ML19031A145

Artificial Island Radiological Environmental Monitoring Program, 1977 Radiological Report, January 1 to December 31, 1977

ML19031A145
Person / Time
Site:	Salem
Issue date:	04/30/1978
From:	Public Service Electric & Gas Co, Radiation Management Corp
To:	Office of Nuclear Reactor Regulation
References
Download: ML19031A145 (93)

Text

RMC -TA-78-04A t fU.ES ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1977 RADIOLOGICAL REPORT JANUARY 1 TO DECEMBER 31, 1977 Prepared For PUBLIC SERVICE ELECTRIC AND GAS COMPANY By RADIATION MANAGEMENT CORPORATION APRIL 1978

RMC-TR-78-04A 1977 RADIOLOGICAL REPORT

~ '. -

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM January 1 to December 31, 1977

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Prepared for Public Service Electric and Gas Company by Radiation Management Corporation April 1978

• This report is the completed version of the original report issued on an interim basis in March 1978. All analytical data for the 1977 program are included in this report.

TABLE OF CONTENTS PAGE

SUMMARY

........ ...... ..* .. .................... 1 INTRODUCTION ........... ................................. -* ... 2.

THE PROGRAM ************************************eeOOOC18CIOOOO 3 Objective ................................................. 3 Sample Collection ........................... 3 Data Interpretation ..................................... 5 RES UL TS AND DISCUSSION ....................................... 6 Aquatic Environment ******************** Cl **************** 6 Atmospheric Environment '* ...................................

11 Terrestrial Environment ................... 15 Direct Ra di ati on .......................................** .. 19 CONCLUSIONS .................................................. 22 REFERENCES ................................................... 23 APPENDIX A PRO GRAM

SUMMARY

................................. 25 APPENDIX B SAMPLE DESIGNATION &LOCATIONS ................... 35 APPENDIX C - 1977 DATA TABLES ................................ 43 i

LIST OF FIGURES NUMBER PAGE

1. Average Concentrations of Tritium in the Delaware River in the Vicinity of Artificial Island, 1973 through 1977 7

2. Average Concentrations of Beta Emitters and Potassi um-40 in the Delaware River in the Vicinity of Artificial Island, 1973 through 1977............................................ a

3. Comparison of Average Concentrations of Beta Emitters in Precipitation and in Air Particulates, 1973 through 1976 12

4. Average Concentrations of Beta Emitters in Precpiitation and in Air Particulates in the Vicinity of Artificial Isl*and, 1977 ............... *.*-*............................. *13

5. Average Concentrations of Iodine-131 in Milk in the Vicinity of Artificial Island, May 1974 through December 1977 * . . * . . . . 17

6. Average Ambient Radiation Levels from Monthly and Quarterly TLDs in the Vic_inity of Artificial Island, 1973 through 19 76 ................................................ ~ . . . . . . . 20

7. Ave.rage Ambient Radiation Levels from Monthly and Quarterly TLDs in the Vicinity of Artificial Island, 1977 ......... ~... 21 ii

SUMMARY

During the peri ad January 1 to. December* 31, 1977, Radiation *Management Corporation participated in. the Operational Radiological Environmental Monitoring Program conducted.by Public Service Electric and Gas Cor:npany*at

• Artificial Island, New Jersey. Salem.Nu'clear Generating Station. (SNGS)

• Unit.#1 becam~ critical on December 11, 1976, thereby initiating the operational phase of the Radiological Environmental Monitoring Program (REMP).

This program was designed t.o identify and quantify concentrations of

• radi oacti vi ty in various en vi ronmenta 1 me di a and to quantffy 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 Envi ronmenta 1 Technical Spec; fi cations, and provide background data for SNGS Unit #2 and Hope Creek Generating Station. 'This report presents the results of thermo luminescent dosimetry *and radiochemical*

analyses of environmental samples collected during 1977.' . **. . ..

A total of 3592 analyses were performed on 1475 enVir~nmental samples during the perjod covered by this report. Samples from the aquatic environment,

. ir;u~luded surface water, edible and.*prey fish, hardshell crabs, benthos, and sediment. Air particulates, air iodine, and precipitation samples.were taken from.the atmospheric environment. Samples from the terrestrial.

environment include well water, potable water, milk, fruits, vegetables,,'.*

beef, fodder crops, game, and soil. 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 s*imilar' to those found during the. peroperational phase of th1s progr.am~

• In .general *:

no significant differences were observed between indicator and control stations. 1 Some media showed the after effects of the Peoples Republic of Chfoa's . **

• nuclear test of September 17, 1977. It is concluded that the radiological characteristics of the environment around Artificial Island were not affected by SNGS Unit #1-during 1977.

1

I NT RO DU CTI ON 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), and 1975(3). On December 11, 1976, SNGS Unit #1 became critical, 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). This report summarizes the operational period between January 1 and December 31, 1977. Interpretation of the data and conclusions are also presented.

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

Two of the reactors will be part of the Salem Nuclear Generating Station.

Unit #1 is a l090 t+le pressurized water reactor ( PWR), and is presently operational. un*it #2, now under construction, will consist of an 1115 Mt.le 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, Sal em County, New Jersey. The environment around Artificial Isl and 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. (6)

Mo.re. spedfic information on the demography, hydrology, meteorology, and* land

• use characteristics of the local area may be found in the Environmental

.Report (6), Environmental Statement (7), and the Final Safety Analyses Report

• * (Uni ts 1 and *2). for SNGS (8).

2 l_

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 for comparison with results from the preoperational phase. Differences between these periods were examined statistically to determine whether any station effects exist. These observations were based on the magnitude and fluctuations of radioactivity levels determined in the preoperational phase.

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. *ro,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 .

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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 1977 REMP. Results of the four year preoperational program have been summarized in reference 4 for purposes of comparison with subsequent operational reports.

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.

The operational REMP includes samples from the aquatic, atmospheric, and terrestrial environments, as well as TLDs to measure ambient radiation.

Samples of various media were selected to obtain data for the evaluation of the radiation dose to man and other organisms. Sample types were 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.

Sampli.ng 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.

All samples from the aquatic environment were collected by Ichthyological Associates and shipped to RMC for analysis. Surface water samples were collected in new polyethylene bottles. Sample containers were rinsed twice with the sample medium prior to collection. Edible and prey fish were taken by net, sealed in a bag or jar and shipped frozen. Blue hardshell crabs were taken with wire crab traps, sealed in plastic jars and shipped fresh.

Benthos and sediment were taken with a bottom grab sampler.

The. atmospheric env.ironment was examined by analyzing air particulate filters, iodine charcoal cartridges, and precipitation. 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 adsorption 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 precipitation 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.

,Jhe terrestrial environment was examined by analyzing samples of well water, potable water, milk, beef, food products, fodder crops, bovine thyroid, and soil.

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. Milk samples were taken in new polyethylene bottles and shipped fresh. Food products, fodder crops, game, bovine thyroid, and soil samples were taken and sealed in plastic bags or jars .. Perishable samples were frozen at the time of sampling without any prevervatives.

• Ambient radiation levels in the environs were measured with energy-compensated CaS04(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.

Appendix A describes and summarizes, in the format of table 5.6-1 of the Salem ETS, the entire operational program as performed in 1977. 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 a,ssurance program designed to maximize confidence in the analytical procedures used. The

• analytical methods and quality control procedures utilized in* this program are described in an RMC publicatian (9). 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. The analytical data generated during the program also are routinely evaluated by the RMC project leader who is the liaison with Public Service Electric and Gas Company personnel. Several factors are important in the interpretation of the data. These factor&

are discussed here to avoid repetition in sections that follow.

Grab Sampling is a useful and acceptable procedure for taking environmental samp.l es of a medium in which the concentration of radionucl ides is expected to vary slowly with time or where intermittent sampling is deemed s.ufficient to esta*blish 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.

It is characteristic of environmental monitoring data that many results occur at or below the minimum detectable level (MDL), as defined in reference 9.

• For reporting and calculation of averages, any result occurring a.t or below the minimum detectable level is considered to be at that level. Averages obtained using this method are.therefore biased high.

