0.9 12 (9/9) . 2F4 6.3 mi NNE 20 (1/1) 13 (3/3) 0 (4.3-20) (6. 5-20)

Ru-106 0.2 0.4 (1/9) 14Fl 5.5 mi WNW 0.4 (1/1) - (0/3) 0 Sb-125 0.07 0.12 (1/9) 14Fl 5.5 mi WNW 0.12 (1/1) - (0/3) 0 Cs-137 0.02

.08 (2/9) 14Fl 5.5 mi WNW 0.10 (1/1) - (0/3) 0 (0.06-0.10)

Ce-144 0.07 0.7 (1/9) 14Fl 5.5 mi WNW 0.7 (1/1) - (0/3) 0

MDL listed is the lowest calculated MDL during reporting period.

- Mean calculated using values above MDL only. Fraction of measurements above MDL in parentheses.

APPENDIX B SAMPLE DESIGNATION AND LOCATIONS 29

APPENDIX B Sample Designation RMC identifies samples by a three part code. The first two letters 11 are the power station identification code, in this case SA 11

The next one to three letters are for the media sampled.

AIO = Air Iodine GAM = Game APT = Air Particulates IDM = Irrrnersion Dose (TLD)

AQS = Sediment MLK = Milk SOL = Soi 1 PWA = Potable Water; (PWR = raw, ECH = Hard Shell Blue Crab PWT = treated)

ESB = Benthos ESF ~ Edible Fish RWA = Rain Water ESS = Sediment SWA = Surface Water FPB = Beef THB = Bovine Thyroid FPV = Food Products, Various VGT = Fodder Crops WWA =Well Water The last four symbols 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 SAMPLE CODE LOCATION TYPES 2Sl 1575 ft. NNE of vent APT,AIO,IDM 4Sl Site well #5 ENE of Vent WWA 5Sl 1.0 mi. E of vent; site access road IDM ,APT ,AIO 6Sl 0.2 mi. ESE of vent; observation platform IDM,SOL 6S2 0.2 mi. ESE of vent; observation bldg. IDM 7Sl 0.12 mi. SE of vent; station personnel gate IDM lOSl 0.14 mi. SSW of vent; site shoreline IDM 11Sl 0.09 mi. SW of vent; site shoreline IDM llAl 0.2 mi. SW of vent; outfall area SWA,ESF ,ECH, ESB,ESS 12Cl 2.5 mi. WSW of vent; west bank of 'Delaware SWA,ESF ,ECH, river ESB,ESS 5Dl 3.5 mi. E of vent; local farm IDM,VGT,SOL,WWA, APT ,AIO lODl 3.9 mi. SSW of vent; Taylor's Bridge Spur IDM,APT,AIO,SOL 1101 3.5 mi. SW of Vent GAM 1401 3.4 mi. WNW of vent; Bay View, Delaware IDM 2El 4.4 mi. NNE of vent; local farm IDM, FPV ,SOL 3El 4.1 mi. NE of vent; local farm IDM,THB,WWA, GAM,FPB,FPG 32

TABLE B-1 (CONT.)

?El 4.5 mi. SE of vent; 1 mi. Wof Mad Horse SWA,ESF ,ESB, Creek ESS 13El 4.2 mi. Wof vent; Diehl House Lab IDM 13E3 4.9 mi Wof vent; local farm MLK,SOL,VGT 15El 4.1 mi. NW of vent; local farm FPV 16El 4.1 mi. NNW of vent; Port Penn IDM,APT ,AIO,SOL lFl 5.8 mi. N of vent; Fort Elfsborg IDM,APT,SOL 1F2 7.1 mi. N of vent; midpoint of Delaware SWA River 2Fl 5.0 mi. NNE of vent; local farm SOL,VGT,MLK 2F2 8.7 mi. NNE of vent; Salem substation IDM ,APT ,AIO, RWA,SOL 2F3 8.0 mi. NNE_of vent; Salem Water Company PWR,PWT 2F4 6.3 mi NNE of vent; local farm SOL,VGT,MLK 5Fl 8.0 mi. E of vent FPV,IDM,SOL 5F2 7.0 mi. E of vent; local farm MLK,SOL, VGT 6Fl 6.4 mi. ESE of vent; Stow Neck Road 7F2 9.1 mi. SE of vent; Bayside, New Jersey llFl 5.2 mi. SW of vent; Taylor's Bridge, Delaware 13Fl 9.8 mi. Wof vent; Middletown, Delaware IDM 14Fl 5.5 mi. WNW of vent; local farm VGT,MLK,FPB,THB,SOL 15Fl 5.2 mi. NW of vent; local farm VGT,MLK,SOL 16Fl 6.9 mi. NNW of vent; C &D Canal SWA,ESB,ESS lGl 13 mi. N of vent; local farm FPV 1G2 12 mi. .N of vent; local farm FPV 3Gl 17 mi. NE of vent; local farm IDM,VGT,MLK 2Hl 34 mi. NNE of vent; RMC, Phi la. IDM 3Hl 32 mi. NE of vent; National Park, N.J. IDM 3H3 110 mi. NE of vent; Maplewood Laboratories IDM,APT,AIO,SOL 3H4 18 mi. NE of vent; local farm FPV 33

MAP B-1 ON SITE SAMPLING LOCATIONS ARTIFICIAL ISLAND - 1978 0

I i _ L:: I SCALE OF MILES 34

MAP B-2 OFF SITE SAMPLING LOCATIONS ARTIFICIAL ISLAND

/

0 1 2 3 4 H-H I I I I SCA.LI Of Ml LIS 35

APPENDIX C 1978 DATA TABLES 37

DATA TABLES Appendix C presents the analytical results of the 1978 Artificial Island Radiological Environmental Monitoring Program for the period of January 1 to December 31.

TABLE TABLE TITLE PAGE NUMBER C-1 Concentrations of Beta Emitters in Air Particulates 41 C-2 Concentrations of Alpha Emitters in Air Particulates ......... 43 C-3 Concentrations of Gamma Emitters in Quarterly Composites of 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, Alpha and Beta Emitters in P*reci pi ta ti on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 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 Alpha Emitters in Surface Water *** ; ******** 61 C-13 Concentrations of 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, Alpha and Beta Emitters, and Potassium-40 in Well Water *******.********************.****** 65 C-17 Concentrations of Strontium-89 and -90, and Gamma Emitters in Quarterly Composites of Well Water ***..********************** 66 C-18 Concentrations of Tritium, Alpha and Beta Emitters, and Potassium-40 in Raw and Treated Potable Water **************** 67 39

DATA TABLES (cont.)

TABLE TABLE TITLE PAGE NUMBER 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 and Strontium-90 in Sediment *..**.*.*.*.*******************.***** 69 C-21 Concentrations of Gamma Emitters in Sediment **.*****.*.****** 70 C-22 Concentrations of Iodine-131 in Milk *********************.*** 71 C-23 Concentrations of.Garmna Emitters and Strontium-89 and -90 in Mi 1k * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

72 C-24 Sampling Dates for Milk Samples . .*******.******************** 74 C-25 Concentrations of Ganma Emitters in Edible Fish ************** 77 C-26 Concentrations of Strontium-89 and -90, and Tritium in Edible Fish Samples ****.***.*.*.***.*****.****.***.**..*****. 78 C-27 Concentrations of Strontium-89 and -90, and Gamma Emitters in Food Products ............................................ r * *

79 C-28 Concentrations of Strontium-89 and -90, and Gamma Emitters in Meat, Game and Bovine Thyroid *.*..***********..***.*.******** 80 C-29 Concentrations of Ganma Emitters in Fodder Crop Samples ****** 81 C-30 Typical MDLs for Gamma Spectrometry 82 40

TABLE C-1 CONCENTRATIONS OF BETA EMITTERS IN AIR PARTICULATES 3 3 Results in Units of 10- pCi/m +/- 2 sigma STATION NO.

SA-APT-5Sl SA-APT-501 SA-APT-1001 SA-APT-16El SA-APT-lFl SA-AF'T-2F2 SA-APT-3H3 AVERAGE MONTH SA-APT-2Sl 88+/-9 83+/-9 86+/-9 90+/-10 99+/-11 91+/-9 94+/-9 103+/-10 92+/-13 JANUARY* 87+/-10 75+/-16 77+/-8 70+/-8 78+/-8 68+/-7 61+/-8 80+/-9 76+/-8 70+/-8 66+/-8 68+/-8 77+/-8 75+/-9 76+/-8 72+/-8 63+/-8 71+/-10 70+/-8 77+/-8 62+/-7 63+/-8 67+/-9 71+/-8 67+/-8 78+/-9 69+/-12 83+/-8 79+/-8 84+/-8 76+/-8 79+/-8 77+/-8 89+/-9 101+/-10 84+/-16 FEBRUARY 78+/-8 77+/-8 82+/-8 84+/-8 77+/-8 81+/-8 73+/-7 73+/-7 78+/-8 80+/-8 76+/-8 76+/-8 84+/-8 82+/-8 73+/-8 73+/-8 77+/-8 78+/-8 66+/-7 63+/-7 67+/-7 72+/-8 73+/-8 65+/-8 63+/-7 74+/-9 68+/-9

.j:::> 74+/-8 69+/-8 80+/-9 81+/-9 84+/-10 90+/-9 72+/-8 92+/-9 80+/-17 I-'

104+/-10 111+/-11 100+/-10 103+/-10 105+/-11 106+/-11 108+/-11 112+/-11 106+/-8 MARCH 154+/-15 142+/-17 144+/-14 148+/-15 141+/-14 133+/-13 130+/-13 150+/-15 137+/-14 76+/-8 . 74+/-8 71+/-8 85+/-9 99+/-10 75+/-8 77+/-8 75+/-8 79+/-18 958+/-96 1000+/-100 1030+/-100 908+/-91 179+/-36(1) 961+/-96 1030+/-100 742+/-74 851+/-574 APRIL 180+/-18 210+/-21 201+/-20 226+/-23 218+/-22 201+/-20 185+/-19 200+/-20 203+/-31 189+/-19 190+/-19 204+/-20 205+/-21 229+/-23 191+/-19 174+/-17 143+/-14 191+/-50 168+/-17 179+/-18 195+/-20 158+/-16 155+/-15 186+/-19 193+/-19 197+/-20 179+/-33 104+/-10 108+/-11 110+/-11 110+/-11 117+/-12 109+/-11 117+/-12 111+/-11 111+/-9 148+/-15 137+/-14 137+/-14 151+/-15 144+/-14 148+/-15 147+/-15 154+/-15 146+/-12 MAY 86+/-9 73+/-8 69+/-8 46+/-6 66+/-7 68+/-8 76+/-8 97+/-10 73+/-30 112+/-11 107+/-11 107+/-11 122+/-12 112+/-11 110+/-11 88+/-9 70+/-8 104+/-33 70+/-8 69+/-8 71+/-8 79+/-8 77+/-8 93+/-9 67+/-8 51+/-7 72+/-24 65+/-7 54+/-7 66+/-7 46+/-6 51+/-7 70+/-8 52+/-6 80+/-8 61+/-23 JUNE 109+/-11 110+/-11 109+/-11 102+/-10 107::':11 112+/-11 108+/-11 95+/-10 107+/-11 124+/-12 119+/-12 119+/-12 121+/-12 129+/-13 138+/-14 111+/-11 142+/-14 125+/-21 175+/-18 156+/-16 182+/-18 206+/-24 160+/-16 206+/-21 152+/-15 162+/-16 175+/-43 150+/-15 148+/-15 135+/-14 162+/-16 151+/-15 155+/-15 150+/-15 152+/-15 150+/-15 135+/-14 123+/-12 130+/-13 127+/-13 125+/-13 134+/-13 129+/-13 141+/-14 131+/-12

TABLE C-1 (cont.)

CONCENTRATIONS OF BETA EMITTERS IN AIR PARTICULATES Results in un'its 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 JULY 112+/-11 130+/-13 123+/-12 106+/-11 125+/-13 126+/-13 114+/-11 ** 119+/-18 104+/-10 86+/-9 93+/-9 85+/-9 98+/-10 89+/-9 81+/-8 97+/-10 92+/-15 99+/-10 89+/-9 95+/-10 83+/-8 87+/-9 79+/-8 85+/-9 111+/-11 .91+/-21 61+/-7 68+/-8 66+/-8 64+/-8 75+/-9 66+/-8 74+/-8 59+/-8 67+/-11 AUGUST 31+/-6 29+/-6 32+/-6 <61(l) 27+/-5 25+/-6 26+/-5 36+/-6 33+/-23 40+/-6 38+/-6 33+/-6 23+/-5 28+/-6 30+/-6 29+/-5 44+/-6 33+/-14 42+/-7 43+/-6 42+/-6 49+/-8 54+/-8 43+/-7 45+/-6 47-H 46+/-8 66+/-7 65+/-7 53+/-7 52+/-7 57+/-7 62+/-7 59+/-7 56+/-7 59+/-10 SEPTEMBER 49+/-6 47+/-6 44+/-6 41+/-6 46+/-6 43+/-6 43+/-5 51+/-6 46+/-7 56+/-8 50+/-7 53+/-7 56+/-7 60+/-7 50+/-7 46+/-7 45+/-7 52+/-10 47+/-6 37+/-6 43+/-6 41+/-7 39+/-6 44+/-6 39+/-6 41+/-6 41+/-6 40+/-6 34+/-6 36+/-6 34+/-5 34+/-5 42+/-6 43+/-7 37+/-6 38+/-7

..j::>. 30+/-5 33+/-6 27+/-5 29+/-6 35+/-6 37+/-6 30+/-5 33+/-6 32+/-7 N

OCTOBER 23+/-5 24+/-5 19+/-5 20+/-4 21+/-5 23+/-5 25+/-5. 22+/-5 22+/-4 31+/-6 29+/-6 31+/-6 22+/-6 27+/-7 31+/-6 34+/-6 38+/-7 30+/-9 40+/-6 33+/-6 37+/-6 31+/-5 34+/-6 32+/-6 36+/-6 34+/-6 35+/-6 33+/-5 35+/-6 34+/-6 31+/-5 32+/-6 37+/-6 32+/-5 35+/-6 34+/-4 NOVEMBER 47+/-6 41+/-6 42+/-6 40+/-6 47+/-7 47+/-7 53+/-7 55+/-7 47+/-11 45+/-6 45+/-6 40+/-6 38+/-5 40+/-5 36+/-6 41+/-6 44+/-6 41+/-7 40+/-6 41+/-6 41+/-6

41+/-6 39+/-6 41+/-6 36+/-6 40+/-4 28+/-5 27+/-5 29+/-5 24+/-5 27+/-5 28+/-5 30+/-5 29+/-6 28+/-4 DECEMBER ~4+/-6 31+/-6 33+/-6 34+/-6 35+/-6 30+/-6 34+/-6 35+/-6 33+/-4 4+/-6 36+/-6 42+/-6 39+/-6 47+/-7 40+/-6 36+/-6 49+/-7 42+/-10 32+/-6 31+/-5 35+/-6 36+/-6 33+/-6 40+/-6 33+/-6 32+/-6 34+/-6 4~+/-6 46+/-6 40+/-6 52+/-7 47+/-6 45+/-6 39+/-6 33+/-6 44+/-12 42+/-6 42+/-6 42+/-6 37+/-6 35+/-6 40+/-6 43+/-6 33+/-6 39+/-8 AVERAGE 95+/-257 94+/-270 96+/-278 94+/-250 81+/-99 97+/-261 94+/-276 92+/-206 93+/-242

~

Sampling dates can be found on Table C-6.

L _ ** No sample was received, due to sampler malfunction.

Pump working only one day.