• 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. ~~hen a group of data was composed of mainly (>50%) MDL values, averages were not calculated.

5

RESULTS AND DISCUSSION The analytical results of the 1977 REMP samples are typic_ally divided into four categories: Aquatic, Atmospheric, Terrestrial, and Direct Radiation.

The individual samples and analyses within each category display the unique radiological characteristics of that type of environment.

• The analytical results for the 1977 REMP samples are summarized in appendix A. The data for individual samples are presente~ i_!l_~~~endix C.

• A census of milk-producing animals was conducted twice during 1977 as part of the REMP. These censuses indicated no new dairy operations within 5 miles of SNGS. They also indicated some slight fluctuations in the number of cows*

on individual farms and that one farm ceased dairy operations.

Aquatic Environment The aquatic environs of Artificial Island comprise a portion of the Delaware.

River-Bay estuary. Usage by man and the physical characteristics of this system have been described by Thomann {10). Ichthyological Associates is making continual ecological studies {11) of the estuary in the vicinity of Artificial Island. This information has been used in evaluating the aquatic portions of the REMP. The radiological characteristics of the aquatic environs of Artificial Island were studied by analyzing samples of surface water, edible fish, blue crabs, prey fish, benthos and sediment.

Sut-'f<ic*e Water "M<intnly surface water samples were taken at five locations in the Del aware estuary. One is downstream from the outfall *area, one is in the outfall area, and another is directly west of the outfa 11 area at the mouth of the Appoquinimink River. Two other stations are located upstream--one station is in the river and the other is in the Chesapeake and Delaware Canal.

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 gamma emitters.

Analysis of surface water for H-3 yielded an average concentration of 177 pCi/l and ranged from <80 to 460 pCi/l. These levels are similar to those measured in the preoperational program as shown in figure 1.

Gross alpha concentrations were generally below MDL, which ranged from 1.5 to 33 pCi/l. Only 2 of the 55 samples analyzed showed detectable gross alpha activity. Those results {2 and 14 pCi/l) were within the same range as the*

MDLs. Alpha activity may be expected in suspended solids from naturally occurring radionuclides especially during periods of high surfac~ runoff.

Gross beta concentrations ranged from 4.3 to 140 pCi/l and averaged 43 pCi/l.

Nearly all of the beta activity was contributed by K-40 {<7 to 170 pCi/l),

a natural component of salt and brackish waters, as illustrated in figure 2, comparing gross beta and K-40 concentrations in the Delaware River. Due to the flow rate variations and the tidal nature of the estuarine enviornment, large variations in the gross beta concentration were observed throughout the year. Much of this variation can be attributed to the tidal stage at the time of sampling.

6

AVERAGE CoNcENTRATIONS OF TRITILN IN DELAWARE EsTUARY WATERS IN THE VIcINilY OF ARTIFICIAL ISLAND 1973 THROUGH 1977 10000 . . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - .

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7

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Ganma spectrometric analysis of surfacewater samples showed.detectable*,'::::

concentrations of K-40 in 49 of 55 samples. The average K-40 concentration" *:

was 36 pCi/l and ranged from <7 to 170 pCi/l. Two additional gamma-emittirig 1 :

nu cl ides, Cs-134 and Cs-137, with concentrations of 0. 8 pCi /1 and 1. 2 pCi /1 <<

respectively, were observed in the February sample from control location 16Fl.

Cesium-137, which has randc;>mly occurred throughout the preoperational period,

• is associated with fallout from past nuclear weapons testing and can* be expected to occur periodically in the future *

.The Cs-134 result of 0.8+/-0.6 pCi/l is comparable to the minimum detectable level of 0.5 pCi/l for the other samples.* In addition; the sample was taken -

6.9 miles upstream of the site; and since the SNGS did not r*elease any cesium during February 1977 it can be concluded that the observed Cs-134 was not plant related. (12)

Levels of Sr-89 were below MDL (0.6 to 1.6 pCi/l) in all samples. Levels of detectable Sr-90 ranged from 0.3 to 0.7 pCi/l in 6 of the 20 samples~ The .

MDLs *values ranged from 0.4 to 0.9 pCi/l. The* maximum level of Sr-90. detected iri the preoperation~l program was 1.6 pCi/1.

Aquatic Organisms.

Biological samples from various levels of the human food chain were taken from the same stations as surface water samples. These included edible fish; blue crabs, *prey fish, and benthic organisms.

Edible fish samples (American Shad, alewife, etc.) were collected at three locations and analyzed for gamma emitters and tritium. Fish bones were analyzed for Sr-89 and Sr-90.

Ganma sp.ectrometry of these samples showed only K-40 at detectable levels.

This* nuclide was detected in all fish flesh samples at an average concentration of)~OO. pCi/kg-wet, which is typical for this naturally occurring nuclide.

Tritium analyses were performed on both aqueous and organic fractions* of the flesh *portions'of these samples. The average concentration of tritium was

• 131 pCi/1 for the aqueous fraction and 214 pCi/l for the organic fraction.

The observed results are essentially the sameas those found in surface water for the same period, indicating no biological accumulation of tritium.

All the bone. samples analyzed for Sr-89 were below mi'nimum detectable level *

(1.7 to 8.8 pCi/g-dry), with one exception. The June sample' from station llAl had a detectable level of 0.1 pCi/g-dry, which *is below the MDL of all the other samples. One of the four samples* analyzed for Sr-90 had a.detectable con~entration of 0.09 pCi/g-dry. This concentration is below* the MDL range (0.4 to 1.6 pCi/g-dry) of the other analyses and is similar to the other values.

Blue hardshell crabs were taken *at two locations with the edible portions being analyzed for gamma emitters, tr.itium and Sr-89 and-90. The shells were also analyzed for Sr-89 and-90.

9

Ganma spectrometry of the edible portions showed K-40 concentrations in all samples ranging between 2200 and 3300 pCi/kg-wet, with the average being 2800 pCi/kg-wet. One sample taken at control station 12Cl had a trace amount of Cs-137 (18 pCi/kg-wet).

Tritium analyses performed on the edible portions showed an average concentration of 206 pCi/l. No significant differences in H-3 levels were observed between samples, reflecting an equilibrium between the blue crabs and their estuarine environment.

Radiostrontium analyses on the flesh portions of the samples indicated no detectable concentrations of Sr-89, with the MDL ran9ing between 0.03 and 0.04 pCi/g-wet. Detectable concentrations of Sr-90 (0.006 pCi/g-wet) were observed in the August sample collected at both locations. This activity was similar to the Sr-90 MDL of the June samples, which were 0.007 and 0.008 pCi/g-wet.

The blue crab shell samples analyzed for Sr-89 showed detectable concentrations of 0.18 and 0.30 pC1/g-dry at station llAl during June and August. Detectable Sr-89 activity of 0.4 pCi/g-dry was also observed at control location 12Cl in the August sample. The June sample at the control location 12Cl was less than 0.1 pCi/g-dry. Therefore, the concentrations of Sr-89 observed at the indicator station (0.18 and 0.3 pCi/g-dry) are similar to those observed at the control location (<0.1 and 0.4 pCi/g-dry). All the shell samples contained Sr-90 concentrations ranging between 0.15 and 0.32 pCi/g-dry. Because strontium concentrations in skeletal structures, the shells of the crabs are expected to contain higher levels of radiostrontium than the flesh. Observable radiostrontium activity at both locations indicate that the probable source for the Sr-89 and-90 can be attributed to world-wide fa 11 out from nu cl ear weapons testing.

Small fish species (prey fish) which serve as a* primary food source. for larger edible species were sampled. Total samples (flesh and bones) were analyzed for gamma emitters, and Sr-89 and Sr-90. D.etectable concentrations of K-40 were found in all samples, averaging 2900 pCi/kg-wet, similar to the 2800 pCi/kg average for edible fish. Concentrations of Sr-89 were below the MDL (0.01 to 0.20 pCi/g-wet) in all but one sample. The detectable Sr.;..89 concentration was 0.13 pCi/g-wet, which is within the range of the MDL values of the other samples. Strontium-90 was detected in one of six samples. The detectable level in this sample (0.004 pCi/g-wet) also fell within the MDL range (0.004 to 0.04 pCi/g-wet) of the other samples. . .

Benthic organisms were collected at four locations and analyzed for Sr-89 and-90. Since only small *samples were available, analytical results vary considerably. Strontium-89 was detected in one of six samples. The detectable activity was 20 pCi/g-dry, which was between the MDL range (0.7 to 2370 pCi/g-dry) of the other samples. Two of six samples showed detectable Sr-90 concentrations of 0.1 pCi/g-dry and 0.3 pCi/g-dry. These detectable activities are below the MDL range (0.8 to 309 pCi/g-dry) of the other four samples.

The MDL for radiosttontium as required by the Environmental Technical Specifications for benthic organisms cannot be met in any of the samples due to the impracticality of obtaining a large sample size of benthic organisms.

10

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 *. The various fallout nuclides were observed intermittently at control stations as well as at indicator stations. With the exception of Cs-137, which ranged between 0.04 and O. 25 pCi /g-dry, no other fall out nuclide was detected in more than 20% of the samples. Manganese-54, with a detectable concentration of 0.02 pCi/g-dry at control location 12Cl, was the only nuclide observed in 1977 that was not detected during the preoperational period.

No Sr-90 was observed in any of the eight samples analyzed, with the MDL ranging between 0.03 and 0.06 pCi/g-dry.

All results observed in the aquatic samples analyzed in 1977 showed no apparent differences from results observed during the preoperational period.

Atmospheric Environment

The atmospheric environment in the vicinity of Artificial Island was examined.

by analyzing samples of air particulates, air iodine, and precipitation.

Air particulates were collected at eight stations, while air iodine cartridges were collected at seven locations~ Precipitation was also collected at .one of these locations - the Salem Substation.

• Air Particulates Weekly air particulate samples were analyzed for alpha and beta .emitters.

Quarterly composites of the weekly samples from each station were analyzed

-for Sr-89, Sr-90 and gamma emitters. Due to a temporary laboratory problem Sr-89 and-90 and gamma emitter analyses for the fourth quarter include only December samples. The results of these analyses and subsequent gamna emitter analyses of the October and November samples are included in this report.

Results of Sr-89 and-90 analyses for the October and November samples are

.available and are included in this report.

Of the 102 weekly air particulate samples (2 stations) analyzed for alpha emitters, 85 showed detectable c0ncentrations. The range of alpha activity was from <0. 0002. to O. 0026 pCi /m 3 and averaged 0. 0012 pCi /m3

• Weekly gross beta analyses showed concentrations ranging from 0.023 to 0.540 pCi/m3 , with the average for the 8 sampling stations being 0.144 pCi/nr.

In addition to normal seasonal fluctuations, increased activity was noted in early October and was directly attributed to fallout from the September 17 atmospheric nuclear weapons test. Figures 3 and 4 show the relation between gross beta and precipitation for the preoperational versus the operational periods, showing both seasonal and weapons-testing fluctuations.

11

FIGURE 3 AVERAGE CoNCENTRATIONS OF BETA EMITTERS IN PRECIPITATION AND IN AIR PARTICULATES IN 1HE VICINITY OF ARTIFICIAL ISLAND 1973 THROUGH 1976 10-3 pCi/m3

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Results of gamma spectrometry showed det~ctable level:s,_,q_f,several radionuclides, both naturally occurring and man-made (Be-7, K-40, Mn-54~ Cr-51, Co-58, Co-60, ZrNb-95, Ru-103, Ru-106, Sb-125, 1-131, Cs-137, BaLa-140, Ce-141, and Ce-144). *J All gamma-emitting nuclide concentrations observed were below or similar to ihose concentrations noted during the preoperational* period, with the exception of Co-58 and 1-131. Cobalt-58 was observed in the third quarter composite sample3 from station 501 with a decay correc.ted concentration of 0.00034+/-0.00026 pCi/m

• The high associated error indicates that the value detected is close to the minimum detectable level. This concentration is probably not plant related since no other detectable amounts of Co-58 were observed during the .

third quarter. In addition Co-58 was detected in the October-November composite samples at locations 5Sl and 16El. The concentrations at these locations were 0.00047 and 0.00052 pCi/m 3 , respectively. The Co-58 observed is most probably attributed to the world wide fallout resulting from the atmospheric nuclear weapons test of September 17, 1977. Iodine-131 was observed in a December composite sample at station 1001 with a concentrati,on of 0.014+/-0.010 pCi/m3 * ,

Since no gaseous 1-131 was observed during the period and SNGS did not release any detectable I-131 during 1977 (12,13) it can be concluded that this incident was not plant related. Gamma analyses were performed on three additional weekly air particulate samples from stations 2Sl, lFl and 2F2 for the week of September 19 through September 27. These samples were analyzed for gamma emitters in accordance with the SNGS technical specifications because the beta activity in these samples exceeded the control location activity by a factor of

.four. It was determined that the reason for the difference was a low sample

• ---;:volume at the control location. Results of these analyses are found in table 36.

All the gamma emitters observed in these weekly samples were similar in concen~

tration to those observed in the quarterly composites except for two nuclides.*

Iodine-131 of undetermined origin was observed in the filter collected at station 2Sl at a decay-corrected concentration of 0.047+/-0.027 pCi/m3

• The above-mentioned I-131 was detected_ in a particulate form, and, in addition; no gaseous 1-131 was observed during this period from 2Sl. Therefore, it is probably that this incident was not plant related. The other gamma-emitting nuclide BaLa-140, was observed in all of the special analyses.

The radiostrontium analyses performed on the quarterly composites showed detectable levels of Sr-89 ranging between 0.0013 and 0.013 pCi/m3 , with the average being 0.0055 pCi/m3 while Sr-90 ranged between <0.0003 and 0.0026 pCi/m3 with the .

average being 0.0011 pCi/m3

• The activities noted are the result of the recent atmospheric nuclear weapons testing since the fall of 1976 and are not related.

to the operation of SNGS since the effluent release records of SNGS indicate that less than 5x10- 4 µCi of radiostrontium was released during the later part of 1977. (13)

The results of all air particulate analyses did not:differ, except where noted above, from preoperational results, nor were any significant differences between indicator and control stations observed.

Air Iodine Iodine cartridges were connected in series behind each of the air particulate filters for adsorption of gaseo1,1s ipc;line. The adsorption media used in. these cartridges was 11 TEDA 11 impregnated charcoal. Eighteen of 339 cartridges

analyzed had detectable concentrations of I-131 ranging between 0.0038 and 0.031 pCi/m 3

• The majority of the detectable I-131 was observed in Jan*uary at both control and indicator stations. The I-131 observed can therefore be attributed to*the world-wide fallout from the nuclear wepaons testing in the fall of 1976. One additional week of detectable I-131 activity was noted in October. This again was observed following the September 1977 nuclear .

weapons testing. No additional I-131 activity was observed throughout the reporting period.

Precipitation Although not specifically required by the Salem ETS, precipitation was" sampled continuously and collected monthly at the Salem substation sampling location.

Concentrations of H-3 in these samples ranged from <80 to 195 pCi/l~ The concentrations of alpha emitters were below MDL (1.5 pCi/l) in seven of the twelve samples. The other five samples had alpha concentrations ranging between 0.7 and 12 pCi/l. Beta-emitter concentrations ranged from <3.7 to 776.pCi/l and averaged 107 pCi/l. The highest activity of both the alpha and beta (12 and 776 pCi/l, respectively) was found in the May sample and had elevated results due to the extremely low*sample volume.