(1)

TABLE C-2 CONCENTRATIONS OF ALPHA EMITTERS IN AIR PARTICULATES Results in Units of 10~ 3 pCi/m3 +/- 2 sigma STATION NO~ JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-APT-16El 1.1+/-0. 7 0.9+/-0.6 <0.7 0.9+/-0.7 <0.4 <0.5

<0.4 0.8+/-0.6 <0.8 0.7+/-0.5 <0.3 0.8+/-0.5 0.9+/-0 .8 <0.5 <0.5 <0.8 0.5+/-0.5 0.9+/-0.5 0.5+/-0.5 <1.6 3.8+/-3.4 0.5+/-0.4 0.4+/-0.3 <0.4 0.7+/-0.6 0.8+/-0.8 0.7+/-0.5 SA-APT-3H3 2.1+/-0.8 1.1+/-0.6 <0.7 0.8+/-0.6 0.7+/-0.6 0.9+/-0.7 2.6+/-0.9 <0.4 1.2+/-1.0 <0.4 0.9+/-0.5 1.1+/-0.6

<0.6 1.0+/-0.7 <0.5 <0.7 0.5+/-0.5 0.7+/-0.5 1.4+/-0.6 <1.3 1.3+/-0.6 0.9+/-0.5 1.0+/-0.5 0.7+/-0.6 1.2+/-0 .8 1. 0+/-0 .8 <0.5

..i:::.

w STATIJN NO. JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE SA-APT-16El <0.4 0.7+/-0.6 0.9+/-0.6 0.7+/-0.4 1.4+/-0.7 <0.6

<0.4 0.7+/-0.5 1.5+/-0.7 1.0+/-0.8 1.3+/-0.6 1.3+/-0.7 1.1+/-0.6 <0.6 0.5+/-0.5 0.8+/-0.6 1~0+/-0.7 0.9+/-0.6

<0.4 0.8+/-0.6 0.7+/-0.5 0.6+/-0.6 <0.5 <0.8 0.9+/-0.5 <0.5 0.8+/-1.0 SA-APT-3H3 ** 0.7+/-0.7 0.7+/-0.6 0.5+/-0.4 2.2+/-0.9 <0.6

<0.4 <0.4 1. 2+/-0.6 0.7+/-0.7 2.8+/-0.9 2.0+/-0.8 0.8+/-0.5 0.9+/-0.7 1.2+/-0.6 1.5+/-0.7 <0.5 1. 5+/-0. 7 0.7+/-0.6 <0.4 0.7+/-0.5 1.2+/-0.8 <0.5 <0.8 0.7+/-0.5 0.8+/-0.7 1.0+/-1.1

Sampling dates can be found on Table C-6.

- No sample received due to sampler malfunction.

TABLE C-3 CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES Results in Units of 10- 3 pCi/m 3 +/- 2 sigma STATION NUMBER AND DATE SA-APT-2Sl 12-27-77 3-27-78 7-03-78 10-02-78 to to to to NUCLIDES* 3-27-78 7-03-78 10-02-78 1-02-79 Be-7 63+/-6 78+/-8 68+/-7 72+/-7 Mn-54 <0.2 <0.3 0.3+/-0.3 <0.2 Zr-95 2.2+/-0.4 1. 9+/-0. 7 <0.4 <0.3 Nb-95 3.8+/-0.4 2.9+/-0.4 <0.3 <0.2 Ru-103 4.9+/-0.5 0.7+/-0.3 <0.2 <0.2 Ru-106 12+/-3 17+/-4 7.2+/-2.6 <2.0 Sb-125 1.5+/-0.5 2.6+/-0.8 1.1+/-0. 5 <0.6 I-131 11+/-1** <0.2 <0.2 <0.2 I-132 0.3+/-0.1**

Te-132 0.4+/-0.2 <0.2 <0.2 <0.2 Cs-137 2.9+/-0.4 6.5+/-0.7 2.9+/-0.5 1.3+/-0.3 BaLa-140 5.3+/-0.6 <0.4 <0.3 0.6+/-0.5 Ce-141 3.5+/-0.4 <0.3 <0.2 0.5+/-0.4 Ce-144 25+/-3 35+/-4 11+/-1 4.2+/-1.8 STATION NUMBER AND DATE SA-APT-5Sl 12-27-77 3-27-78 7-03-78 10-02-78 to to to to to NUCLIDES* 3-27-78 7-03-78 10-02-78 1-02-79 Be-7 69+/-7 66+/-7 66+/-7 67+/-7 Mn-54 <0.3 <0.3 <0.2 <0.3 Zr-95 3.0+/-0.6 1.0+/-0.4 <0.4 <0.5 Nb-95 4.9+/-0.6 2.9+/-0.4 <0.3 <0.2 Ru-103 6.2+/-0.7 0.7+/-0.3 <0.2 0.3+/-0.3 Ru-106 14+/-4 17+/-3 5.7+/-2.9 <3.0 Sb-125 <1.0 2.4+/-0.6 1. 2+/-0.8 0.9+/-0.6 I-131 16+/-2** <0.2 <0.2 0.9+/-0.6**

I-132 0.8+/-0.4**

Te-132 0.4+/-0.3 <0.2 <0.2 <0.2 Cs-137 3.7+/-0.7 5.3+/-0.5 2.9+/-0.5 1.3+/-0.6 BaLa-140 8.4+/-0.9 <0.4 <0.4 <0.5 Ce-141 5.7+/-0.6 0.81+/-0.08 <0.3 <0.3 Ce-144 33+/-3 32+/-3 17+/-3 4.1+/-1.3 44

TABLE C-3 (cont.)

CONCENTRATIONS OF GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES Results. i~ Units of 10- 3 pCi/m3 +/- 2 sigma STATION NUMBER AND DATE SA-APT-5Dl 12-27-77 3-27-78 7-03-78 10-02-78 to to to to NUCLIDES* 3-27-78 7-03-78 10-02-78 1-02-79 Be-7 56+/-6 63+/-6 50+/-5 75+/-8 Mn-54 <0.2 0.3+/-0.2 <0.2 <0.3 Zr-95 1. 9+/-0.4 1.3+/-0. 5 <0.4 <0.4 Nb-95 4.0+/-0.4 2.6+/-0.4 0.6+/-0.3 <0.3 Ru-103 3.6+/-0.4 0.9+/-0.3 <0.2 <0.3 Ru-106 13+/-3 16+/-3 7.2+/-2.3 <3.0 Sb-125 1.5+/-0.7 2.9+/-0.7 1. 2+/-0.5 <0.8 I-131 10+/-1** <0.2 <0.2 <0.3 I-132 0.3+/-0.1**

Te-132 <0.2 <0.2 <0.1 <0.2 Cs-137 2.9+/-0.4 5.5+/-0.6 2.2+/-0.4 1.0+/-0.4 BaLa-140 5.4+/-0.6 <0.4 <0.4 0.6+/-0.5 Ce-141 3.5+/-0.5 0.5+/-0.5 <0.2 0.7+/-0.4 Ce-144 31+/-3 35+/-4 12+/-1 5.0+/-1.3 STATION NUMBER AND DATE SA-APT-lODl 12-28-77 3-28-78 7-03-78 10-02-78 to to to to NUCLIDES* 3-28-78 7-03-78 10-02-78 1-02-79 Be-7 52+/-5 59+/-6 59+/-6 59+/-6 Mn-54 <0.3 0.4+/-0.3 <0.2 <0.3 Zr-95 2.7+/-0.5 1. 3+/-0. 6 <0.4 <0.6 Nb-95 3.8+/-0.4 2.3+/-0.4 <0.3 <0.3 Ru-103 4.5+/-0.5 0.7+/-0.3 <0.2 <0.3 Ru-106 11+/-2 16+/-3 10+/-4 <3.0 Sb-125 1.8+/-0.6 3.2+/-0.8 <0.8 <0.8 I-131 12+/-1** <0.2 <0.2 <0.3 Te-132 <0.2 <0.2 <0.2 <0.3 Cs-137 3.0+/-0.4 7.7+/-0.8 2.9+/-0.6 0.9+/-0.5 Bala-140 5.8+/-0.6 <0.4 <0.4 <0.6 Ce-141 4.1+/-0.4 <0.3 <0.3 <0.5 Ce-144 23+/-2 30+/-3 15+/-3 3.8+/-3.0 45

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 12-28-77 3-28-78 7-03-78 10-02-78 to to to to NUCLIDES* 3-21-78 7-03-78 10-02-78 1-02-79 Be-7 63+/-6 68+/-7 51+/-5 62+/-6 Mn-54 <0.4 <0.3 <0.2 <0.2 Zr-95 1. 7+/-0.6 0.8+/-0.4 <0.4 <0.5 Nb-95 3.5+/-0.6 2.6+/-0.4 0.4+/-0.3 <0.3 Ru-103 <0.3 0.5+/-0.3 <0.2 0.4+/-0.4 Ru-106 12+/-4 19+/-3 7.9+/-2.4 <3.0 Sb-125 2.8+/-1. l 3.2+/-0.9 1. 0+/-0. 5 0.8+/-0.8 I-131 <0.3 <0.2 <0.2 <0.3 Te-132 <0.3 <0.2 <0.1 <0.2 Cs-137 3.2+/-0.6 5.1+/-0.5 2.0+/-0.4 1.3+/-0.4 BaLa-140 <0.6 <0.4 <0.4 0.5+/-0.5 Ce-141 <0.5 0.43+/-0.07 <0.2 0.5+/-0.4 Ce-144 26+/-3 34+/-3 12+/-1 3.5+/-1.4 STATION NUMBER AND DATE SA-APT-lFl 12-27-77 3-27-78 7-03-78 10-02-78 to to to to NUCLIDES* 3-27-78 7-03-78 10-02-78 1-02-79 Be-7 57+/-6 65+/-7 57+/-6 65+/-7 Mn-54 <0.3 0.4+/-0.3 <0.3 <0.3 Zr-95 2.5+/-0.4 1.4+/-0.5 <0.5 <0.5 Nb-95 3.7+/-0.4 2.3+/-0.4 0.5+/-0.3 0.6+/-0.4 Ru-103 4.4+/-0.4 0.5+/-0.3 <0.2 <0.3 Ru-106 13+/-3 17+/-3 7.7+/-2.8 5.5+/-3.7 Sb-125 2.1+/-0.6 2.5+/-0.6 1.5+/-0.5 <0.9 I-131 13+/-1** <0.2 <0.2 <0.3 Te-132 <0.2 <0.1 <0.2 <0.3 Cs-137 3.0+/-0.5 4.3+/-0.4 2.3+/-0.4 1.6+/-p.5 BaLa-140 6.1+/-0.6 <0.4 <0.4 <0.6 Ce-141 4.2+/-0.4 0.3+/-0.3 <0.2 0.9+/-0.7 Ce-144 23+/-2 26+/-3 13+/-1 3.1+/-2.6 46

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 12-27-77 3-27-78 7-03-78 10-02-78 to to to to NUCLIDES* 3-27-78 7-03~78 10-02-78 1-02-79 Be-7 67+/-7 62+/-6 55+/-6 82+/-8 Mn-54 <0.3 0.4+/-0.3 <0.2 <0.2 Zr-95 2.8+/-0.6 0.9+/-0.4 <0.4 <0.4 Nb-95 5.0+/-0.7 2.2+/-0.4 <0.2 <0.2 Ru-103 6.3+/-0.6 0.6+/-0.3 <0.2 0.3+/-0.3 Ru-106 12+/-4 16+/-3 7.7+/-3.0 3.9+/-2.5 Sb-125 1. 9+/-1. 2 3.2+/-0.8 <0.7 1.3+/-1.1 I-131 14+/-2** <0.2 <0.2 <0.3 I-132 0.4+/-0.2**

Te-132 0.6+/-0.5 <0.2 <0.2 <0.2 Cs-137 4.0+/-0. 7 5.0+/-0.5 2.2+/-0.5 1,.1+/-0.3 Bala-140 6.9+/-1.0 <0.4 <0.4 *o.7+/-0.5 Ce-141 4.5+/-0.6 0.3+/-0.2 <0.3 0.5+/-0.5 Ce-144 30+/-3 31+/-3 13+/-2 3.9+/-1.7 STATION NUMBER AND DATE SA-APT-3H3 12-27-77 3-27-78 7-10-78 10-02-78 to to to to NUCLIDES* 3-27-78 7-03-78 10-02-78 1-02-79 Be-7 69+/-7 63+/-6 50+/-5 78+/-8 Mn-54 <0.4 0.5+/-0.3 <0.2 <0.4 Zr-95 2.3+/-0.6 1.8+/-0.8 <0.4 <0.6 Nb-95 4.3+/-0.6 2.4+/-0.4 0.6+/-0.4 <0.4 Ru-103 4.0+/-0.5 0.9+/-0.5 <0.2 <0.3 Ru-106 13+/-4 19+/-3 <4.0 <3.0 Sb-125 1. 7+/-0. 9 2.9+/-0.8 <0.8 <1.0 I-131 8.8+/-1.9** <0.2 <0.2 <1.0**

I-132 <0.3**

Te-132 <0.3 <0.2 <0.2 <0.3 Cs-137 3.3+/-0.6 5.5+/-0.6 2.0+0.5 0.9+/-0.5 Bala-140 4.9+/-1.0 <0.4 <0.5 <0.6 Ce-141 2. 7+/-0.6 <0.3 <0.4 <0.5 Ce-144 32+/-3 34+/-3 12+/-3 10+/-5

All other ganvna emitters searched for were <MDL; typical MDLs are given in table C-30.

Those nuclides not searched for are indicated by a dash (_-}.

- Results decay corrected to sample stop date.

47

TABLE C-4 CONCENTRATIONS OF STRONTIUM-89* AND -90 IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES 3

Results in Units of 10- 3 pCi/m +/- 2 sigma JAN to MAR APR to JUN JUL to SEP OCT to DEC STATION NO. Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 5r-89 5r-90 SA-APT-251 4.2+/-0.7 2.0+/-0.4 1.1+/-0.4 1. 7+/-0.2 <0.7 0.8+/-0.2 <0.6 *o.3+/-0.2 5A-APT-551 5.0+/-0.6 1. 2+/-0 .3 1.4+/-0.6 3. 2+/-.0 .4 <1.1 1.4+/-0.3 <0.6 0.5+/-0.2

.+::>

co SA-APT-501 3.7+/-0.9 1.8+/-0.5 1.2+/-0.5 2.7+/-0.3 <1.1 1.5+/-0.3 0.6+/-0.3 0.2+/-0.2 5A-APT-1001 4.6+/-0.8 1.3+/-0.4 1. 8+/-0. 6 2.2+/-0.3 <i.2 1.4+/-0.3 <0.6 0.4+/-0.2 5A-APT-16El <1.6 1.8+/-0.5 1.1+/-0.6 2.8+/-0.3 <1.3 1.1+/-0.3 0.4+/-0.3 0.3+/-0.2 5A-APT-1Fl 2.6+/-0.7 2.1+/-0.4 1.1+/-0.5 2.8+/-0.3 <1.0 1.3+/-0.3 <0.5 0.4+/-0.2 SA-APT-2F2 4.2+/-0.8 2.0+/-0.4 2.2+/-0.6 2.2+/-0.3 <1.2 1. 4+/-0 .3 <0.5 0.4+/-0.2 SA-APT-3H3 3.7+/-0.7 1.4+/-0.4 1.5+/-0.6 2.4+/-0.3 <1.4 1. 3+/-0. 3 0.5+/-0.4 0.2+/-0.2

5r-89 results are decay corrected to sample stop date.

TABLE C-5 CONCENTRATIONS OF IODINE-131 IN FILTERED AIR Results* in Units of 10-3 pCi/m 3 MONTH SA-AI0-2Sl SA-AI0-5Sl SA-AI0-501 SA-AI0-1001 SA-AI0-16E1 SA-AI0-2F2 SA-AI0-3H3 JANUARY** <5.4 <5.7 <5.7 <6.2 <6.9 <6.3 <6.6

<6.3 <6.5 <6.2 <5.0 <5.9 <6.5 <7.7

<5.3 <5.4 <5.4 <5.2 <6.0 <6.0 <6.6

<5.0 <5.3 <4.9 <5.5 <6.2 <5.3 <5.7

<4.9 <4.7 <4.4 <5.0 <5.9 <5.3 <6.8 FEBRUARY <3.8 <3.9 <3.7 <4.0 <4.5 <3.7 <4.8

<6.0 <5.9 <6.0 <5.0 <5.6 <6.7 <7.1

<4.7 <5.1 <4.7 <4.4 <4.8 <5.2 <5.7

<5.1 <5.6 <5.3 <5.6 <7.0 <5.2 <6.5

+::>

c..o MARCH <4.8 <5.2 <5.1 <4.4 <5.5 <5.2 <5.7

<4.9 <4.9 <5.4 <4.2 <4.5 <5.5 15+/-8

<4.8 <5.1 <5.4 <5.7 <5.9 <5.4 <5.5 45+/-8 45+/-8 46+/-8 49+/-7 <58(1) 51+/-9 37+/-8 APRIL <4.8 8.4+/-6.4 <5.0 <5.1 11+/-8 <4.9 9.8+/-6.8

<6.3 <5.4 <5.8 <4.0 <4.9 <5.6 <6.2

<5.5 <5.3 <4.7 <5.3 <6.4 <4.9 <6.0

<4.8 <4.8 <5.6 <4.0 <4.7 <5.6 <5.8

<5.5 <5.8 <5.6 <6.0 <6.8 <5.6 <6.2 MAY <5.2 <4.9 <6.1 <4.2 <4.8 <5.6 <5.5

<5.3 <4.8 <5.2 <5.5 <6.3 <7.2 <5.4

<5.5 <5.1 <5.7 <4.4 <5.3 <5.8 <5.9

<4.2 <4.0 <4.4 <4.9 <5.1 <4.3 <4.6 JUNE <5.4 <5.3 <5.2 <6.1 <6.3 <5.1 <6.4

<5.8 <5.9 <6.2 <4.7 <4.5 <5.0 <5. 7

<5.5 <5.2 <6.4 <28* <5.7 <6.1 <5.8

<4.9 <4.6 <5.3 <6.0 <6.3 <4.9 <5.6

<7.5 <7.4 <8.5 <8.2 <7.4 <6.6 <7.8

TABLE C-5 (cont.)