Quarterly composites of precipitation were analyzed for radiostrontium and gamma emitters. The gamma emitters detected were naturally occurring Be-7 and K-40 while the man-made nuclides observed were ZrNb-95, Ru-103, Cs-137, BaLa-140, Ce-141 and Ce-144. Most of the nuclides were detected in the third quarter sample, which included samples that were affected by the September.

atmospheric nuclear weapons test. The Sr-89 levels ranged between <4.5 and 7.8 pCi/l,.while those for Sr-90 ranged from <0.5 to 2.4 'pCi/l. These levels indicate fluctuations resulting from atmospheric nuclear weapons testing in*

.1976 and 1977.

Terrestrial Environment

• The terrestrial environment in the vicinity of Artificial Island was examined by analyzing samples of well water, raw and treated potable water, milk; fruits, vegetables, beef, fodder crops, game, beef thyroid tissue, and soil.

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 (atomic absorption). Quarterly composites were analyzed for gamma emitters, and Sr-89 and Sr-90.

Detectable concentrations of H-3 were observed in eleven of 36 samples ranging between the MDL (80 pCi/l) and 402 pCi/l. Alpha-emitter concentrations were

.below ihe MDL (1.5 to 2.7 pCi/l) in all but one sample, and that sample had a detectable concentration of 1.5 pCi/l. The concentrations of beta emitters averaged 7.6 pCi/l and ranged from <3.0 to 13 pCi/l. The potassium-40 activity as determined by atomic absorption averaged 6.4 pCi/l. This indicates that the beta activity observed in these samples is primarily the result of naturally occurring K-40, a beta emitter.

15

The only nuclide detected by gamma spectrometry was K-40 (10 to 16 pCi/l) .

in three of twelve samples. Strontium-89 was detected in the second quarter sample from locations 4Sl and 501 with a concentration at or lower than the MDLs of the other 10 samples, which ranged between 0.5 pCi/l and 1.1 pCi/l.

One detectable Sr-90 activity was observed with a concentration of 0.6 pCi/l.

This again is within the range of MDLs for Sr-90 (0~3 pCi/l to 0.7 *pCi/l).

Potable Water Both raw and treated water s*amples were taken at the Salem Water Company, the only drinking water processing plant in the vicinity of Artificial Island. The raw water source for this plant is Laurel Lake (a tributary of the Delaware River) and several adjacent wells. Potable* water samples were analyzed monthly for H-3, alpha and beta activity, and K-40 (atomic absorption); Sr-89 and-90, and gamma emitters were analyzed on a quarterly basis.

The concentration of H-3 averaged 143 pCi/l for all analyses, with no significant differences between the raw and treated samples. Detectable alpha activity was observed in 17 of 24 samples ranging between 0.4 pCi/l and 1.8 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 4.5 pCi/l (raw) and 5.1 pCi/l (treated). The average K-40 results were 1.4 pCi/l (raw) and.1.7 pCi/l (treated).

Eight quarterly composites were analyzed for Sr-89 and-90, and gamma emitters.

Two detectable concentrations of Sr-89 were noted, which were between the MDL range (0.9 pCi/l to 1.9 pCi/l) of the other samples. Strontium-90 was observed in seven of the eight samples with the concentrations ranging between 0.5 pCi/l and 1.0 pCi/l. No gamma emitters were detected in any of these samples. Water treatment had no significant effect on any of the analytical parameters measured.

No annual trends in the radiological characteristics of potable water were observed.

Milk Milk samples were taken twice a month from five local farms during 1977 and analyzed for I-131; gamma emitters, Sr-89, and Sr-90 were analyzed monthly.

Following the nuclear weapons test of September 17, additional milk samples were collected in order to meet the ETS requirements concerning collection during*time of elevated I-131 concentrations.

Detectable concentrations of 1-131 were observed in 30 of 37 samples collected from all stations between the last week of September through the first collection in December. The l-131 observed ranged between 0.29 and 25.00 pCi/l and was attributed to the world-wide fallout from the September 1977 nuclear weapons test. Figure 5 shows the average I-131 concentratioils in milk samples resulting from three atmospheric nuclear weapons tests by the Peoples Republic of China between June 1974 and September 1977. No other I-131 was observed in any of the samples.

16

FIGUI£ 5 AVE.RAGE WNCENTRATIONS OF IoDINE-131 IN MILK IN THE VIcmrrv OF ARTIFICIAL ISLA.ND MW 1974 THROuGH DECEMBER 1977 100....-~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~--'-~~~~~~~~~~~~~~~~~~~~---.

90 80 70 60 50 1' AVERAGE VALUE LESS THAN .1 pCi/l 40 30 20 10 9

8 7

-c 6 9.

.....i

..... 5 4

3 2

l

.9

• 8

• 7

.6

.5

• 4

• 3

.2 CHINESE NUCLEAR TEST SEPT. 26, 1976 CHINESE NUCLEAR TEST.

SEPT. 17, 1977 i

SNGS-1 CHINESE NUCLEAR TEST INITIAL CRITICALITY JUNE 17, 1974

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Two incidents concerning I~l31 in milk samples were reported in 1977. In all cases, the I-131 concentrations at the various indicator locations were a factor of ten greater than was the concentration at the control location. The first incident occurred with the October 17 and 18 sample collected at station 2Fl.

The second occurred with the November 6 and 7 samples collected at stations 2Fl and 15Fl. It was concluded that the cause of reportable I-131 was world-wide nuclear fallout from the September 17 nuclear weapons test since SNGS did not release detectable I-131 during this reporting period (12,13).

Ganma spectrometry showed detectable concentrations of K-40 in all samples and of Cs-137 in all but five of the sixty samples analyzed. The annual average concentrations were 1400 pCi/1 for K~4o and 2.8 pCi/l for Cs-137. These levels were not significantly different between stations. Iodine-131 was the only other gamma-emitting nuclide detected during 1977. Observable levels were detected in the October samples following the September nuclear weapons test and ranged from 14 to 45 pCi/l.

Strontium-89 was detected in seven of the fifteen samples analyzed following the September nuclear weapons test, with results ranging between <4.4 pCi/l .

and 15 pCi/1. The concentration of Sr-90 exceeded the MDL in forty six of the sixty samples analyzed and averaged 2.3 pCi/l. Seven Sr-89 analyses did not meet the required sensitivity because the MDLs were decay corrected.* Presently, a study is being conducted to verify the accuracy and precision of the strontium methodology.

• Game Five game samples (4 muskrat, 1 deer) were taken during this period. Flesh from all five samples was analyzed for ganma emitters while bones from the muskrats were analyzed for Sr-89 and Sr-90. Naturally occurring K-40 was detected in all five samples ranging from o. 7 to 3. 7 pCi/g. In addition, Cs-137 was present in two of the five samples. Muskrat bones showed detectable Sr-89, with concentrations ranging between 0.6 and 1.2 pCi/g-dry.

Detectable Sr-90 concentrations were observed in all samples ranging from

0. 5 to 1. O pCi/ g-dry.

Beef Three beef samples were collected during this reporting period. Two ganma-emitting nuclides, K-40 and Cs-137, were detected at similar concentrations to those observed during the preoperationa1- period. All other ganma emitters were below the MDL.

Beef Thyroid Three beef thyroids were taken during this period and analyzed for gamma emitters. One thyroid showed a detectable concentration of naturally occurring K-40. One sample showed a detectable concentration of I-131 (2.3 pCi/g); no other ganma emitters were detected in these samples.* The most probable explanation is that this I-131 was concentrated from atmospheric fallout due to the series of nuclear detonations by the Peoples Republic of China in September 1977 since SNGS did not release and detectable I-131 during 1977. (12,13) 18

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, corn, tomatoes, squash, and eggplant. All samples contained K-40 at concentrations from 1.0 to 3.5 pCi/g-wet. One squash sample at control station 1G2 contained a detectable level of Cs-137, while one asparagus sample collected from station 2El showed a detectable amount of ZrNb-95. N9 other gamma emitters were detected in those food products. All analyses for Sr-89 were below the MDL {5 pCi/kg to 40 pCi/kg). Concentrations of Sr-90 were detected in the asparagus sample {4 pCi/kg), which is similar to concentrations observed during the preoperational period.