CONCENTRATIONS OF IODINE-131 IN FILTERED AIR 3

Results* in Units of 10-3 pCi/m MONTH SA-AI0-2Sl SA-AI0-5Sl SA-AI0-501 SA-AI0-1001 SA-AI0-16El SA-AI0-2F2 SA-AI0-3H3 JULY <5.6 <6.6 <6.3 <5.1 <5.5 <5.0 (2)

<5.0 <4.6 <5.9 <4.7 <5.4 <6.0 <5.4

<4.4 <5.4 <4.9 <5.0 <5.0 <5.1 <5.9

<5.5 <5.2 <6.1 <6.1 <6.8 <5.9 <6.2 AUGUST <5.7 <5.6 <6.3 <211(1) <4.9 <5.8 <5.8

<5.7 <5.2 <6.2 <5.4 <5.3 <5.0 <5.9

<5.4 <4.9 <5.7 <6.4 <6.6 <5.3 <6.0

<5.5 <5.2 <6.0 <5.6 <5.5 <5.0 <5.9 SEPTEMBER <4.8 <4.7 <5.2 <5.3 <5.1 <4.0 <5.5

<6.1 <5.6 <6.7 <5.2 <5.4 <6.7 <6.6

<5.4 <5.1 <5.7 <6.3 <6.1 <2.0 <5.7 CJ1 <5.2 <5.7 <6.0 <4.6 <4.6 <5.5 <5.8 0

<4.7 <4.7 <5.2 <5.9 <5.6 <4.3 <5.3 OCTOBER <4.7 <4.4 <5.2 <4.2 <4.3 <5.1 <5.3

<6.0 <5.5 <6.4 <7.1 <7.4 <6.3 <6.9

<4.5 <5.5 <5.2 <5.2 <5.3 <5.4 <5.9

<5.1 <4.9 <6.1 <6.2 <5.8 <4.8 <6.8 NOVEMBER <5.1 <5.1 <6.0 <5.5 <5.8 <4.8 <5.8

<4.2 <5.1 <4.6 <4.3 <5.4 <5.0 <6.0

<5.4 <5.3 <5.6 (2) <5.1 <5.0 <5.9

<3.8 <4.7 <4.7 <5.0 <4.5 <4.2 <5.3 DECEMBER <5.8 <4.8 <5.2 <5.1 <4.6 <5.1 <5.7

<4.3 <5.0 <4.8 <5.3 <5.4 <5.4 <5.7

<5.2 <4.7 <5.6 <5.2 <5.4 <6.3 <5~5

<4.3 <3.8 <4.6 <4.4 <4.3 <4.5 <4.9

<5.2 <4.7 <5.3 <6.1 <6.8 <5.0 <7.0

I-131 results are decay corrected to sample stop date.

- Actual sampling dates* can be found on Table C-6.

(1) High MDL due to low sample volume.

(2) No sample was received, due to sampler malfunction.

TABLE C-6 SAMPLING DATES FOR AIR SAMPLES STATION NO.

MONTH 2Sl 5Sl 501 1001 16El lFl 2F2 3H3 JANUARY 12-27-77 12-27-77 12-27-77 12-28-77 12-28-77 12-27-77 12-27-77 12-27-77 to to to to to to to to 1-03-78 1-03-78 1-03-78 1-03-78 1-03-78 1-03-78 1-03-78 1-03-78 1-03-78 1-03-78 1 78 1-03-78 1-03-73 1-03-73 1-03-73 1-03-78 to to to to to to to to 1-09-78 1-09-78 l-09-7il 1-10-78 1-10-78 1 78 1-09-78 1-09-78 1 78 1-09-78 1-09-78 1-10-78 1-10-78 1 78 1-09-78 1-09-78 to to to to to to to to 1 78 1 78 l-16-7il 1-17-78 1-17-7il 1-16-78 1 78 1-16-78 1 78 1 78 1-16-78 1-17-78 1-17-78 1-16-78 1-16-78 1-16-78 to to to to to to to to 1-23-78 1-23-78 1-23-78 1-23-78 1-23-78 1-23-78 1-23-78 1-23-78 1 78 1-23-78 1-23-78 1-23-78 1-23-78 1-23-78 1-23-78 1-23-78 to to to to to to to to U1 1-30-78 1-30-78 1-30-78 1-30-78 1-30-78 1-30-78 1-30-78 1-30-78 FEBRUARY 1-30-78 1-30-78 1-30-78 1-30-78 1-30-7il 1 78 1-30-78 1-30-78 to to to to to to to to 2-08-78 2-08-78 2-08-78 2-08-78 2-08-78 2-08-78 2-08-78 2-08-78 2-08-78 2-08-78 2-08-78 2-08-78 2-03-78 2-03-78 2-08-78 2-08-78 to to to to to to to to 2-14-78 2-14-78 2-14-78 2-15-78 2 78 2-14-78 2 78 2-14-78 2-14-78 2-14-78 2-14-78 2-15-78 2-15-73 2-14-78 2 78 2-14-78 to to to to to to to to 2-21-78 2-21-78 2-21-78 2-22-78 2-22-78 2-21-78 2-21-78 2-21-78 2-21-78 2-21-78 2-21-78 2-22-78 2-22-78 2-21-78 2-21-78 2-21-78 to to to to to to to to 2-27-78 2-27-78 2-27-78 2-27-78 2-27-78 2-27-73 2-27-78 2-27-78 MARCH 2-27-78 2-27-78 2-27-78 2-27-78 2-27-78 2-27-78 2~27-78 2-27-78 to to to to to to to to 3-06-73 3-06-78 3-06-78 3-06-78 3-06-78 3-06-78 3-06-78 3-06-78 3-06-78 3-06-78 3-06-78 3-06-78 3-06-78 3-06-78 3-06-78 3-06-78 to to to to to to to to 3-13-78 3-13-78 3-13-78 3 78 3-14-78 3-13-78 3-13-78 3-13-78 3-13-78 3-13-78 3-13-78 3-14-78 3-14-78 3-13-78 3-13-78 3-13-78 to to to to to to to to 3-20-78 3-20-78 3-20-78 3-20-78 3-20-78 3-20-78 3-20-78 3-20-78

TABLE C-6 (cont.)

SAMPLING DATES FOR AIR SAMPLES STATION NO.

MONTH 2Sl 5Sl 501 1001 16El lFl 2F2 3H3 MARCH 3-20-78 3-20-78 3-20-78 3-20-78 3-20-73 3-20-78 3-20-78 3-20-78 to to to to to to to to 3-27-78 3-27-78 3-27-78 3-28-78 3-21-78 3-27-78 3-27-78 3-27-78 APRIL 3-27-78 3-27-78 3-27-78 3-28-78 3-28-78 3-27-78 3 78 3-27-78 to to to to to to to to 4-03-78 4-03-78 4-03-78 4-03-78 4-03-78 4-03-78 4-03-78 4-03-78 4-03-78 4-03-78 4-03-78 4-03-78 4-03-78 4 78 4-03-78 4-03-78 to to to to to to to to 4-10-78 4-10-78 4-10-78 4-11-78 4-11-78 4 78 4-10-78 4-10-78 4-10-78 4-10-78 4-10-78 4-11-78 4-11-78 4 78 4-10-78 4 78 to to to to to to to to 4-17-78 4-17-78 4-17-78 4-17-78 4-17-78 4-17-78 4-17-78 4-17-78 4-17-78 4-17-78 4-17-78 4-17-78 4-17-78 4-17-78 4-17-78 4-17-78 U1 to to to to to to to to N 4-24-78 4-24-78 4-24-78 4-25-78 4-25-78 4-24-78 4-24-78 4-24-78 4-24-78 4-24-78 4-24-78 4-25-78 4-25-78 4-24-78 4-24-78 4-24-78 to to to to to to to to 5-01-78 5-01-73 5-01-78 5-01-78 5-01-78 5 78 5-01-78 5-01-78 MAY 5-01-78 5-01-78 5-01-78 5-01-78 5-01-78 5-01-78 5-01-78 5-01-78 to to to to to to to to 5-08-78 5-08-78 5-08-78 5-09-78 5-09-78 5-08-78 5-08-78 5-08-78 5-08-78 5-08-78 5-08-78 5 78 5-09-73 5-08-78 5-08-78 5-08-78 to to to to to to to to 5-15-78 5-15-78 5-15-78 5-15-78 5-15-78 5,-15-78 5-14-78 5-15-78 5 78 5-15-78 5-15-78 5-15-78 5 73 5 78 5 78 5-15-78 to to to to to to to to 5-22-78 5-22-78 5-22-78 5-23-78 5-23-78 5-22-78 5 78 5-22-78 5-22-78 5-22-78 5-22-78 5-23-78 5-23-78 5-22-78 5-22-78 5-22-78 to to to to to to to to 5-30-78 5-30-78 5-30-78

..../

5-30-78 5 78 5-28-78 5-30-78 5-30-78 JUNE 5-30-78 5-30-78 5-30-78 5-30-78 5-30-78 5 78 5-30-78 5-30-78 to to to to to to to to 6-06-78 6-06-78 6-06-78 6-05-78 6-05-78 6-06-78 6-06-78 6-05-78 6-06-78 6-06-78 6-06-78 6-05-78 6-05-78 6-06-78 6-06-78 6-05-78 to to to to to to to to 6-12-78 6-12-78 6-12-78 6-13-78 6-13-78 6-12-78 6-12-78 6-12-78

TABLE C-6 (cont.)

SAMPLING DATES FOR AIR SAMPLES STATION NO.

MONTH 2Sl 5Sl 501 1001 16El lFl 2F2 3H3 JUNE 6-12-78 6-12-78 6-12-78 6-13-78 6 78 6-12-78 6-12-78 6 78 to to to to to to to to 6-19-78 6-19-78 6-19-78 6-15-78 6-20-78 6-19-78 6-19-78 6-19-78 6 78 6-19-78 6 78 6-20-78 6-20-78 6-19-78 6-19-78 6-19-78 to to to to to to to to 6-26-78 6-26-78 6-26-78 6-26-78 6-26-78 6-26-78 6-2G-78 6-26-78 6-26-78 6-26-78 6-26-78 6-26-78 6-26-78 6-26-78 6-26-78 6-26-78 to to to to to to to to 7-03-78 7-03-78 7-03-78 7-03-78 7-03-78 7-03-78 7-03-78 7-03-78 JULY 7-03-78 7-03-78 7-03-78 7-03-78 7-03-78 7-03-78 7-03-78 to to to to to to to

7-10-78 7-10-78 7-10-78 7-11-78 7-11-78 7-10-78 7-10-78 7-10-78 7-10-73 7-10-78 7-11-78 7-11-78 7-10-78 7-10-73 7-10-78

()1 to to to to to to to to w 7-17-78 7-17-78 7-17-78 7-18-78 7-18-78 7-17-78 7-17-78 7-17-78 7-17-78 7-17-78 7-17-78 7 78 7-18-78 7-17-78 7-17-78 7-17-78 to to to to to to to to 7-24-78 7-24-78 7-24-78 7 78 7-25-78 7 78 7-24-78 7-24-78 7-24-78 7-24-78 7-24-78 7-25-78 7-25-78 7-24-78 7-24-78 7-24-78 to to to to to to to to 7-31-78 7-31-78 7-31-78 7-31-78 7 78 7 78 7-31-78 7-31-78 AUGUST 7-31-78 7-31-78 7-31-78 7-31-78 7-31-78 7-31-78 7-31-78 7-31-78 to to to to to to to to 8-07-78 8-07-78 8-07-78 7-31-78 8-08-78 8-07-78 8-07-78 8-07-78 8-07-78 8-07-78 d-07-78 8-08-78 8-08-78 8-07-78 8-07-78 8-07-78 to to to to to to to to 8-14-78 8-14-78 8-14-78 8-15-78 8 78 8 78 8 78 8-14-78 8-14-78 8-14-78 8-14-78 8-15-78 8-15-78 8-14-78 8 78 8 78 to to to to to to to to 8-21-78 8-21-7 8 8-21-78 8-21-78 8 78 8-21-78 8-21-78 8-21-78 8-21-78 8-21-73 8-21-78 8-21-78 8-21-78 8-21-78 8-21-78 8-21-78 to to to to to to to to 8-28-78 8-28-78 d-28-78 8-28-78 8-28-78 8-28-78 8-28-78 8-28-78 SEPTEMBER 8-28-78 8-28-78 8-28-78 8-28-78 8-28-78 8-28-78 8-28-78 8-28-78 to to to to to to to to 9-05-78 9-05-78 9-05-78 9-05-78 9-05-78 9-05-78 9 78 9-05-78

TABLE C-6 (cont.)

SAMPLING DATES FOR AIR SAMPLES MONTH 2Sl 5Sl 501 1001 16El lFl 2F2 3H3 SEPTEMBER 9-05-78 9-05-78 9-05-78 9-05-78 9-05-78 9-05-78 9-05-78 9-05-78 to to to to to to to to 9-11-78 9-11-78 9-11-78 9-12-78 9-12-78 9-11-78 9-11-78 9-11-78 9-11-78 9-11-78 9-11-78 9-12-78 9-12-78 9-11-78 9-11-78 9-11-78 to to to to to to to to 9-18-78 9-18-78 9-18-78 9-18-78 9-18-78 9-18-78 9-18-78 9-18r78 9-18-78 9-18-78 9-18-78 9-18-78 9-18-78 9-18-78 9-18-78 9-18-78 to to to to to to to to 9-25-78 9-25-78 9-25-78 9-26-78 9-26-78 9-25-78 9-25-78 9-25-78 9-25-78 9-25-78 9-25-78 9-26-78 9-26-78 9-25-78 9-25-78 9-25-78 to to to to to to to to 10-02-78 10-02-78 10-02-78 10-02-78 10-02-78 10-02-78 10-02-78 10-02-78 OCTOBER 10-02-78 10-02-78 10-02-78 10-02-78 10-02-78 10-02-78 10-02-78 10-02-78 to to to to to to to to U'1 10-10-78 10-10-78 10-10-78 10-11-78 10-11-78 10-10-78 10-10-78 10-10-78

~

10-10-78 10-10-78 10-10-78 10-11-78 10-11-78 10-10-78 10-10-78 10-10-78 to to' to to to to to to 10-16-78 10-16-78 10-16-78 10-16-78 10-16-78 10-16-78 10-16-78 10 78 10-16-78 10-16-78 10-16-78 10-16-78 10-16-78 10-16-78 10-16-78 10-16-78 to to to to to to to to 10-23-78 10-23-78 10-23-78 10-23-78 10-23-78 10-23-78 10-23-78 10-23-78 10-23-78 10-23-78 10-23-78 10-23-78 10-23-78 10-23-78 10-23-78 10-23-78 to to to to to to to to 10-30-78 10-30-78 10-30-78 10-30-78 10-30-78 10-30-78 10-30-78 10-30-78 NOVEMBER 10-30-78 10-30-78 10-30-78 10-30-78 10-30-78 10-30-78 10-30-78 10-30-78 to to to to to to to to 11-06-78 11-06-78 11-06-78 11-06-78 11-06-78 11-06-78 11-06-78 11-06-78 11-06-78 11-06-78 11-06-78 11-06-78 11-06-78 11-06-78 11-06-78 11-06-78 to to to to to to to to 11-13-78 11-13-78 11-13-78 11-14-78 11-14-78 11-13-78 11-'13-78 11-13-78 11-13-78 11-13-78 11-13-78 11-14-78 11-14-78 11-13-78 11-13-78 11-13-78 to to to to to to to to 11-20-78 11-20-78 11-20-78 11-21-78 11-21-78 11-20-78 11-20-78 11-20-78 11-'20-78 11-20-78 11-20-78 11-21-78 11-21-78 11-20-78 11-20-78 11-20-78 to to to to to to to to 11-28-78 11-27-78 11-27-78 11-28-78 11-28-78 11-27-78 11-27-78 11-27-78

TABLE C-6 (cont.)

SAMPLING DATES FOR AIR SAMPLES MONTH 2Sl 5Sl 5Dl lODl 16El lFl 2F2 3H3 DECEMBER 11-28-78 11-27-78 11-27-78 11-28-78 11-28-78 11-27-78 11-27-78 11-27-78 to to to to to to to to 12-04-78 12-04-78 12-04-78 12-05-78 12-05-78 12-04-78 12-04-78 12-04-78 12-04-78 12-04-78 12-04-78 12-05-78 12-05-78 12-04-78 12-04-78 12-04-78 to to to to to to to to

<..Tl

<..Tl 12-11-78 12-11-78 12-11-78 12-12-78 12-12-78 12-11-78 12-11-78 12-11-78 12-11-78 12-11-78 12-11-78 12-12-78 12-12-78 12-11-78 12-11-78 12-11-78 to to to to to to to to 12-18-78 12-18-78 12-18-78 12-19-78 12-19-78 12-18-78 12-18-78 12-18-78 12-18-78 12-18-78 12-18-78 12-19-78 12-19-78 12-18-78 12-18-78 12-18-78 to to to to to to to to 12-26-78 12-26-78 12-26-78 12-27-78 12-27-78 12-26-78 12-26-78 12-26-78 12-26-78 12-26-78 12-26-78 12-27-78 12-27-78 12-26-78 12-26-78 12-26-78 to to to to to to to to 1-02-79 1-02-79 1-02-79 1-02-79 1-02-79 1-02-79 1-02-79 1-02-79

No sample was received due to sampler malfunction.

TABLE C-7 CONCENTRATIONS OF TRITIUM, ALPHA AND BETA EMITTERS IN PRECIPITATION (Station SA-RWA-2F2)

Results in Units of pCi/l +/- 2 sigma COLLECTION PERIOD H-3 ALPHA BETA 1-03-78 to 2-08-78 <79 <1. 4 22+/-3 2-08-78 to 3-06-78 <81 <1.2 43+/-4 3-06-78 to 4-03-78 <147 1. 4+/-0. 7 565+/-57 4-03-78 to 5-01-78 <83 2. 0+/-1.2 138+/-14 5-01-78 to 6-06-78 <84 <0.4 28+/-4 6-06-78 to 7-03-78 <81 <0. 7 23+/-3 7-03-78 to 7-31-78 <66 <0.6 16+/-3 7-31-78 to 9-06-78 <62 <0.4 6.2+/-2.2 9-06-78 to 10-02-78 <84 2. 0+/-1. 0 34+/-4 10-02-78 to 10-31-78 <50 <0.6 18+/-3 10-31-78 to 12-04-78 <63 <0.5 5. 9+/-2. 3 12-04-78 to 1-03-79 <71 <0.5 .3.8+/-2.3 Average 75+/-317 56

TABLE C-8 CONCENTRATIONS OF STRONTIUM-89* AND -90, AND GAMMA EMITTERS**

IN QUARTERLY COMPOSITES OF PRECIPITATION (Station: SA-RWA-2F2)

Results in Units of pCi/l +/- 2 sigma 1-03-78 4-03-78 7-03-78 10-02-78 to to to to NUCLIDE 4-03-78 7-03-78 10-02-78 1-03-79 Sr-89 26+/-2 <1 ..3 <1.2 <0.7 Sr-90 1.7+/-1.l 1. 6+/-0. 5 <0.7 0.3+/-0.3 Be-7 17+/-7 33+/-4 9.5+/-2.0 24+/-7 Zr-95 1. 2+/-0. 8 <0.6 <0.3 <0.4+

Nb-95 1. 2+/-0. 7 <0.3 <0.2 <0.4+

Ru-103 23+/-2 <0.3 <0.1 Ru-106 8.5+/-4.7 5.0+/-3.3 <2.0 <4.0 I-131 15+/-3 <0.3 <0.2 <0.4 Cs-137 2.0+/-0.7 2.3+/-0.5 0.5+/-0.3 <0.5 BaLa-140 5.6+/-1.5 <0.5 <0.3 <0.4 Ce-141 3.0+/-1.3 <0.3 <0.2 Ce-144 <3.0 9.9+/-2.0 1.1+/-0. 8 <2.0 Ra-226 <1. 0 <0.8 0.8+/-0.4 <0.8

Sr-89 results are decay corrected to sample stop date.

- All other gamma emitters searched for were <MDL; typical MDLs are given in Table C-30. Nuclides not routinely searched for are indi-cated by a dash (-).

+ MDL for Zr-95 and Nb-95 is that of ZrNb-95.

57

TABLE C-9 DIRECT RADIATION MEASUREMENTS - MONTHLY TLD RESULTS mrad/standard month*

STATION NO. JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-IDM-2Sl 5.04+/-0.19 5.99+/-0.55 5.65+/-0.23 5.43+/-0.30 5.43+/-0.10 4.98+/-0.74 SA-IDM-5Sl 4.20+/-0.71 4.68+/-0.31 4.40+/-0.19 4.44+/-0.43 4.49+/-0.29 4.32+/-0.57 SA-IDM-6Sl 4.89+/-0.44 5.15+/-0.44 5.22+/-0.22 5.38+/-0.62 5.36+/-0.43 5.10+/-0.59 SA-IDM-7Sl 5.76+/-0.30 6.33+/-0.43 5.53+/-0.12 5.65+/-0.22 5.63+/-0.26 5.13+/-0.19 SA-IDM-lOSl 5.02+/-0.55 5.86+/-0.29 5.21+/-0.22 5.09+/-0.20 5.29+/-0.25 5.19+/-0.52 SA-IDM-llSl 3.94+/-0.26 4.27+/-0.38 4.18+/-0.20 3.90+/-0.47 4.13+/-0.70 3.91+/-0.17 SA-IDM-5Dl 4.62+/-0.34 4.33+/-0.74 4.56+/-0.38 4.55+/-0.25 4.98+/-0.23 4.50+/-0.48 SA-IDM-lODl 5.31+/-0.19 5.30+/-0.60 5.31+/-0.25 5.73+/-0.34 5.64+/-0.32 5.99+/-0.56 SA-IDM-14Dl 4.85+/-0.34 5.08+/-0.35 5.04+/-0.38 4.99+/-0.27 5.49+/-0.74 4.87+/-0.55 SA-IDM-2El 4.88+/-0.52 5.62+/-0.46 4.96+/-0.14 4.76+/-0.24 5.52+/-0.43 4.97+/-0.93 SA-IDM-3El 4. 71+/-0.28 4.94+/-0.17 4.60+/-0.19 5.02+/-0.26 5.06+/-0.39 4.37+/-0.53 SA-IDM-13El 4.89+/-0.28 5.04+/-0.30 4.81+/-0.13 4.84+/-0.46 4.98+/-0.33 5.08+/-0.55 SA-IDM-16El 4.99+/-0.35 5.75+/-0.49 5.14+/-0.51 5.43+/-0.23 5.40+/-0.30 5.14+/-0.45 SA-IDM-lFl 4.95+/-0.34 5.71+/-0.19 5.20+/-0.35 5.62+/-0.12 5.33+/-0.29 5.07+/-0.64 SA-IDM-2F2 4.24+/-0.08 4.70+/-0.29 4.29+/-0.23 4.35+/-0.54 4.36+/-0.20 4.14+/-0.50 SA-IDM-5Fl 4.32+/-0.44 5.12+/-0.41 4.66+/-0.23 5.21+/-0.23 4.80+/-0.29 4.78+/-0.44

SA- IDM-6 Fl 4.25+/-0.51 4.47+/-0.70 4.24+/-0.15 4.37+/-0.43 4.17+/-0.39 4.25+/-0.56 SA-IDM-7F2 3.44+/-0.35 3.95+/-0.32 3.68+/-0.38 3.96+/-0.23 3.70+/-0.22 3.90+/-0.33 SA-IDM-11 Fl 5.47+/-0.82 5.68+/-0.27 5.45+/-0.21 5.71+/-0.56 5.54+/-0.23 5.54+/-0.41 SA-IDM-13Fl 5.17+/-0.58 4.99+/-0.93 4.63+/-0.21 4.88+/-0.14 5.13+/-0.20 5.07+/-0.57 SA-IDM-2Hl 5.49+/-0.35 6.28+/-0.18 5.81+/-0.42 5.30+/-0.38 6.42+/-0.28 4.25+/-0.51 SA-IDM-3Hl 5.20+/-0.44 5.91+/-0.23 5.71+/-0.40 5.04+/-0.09 5.25+/-0.24 4.83+/-0.63 SA-IDM-3H3 5.30+/-0.24 5.65+/-0.52 5.28+/-0.33 5.22+/-0.34 5.53+/-0.34 5.60+/-0.35 SA-IDM-3Gl 5.62+/-0.37 5.65+/-0.14 5.41+/-0.31 5.37+/-0.77 5.88+/-0.63 5.69+/-0.76 AVERAGE 4.86+/-1.12 5.27+/-1. 30 4.96+/-1.10 5.01+/-1.06 5 .15+/-1.23 4.86+/-1.12 STATION NO. JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE SA-IDM-2Sl 5.86+/-0.72 5.14+/-0.50 5.44+/-0.50 5.75+/-0.96 5.79+/-0.41 5.99+/-0.16 5. 54+/-0. 71 SA-IDM-5Sl 4.39+/-0.56 4.07+/-0.18 4.16+/-0.27 4.61+/-0.23 4.35+/-0.36 4.56+/-0.45 4.39+/-0.37 SA-I DM-6Sl 5.86+/-0.36 5.04+/-0.57 5.19+/-0.62 5.58+/-0.31 5.47+/-0.76 5.60+/-0.16 5.32+/-0.55 SA-IDM-7Sl 5.74+/-0.36 5.00+/-0.51 5.21+/-0.44 5.58+/-0.66 5.26+/-0.24 6.06+/-0.46 5.57+/-0.77 SA-IDM-lOSl 5.10+/-0. 73 4.53+/-0.74 4.84+/-0.38 4.62+/-0.22 4.97+/-0.51 5.53+/-0.32 5.10+/-0.73 SA-IDM-llS 1 3.94+/-0.38 3.57+/-0.20 4.31+/-0.51 4.09+/-0.60 4.40+/-0.26 5.D9+/-0.24 4.14+/-0.75 SA-IDM-5Dl 4.87+/-0.24 4.56+/-0.55 4.71+/-0.26 4.87+/-0.47 4.88+/-0.47 5.09+/-0.49 4.71+/-0.45 SA-IDM-1001 5.74+/-0.43 5.37+/-0.69 5.73+/-0.38 5.78+/-0.17 5.71+/-0.32 5.86+/-0.50 5.62+/-0.48 SA-IDM-14Dl 5.68+/-0.30 5.30+/-0.49 5.35+/-0.21 5.27+/-0.34 5.49+/-0.23 5.69+/-0.32 5.26+/-0.59 SA-IDM-2El 5.42+/-0.44 4.77+/-0.70 5.07+/-0.11 5.12+/-0.44 5.43+/-0.92 5.30+/-0.25 5.15+/-0.60 SA-IDM-3El 5.26+/-0.35 4.59+/-0.46 4.98+/-0.38 5.07+/-0.58 5.05+/-0.50 5.17+/-0.64 4.90+/-0.54 SA-IDM-13El 5.12+/-0.56 4.74+/-0.23 4.84+/-0.40 4. 95+/-1.11 4.96+/-0.36 5.52+/-0.54 4.98+/-0.41 SA-IDM-16El 5.48+/-0.39 4.83+/-0.30 5.22+/-0.39 5.32+/-0.50 5.31+/-0.60 5.68+/-0.20 5.31+/-0.53 SA-IDM-lFl 5.45+/-1.30 5.25+/-0.45 5.52+/-0.64 5.53+/-0.52 5.40+/-0.51 5.49+/-0.37 5.38+/-0.45 SA-IDM-2F2 4.23+/-0.20 3.76+/-0.17 4.00+/-0.15 4.05+/-0.40 4.29+/-0.42 4.34+/-0.49 4.23+/-0.46 SA-IDM-5Fl 5.13+/-0.52 4.60+/-0.58 5.14+/-0.36 5.28+/-0.21 4.90+/-0.54 5.07+/-0.46 4.92+/-0.58 SA-IDM-6Fl 4.35+/-0.17 4.07+/-0.16 4.24+/-0.16 4.57+/-0.26 4.29+/-0.47 4.52+/-0.33 4.32+/-0.29 SA-IDM-7F2 3.83+/-0.54 3.54+/-0.20 3.90+/-0.49 3.69+/-0.28 3.98+/-0.23 4.33+/-0.25 3.83+/-0.47 SA-IDM-11 Fl 5.60+/-0.52 5.22+/-0.44 5.81+/-0.70 5.51+/-0.35 5.85+/-0.28 6.02+/-0.84 5.62+/-0.43 SA-IDM-13 Fl 5. 93+/-1. 29 4.47+/-0.22 5.08+/-0.12 5.00+/-0.28 5.25+/-0.61 5.60+/-0.43 5.10+/-0. 78 SA-IDM-2Hl 5.63+/-0.32 5.06+/-0.30 5.46+/-0.49 5.57+/-0.57 5.17+/-0.17 5.97+/-0.43 5. 53+/-1.16 SA-IDM-3Hl 5.52+/-0.49 4.79+/-0.23 4.83+/-0.54 5.34+/-0.57 5.46+/-0.75 5.85+/-0.75 5.31+/-0.79 SA-IDM-3H3 5.75+/-0.64 4.53+/-0.90 5.42+/-0.43 5.47+/-0.66 5.51+/-0.27 5.73+/-0.50 5.42+/-0.65 SA-IDM-3Gl 5.79+/-0.65 5.09+/-1.14 5.42+/-1.01 5.71+/-0.78 5.62+/-0.12 6.10+/-0.38 5.61+/-0.53 SA-IDM-6S2** 4.46+/-0.40 4.18+/-0.21 4.49+/-0.31 5.16+/-0.66 5.11+/-0.56 4.92+/-0.27 4.72+/-0.80 AVERAGE 5.21+/-1.29 4.64+/-1.06 4.97+/-1.07 5.10+/-1.12 5.12+/-1.03 5.40+/-1.09 5.05+/-1.18

The standard month = 30.4 days.

- Station 6S2 was added on 6-26-78.

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 5.19+/-0.38 4.68+/-0.31 5.17+/-0.34 5.24+/-0.09 5.07+/-0.52 SA-I DM-5Sl 3.89+/-0 .11 3.90+/-0.25 4.08+/-0.24 4.51+/-0.48 4.10+/-0.58 SA-IDM-6Sl 4.53+/-0.28 4.66+/-0.21 4.95+/-0.47 5.22+/-0.38 4.84+/-0.62 SA-IDM-7Sl 5.16+/-0.10 4.86+/-0.36 5.25+/-0.44 5.44+/-0.32 5.18+/-0.48 SA-IDM-lOS 1 4.98+/-0.33 4.50+/-0.24 4.62+/-0.20 4.65+/-0.30 4.69+/-0.41 SA- IDM-llS 1 3.87+/-0.24 3.30+/-0.27 3.95+/-0.25 4.34+/-0.11 3.87+/-0.86 SA-IDM-5Dl 4.20+/-0.21 4.37+/-0.51 4.63+/-0.44 4.71+/-0.41 4.48+/-0.47 SA-IDM-lODl 5.06+/-0.08 5.02+/-0.19 5.45+/-0.26 5.74+/-0.26 5.32+/-0.68 CJ1 l.O SA-IDM-14Dl 4.55+/-0.11 4.37+/-0.14 5.09+/-0.19 5.24+/-0.52 4.81+/-0.84 SA-IDM-2El 4.90+/-0.09 4.66+/-0.18 5.02+/-0.10 5.43+/-0.46 5.00+/-0.64 SA-IDM-3El 4. 33+/-0.19 4.63+/-0.11 4.84+/-0.27 4.84+/-0.28 4.66+/-0.48 SA-IDM-13E 1 4.63+/-0.30 4.41+/-0.17 4.75+/-0.17 4.61+/-0.14 4.60+/-0.28 SA-IDM-16El 5.01+/-0.22 4.70+/-0.48 5.40+/-0.25 5.39+/-0.32 5.13+/-0.67 SA-IDM-lFl 5.00+/-0.49 4.60+/-0.24 5.17+/-0.31 5.23+/-0.10 5.00+/-0.57 SA-IDM-2F2 3.79+/-0.35 3.76+/-0.32 4.10+/-0.30 3.88+/-0.50 3.88+/-0.31 SA-IDM-5Fl 4.33+/-0.08 4.25+/-0.14 4.67+/-0.64 4.63+/-0.39 4.47+/-0.42 SA-IDM-6Fl 3.95+/-0.34 3.73+/-0.12 3.85+/-0.19 4.22+/-0.37 3.94+/-0.42 SA-IDM-7F2 3.57+/-0.09 3.38+/-0.20 3.58+/-0.13 3. 71+/-0.32 3.56+/-0.27 SA-IDM-llFl 5.39+/-0.22 5.21+/-0.15 5.59+/-0.25 5.81+/-0.43 5.50+/-0.52 SA- IDM-13 Fl 4.61+/-0.16 4.35+/-0.39 5.02+/-0.30 5.33+/-0.27 4.83+/-0.87 SA-IDM-2Hl 5.59+/-0.19 5.00+/-0.16 5.22+/-0.44 5.42+/-0.24 5 .31+/-0. 51 SA-IDM-3Hl 5.17+/-0.37 4.53+/-0.44 5.03+/-0.40 5.12+/-0.19 4.96+/-0.59 SA-IDM-3H3 4.97+/-0.25 4.86+/-0.15 5.27+/-0.31 5.21+/-0.39 5.08+/-0.39 SA-IDM-3Gl 5.25+/-0.29 4.89+/-0.26 5.35+/-0.33 6.07+/-0.56 5.39+/-0.99 SA-IDM-6S2 ** ** 4.42+/-0.34. 4. 51+/-0 .14 4.47+/-0.13 AVERAGE 4.66+/-1.13 4.44+/-1.01 4.82+/-1. 09 4. 98+/-1.18 4. 73+/-1.16

The standard month = 30.4 days.