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 sample~, with an average of 15 pCi/g-dry. Other detected naturally occurring*nuclfdes were Be-7 and Ra-226. The man-made nuclides Mn-54, Zr-95, Nb-95, Ru-103, Ru-106, Sb-125, Cs-137, Ce-141, and Ce-144 were also observed. With the exception of Mn-54 and Ru-103, all were observed during the preoperational period. Manganese-54 was detected in four of eleven samples at concentrations at or just barely above the MDL (0.02 pCi/g-dry), while Ru-106 was found in three of the eleven

• samples. All man-made radionuclides are assumed to be from the residual world-wide fallout from the 1976 nuclear weapons tests since all were d~tected in the preoperational air particulate samples collected following the above-mentioned tests.

Soil

• Fourteen soi 1 samples were analyzed for gamma emitters and Sr-90. Gamma .

spectrometry of these samples showed detectable concentrations of the naturally

.. occurring nuclides {K-40, Ra-226, and Th-232) and the fission products Cs-137 and Ru-103. The Cs-137 concentration averaged O. 70 pCi/g with a range from 0.11 to 3.7 pCi/g. Ruthenium-103 was detected in one sample at a concentration of 0.02 pCi/g, which was just above the.MDL (0.01 pCi/g). All other gamma emitters were at or below their respective MDLs. The concentrations of Sr-90 ranged from 0.06 to 0.68 pCi/g with an average of 0.16 .PCi/g.

Direct Radiation Direct radiation measurements were made at 24 locations using CaSO. (Tm) thermo-luminescent dosimeters. During 1977, 288 monthly and 96 quarterly TLD packets were collected *. t:ach packet included four dosimeters for a total of 1536 analyses. These analyses resulted in an average dose rate of 5.09 mrads/standard month for monthly TLDs and 4.90 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 1977 shows a similarity between the average monthly dose for both indicator stations. {4.97 mrem/std. month) and control. stations. {5.64 .mrem/std. month). Jhese results . . ,

compare favorably to the*preoperational results as shown in figures 6 and 7, therefore, indicating no effect from SNGS operation.

19

FIGURE 6 AVERAGE .'\MBIENT RADIATION LEVELS FROM f'bNTHLY AND QUARTERLY Tl.D'S IN THE VICINITY OF ARTIFICIAL ISLAND 1973 THROUGH 1976 10