- Station 6S2 was added on 6-26-78.

TABLE C-11 CONCENTRATIONS OF TRITIUM IN SURFACE WATER Results in Units of pCi/l +/- 2 sigma 1-06-78 ( l) 3-13-78 4-04-78 5-04-78 6-02-78 7-12-78 STATION NO.

90+/-78 83+/-72 <84 <83 203+/-81 <77 SA-SWA-llAl 110+/-78 94+/-73 <84 <83 91+/-81 94+/-75 SA-SWA-12Cl

<80 229+/-71 <84 314+/-80 199+/-87 161+/-73 SA-SWA-7El

<80 94+/-72 <84 261+/-80 <74 164+/-73 SA-SWA-1F2 110+/-78 115+/-73 <84 <83 187+/-81 147+/-75 SA-SWA-16Fl 94+/-30 123+/-121 <84 165+/-227 151+/-126 129+/-81 Average

°'

0 8-08-78 9-05-78 10-06-78 11-08-78 12-07-78 ANNUAL S1ATION NO. AVERAGE

<66 <64 <70 113+/-68 101+/-71 94+/-78 SA-SWA-llAl

<66 <64 <70 88+/-67 <71 83+/-28 SA-SWA-12Cl

<66 103+/-61 <70 156+/-68 82+/-71 140+/-160 SA-SWA-7El

<66 <64 <70 223+/-66 <74 114+/-139 SA-SWA-1F2

<66 <64 <70 72+/-67 <71 97+/-79 SA-SWA-16Fl Average <66 72+/-35 <70 130+/-121 80+/-25 106+/-111 (1) No surface water sample was received for February 1978 due to river icing.

--~-

TABLE C-12 CONCENTRATIONS OF ALPHA EMITTERS IN SURFACE WATER Results in Units of pCi/l +/- 2 sigma STATION NO. 1.;.06-78(1) 3-13-78 4-04-78 5-04-78 6-02-78 7-12-78 SA-SWA-llAl <10 <36 <3.9 <23 <6.0 <13 SA-SWA-12Cl <3.2 <32 <4.0 <13 <2.8 <12 SA-SWA-7Fl <12 <51 <10 <23 <7.7 <20 SA-SWA-1F2 <2.0 <16 <1. 7 <13 <1.0 <7.1 en SA-SWA-16 Fl 7.9+/-4.3 <32 <l.B <9.5 <11 <10 I-"

STATION NO. 8-08-78 9-05-78 10-06-78 11-08-78 12-07-78 SA-SWA-llAl <17 27+/-23 <8.9 <14 <14 SA-SWA-12Cl <12 <13 <7.0 <28 <16 SA-SWA-7El <27 <23 <12 <20 <23 SA-SWA-1F2 <6.6 <7.8 <6.4 <14 <12 SA-SWA-16Fl <4.9 <8.5 <7.6 <14 <16 (1) No surface water was received for February 1978 due to river icing.

TABLE C-13 CONCENTRATIONS OF BETA EMITTERS IN SURFACE WATER Results in Units of pCi/1 +/- 2 sigma STATION NO. 1-06-78 (1) 3-13-78 4-04-78 5-04-78 6-02-78 7-12-78 SA-SWA-llAl 43+/-5 63+/-7 22+/-3 34+/-4 22+/-4 43+/-5 SA-SWA-12Cl 12+/-3 60+/-6 23+/-3 28+/-4 9.3+/-2.4 37+/-5 i"SA-SWA-7El 46+/-5 96+/-10 23+/-4 41+/-4 36+/-5 67+/-7 SA-SWA-1F2 8.0+/-2.4 17+/-3 18+/-3 29+/-4 4.3+/-2.1 18+/-3 SA-SWA-16Fl 8,5+/-2.4 53+/-6 16+/-3 22+/-3 6.0+/-2.2 32+/-4 Average 24+/-39 58+/-56 20+/-6 31+/-14 16+/-27 39+/-36

°'

N STATION NO. 8-08-78 9-05-78 10-06-78 11-08-78 12-07-78 ANNUAL AVERAGE SA-SWA-llAl 42+/-5 66+/-7 71+/-8 65+/-8 34+/-5 46+/-35 SA-SWA-12Cl 34+/-5 45+/-5 70+/-7 48+/-5 58+/-6 39+/-39 SA-SWA-7El 83+/-8 9~+/-10 118+/-12 62+/-7 100+/-10 70+/-62 SA-SWA-1F2 16+/-3 32+/-4 50+/-6 44+/-5 44+/-5 25+/-31 SA-SWA-16Fl 13+/-3 35+/-5 62+/-7 33+/-5 62+/-6 31+/-41 Average 38+/-56 55+/-56 74+/-52 50+/-26 60+/-50 42+/-52 (1) No surface water sample was received for February 1978 due to river icing.

TABLE C-14 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER Results in Units of pCi/l +/- 2 sigma STATION NO. NUCLIDE* l-06-78(l) 3-13-78 4-04-78 5-04-78 6-02-78 7-12-78 SA-SWA-llAl K-40 36+/-7 54+/-10 <.7.0 56+/-12 20+/-7 32+/-9 SA-SWA-12Cl K-40 <7.0 55+/-9 <7.0 28+/-8 14+/-8 34+/-8 SA-SWA-7El K-40 52+/-10 94+/-10 13+/-9 62+/-8 36+/-9 70+/-8 SA-SWA-1F2 K-40 <7.0 35+/-10 <7.0 35+/-8 <6.0 23+/-8 SA-SWA-16Fl K-40 <7.0 42+/-9 <6.0 <6.0 <5.0 32+/-7 Average 22+/-42 56+/-46 8+/-6 37+/-45 16+/-25 38+/-37 0) w STATION NO. NUCLIDE* 8-08-78 9-05-78 10-06-78 11-08-78 12-07-78 ANNUAL AVERAGE SA-SWA- llAl K 46+/-7 81+/-9 75+/-8 66+/-8 63+/-8 49+/-46 SA-SWA-12Cl K-40 27+/-8 37+/-8 81+/-9 74+/-9 68+/-9 39+/-53 SA-SWA-7El K-40 55+/-9 96+/-10 120+/-12 93+/-9 90+/-9 71+/-62 SA-SWA-1F2 K-40 20+/-7 18+/-7 51+/-8 43+/-8 39+/-8 26+/-31 SA-SWA-16Fl K-40 <6.0 33+/-9 51+/-9 43+/-9 59+/-13 26+/-42 Average 31+/-40 53+/-67 76+/-57 64+/-43 64+/-37 42+/-57

By garrma spectrometry, all other garrnna emitters searched for were <MDL; typical MDLs are given in Table C-30.

(1) No surface water sample was received for February 1978, due to river icing.

TABLE C-15 CONCENTRATIONS OF STRONTIUM-89* AND -90 IN SURFACE WATER Results in Units of pCi/l +/- 2 sigma (1) 7-12-78 to 9-05-78 10-06-78 to 12-07-78 STATION 1-06-78 and 3-13-78 4-04-78 to 6-02-78 NUMBER

Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 .sr~9o.

SA-SWA- llAl <0.7 0.7+/-0.3 <1.2 0.7+/-0.5 <0.9 <0.5 <0.9 <0.8 SA-SWA-12Cl <0.7 0.3+/-0.3 <1.2 <0.7 <0.8 0.4+/-0.3 <0.9 <0.5 SA-SWA-7El <0.7 0.4+/-0.3 <1.6 <0.9 <0.8 <0.4 <1.1 <0.7

~ SA-SWA-1F2 <0.4 <0.3 <1.0 <0.6 <0.8 0.5+/-0.3 <0.7 <0.4 SA-SWA-16Fl <0.6 0.4+/-0.3 <1.3 0.7+/-0.5 <0.9 0.5+/-0.3 <0.9 <0.6

/

Sr-89 results are decay corrected to sample stop date.

( 1) No surface water sample was received for February 1978, due to river icing.

TABLE C-16 CONCENTRATIONS OF TRITIUM, ALPHA AND BETA EMITTERS, AND POTASSIUM-40 IN WELL WATER Results in Units of pCi/l +/- 2 sigma STATION NO.

RAD IO ACTI VITV 1-09-78 2-14-78 3-13-78 4-10-78 5-08-78 6-12-78 SA-WWA-4Sl H-3 <80 <79 <81 <84 225+/-80 <83 Alpha <1.5 <1.7 <1.7 <2.0 <1. 7 <1.0 Beta 9.3+/-2.5 16+/-3 12+/-3 15+/-3 15+/-3 10+/-3 K-40 16+/-2 11+/-1 12+/-1 12+/-1 13+/-1 14+/-1 SA-WWA-5Dl H-3 <80 <79 <81 <84 109+/-79 <71 Alpha <1.5 <1.3 <1.3 <1.8 <1.4 <0.8 Beta 2.8+/-2.0 3.4+/-1.9 3.5+/-2.1 2.3+/-2.2 <2.2" 2.1+/-1.9 K-40 3.0+/-0.3 3.2+/-0.3 1.2+/-0.1 1. 5+/-0.2 2.1+/-0.2 1.2+/-0.1 SA-WWA-3El H-3 <80 <79 <81 <84 189+/-80 <83 Q)

Alpha <1.5 <1. 7 <1. 7 <2.2 <1. 7 <1.1 U1 Beta 12+/-3 10+/-3 8.7+/-2.5 7.1+/-2.6 9.4+/-2.8 7.1+/-2.3 K-40 14+/-1 9.1+/-0.9 9.0+/-0.9 9.3+/-0.9 10+/-1 11+/-1 STATION NO.

RADIOACTIVITY 7-10-78 8-14-78 9-12-78 10-10-78 il-13-78 12-11-78 AVERAGE SA-WWA-4Sl H-3 <81 <66 <62 <70 <62 <74 Alpha <1.8 <1.5 <1.0 <0.5 <1. 7 <1.4 Beta 14+/-3 13+/-3 14+/-3 12+/-3 14+/-3 13+/-3 12+/-4 K-40 12+/-1 12+/-1 14+/-1 13+/-1 10+/-1 12+/-1 13+/-3 SA-WWA-5Dl H-3 <81 <66 <64 <70 <62 <74 Alpha <1.4 <l'. 2 2.4+/-1.4 <0.4 <1.2 <1.0 Beta 2.0+/-1.8 <1.9 <1.8 2.8+/-2.3 2.5+/-2.0 2.2+/-2.2 2.5+/-1.1 K-40 1.6+/-0.2 1.1+/-0.1 1.5+/-0.2 3.5+/-0.4 2.5+/-0.3 4.2+/-0.4 2.2+/-2.1 SA-WWA-3El H-3 <81 <66 <62 <70 <62 <74 Alpha <1.8 <1.5 <1.0 <0.5 <1.6 <1.4 Beta 11+/-3 8.5+/-2.5 11+/-3 7.4+/-2.6 11+/-3 12+/-3 10+/-4 K-40 8.9+/-0.9 1.2+/-0.1 8.7+/-0.9 9.8+/-1.0 8.1+/-0.8 9.5+/-1.0 10+/-3

TABLE C-17 CONCENTRATIONS OF STRONTIUM~89* AND -90, AND GAMMA EMITTERS** IN QUARTERLY COMPOSITES OF WELL WATER Results in Units of pCi/l +/- 2 sigma 1-09-78 4-10-78 7-10-78 10-10-78 STATION NUMBER to to to to RAD! OACTI VI TY 3-13-78 6-12-78 9-12-78 12-11-78 SA-WWA-451 Sr-89 <0.7 <0.9 <0.8 <0.5 Sr-90 <0.5 <0.5 <0.5 <0.3 K-40 <7.0 16+/-9 14+/-6 <7 .o SA-WWA-5Dl Sr-89 <0.5 <1.1 <0.8 <0.6 Sr-90 <0.4 <0.6 <0.4 <0.4 K-40 <6.0 <5.0 <6.0 <6.0 SA-WWA-3El Sr-89 <0.6 <1. 0 <0.8 <0.6 Sr-90 <0.4 <0.7 <0.4 <0.4 K-40 <6.0 9.8+/-7.6 9.8+/-7.3 <6.0

Sr-89 results are decay corrected to sample stop date.

- All other gamma emitters searched for were <MDL; typical MDLs are given in Table C-30.

TABLE C-18 CONCENTRATIONS OF TRITIUM, ALPHA AND BETA EMITTERS, AND POTASSIUM-40 IN RAW AND TREATED POTABLE WATER (Sampled at location 2F3)

Results in Units of pCi/l +/- 2 sigma RADIOACTIVITY JANUARY FEBRUARY MARCH APRIL MAY JUNE H-3 (Raw) <79 <81 <84 438+/-81 114+/-79 <81 (Treated) <79 <81 <84 234+/-80 332+/-80 <81 Alpha( Raw) 1.4+/-0.6 o. 8+/-0. 5 1. 0+/-0. 6 1.3+/-0.5 2.8+/-1.1 <0.4 (Treated) 0.8+/-0.6 0.9+/-0.6 1. 3+/-0.8 0.6+/-0.4 1.1+/-0.6 <0.5 Beta (Raw) 5.0+/-0.5 4.0+/-0.5 11+/-1 11+/-1 7. 8+/-1. 9 4.1+/-0.5 CJ')

(Treated) 3.4+/-0.5 3.4+/-0.5 5.2+/-0.6 6.5+/-0.7 3. 9+/-1. 7 3.3+/-0.5

-.....i K-40 (Raw) 1. 5+/-0. 2 0.43+/-0.04 0.65+/-0.07 0.73+/-0.07 0.56+/-0.06 1.1+/-0.1 (Treated) 1. 6+/-0. 2 0.43+/-0.04 0.65+/-0.07 0.73+/-0.07 0.56+/-0.06 1.1+/-0 .1 RADIOACTIVITY JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE H-3 (Raw) <66 <62 <84 <62 84+/-60 <79 (Treated) <66 <62 <84 <62 <63 <79 Alpha( Raw) 0.7+/-0.5 0.4+/-0.3 0.3+/-0.2 0.9+/-0.5 <0.3 0.8+/-0.5 0.9+/-1. 4 (Treated) <0.5 0.6+/-0.5 0.7+/-0.5 0.6+/-0.4 <0.5 <0.5 0.7+/-0.5 Beta (Raw) 3.2+/-0.5 3.1+/-0.7 2.0+/-0.7 2.9+/-0.5 2.5+/-0.5 3.9+/-0.5 5.0+/-6.3 (Treated) 2.7+/-0.5 2.0+/-0.6 2.2+/-0.7 2.1+/-0.5 2.9+/-0.5 3. 5+/-0. 5 3. 4+/-2. 6 K-40 (Raw) 1. 3+/-0.1 1.4+/-0.1 1.2+/-0.1 0.80+/-0.08 1. 0+/-0.1 1.0+/-0.1 1.0+/-0.7 (Treated) 1. 4+/-0.1 1. 2+/-0 .1 1. 3+/-0.1 0.69+/-0.07 1. 4+/-0.1 1. 4+/-0 .1 1.0+/-0.8

TABLE C-19 CONCENTRATIONS OF STRONTIUM-89* AND -90, AND GAMMA EMITTERS IN QUARTERLY COMPOSITES OF POTABLE WATER (Station: SA-PWA-2F3)

Results in Units of pCi/l +/- 2 sigma 1-01-78 4-01-78 7-01-78 10-01-78 to to to to SAMPLE 3-13-78 6-30-78 9 78 12-31-78 Raw Sr-89 <1.4 <1. 3 <1.2 <0.8 Sr-90 <0.8 0.9+/-0.5 <0.7 0.5+/-0.3 Gamma**

Emitters All <MDL All <MDL All <MDL All <MDL Treated Sr-89 <1.4 <1.4 <0.9 <0.8 Sr-90 <0.8 0.6+/-0.5 <0.5 0.9+/-0.3 Gamma**

Emitters All <MDL All <MDL All <MDL A11 <MDL

Sr-89 results are decay corrected to sample stop date.

- Typical MDLs are given in Table C-30.

68

TABLE C-20 CONCENTRATIONS OF Sr-89* AND -90 IN BENTHOS AND Sr-90 IN SEDIMENT Results in Units of pCi/g(dry) +/- 2 sigma Benthos Sediment**

STATION NUMBER DATE Sr-89 Sr-90 , Sr-90 SA-ESB-llAl 6-07-78 <2.5 <1.3 <0.04 9-12-78 <0.2 0.03+/-0.02 <0.06 SA-ESB-12Cl 6-07-78 <15 . <7.7 <0.03 9-12-78 <0.2 <0.04 <0.06 SA-ESB-7El 6-07-78 <1.0 <0.5 <0.03 9-12-78 <0.2 <0.04 0.03+/-0.03 SA-ESB-16Fl 6-07-78 <1100 (1) <546(l) <0.03 9-12-78 <0.2 <0.04 0.04+/-0.04

Sr-89 results are decay corrected to sample stop date.

- Sediment samples included associated benthic organisms.

(1) High MDL values due to small sample size.

69

TABLE C-21 CONCENTRATIONS OF 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 6-07-78 9-12-78 6-07-78 9-12-78 6-07-78 9-12-78 6-07-78 9-12-78 NUCLIDE**

K-40 15+/-2 15+/-2 15+/-2 16+/-2 14+/-1 19+/-2 17+/-2 18+/-2 Mn-54 0.03+/-0.02 <0.02 <0.02 <0.02 <0.02 <0.02 <0.02 <0.02 Co-58 0.09+/-0.02 <0.02 <0.01 <0.02 <0.02 <0.02 <0.02 <0.02 Co-60 0.13+/-0 .03 <0.02 <0.02 <0.03 <0.02 <0.03 <0.02 <0.02 Nb-95 0.12+/-0.03 <0.02 <0.02 <0.02 <0.02 <0.02 <0.02 <0.02 Zr-95 0.06+/-0.04 <0.04 0.05+/-0.05 <0.03 <0.03 <0.03 <0.03 <0.04

'-I 0 Ru-103 0.09+/-0.02 <0.02 <0.02 <0.01 0.02+/-0.02 <0.02 <0.02 <0.02 Ru-106 0.4+/-0.2 <0.2 <0.2 <0.2 <0.2 <0.2 <0.2 <0.2 Sb-125 0.09+/-0.06 <0.06 <0.05 <0.04 <0.05 <0.05 <0.05 <0.05 Cs-137 0.21+/-0.04 0.20+/-0.05 <0.02 0.04+/-0.02 0.08+/-0.03 0.06+/-0.03 <0.02 <0.02 Ce-141 0.06+/-0.05 <0.03 0.03+/-0.02 <0.02 0.04+/-0.02 0.03+/-0.02 <0.03 <0.03 Ce-144 0.5+/-0.2 <0.10 <0.09 <0.09 <0.1 <0.09 <0.1 <0.1 Ra-226 0.74+/-0.07 0.72+/-0.07 1.1+/-0.1 0.80+/-0.08 0.74+/-0.07 0.86+/-0.09 0.6+/-0.1 0.64+/-0.06 Th-232 0.9+/-0.1 1.1+/-0.1 1.1+/-0.1 0.9+/-0.1 0.83+/-0.09 1.1+/-0.1 1.1+/-0.1 1.1+/-0.1

Sediment samples included associated benthic organisms.

- All other gamma emitters searched for were <MDL; typical MDLs are given in Table C-30.

TABLE C-22 CONCENTRATIONS OF IODINE-131 IN MILK Results* in Units of rCi/l STATION NO. JANUARY** FEBRUARY MARCH APRIL MAY JUNE SA-MLK-2F4 <0.05 (1) <0.05 0.46+/-0.07 0,09+/-0.03 <0.03

<0.07 <0.05 <0.04 0.25+/-0.05 <0.05 <0.04

1. 0+/-0.1 SA-MLK-5F2 <0.06 <0.05 <0.04 12+/-1 0.27+/-0.05 <0.03

<0.08 <0.05 <0.03 4.1+/-0.4 <0.04 <0.05 1.9+/-0.2 SA-MLK-14Fl <0.06 <0.05 <0.06 4.7+/-0.5 0.12+/-0.05 <0.03

<0.07 <0.04 <0.05 1.1+/-0.1 <0.04 <0.05 0.84+/-0.08 SA-MLK-15Fl <0.06 <0.08 <0.05 1.6+/-0.2 <0.04 <0.04

<0.08 <0.05 <0.05 0.48+/-0.06 <0.04 <0.05 0.31+/-0.05 SA-MLK-3Gl <0.05 <0.05 <0.05 0.70+/-0.08 0.18+/-0.05 <0.03

<0.08 <0.06 <0.04 0.24+/-0.04 <0.04 <0.04 1.3+/-0.1 SA-MLK-13E3( 2) <0.05 <0.03

<0.05 <0.06 0.09+/-0.04 STATION NO. .JlJLY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER SA-MLK-2F4 <0.04 <0.04 <0.04 <0.04 <0.08 <0.04

<0.04 <0.04 <0.05 <0.05 <0.05 <0.04

<0.08 SA-MLK-5F2 <0.06 <0.03 <0.03 <0.04 <0.05 <0.04

<0.04 <0.01 <0.05 <0.05 <0.05 <0.04

<0.04 SA-MLK-14Fl <0.05 <0.03 <0.04 <0.05 <O.Ofi .<0.04

<0.03 <0.03 <0.05 <0.05 <0.05 <0.04

<0.04 SA-MLK-15Fl <0.06 <0.05 <0.04 <0.05 <0.06 <0.05

<0.04 <0.05 <0.06 <O.Ofi <0.05 <0.04

<0.04 SA-MLK-3Gl <0.04 <0.04 <0.04 <0.04 <0.05 <0.04

<0.04 <0.03 <0.05 <0.05 <0.05 <0.04

<0.04 SA-MLK-13E3 <0.06 <0.04 <0.04 <0.04 <0.08 <0.04

<0.04 <0.04 <0.05 <0.06 <0.05 <0.04

<0.04

I-131 results are decay corrected to samrle star date.

- Actual sampling dates can be found on Table C-24.

(1) Station 2Fl was discontinued in ,January 1978. It was replaced by station 2F4 on February 20, 1978.

(2) Sampling was started at station 13E3 on April 17, 1978.

71

TABLE C-23 CONCENTRATIONS OF GAMMA EMITTERS* AND STRONTirn~-89** AND -90 IN MILK Results in Units of pCi/l +/- 2 sigma STATION NO. NUCLIDE JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-MLK-2F4 K-40 1700+/-170 (1) 1300+/-130 1500+/-150 1600+/-160 2ln0+/-210 Cs-137 5.2+/-1.3 (1) 3.8+/-1.2 1.3+/-1. 2 3.1+/-1. l 6.8+/-1.2-Sr-89 <3.6 (1) <1.5 <1.4 <2.3 <2.1 Sr-90 7.7+/-1.2 (1) 3.9+/-0.7 2.3+/-0.7 3.2+/-1.0 3.5+/-1.0 SA-MLK-5F2 K-40 1700+/-170 1500+/-150 1400+/-140 1300+/-130 1300+/-130 1400+/-140 Cs-137 3.5+/-1.4 3.1+/-1.3 1.6+/-1. 0 2.4+/-1.2 3.7+/-1.3 4.8+/-1.2 Sr-89 2.3+/-2.0 <1.9 <1.4 12+/-2 1.8+/-1. 7 4.0+/-2.1 Sr-90 5.0+/-1.0 5.7+/-0.8 2.7+/-0.6 5.9+/-1.4 8.4+/-1.2 6.6+/-1.4 SA-MLK-13E3 ( 2 ) K-40 1300+/-130 1100+/-110

........ Cs-137 2.5+/-1.2 8.1+/-1.0 N

Sr-89 <l.8 <1.9 Sr-90 3~2+/-0.8 3.8+/-0.9 STATION NO. NUCLIDE JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER SA-MLK-2F4 K-40 1200+/-120 1400+/-140 1300+/-130 1400+/-140 1300+/-130 1500+/-150 Cs-137 2.4+/-0.7 4.6+/-1.2 1.6+/-1.0 2. 0+/-1. 0 1. 6+/-1. l 1. 9+/-1. 2 Sr-89 1. 7+/-1.2 <2.5 <1.6 <1.4 2.6+/-1.8 <3.5 Sr-90 2.9+/-0.8 3.4+/-0.9 2.7+/-0.7 2.5+/-0.6 2.3+/-1. 0 2.9+/-1.6 SA-MLK-5F2 K-40 950+/-95 1400+/-140 1900+/-190 1400+/-140 1700+/-170 1400+/-140 Cs-137 3 .1+/-0. 7 5.0+/-1.2 3.4+/-1.0 3.3+/-1.l 3.7+/-1.0 1.7+/-1.2 Sr-89 2.1+/-1.7 <3.9 <3.3 <2.0 <2.6 <1.8 Sr-90 7.6+/-0.9 6 .8+/-1.6 9.0+/-1.4 5.5+/-0.8 6.1+/-1.0 2.9+/-0.8 SA-MLK-13E3 K-40 1300+/-130 1800+/-180 1400+/-140 1500+/-150 1300+/-130 1400+/-140 Cs-137 6.4+/-0.7 12+/-1 9.1+/-1.3 3.1+/-1.2 3. 6+/-1. 2 3.3+/-1.2 Sr-89 <2.5 <2.3 <2.7 <3.0 <3.2 <1.4 Sr-90 4.8+/-1.1 4.8+/-0.9 4.4+/-1.2 3.3+/-1.l 3.3+/-1.1 1.4+/-0.6

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 1700+/-170 1400+/-140 1400+/-140 13Clfl+/-l30 l?.00+/-120 1100+/-110 Cs-137 5.6+/-1.5 2.5+/-1.0 1.7+/-1.1 2.8+/-1. 2 4.0+/-1.1 4.4+/-1.1 Sr-89 2.3+/-1.7 <2.4 <1.6 4.9+/-1.4 <1. 7 1.3+/-1.1 Sr-90 2.0+/-0.8 2.5+/-0.9 3.7+/-0.8 2.2+/-0.9 3.2+/-0.8 1. 9+/-0 .8 SA-MLK-15Fl K-40 1600+/-160 1400+/-140 1600+/-160 1500+/-150 1400+/-140 1100+/-110 Cs-137 5. 7+/-1.3 3. 2+/-1.1 3.7+/-1.1 3.9+/-1.4 3.1+/-1.2 4.1+/-0.9 Sr-89 <2.7 <2.0 2.8+/-0.6 <2.1 <1.5 <1.7 Sr-90 3.3+/-0.9 3.2+/-0.8 <1.4 3.0+/-0.9 3.6+/-0.7 3.5+/-0.8 SA-MLK-3Gl K-40 1600+/-160 1300+/-130 1500+/-150 1200+/-120 1200+/-120 1300+/-130 Cs-137 3.9+/-1.2 2.2+/-1.1 2.4+/-1.2 3.4+/-1.2 3.7+/-1.2 1.9+/-1.1 Sr-89 <2.8 <2.0 <1.3 <1.9 2.1+/-1.3 2.0+/-1.3 Sr-90 3.4+/-0.9 5.3+/-0.9 2.2+/-0.6 4.5+/-0.9 5.1+/-1.0 4.5+/-0.9

'1 w

STATION NO. NUCLIDE ,JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER SA-MLK-14Fl K-40 820+/-82 1300+/-130 1500+/-150 1600+/-160 1400+/-140 1500+/-150 Cs-137 1.2+/-0.7 1.4+/-1.l 2.2+/-1.2 1.6+/-1.0 2.8+/-1.1 <0.9 Sr-89 <1.9 <1. 6 <1.5 <2.8 <2.1 <1. 7 Sr-90 3.7+/-0.8 2.7+/-0.7 2.8+/-0.6 2.5+/-1.1 3.2+/-0.8 2.0+/-0.8 SA-MLK-15Fl K-40 790+/-79 1200+/-120 1500+/-150 1500+/-150 1400+/-140 1700+/-170 Cs-137 2.3+/-0.7 2.8+/-1.1 2.2+/-1.1 3.4+/-1.1 3.6+/-1.3 3.6+/-1.0 Sr-89 1.3+/-1.3 <2.8 1.3+/-1.0 <2.7 <2.7 <2.7 Sr-90 3.2+/-0.7 3.7+/-1.1 1.9+/-0.6 3.2+/-1.1 2.8+/-1.0 1.9+/-1.2 SA-MLK-3Gl K-40 850+/-85 1500+/-150 1400+/-140 1400+/-140 1300+/-130 1400+/-140 Cs-137 1.3+/-0. 7 4.9+/-1.2 4.8+/-0.8 4.7+/-0.7 3.2+/-0.8 3.8+/-1.1 Sr-89 1.8+/-1.6 <2.8 1.8+/-1.3 <1. 7 <2.1 <2.5 Sr-90 5.4+/-1.1 4.2+/-1.2 4.8+/-0.8 4.7+/-0.7 3.2+/-0.8 3.8+/-1.1

All other gamma emitters searched for were <MDL; typical MDLs are given in table C-30.

- Sr-89 results are decay corrected to sample stop date.

( 1) Station 2Fl was discontinued in January 1978. It was replaced by station 2F4 on February 20, 1978. Analysis of gamma emitters and Sr-89 and -90 was not performed during February.

(2) Station 13E3 was added April 17, 1978.

TABLE C-24 SAMPLING DATES FOR MILK SAMPLES MONTH 2F4 5F2 14Fl 15Fl 3Gl 13E3*

JANUARY 1-03-78 1-03-78 1-02-78 1-02-78 1-03-78 to to to to to 1-04-78 1-04-78 1-03-78 1-03-78 1-04-78 1-15-78 1-15-78 1-16-78 1-16-78 1-15-78 to to to to to 1-16-78 1-16-78 1-17-78 1-17-78 1-16-78 FEBRUARY 2-08-78 2-08-78 2-05-78 2-06-78

- to to to to 2-09-78 2-09-78 2-08-78 2-08-78 2-20-78 2-20-;-78 2-21-78 2-21-78 2-20-78 to to to to to 2-21-78 2-21-78 2-22-78 2-22-78 2-21-78

-....J MARCH 3-06-78 3-06-78 3-05-78 3-05-78 3-06-78

-!'=>

to to to to to 3-07-78 3-07-78 3-06-78 3-06-78 3-07-78 3-20-78 3-20-78 3-19-78 3-19-78 3-20-78 to to to to to 3-21-78 3-21-78 3-20-78 3-20-78 3-21-78 APRIL 4-03-78 4-03-78 4-02-78 4-02-78 4-03-78 to to to to to 4-04-78 4-04-78 4-03-78 4-03-78 4-04-78 4-09-78 4-09-78 4-09-78 4-09-78 4-09-78 to to to to to 4-10-78 4-10-78 4-11-78 4-11-78 4-10-78 4-17-78 4-17-78 4-17-78 4-17-78 4-17-78 4-17-78 to to to to to to 4-18-78 4-18-78 4-18-78 4-18-78 4-18-78 4-18-78 MAY 5-01-78 5-01-78 5-01-78 5-01-78 5-01-78 5-01-78 to to to to to to 5-02-78 5-02-78 5-02-78 5-02-78 5-02-78 5-02-78 5-15-78 5-15-78 5-15-78 5-15-78 5-15-78 5-15-78 to to to to to to 5-16-78 5-16-78 5-16-78 5-16-78 5-16-78 5-16-78

TABLE C-24 (cont.)