~

8 7

6 5 QUARTERLY 4

i 2

10 9

8 7

6 MONTHLY 5

4 3

CHINESE NUCLEAR TEST 2

1 CHINESE NUCLEAR TEST 1 SEPT. 26, 1976 SNGS-1 1

. JUNE 17, 1974 INITIAL CRITICALITY

i: ...J

~~~ft~~~~~~~~~~

1973 1974 1975 1976

FIGUI{ 7 Ave.RAGE JV.1BIENT IWlIATION LEVE.LS FROM fbm.!LY AND Q~RTERLY TLD's IN THE VICINilY OF ARTIFICIAL ISLAND

. 1977.

10 9

8

• QUARTERLY 7

6 5

4 3

2 1

10 9 ---

8 MONTHLY 7

6 5

4 31 2 1 CHINESE NUCLEAR TEST 1 SEPT. 17 1977 I

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CONCLUSIONS The Radiological Environmental Monitoring Program for Salem Nuclear Generating Station at Artificial Island was conducted during 1977 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 5.09 mrem/std.

month and were similar to preoperational results. The observation of the fission product I-131 in a few samples was attributed to residual fallout from the September 1977 atmospheric weapons tests by the People's Republic of China.

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 ~adiological characteristics of the environs of Artificial. Island.

• .i 22

. REFERENCES

{1} Radiation Management Corporation. "Salem Nuclear Generating Station -

Radial ogi cal Environmental Mani taring Program - 1973. 11 RMC-TR-74-09, 1974.

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

(3) Radiation Management Corporation "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. II RMC-TR-77-03, 1978.

(5) Radiation Management Corpora ti on. 11 Arti fi ci al Isl and Radiological Environmental Monitoring Program - December 11 to December 31, 1976. 11 RMC-TR- 77-02.

(6) Public Service Electric and Gas Company. "Environmental Report, Operating License Stage - Salem Nuclear Generating Station Units 1 and 2. 11 1971.

(7) United States Atomic Energy Commission. "Final Environmental Statement -

Salem Nuclear Generating Stati.on, Units 1 and 2. 11 Docket No. 50-272 and 50-311, 1973.

(8) Public Service Electric and Gas Company. "Final Safety Analysis Report -

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

(9) Radiation Management Corporation. "Radiation Management Corporation -

Analysis and Quality Control Program. 11 RMC-TM-75-3, 1975.

(10) Thomann, Robert V. 11 The Delaware River - A study in Water Quality Management, 11 River Ecology and Man. Academic Press, New York, 1972.

11 (11) Ichthyological Associates, Victor Shular, Project Leader. An Ecological Study of the Delaware River in the Vicinity of Artificial Island. 11 A Seri es of Progress Reports si nee 1971.

{12) Public ServidtElectric and Gas Company. "Radioactive Effluent Release Report, January - June 1977. 11 1977.

(13) Public Service Electric and Gas Company. "Radioactive Effluent Release Report, July - December 1977. 11 1978.

-- ~.

23

APPENDIX A

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

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM NUCLEAR GEN~RAT.ING STATION DOCKET NO. 50-272 SALEM COUNTY. NEW JERSEY JANUARY 1, 1977 to 'DECEfvBER 31, 1977 ANALYSIS AND LOWER LIMIT NUMBER OF MEDIUM OR PATHWAY TOTAL NUM3ER OF ALL* INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATIONS NON ROUTINE SAMPLED OF ANALYSES DETECTION MEAN* NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (MDL) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS Surface Water Alpha 55 1.5 - (0/22) 12Cl 2.5 mi. WSW - (1/11) - (2/33) 0 (pCi/l)

Beta 55 3.0 60 (22/22) 7El 4.5 mi. SW (14) 69 (11/11)

(2-14) 32 (33/33) 0

(19-140) (35-140) ( 4-77)

H-3 55 80 189 ( 17/22) 12Cl 2.5 mi. WSW 228 (10/11) 196 (30/33) 0 (65-460~ (76-431) (76-431)

Sr-89 20 5.0 - (1/8 7El 4.5 mi. SW - (1/4) - (0/12) 0

( 1. 0) ( 1. 0)

Sr-90 20 1.0 - (1/8) 12Cl 2.5 mi. WSW 0.6 (2/4) - (5/12) 0 (0.4) (0.4-0.7) (0.3-0.7)

Gamna 55 N K-40 7.0 79 (22/22) 7El 4,'5 mi. SW 89 (11/11) 48 (27/33) 0

'-I (27-170j (41-170) (11-100)

Cs-134 0.5 - (0/22) 16Fl 6. 9 mi. NNW - (1111) - ( 1/33) 0 Cs-137 0.5 -

(0/22) 16Fl 6.9 mi. NNW (0. 8)

- (1/11)

(0.8)

- (3/33) 0 (2.1) (1.0-2.1) .

Edible Fish H-3 6 80 118 (3/4) 12Cl 2.5 mi. WSW - (1/2) - ( 112) 0 (pCi/1) (aqueous) ( 112-122~ (270) (270)

(pCi/1) H-3 6 80 245 (3/4 llAl 650 ft. SW 297 (2/2) 233 (2/2) 0 (organic) (142-358) (235-358) (175-290)

(pCi/g-dry) Sr-89(1) 4 0.5 - ( 1/3) llAl 650 ft. SW - (1/2) - (0/1) 0 (0.10) (0.10)

(pCi/g-dry) Sr-90(1) 4 0.1 - ( 1/3) llAl 650 ft. SW - ( 1/2) - (0/1) 0 (0.09) (0. 09)

(pCi/g-wet) Gamna 6 K-40 3.9 (4/4) llAl 650 ft. SW 4 (2/2) 3.7 (2/2~ 0 (3.3-4.2) (3.8-4.2) (3.1-4.3 Prey Fish Sr-89 6 0.05 - ( 1/4) 7El 4.5 mi. SW - ( 1/2) - ( 0/2) 0 (pCi/g-wet) (0.13) (0.13)

Sr-90 6 0.01 - (0/4) 12Cl 2.5 mi. WSW - (1/2) - ( 1/2) 0 (0.004) (0.004)

Gamna 6 K-40 2;7_ (4/4r .,*.

. . -* 12c.1 2.5 mi. w~w 2. 9 (-2/2) 2. 9 (2/2) 0 (1.9-3.1 (2.5-3.3) (2.5-3.3)

ARTIFICIAL ISLAND RA!lIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 SALEM COUNTY, NEW JERSEY JANUARY 1, 1977 to DECEMBER 31, 1977 ANALY.SIS AND LOWER LIMIT NUMBER OF MEDIUM OR PATHWA'f

• TOTAE--NUMBER OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATIONS NON ROUTINE SAMPLE It" OE ANAL 'lSES DETECTION MEAN* NAME MEAN MEAN REPORTED (UNIT OF MEASURf'.MENT) PERFORMED (MDL) RANGE DISTANCE Arm DIRECTION RANGE RANGE MEASUREMENTS Blue Crab H-3 4 80 279 (2/2) llAl 650 ft. SW 279 (2/2) 134 (2/2) 0 (pCi/l) (226-331) (226-331) (83-184)

(pCi/g-dry) Sr-89(2) 4 0.5 0.24 (2/2) llAl 650 ft. SW 0.24 (2/2) - ( 1/2) 0 (0.18-0.30) (0.18-0.30) (0.40)

(pCi/g-dry) Sr-90(2) 4 0.1 0.24 (2/2) 12Cl 2.5 mi. WSW 0.27 (2/2) 0.27 (2/2) 0 (0.15-0.33) (0.21-0.32) (0.21-0.32)

(pCi/g-wet) ~r-89(3) 4 0.5 - (0/2) N/A - ( 0/2) 0 (pCi/g-wet) Sr-90(3) 4 0.1

- (1/2) 12Cl 2.5 mi. WSW - ( 1/2) -

( 1/2) 0 (0.006) (0.006) (0.006)

(pCi/g-wet) Gamna 4 K-40 2.8 (2/2) llAl 650 ft. SW 2.8 (2/2) 2.8 (2/2) 0 (2.2-3.3) (2.2-3.3) (2.6-2.9)

CQ Cs-137 0.004 - (0/2) 12Cl 2.5 mi. WSW - ( 1/2) - ( 1/2) 0 (0.02) (0.02)

Benthos Sr-89 6 0.5 - (1/4) llAl 650 ft. SW - ( 1/2) - (0/2) 0 (pCi/g-dry) (20) (20)

Sr-90 6 0.1 0.2 (2/4~ llAl 650 ft. SW - (1/2) - (0.2) 0 (0.1-0 *.3 (0.3)

Sediment Sr-90 8 0.1 - (0/6) N/A - ( 0/2) 0 (pCi/g-dry)

Gamna 8 K-40 14 (4/4) 16Fl 6.9 mi. NW 18 (2/2) 16 (4/4) 0 .

( 11-17) (18) ( 11-18) rti-54 .* 0.02 - (0/4) 12Cl 2.5 mi. WSW - (1/2) - (1/4) 0 Nb-95 0*.02 -

(2/4) 7El 4.5 mi. SW (0.02)