SAMPLING DATES FOR MILK SAMPLES MONTH 2F4 5F2 14Fl 15Fl 3Gl 13E3 JUNE 6-04-78 6-04-78 6-05-78 6-04-78 6-04-78 6-05-78 to to to to to to 6-05-78 6-05-78 6-06-78 6-05-78 6-05-78 6-06-78 6-18-78 6-18-78 6-19-78 6-x9-78 6-18-78 6-19-78 to to to to to to 6-19-78 6 78 6-20-78 6-20-78 6-19-78 6-20-78 JULY 7-02-78 7-02-78 7-01-78 7-01-78 7-02-78 7-02-78 to to to *to to to 7-03-78 7-03-78 7-03-78 7-03-78 7-03-78 7-03-78 7-16-78 7-16-78 7-17-78 7-17-78 7-16-78 7-17-78 to to to to to to

-.....i 7-17-78 7-17-78 7-18-78 7-18-78 7-17-78 7-18-78 Ul AUGUST 8-07-78 8-07-78 8-07-78 8-06-78 8-07-78 8-07-78 to to to to to to 8-08-78 8-08-78 8-08-78 8-08-78 8-08-78 8-08-78 8-21-78 8-21-78 8-21-78 8-20-78 8-21-78 8-21-78 to to to to to to 8-22-78 8-22-78 8-22-78 8-22-78 8-22-78 8-22-78 SEPTEMBER 9-04-78 9-04-78 9-04-78 9-05-78 9-04-78 9-05-78 to to to to to to 9-05-78 9-05-78 9-05-78 9-06-78 9..:05-78 9-06-78 9-18-78 9-18-78 9-18-78 9-17-78 9-18-78 9-18-78 to to to to to to 9-19-78 9-19-78 9-19-78 9-18-78 9-19-78 9-19-78 OCTOBER 10-02-78 10-02-78 10-02-78 10-01-78 10-02-78 10-02-78 to to to to to to 10-03-78 10-03-78 10-03-78 10-02-78 10-03-78 10-03-78 10-16-78 10-16-78 10-16-78 10-15-78 10-16-78 10-16-78 to to to to to to 10-17-78 10-17-78 10-17-78 10-16-78 10-17-78 10-17-78

TABLE C-24 (cont.)

SAMPLING DATES FOR MILK SAMPLES MONTH 2F4 5F2 14Fl 15Fl 3Gl 13E3*

NOVEMBER 11-05-78 11-05-78 11-05-78 11-04-78 11-05-78 11-05-78 to to to to to to 11-06-78 11-06-73 11-06-78 11-06-78 11-06-78 11-06-78 11-19-78 11-19-78 11-20-78 11-20-78 11-19-78 11-20-78 to to to to to to 11-20-78 11-20-78 11-21-78 11-21-78 11-20-78 11-21-78

-.....J O'l DECEMBER 12-03-78 12-03-78 12-04-78 12-04-78 12-03-78 12-04-78 to to to to to to 12-04-78 12-04-78 12-05-78 12-05-78 12-04-78 12-05-78 12-17-78 12-17-78 12-18-78 12-18-78 12-17-78 12-18-78 to to to to to to 12-18-78 1,2-18-78 12-19-78 12-19-78 12-18-78 12-19-78 12-25-78 12-25-78 12-26-78 12-26-78 12-25-78 12-26-78 to to to to to to 12-26-78 12-26-78 12-27-78 12-27-78 12-26-78 12-27-78

Station 2Fl was discontinued in January 1978. It was replaced by station 2F4 on February 20, 1978.

- Station 13E3 was added on April 17, 1978.

TABLE C-25 CONCENTRATIONS OF GAMMA EMITTERS* IN EDIBLE FISH Results in Units of pCi/g(wet) +/- 2 sigma STATION SAMPLING DATE K-40 Cs-137 SA-ESF-llAl 6-03-78 3.1+/-0.3 0.007+/-0.006 11-03-78 to 2.3+/-0.2 <0.005 11-09-78 SA-ESF-12Cl 6-03-78 2.2+/-0.2 <0.005 11-02-78 to 3.2+/-0.3 <0.005 11-06-78 SA-ESF-7El 6-02-78 2.2+/-0.2 <0.005 11-02-78 to 2.5+/-0.3 <0.006 11-09-78

All other gamma emitters searched for were <MDL; typical MDLs are given in Table C-30.

77

TABLE C-26 CONCENTRATIONS OF STRONTIUM-89* AND -90, AND TRITIUM IN EDIBLE FISH SAMPLES Bones Flesh Aqueous Fraction Organic Fraction (pCi/g +/- 2 sigma) (pCi/l +/- 2 sigma) (pCi/l +/- 2 sigma)

STATION DATE Sr-89 Sr-90 H-3 H-3 SA-ES F-llAl 6-03-78 0.07+/-0.07 0.19+/-0.04 127+/-71 227+/-79 11-03-78 to <0.3 <0.1 88+/-55 241+/-73 11-09-78

""-J co SA-ES F-12Cl .6-03-78 <0.1 0.22+/-0.04 169+/-81 466+/-72 11-02-78 to <0.1 0.25+/-0.04 69+/-55 238+/-73 11-06-78 SA-ESF-7El 6-02-78 0.11+/-0.08 0.29+/-0.04 <75 403+/-71 11-02-78 to <0.2 0.22+/-0.07 <57 255+/-73 11-09-78

Sr-89 results are decay corrected to sample stop date.

TABLE C-27 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND GAMMA EMITTERS** IN FOOD PRODUCTS Results in Units of pCi/g(wet) +/- 2 sigma STATION NO. DATE SAMPLE TYPE K-40 Sr-89 Sr-90 SA-FPV-2El 5-14-78 Asparagus 2.9+/-0.3 0.009+/-0.007 <0.007 SA-FPV-2El 8-07-78 Peppers 1.9+/-0.2 <0.006 <0.004 SA-FPV-15El 8-15-78 Corn 2.5+/-0.3 <0.006 0.007+/-0.003 SA*FPV-5Fl 8-07-78 Tomatoes 1.7+/-0.2 <0.006 0.003+/-0.002 SA.:..FPV-lGl 8-01-78 Peppers 1.1+/-0.1 + +

8-01-78 Tomatoes 0.93+/-0.09 <0.005 0.002+/-0.002

'-I l.O 8.:.14-78. Corn 2.2+/-0.2 <0.004 <0.003 8-21-78 Cabbage 1.4+/-0.1 <0.01 0.021+/-0~005 8-21-78 Cucumbers 1.2+/-0.1 <0.006 0.010+/-0.003 8-21-78 Eggplant 1. 7+/-0.2 <0.005 <0.003 SA-FPV-1G2 8-14-78 Zucchini 0.9+/-0.1 <0.006 0.006+/-0.003 SA-FPV-3H4 8-07-78 Peppers 1.0+/-0.1 <0.005 <0.003 8-07-78 Tomatoes 1.1+/-0.1 <0.005 0.003+/-0.002 8-14-78 Corn 1.9+/-0.2 <0.006 <0.004 8-21-78 Eggplant 1.6+/-0.2 <0.004 <0.003

Sr-89 results are decay corrected to sample stop date.

- All other gamma emitters searched for were <MDL; typi'cal MDLs are given in Table C-30.

+ Sample lost during analysis.

TABLE C-28 CONCENTRATIONS OF STRONTIUM-89 AND -90* AND GAMMA EMITTERS** IN MEAT, GAME, AND BOVINE THYROID Results in Units of pCi/g(wet) +/- 2 sigma STATION NO. DATE SAMPLE TYPE K-40 Sr-89 Sr-90 SA-GAM-4Dl 3-10-78 Muskrats 2.7+/-0.3 0.3+/-0.1 0.39+/-0.08 SA-GAM-1101 3-09-78 to Muskrats 2.2+/-0.2 0.18+/-0.08 0.25+/-0.05 3-12-78 co SA-GAM-1101 12-25-78 C) to Muskrats 2.3+/-0.2 0.2+/-0.1 1. 56+/-0.08 12-26-78 SA-GAM-3El 12-23-78 to Muskrats 2.7+/-0.3 0.1+/-0.1 0.46+/-0.06 12-24-78 SA-FPB-14Fl 10-03-78 Beef 1. 7+/-0. 2 SA-THB-14Fl 10-03-78 Beef Thyroid 0.6+/-0.4

Radiostrontium performed on muskrat bones only. Sr-89 results are decay corrected to sample stop date.

- All other gamma emitters searched for were <MDL; typical MDLs are given in Table C-30.

TABLE C-29 CONCENTRATIONS OF GAMMA EMITTERS* IN FODDER CROP SAMPLES Results in Units of pCi/g(dry) +/- 2 sigma STATION SAMPLE NUMBER DATE TYPE Be-7 K-40 Ru-106 Sb-125 Cs-137 Ce-144 SA-VGT-2F4 9-15-78 Green Chop to and 20+/-2 <0.3 <0.04 <0.1 9-25-78 Silage Mix ~

SA-VGT-5Dl 9-24-78 Grass 1.1+/-0.4 19+/-2 <0.3 <0.07 0.06+/-0.04 <0.2 SA-VGT-5F2 9-24-78 Corn Sil age 11+/-1 <0.4 <0.05 <0.1 SA-VGT-13E3 9-25-78 Corn Silage 4.8+/-0.7 <0.4 <0.05 <0.2 co SA-VGT-15Fl 9-25-78 Sil age 0.8+/-0.5 4.3+/-1.0 <0.3 <O.l <0.04 <0.3 SA-VGT-3Gl 9-25-78 Corn Silage 6.5+/-0.7 <0.3 <0.04 <0.1 SA-VGT-3Gl 9-25-78 Grass 20+/-2 <0.4 <0.04 <0.3 SA-VGT-14Fl 9-26-78 Grass 4.3+/-0.5 14+/-1 0.4+/-0.4 0.12+/-0.09 0.10+/-0.06 0.7+/-0.2 SA-FPG-501 10-23-78 Soybeans 12+/-1 <0.2 <0.02 <0.07 SA-FPG-3El 10-22-_78 Soybeans 11+/-1 <0.2 <0.02 <0.07 SA-FPG-3Gl 10-21-78 Soybeans 13+/-1 <0.2 <0.02 <0.07

. SA-FPG-15Fl 11-11-78 Soybeans 14+/-1 <0.2 <0.02 <0.07

All other garrma emitters searched for were <MDL; typical MDLs are given in Table C-30.

Those nuclides not searched for are indicated by a dash (-).

TABLE C-30 TYPICAL MDLs FOR GAMMA SPECTROMETRY*

SURFACE AIR WELL/POTABLE FOOD FODDER WATER FISH SEDIMENT PART! CULATES PRECIPITATION WATER MILK PRODUCTS CROPS GAME NUCLIDES (pCi/l) (pCi/g) (pCi/g) ( 10-3pCi /rn 3 ) (pCi/l) (pCi/l) (pGi/l) (pCi/g-wet) ( pCi I g-dry) ( pCi /g-wet)

Na-22 0.5 0.006 0.02 0.2 0.5 0.5 0.9 0.003 0.05 0.003 K-40 7 4 10 6 Cr-51 3 0.03 0.1 2 4 3 5 0.02 0.3 0.06 Mn-54 0.5 0.005 0.02 0.3 0.5 0.5 0.8 0.003 0.04 0.006 Co-58 0.5 0.005 0.02 0.2 0.5 0.5 0.9 0.003 0.04 0.005 Fe-59 1 0.01 0.04 0.4 0.8 0.8 2 0.02 0.04 0.02 Co-60 0.6 0.01 0.02 0.3 0.6 0.5 0.9 0.01 0.05 0.01 co Zn-65 1 0.01 0.04 0.5 1 1 2 0.02 0.1 0.02 N

ZrNb-95 0.4 0.005 0.04 0.5 1 0.4 0.8 0.003 0.04 0.005 Mo-99 3 0.03 0.1 1 3 3 5 0.02 0.3 0.04 RuRh-106 4 0.04 0.2 3 4 4 7 0.03 0.4 0.09 Ag-llOm 0.4 0.005 0.05 0.6 1 0.4 0.8 0.003 0.04 0.005 Te-129m 7 0.07 0.3 3 7 7 10 0.1 0.3 0.4 I-131 0.4 0.004 0.02 0.2 0.4 0.4 0.6 0.002 0.04 0.004 Te-132 0.3 0.003 0.02 0.2 0.5 0.3 0.5 0.002 0.03 0.006 I-133 0.5 0.005 0.02 0.2 0.5 0.5 0.7 0.003 0.02 0.01 Cs-134 0.6 0.006 0.03 0.3 0.6 0.5 1 0.01 0.03 0.01 Cs-136 0.6 0.008 0.03 0.3 0.7 0.6 1 0.01 0.06 0.01 Cs-137 0.5 0.005 0.02 0.5 0.5 0.9 0.003 0.04 0.01 BaLa-140 0.5 0.004 0.03 0.4 0.5 0.6 0.8 0.002 0.02 0.03 Ce-144 2 0.02 0.1 3 2 2 0.02 0.07 0.03 Ra-226 0.8 0.008 0.5 0.8 0.9 1 0.02 0.07 0.02 Th-232 2 0.02 1 2 2 3 0.01 0.2 0.02

At time of analysis.

Dash (-) indicates a positive concentration was measured in all samples analyzed.

APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES 83

GROSS ALPHA ANALYSIS OF SAMPLES Total Water (A0)

A 250 ml aliquot of the sample is evaporated to dryness on a hot plate in a preweighed, 211 X 1/4 11 ringed planchet, allowed to cool, and reweighed, 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 sample of distilled water is evaporated in the same manner and used as a blank.

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 for 100 minutes. The alpha activity per unit volume is calculated from the volume of air filtered. An unused filter is used as a blank.

Calculation of results and two sigma error RESULT =

(pCi/vol) [

C(s+b)

T(s+b) T(b) l fill_. x 1 2.22 x _l_ x E

1 v

x 1 TF

-NC(s+b) + fill_ 'x 1 x _1_ x - 1 1 2 SIGMA ERROR = x (pCi/vol) T(s+b) 2 T(b) 2 2.22 E v TF where:

C(s+b) = gross counts of sample C(b) = counts of blank E = fractional Pu-239 counting efficiency T(s+b) = number of minutes sample was counted T(b) = number of minutes blank was counted v = volume of aliquot utilized TF = transmission factor (based on net weight of sample in counting planchet)

Calculation of minimum detectable level (MDL)

The detection limit is assumed to be exceeded when the counting result is different from the blank reading by at least three times ~he standard devia-tion of that background.

MDL = 3-Vc{b) x 1 x 1 x ' 1 1 x

(pCi/vol) T(b) 2.22 E v TF where:

C(b) = blank counts T(b) = background counting period TF = transmission factor v = volume of aliquot utilized E = fractional Pu-239 counting efficiency 85

GROSS BETA ANALYSIS OF SAMPLES total Water (B0)

A 250 ml aliquot is evaporated to dryness on a preweighed, 2" 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 sample of distilled water is evaporated in the same manner and used as a blank.

Air Particulates (BD)

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 for 20 minutes. The beta activity is calculated from the volume of air filtered. An unused filter paper is used as a blank.

Calculation of results and two sigma error RESULT = C(s+b)

[ T(s+b)

_ illl]x 1 x -1 x _1_ x 1 (pCi/vol) T(b) 2.22 E v TF 2 SIGMA ERROR = ~C(s+b) + fi.!U_ x 1 x x 1 x _1_

(pCi/vol) T(s+b) 2 T(b) 2 2.22 E V TF where:

C(s+b) = gross counts of sample C(b) = counts of blank E = fractional Sr Y-90 counting efficiency T(s+b) = number of minutes sample was counted T(b) = number of minutes blank was counted v = volume of aliquot utilized TF = transmission factor Calculation of minimum detectable levels (MDLs)

The detection limit is assumed to be exceeded when the counting result for the sample is different from the blank reading by at least three times the standard deviation of that background.

MDL = 31/C(b) x 1 x-1-x_l_x 1

{pCi /vol) T(b) 2.22 E v TF where:

C(b) = blank counts T(b) = background counting period v = volume of aliquot utilized E = fractional Sr Y-90 counting efficiency TF = transmission factor 86

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 pf 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.

Aqueous and Organic .Fraction of Milk or Organic Solids (H3, H4)

A carefully measured aliquot of a food product 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).

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. Permanagate 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.

[ C(s+b) 1 1 1 RESULT = - fU?l jx x x (p1cocuries/l) T(s+b) _T(b) 2.22 E v of water) 2 SIGMA ERROR = 21)c(s+b) + fU?l x 1 x -1 x 1 (picocuries/l T(s+b ) 2 T(b) 2 2.22 E v of water) where:

C(s+b) = gross counts of sample C(b) = counts of blank E = fractional H-3 counting efficiency T(s+b) = number of minutes sample was counted T(b) = number of minutes blank was counted v = volume (ml) of distillate counted 87

Calculation of minimum detectable levels (MDLs)

The detection limit is assumed to be exceeded when the counting result is different from the blank reading by at least three times the standard deviation of that background.

1 1 1 MDL = 2.22 x -E- xv (picocuries/l) where:

C(b) = blank counts T(b) = background counting period v = volume of distillate counted E = fractional H-3 counting efficiency 88

ANALYSIS OF SAMPLES FOR STRONTIUM-89 AND -90 Total Water lT~, S~)

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 realized by at least two precipitations of strontium nitrate in concentrated nitric acid. Additional carbonate precipitations and barium chromate separations are performed to remove suspected interferring 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 eluted liquid or dissolved ash 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 carbonate precipitations and barium chromate separations are performed to remove suspected interferring 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 and Shells (SS, 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 solubized 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 stronti.um nitrate in concentrated nitric acid. Addi-tional carbonate precipitations, iron rare earth hydroxide scavenging, and barium chromate separations is performed. 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 concentrated HCl before *drying. Stable strontium carrier is added to the dissolved sample to facilitate 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. Addi-tional carbonate precipitations and barium chromate separations are performed.

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 proportional counter. After about 14 days, the sample is recounted, 89

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 processed with each batch of samples.

Organic Solids (S8, T8)

A 250 g portion of the sample is ashed, and a 25 g portion is then dissolved in concentrated acid. Stable strontium carrier is added to the solubized 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. Addi-tional carbonate precipitations, iron rare earth hydroxide scavenging, and barium chromate separations may be performed depending on sample type and suspected inter-ferring nuclides. The purified strontium is connected 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.

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 concentration and purification is ultimately realized by at least two precipitations of strontium nitrate in concentrated (68%) nitric acid.

Additional hydroxide 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.

Calculation of results and two sigma error A(Sr-90 = Z C 1 Total - C 1) Bk ) - (C(2) Total - C(2) Bk )

pCi/vol. or wt. K vol. /wt. eff Sr-90 yield time 2.22)

ERROR Sr- 90 = z/z 2(C(l) Total + C(l) Bkg) + C(2) Bkg + C(2) Total 2

(pCi/vol. or wt.) VK (vol. /wt.) {eff Sr-90) (yield) (time) (2.22)

A(Sr- 8g) = F(C(l) Total - C(l) Bkg) + H(C(2) Total - C(2) Bkg) : - .693T(4)

(pCi/vol. or wt.) (vol./wt.) (eff Sr-89) (time) (yield) (2.22) e 52.7 2 2 ERROR Sr-89 = 2V'F (C(l) Total + C(l)- Bkg)

- + H (C(2) Total + C(2)

- Bkg)

- * - 693T(4)

T _ ___,,___,_

(pCi/vol. or wt.) (vol./wt.) (eff Sr-89) (yield) (time) (2.22) e 52.7 where:

Sr-89 1 = Sr-89 counts on first count Sr-90 = counts of Sr-90 90

Y-9.0 1 = counts of Y-90 on first count Y-90 2 = counts of Y-90 on second count cl to ta 1 = Sr-89 1 + Sr-90 + Y-90 1 + B1 = ClT c2 total = Sr-89 2 + Sr-90 + Y-90 2 + B2 = C2T c1 BKG = BKG counts on first count = ClB c2 BKG = BKG counts on second count = C2B

-0.693T3 z = .e 52.7 days K = z (E1/R+l) 1 - E2/R R = eff eff Sr-90 Y-90 E

F = 1 - - z - Z(-1)

K KR H = ( _1 ) + El K KR ti = Tel - tsep hours t2 = tc2 - tsep days t3 = tc2 - tc 1 days t4 = tsampling date - tsep days 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

- .693T1 )

E1 = (1 - e - - - - -

64.0 hrs.

-0.693t2 E2 = (1 - e - - - - -

2.667 days Calculation of minimum detectable levels (MDLs)

Due to the method of calculating 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.

91

ANALYSIS OF SAMPLES FOR IODINE-131 Milk or Water (I0)

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 an average recovered volume of 13.2 ml. 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.

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 The spectrum obtained is smoothed to eliminate spurious statistical noise. The presence of Iodine-131 is identified by the presence of a 364 Kev peak. The peak is fitted with a Gaussian curve and the net counting rate above the base-line projection is calculated. This counting rate is converted to activity in curie uni ts, making allowance for counting efficiency and photon abundance *.

A PDP-11 computer program is used for spectrum analysis.

RESULT = [C(s+b 1 x-1-x_l_x_l_

T s+b -.-22._.._ E V Y (pCi/vol) at time of analysis 2 SIGMA ERROR = 2yc(s+b) .+ £U?J.. x 1 x _1_ x _l_ x _l_

( pCi /VO l) 2 T(s+b) T(b) 2 2.22 E v y at time of analysis where:

C(s+b) = gross counts in channels containing I-131 peak C(b) = background counts in channels containing I-131 peak T(s+b) = number of minutes aliquot was counted T(b) = number of minutes blank was counted' E = I-131 counting efficiency v = volume of aliquot utilized y = chemical yield of iodine (for milk or water) 92

ANALYSIS OF SAMPLES FOR IODINE-131 (cont.)

Calculation of minimum detectable level (MDL)

MDL = 3'J 6 x Cr x --,.-.....,1 2.22

_ x _1_ x _1_ x _1_

E V Y Ti)Ci/vol) at time of analysis where:

Cr = number of counts in the channel that would have been the centroid if a peak were there.

E = I-131 counting efficiency v = volume of aliquot utilized *

y. = chemical yield of iodine (for milk or water) 93

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. Distilled water is used as a blank.

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, G8)

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 NaI(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. Identified individual peaks are fitted with Gaussian curves and the net counting rate above the baseline projectirin is calculated. This counting rate is converted to activity in curie units, making allowance for counting efficiency and photon abundance. A PDP-11 computer program was introduced for spectrum unfolding.

RESULT= [ C(s+b) - C(b)l 1 x-1-x 1 x 1 T(s+b) TT6T x 2.22 E -v- Gamma Ab (pCi/vol or wt.)

2 SIGMA ERROR = 2'/c(s+b) + C(b) 2 x 1 x x -1 x 1 T(s+b) T(b) 2 2.22 E v Gamma Ab (pCi/vol or wt.)

94

l where:

C(s+b) = gross counts in channels containing peak of nuclide being quantized C(b) = background counts in channels containing peak of nuclide being quantized T(s+b) = number of minutes aliquot was counted T{b) = number of minutes blank was counted E = measured from efficiency curve for a given energy Gamma Ab = fractional gamma abundance v = volume or wt. of aliquot utilized Calculation of minimum detectable levels (MDLs) 1 x-1-' _l_x 1 MDL = 3\f 6 x Cr x 2.22 E x V Garrrna Ab (pCi/vol or wt) where:

Cr = number of counts in the channel that would have been the centroid if a peak were there.

Eff = measured from efficiency curve for a given energy Gamma Ab = fractional gamma abundance {specific for each nuclide) v = volume or wt. of aliquot utilized 95

ANALYSIS OF WATER SAMPLES FOR POTASSIUM-40 BY AA (E0)

Sample preparation An aliquot sample size of 100 ml is filtered. The concentration of potassium is determined spectrophotometrically 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.

Calculation of results (picocuries/liter) = SR2 Rl X K Where:

\

S = Standard concentration in micrograms/ml Rl = Reading of sample R2 = Reading of standard K = Specific activity of K-40 per unit weight of potassium pCi/µg 96

ENVIRONMENTAL DOSIMETRY (D0)

Measurement Techniques Each dosimeter utilized is a capillary tube containing calcium sulfate (Tm) powder as the 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 intransit dose.

Following the pre-designated exposure period the TLD is heated with hot gas and the luminescense measured with a TLD reader. Data are normalized to standard machine conditions by correcting.machine settings to zero before read out. Data are corrected for in-transit dose using a set of TLDs ~hi ch 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 .: 0.9555 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) - IO x f§B. - DO(i) CF(i) x 0.955 mrad ITO = NET(siteO) - NET(rmcO) x D siteO)

D(rmcO NET TLD(i) = gross TLD(i) - ITO n

2=NET TLD( i) i=l x Df stf)

AVG = n D EX ERROR (g 53 CL) = t(n-l) x sigma NET TLD(i) x D~ST))

n D EX 97

ENVIRONMENTAL DOSIMETRY (cont.)

where: -

gross TLD(i) = individual TLD reading corrected to standard instrument conditions TLD(i) = gross reading of dosimeter i NET TLD(i) = net dose obtained during exposure period in the field IO = instrument zero LS = instrument-light source reading DO(i) = zero for dosimeter, i CF( i) = calibration factor for dosimeter i ITO = in-transit dose NET(site)O = mean of n dosimeters in site lead shield NET(rmc)O = mean of n dosimeters in RMC lead shield D(siteO) = exposure period of siteO D( rmcO) =

AVG = mean exposure per standard exposure period at a given station n = nµmber of readings D(EX) = days expo'sed 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)

LSN -- light source normal reading ERROR = the 95% confidence limit error of AVG 98

APPENDIX E

SUMMARY

OF INTERLABORATORY COMPARISONS 99

INTER-LABORATORY COMPARISONS: GROSS ALPHA AND BETA IN WATER (pCi/liter) and AIR PARTICULATES (pCi/Sample)

TABLE E-1 RMC EPA All Participants DATE RMC # ISOTOPE "'IEAN MEAN+/-S.D. MEAN+/-S.D.

JANUARY 89840 alpha 7+/-1 7+/-5 7+/-3 1978 Water beta 43+/-1 39+/-5 37+/-6 MARCH 90819 alpha 10+/-2 11+/-5 12+/-3 1978 APT beta 40+/-2 38+/-5 40+/-4 MARCH 90820 alpha 16+/-2 20+/-5 ?

1978 Water beta 30+/-3 29+/-5 ?

APRIL 91888 alpha 19+/-2 20+/-5 20+/-7 1978 Water beta 58+/-1 59+/-5 57+/-10 MAY 92636 alpha 14+/-2 13+/-5 13+/-4 1978 Water beta 25+/-1 18+/-5 20+/-4 JUNE 93393 alpha 10+/-1 10+/-5 11+/-2 1978 APT beta 40+/-1 36+/-5 39+/-3 JULY 94118 alpha 25+/-2 22+/-6 17+/-6 1978 Water beta 42+/-1 30+/-5 32+/-7 SEPTEMBER 96793 alpha 2+/-1 5+/-5

1978 Water beta 13+/-1 10+/-5

OCTOBER 98135 alpha 17+/-1 *

1978 Water beta 41+/-1 *

NOVEMBER 98577 alpha 12+/-1 11+/-5

1978 Water beta 29+/-1 26+/-5 *

Full EPA report not available.

101

INTER-LABORATORY COMPARISONS: TRITIUM IN WATER A11 results i.n pCi/l iter TABLE E-2 RMC EPA All Participants DATE RMC# MEAN MEAN+/-S.D. MEAN+/-S.D.

APRIL 91628 2180+/-144 2220+/-349 2198+/-267 1978 Water APRIL 91888 <59 0 1978 Water JUNE 93135 2230+/-147 2270+/-249 2259+/-252 1978 Water AUGUST 95018 1168+/-49 1230+/-330 1245+/-209 1978 Water 102 I

INTER-LABORATORY COMPARISONS: STRONTIUM-89 AND STRONTIUM-90 TABLE E-3 RMC EPA All Participants DATE RMC# ISOTOPE UNITS MEAN MEAN+/-S.D. MEAN+/-S.D.

MARCH 90337 Sr-89 Sample lost during analysis 1978 Food Prod. Sr-90 MARCH 90819 Sr-90 pCi/sample 4+/-1 8+/-1.5 7+/-2 1978 APT APRIL 91888 Sr-89 pCi/l 16+/-1 21+/-5 21+/-3 1978 Water Sr-90 pCi/l 8+/-1

10+/-1.p 9+/-1 APRIL 91948 Sr-89 pCi/l 82+/-24 101+/-5 92+/-10 1978 Mi 1k Sr-90 pCi/l <10 9+/-1.5 9+/-2 JUNE 93381 Sr-90 pCi/sample 8+/-1 9+/-1.5 9+/-2 1978 APT JULY 93535 Sr-89 pCi /kg 38+/-4 39+/-5 36+/-4 1978 Food Prod. Sr-90 pCi/kg

22+/-1 15+/-1.5 17+/-4 JULY 94132 Sr-89 pCi/l 26+/-1 41+/-5 35+/-9 1978 Milk Sr-90 pCi/l 41+/-4 49+/-2.5 46+/-9 OCTOBER 98135 Sr-89 pCi/l 5+/-1 *

1978 Water Sr-90 pCi/l 5+/-1 * *

Full EPA report not available.

103

INTER-LABORATORY COMPARISONS: GAMMA Results reported in pCi/liter for milk and water, pCi/sample for air particulates, and pCi/kilogram for food products except K which is reported in mg/kilogram TABLE E-4 RMC EPA All Participants DATE RMC # ISOTOPE MEAN MEAN+/-S.D. MEAN+/-S.D.

FEBRUARY 90047 Cr-51 <17 0 1978 Water Co-60 38+/-1 34+/-5 33+/-5 Zn-65 29+/-1 29+/-5 29+/-5 Ru-106 36+/-1 36+/-5 39+/-9 Cs-134 52+/-1 52+/-2 49+/-6 Cs-137 2 0 MARCH 90337 I-131 70+/-5. 74+/-5 72+/-7 1978 Food Prod. Cs-137 52+/-1 41+/-5 39+/-4 Ba-140 <4 0 K 4100+/-200 2930+/-147 2823+/-306 MARCH 90819 Cs-137 36+/-10 22+/-5 23+/-5 1978 APT APRIL 91638 Cr-51 <15 0 1978 Water Co-60 46+/-2 49+/-5 49+/-4 Zn-65 59+/-3 59+/-5 58+/-9 Ru-106 83+/-8 113+/-6 100+/-19 Cs-134 61+/-2 74+/-5 72+/-7 Cs-137 <2 0 APRIL 91888 Co-60 17+/-1 20+/-5 21+/-3 1978 Water Cs-134 8+/-1 15+/-5 19+/-5 Cs-137 <1 0 APRIL 91948 I-131 66+/-3 82+/-5 82+/-9 1978 Milk Cs-137 23+/-2 23+/-5 25+/-3 Ba-140 <3 0 K 1510+/-50 1500+/-75 1541+/-102 JUNE 93173 Cr-51 90+/-12 102+/-5 99+/-19 1978 Water Co-60 19+/-2 22+/-5 22+/-3 Zn-65 52+/-5 54+/-5 51+/-7 Ru-106 43+/-4 58+/-5 56+/-12 Cs-134 20+/-2 22+/-5 21+/-4 Cs-137 31+/-3 30+/-5 32+/-4 JUNE 93.393 Cs-137 16+/-2 18+/-5 20+/-5 1978 APT JULY 93!)35 I-131 71+/-3 83+/-5 82+/-6 1978 Food Prod. Cs-137 40+/-2 37+/-5 38+/-4 Ba-140 <1 0 K 2507+/-62 2800+/-140 2744+/-205 104

INTER-LABORATORY COMPARISONS: GAMMA (cont.)

Results reported in pCi/liter for milk and water, pCi/sample for air particulates, and pCikilogram for food products except K which is reported in mg/kilogram TABLE E-4 RMC EPA All Participants DATE RMC # ISOTOPE MEAN MEAN+/-S. D. MEAN+/-S.D.

JULY 94132 I-131 <3 0 1978 Milk Cs-137 48+/-3 53+/-5 54+/-4 Ba-140 <2 0 K 1359+/-29 1560+/-78 1547+/-116 AUGUST 94903 Cr-51 106+/-11 105+/-5 106+/-21 1978 Water Co-60 29+/-1 27+/-5 27+/-4 Zn-65 58+/-5 62+/-5 61+/-11 Ru-106 48+/-6 41+/-5 41+/-11 Cs-134 8+/-1 9+/-5 10+/-2 Cs-137 15+/-1 15+/-5 16+/-3 OCTOBER 97770 Cr-51 152+/-18 *

1978 Water Co-60 29+/-1 *

Zn-65 85+/-2 *

Ru-106 42+/-3 *

Cs-134 25+/-1 *

Cs-137 131+/-1 *

OCTOBER 98135 Co-60 <2 *

1978 Water Cs-134 9+/-1 *

Cs-137 13+/-1 * *

Full EPA report not available.

105

APPENDIX F SYNOPSIS OF DAIRY AND VEGETABLE GARDEN SURVEY 107

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 were 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 was performed to a distance of one mile. No vegetable gardens were found in this area.

109

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