- (1/2) .

(0.02)

- (1/4) 0 (0.04-0.07) (0.07) (0.02)

Zr-95 0.03 - (0/4) 16Fl 6.9 mi. NW - (1/2) - (1/4) 0 Ru-103 0.01 -

(1/4) llAl 650 ft. SW (0.04)

- (1/2)

(0.04)

- ( 0/4) 0 (0.04) (0.04)

- ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 SALEM COUNTY, NEW JERSEY JANUARY 1, 1977 to DECEMBER 31, 1977 ANALYSIS AND LOWER LIMIT NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN* NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (MDL) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS Sediment (cont.) Gamma (pCi/g-dry) Sb-125 0.04 - (0/4) 16Fl 6.9 mi. NW - ( 1/2) - (1/4) 0 (0.06) (0.06)

Cs-137 0.01 0.14 (4/4) llAl 650 ft. SW 0.22 (2/2) 0.05 (3/4) 0 (0.05-0.25) (0.19-0.25) (0.04-0. 07)

Ce-141 0.02 - (0/4) 12Cl 2.5 mi. WSW - (1/2) - ( 1/4) 0 (0.02) (0.02)

Ce-144 0.10 - (114) llAl 650 ft. SW - (1/2) - (0/4) 0 (0.13) (0.13)

Ril-226 0.74 (4/4) 12Cl 2.5 mi. WSW 0.88 (2/2) 0.71 (4/4) . 0 (0.70-0.81) (o. 75-1. 00) (0.50-0.10)

Th-232 0.59 (4/4) 16Fl 6.9 mi. NW 0.67 (2/2) 0.61 (4/4) 0 (0.38-0.80) (0.54-0.80) (0.42-0.80)

Air Particulates Alpha 102 0.4 1.1 (40/51) 3H3 110 mi. NE 1.2 (45/51) 1.2 (45/51) 0 (10- 3 pCi/m3) (0.5-2.4) (0.5-2.6) (0.5-2.6)

Beta 406 5.0 143 (355/355) 2Sl 0.3 mi. NNE 153 (49/49) 144 (51/51) 0 N

(27-543) (32-456) (23-440)

'° Sr-89(5) 32 5 5. 5 (28/28) 5Sl 1. 0 mi. E

• 6.4 (4/4) 5.3 (4/4) 0 (1.3-13) (1.4-13) (1. 6-10)

Sr-90(5) 32 1 1.2 (23/28) 5Dl 3.5 mi. E 1.4 (3/4) 1.2 (3/4) 0 (0.3-2.6) (1. 0-1. 7) (1.0-1.4)

Garmna(5) 32 K-40 5.0 - (2/28) 2F2 8.7 mi. NNE - (1/4) - (0/4) 0 (24-130) (130)

Be-7 76 (28/28) 5Sl 1.0 mi. E 88 (4/4) 83 (4/4) 0

{43-108) (69-108) (73-93)

Cr-51 2 - (1/28) 16El 4.1 mi. NNW - (1/4) - (0/4) 0 (21) (21) -

Mn-54 0.2 - (4/28) 2F2 8.7 mi. NNE - (1/4) - (1/4) 0 (0.3-0.4) (0.4)

Co-58 0.2 - {3/28) 16El 4.1 mi NNW - (1/4) - (0/4) 0 (0.3-2.0) (1.5)

Co-60 0.3 - (1/28) lFl 5.8 mi. N - ( 1/ 4) - ( 0/4) 0 (1.2) (1. 2)

Zr-95 14 (28/28) 5Sl 1.0 mi. E 16 (4/4) 15 (4/ 4) 0 (1.5-35) (3-35) (3-31)

Nb-95 17 (28/28) 5Sl 1.0 mi. NNE 20 (4/4) 13 (4/4) 0 (2.8-49) (4.2-49) (3.6-21)

Ru-103 6.2 (28/28) 5Sl 1.0 mi. E 7.4 (4/4) 7.o (4/4) 0 (1.6-14) (2.3-14) (2. 2-12)

Ru-106 14 (22/28) 2F2 8.7 mi. NNE 17 (3/4) 17 (3/4) 0

( 1.6-18) (16-18) (11-22)

Sb-125 0.3 2. 7 ( 19/28) lFl 5.8 mi. N 6.4 (3/4) 1. 6( 2/4) 0 (1.1-14) (1.7-14) (1.4-1.8)

I-131 0.2 - ( 1/28) lODl 3.9 mi. SSW - (1/4) - (0/4) 0 (14) 14

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 SALEM COUNTY, NEW JERSEY JANUARY 1, 1977 to DECEMBER 31, 1977 ANALYSIS AND LOWER LIMIT NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER OF ALL INDICATOR LOCATIONS LOCATION WITH *HIGHEST MEAN CONTROL LOCATIONS NON ROUTINE SAMPLED OF ANALYSES DETECTION MEAN* NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERPORMED (MDL) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS Air Particulates (cont.) Ganrna (10- 3 pCi/m3) Cs-137 2.0 2.0 (28/28) 2F2 8.7 mi. NNE 2.3 (4/4) 2.1 ( 4/ 4) 0 (0.2-3.4) (0.4-3.2) (0.6-3.3)

BaLa-140 0.4 - ( 2/28) 5Sl 1.0 mi. E - ( 1/ 4) - (Of 4) 0

( 10-11) ( 11)

Ce-141 0.3 5.5 (22/28) 5Sl 1. 0 mi. E 6. 9 ( 4/4) 5. 5 ( 414) 0 (1.3-16) (1.7-16) (1.6-13)

Ce-144 20 29 (28/28) 2Sl 0. 3 mi. NNE 31 (4/4) 28 (4/4) 0 (2.0-56) (2.1-48) ( 1. 3-41)

Air Iodine I-131 339 10 - ( 15/288) N/A - (3/51) 0 (lo- 3 pCi /m3) (3.7-35) (4.5-20)

Precipitation Alpha 12 1.5 4.1 (5/12) 2F2 8.7 mi. NNE 4.1 (5/12) No Control 0 (pCi/l) (0.7-12) (0.7-12) Location Beta 12 3.0 117 (11/12) 2F2 8. 7 mi. NNE 117 (11/12) 0 w (18-776) (18-776) 0 H-3 12 80 - ( 4112) 2F2 8. 7 mi. NNE - (4/12) 0 (97-195) (97-195)

Sr-89 4 5.0 5. 4 ( 3/4) 2F2 8. 7 mi. NNE 5.4 (3/4) 0 (1.1-7.8) (1.1-7.8)

Sr-90 4 1.0 1.9 (2/4) 2F2 8. 7 mi. NNE 1. 9 (2/4) 0 (1.4-2.4) ( 1.4-2.4)

Ganrna 4 Be-7 19 (3/4) 2F2 8. 7 mi. NNE 19 (3/4) 0

( 10-33) (10-33)

K-40 10 - (1/4) 2F2 8. 7 mi. NNE - (1/ 4) 0 (58) (58)

ZrNb-95(6) 2.0 - ( 1/ 4) 2F2 8. 7 mi. NNE - (1/4) 0 (32) ( 32)

Ru-103 3. 9 (2/4) 2F2 8.7 mi. NNE 3. 9 (2/4) 0 (2.2-5.5) (2.2-5.5)

Cs-137 2.0 - (1/4) 2F2 8.7 mi. NNE - ( 1/ 4) 0 (0.8) (0.8)

BaLa-140 3.0 - (1/4) 2F2 8. 7 mi. NNE - (1/4) 0

( 1. 7) ( 1. 7)

Ce-141 0.7 - ( 1/ 4) 2F2 8. 7 mi. NNE - ( 1/ 4) 0

( 1. 9) ( 1. 9)

Ce-144 10 - ( 1/ 4) 2F2 8.7 mi. NNE - ( 1/ 4) 0 (5. 7) (5. 7)

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 SALEM COUNTY, NEW JERSEY JANUARY 1, 1977 to DECEMBER 31, 1977 ANALYSIS AND LOWER LIMIT NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER OF ALL INDICATOR LOCATIONS LOCATION IHTH HIGHEST MEAN CONTROL LOCATIONS NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN* NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (MDL) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS Well Water Alpha 36 1. 5 - (1/24) 5Dl 3.5 mi. E - (1/12) - (0/12) 0 (pCi/l) (1. 5) ( 1. 5)

Beta 36 3.0 7.7 (20/24) 4Sl Site Well 9.9 (11/12) 9.0 (12/12) 0 (2.3-13) (7.2-13) (5.3-13)

H-3 36 80 - (5/24) 3El 4 mi. NE - (5/12) - (5/12) 0 (81-334) (77-402) (77-402)

K-40 36 0.09 5.8 (24/24) 4Sl Site Well 9.0 (12/12) 7.5 (12/12) 0 (0.8-12) ( 1. 7-12) (1.4-11)

Sr-89 12 5.0 0.5 (2/B) 5Dl 3.5 mi. E - (1/4) - (0/ 4) 0 (0.4-0.5) (0.5)

Sr-90 12 1.0 - (0/8) 3El 4 mi. NE - (1/4) - (1/4) 0 (0.6) (0.6) w*. Ganma 12 K-40 7.0 - (2/8) 4Sl Site Well - (2/4) - (114) 0

( 10-16) (10-16) ( 13)

Fruits and Vegetables Sr-89 14 0.05 - (0/5) N/A - (0/9) 0

( pCi I g-wet)

Sr-90 14 0.01 - (1/5) 2El 4.5 mi. NNE - ( 1/2) - (0/9) 0 (0.004) (0.004)

Ganma 14 K-40 2.4 (5/5) 15El 4.1 mi. NW - (1/1) 2.6 (9/9) 0 (1.0-3.3) (3.3) (1.3-3.5)

ZrNb-95 0.001 - ( 1/5) 2El 4.5 mi. NNE - ( 1/2) - (0/9) 0 (0.004) (0.004 Cs-137 0.002 - ( 0/5) 1G2 Background - ( 1/1) - (1/9) 0 (0.004) (0.004)

Fodder Crops Ganma 10 (pCi/g-dry) Be-7 3.5 (6/10) 5Fl 6.5 mi. E - (1/1) No Control 0 (0.8-7.2) (7.2) Location K-40 14.4 (10/10) 15Fl 5.4 mi. NW 20 (3/3) 0 (3.4-23) (19-23)

Mn-54 0.02 . - (4/10) 2Fl 5.0 mi. NNE - ( 1/ 1) 0 (0.01-0.03) (0.3)

Zr-95(4) 0.29 (7/10) 5Fl 6.5 mi. E - ( 1/ 1) 0 (O.OB-0.52) (0.52)

Nb-95 0.66 (6/10) 5Fl 6.5 mi. E - (111) 0 (0.17-1.10) (1.1)

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MO~ITORIN~_PROGRAM

SUMMARY

SALEM NUCLEAR GENERATING STATION DOCKET NO. 50"272 SALEM COUNTY, NEW JERSEY JANUARY 1, 1977 to DECEMBER 31, 1977 ANALYSIS, AND LOWER LIMIT NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER OF ALL INDICATOR LOCATIONi LOCATION WITH HIGHEST MEAN

• CONTROL LOCATIONS NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN* NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (MDL) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS Fodder Cro)s (cont.) Gamna

( pCi I g-dry Ru-103 - (4/10) 5Fl 6~5 mi. E - (1/1) 0 (0.05-0.07) (0. 07)

Ru.,106 - (3/10) 5Fl 6.5 mi. E - (1/1) 0 (0.4-0.6) (0.6)

Sb-125 0.05 - (3/10) 5Fl 6.5 mi. E - (1/ 1) 0 (0.05-0:07) (0.07)

Cs-137 0.02 0.08 (6/10) 5Fl 6.5 mi. E - (1/1) 0 (0.03-0.13) (0.13)

Ce-141 0.01 - (2/10) 5Fl 6.5 mi. E - ( 1/1) 0 (0.02-0.06) . ( 0. 06)

Ce-144 0.1 1.2 (5/10) 5Fl 6.5 mi. E - ( 1/1) 0 w (0.4-2.4) (2. 4)

N Ra-226 0.04 - (2/6) ' 14Fl 5.5 mi. WNW - ( 1/ 1) 0 (0.07-0.10) (0.10)

Potable Water Alpha 24 1.5 0.9 (11/24) 2F3 8 mi. NNE 0.9 (17/24) No Control 0 Raw-Treated (0.4-1.8) (0.4-1.8) Location (pCi/1) Beta 24 3.0 4J : (23/24)' 2F3 8 mi. NNE 4.9 (23/24) 0 (L4-20) (1.4-20)

H-3 24 80 175 (16/24) 2F3 8 mi. NNE 175 (16/24) 0

(76-317) (76-317)

Sr-89 8 5.0 - ( 2/8) 2F3 8 mi. NNE - (2/8) 0

( 0. 8-1. 2) (0.8-1.2)

Sr-90 8 1.0 0.6 (7/8) 2F3 8 mi. NNE 0.6 (7/8) 0 (0.4-1.0) (0.4-1.0)

K-40 24 0.09 1.6 (24/24) 2F3 8 mi. NNE 1.6 (24/24) 0 (0.6-3.2) (0.6-3.2)

Gamna 8 None Detected Mi 1k I-131 130 0.05 5.02 (26/104) 2Fl 5 mi. NNE 7.0 (6/26) 2.33 (4/26) 3 (pCi/l) (0.07-25) (0.3-25) (0.29-5.60)

Sr-89 60 5.0 - (8/48) 2Fl 5 mi. NNE 9.2 (2/12) - (1/ 12) 0 (2.1-14) (4.3-14) ( 15)

Sr-90 60 1.0 2. 7 (37 /48) 2Fl 5 mi. NNE 3.9 (10/12) 3.1 (9/12) 0 (0.3-8.6) (0.4-8.6) (0.6-6.2)

ARTifICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 SALEM COUNTY, NEW JERSEY JANUARY 1, 1977 to .DECEMBER 31, 1977 ANALYSIS AND LOWER LIMIT NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATIONS NON ROUTINE SAMPLED OF ANALYSES DETECTION MEAN* NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (MDL) RANGE DISTANCE AND DIRECTION . RANGE RANGE MEASUREMENTS Milk (cont.) Ganma 60 (pCi/l) K-40 1500 ( 48/ 48) 15Fl 5.4 mi. NW 1500 (12/12) 1500 ( 12/12) 0

( 1000-1800) (1100-1800) (1100-1700)

I-131 0.5 - (3/48) 3Gl 16.6 mi. NE - (1/12) - (l/12) 0 (14/32) (45) ( 45)

Cs-137 0.6 2. 7 ( 43/48) 2Fl 5. 0 mi. NNE 3.4 (11/12) 3.2 (12/12) 0 (0.9-6.4) (1.8-6.2) (1.7-7.3)

Beef Ga nm a 3 (pCi/g-wet) K-40 2.2 (3/3) 3El 4.5 mi. NE 3.1 (2/2) No Control 0 (0.6-3.4) (2.7-3.4) Sample w

w Cs-137 0.002 0.02 (2/3) 3El 4.5 mi. NE 0. 02. (2/3) Available 0 (0.02) (0.02)

Game Sr-89 4 0.5 0.8 (2/2) llDl 3.5 mi. SSW 0.9.(2/2) 0.9 (2/2) 0 (pCi/g-dry) (0.6-0.9 (0.6-1.2) (0.6-1.2)

Sr-90 4 0.1 0.7 (2/2) llDl 3.5 mi. SSW. 0.8 (2/2) 0.8 (2/2) 0 (0.5"-0.8) (0.5-1.0) (0.5-1.0)

Gamma 5 K-40 2.5 (3/3) 1101 3.5 mi. SSW 3.3 (2/2) 3.3 (2/2) 0 (0.7-3.7) (3.2-3.4) (3.2-3.4)

Cs-137 0.002 0.025 (2/3) 3El 4.5 mi. NE - ( 1/ 2) - (0/2) 0 (0.021-0.028) (0.028)

Beef Thyroid Gamma 3 (pCi/g-wet) K-40 0.8 - (1/3) 3El 4.5 mi. NE - (1/2) No Control 0 (0.9} (0.9) Location I-131 0.05 - ( 1/3) 3El 4.5 mi. NE - (1/2) 0 (2.3) (2.3)

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM NUCLEAR GENERATING.STATION DOCKET NO. 50-272 SALEM COUNTY, NEW JERSEY JANUARY 1, 1977 to DECEMBER 31, 1977 ANALYSIS AND LOWER LIMIT NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATIONS NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN* NAME MEAN MEAN REPORTED

{UNIT OF MEASUREMENT) PERFORMED (MDL) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS Soil Sr-90 14 0.05 0.22 (12/12) 3H3 110 mi. NE - {1/1) 0.43 (2/2) 0 (pCi/g-dry) (0.06-0.42) (0.68) (0.17-0.68)

Gamma 14 K-40 9.2 (12/12) 14Fl 5.5 mi. WNW - {1/1) 10 (2/2) 0 (8.4-15) (15) (9.1-11)

Ru-103 0.01 - ( 1/12) 6Sl 0.2 mi. ESE - (1/1) - (0/2) 0 (0.02) (0.02)

Cs-137 0.71 (12/12) lFl 5.8 mi. N - {1/1) 0.62 (2/2) 0 (0.11-3. 70) (3.7) (0.41-0.82)

Ra-226 0.71 (12/12) lFl 5.8 mi. N - {1/1) 0.6 (2/2) 0 w (0.11-3.70) (3. 7) (0.41-0.82)

. """ Th-232 0.6 (12/12) 14Fl 5.5 mi. WNW - (1/1) o. 8 (2/2) 0 (0.4-1. 0) (1.0) (0.77-0.80)

Direct Radiation Gamma 1152 5.00 (960/960) lODl 3.9 mi. SSW 5.90 (48/48) 5. 64 ( 192/ 192) 0 (mrem/std. month) Dose (monthly) (3.29-7.83) (5.49-7.83) (4.96-6.58)

Garrma 384 4.78 (320/320) 2Hl 36 mi. NNE 5.59 (16/16) 5.60 (64/64) 0 Dose (quarterly) (3.55-5.67) (5.29-5.77) (5.09-5.90)

• (1) Mean calculated' using detectable measurements only. Fraction of detectable measurements in parentheses.

Strontium analyses performed on the bones only.

(2) Strontium analyses performed on the shell.

(3) Strontium analyses performed on the flesh.

(4) Includes one ZrNb-95 combined result.

(5) For purposes of averaging a weighted fourth quarter average was obtained.

(6) Includes ZrNb-95 result only.

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

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

AI = Air Iodine FPV = Food Products, Various AP = Air Particulates GM = Game AQS = Sediment ID = Immersion Dose (TLD)

E = Soil M = Mi 1k ECH =Hard Shell Blue Crab PW = Potable Water; (PWR = raw, ESB. = Benthos PWT = treated)

ESF = Edible Fish RW = Rain Water ESP = Prey Fish SW = Surface Water ESS = Sediment THB = Bovine Thyroid FPB = Beef v = Fodder Crops

~~w = ~Jel 1 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 3 miles off-site H = >20 miles off-site D = 3-4 miles off-site

~he last number is the station numerical designation within each sector and zone; e.g., 1,2,3, * . . For example, the designation SA-WW-501 would indicate a sample in the SNGS program SA, consisting~f well water (WW), 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 des1gnated area.

37

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 AP ,AI ,ID 4Sl Site well #5 ENE of Vent WW 5Sl ... ,

1. O mi. E of vent; site access road ID,AP ,AI 6Sl 0.2 mi. ESE pf vent; observation platform* ID,E 7Sl 0.12 mi. SE of vent; station personnel gate ID lOSl. .

.*~ ..*' -~ ...*

0.14 mi. SSW of vent; site ~horeline ID 1ts1 a*. 09 mi . S~ of-vent~ site shoreline ID 11A1 . 0.2 mL SW of vent;* outfall area SW ,ESF ,ESP,

• ECH, ESB ,ESS

~'

• r lBl 2-3 mi. N of vent v 12Cl 2.5 mi. WSW *of vent; west bank of Delaware SW,ESF,ESP, river ECH,ESB,ESS 5Dl 3.5.-mi. E of vent; local farm ID,V,E,~M, AP,AI lODl 3.9 mi. SSW of vent; Taylor's Bridge. Spur

. ~

ID,AP,AI,E 1101 3. 5 mi. SW of Vent . GM 14Dl 3.4 mi. WNW of vent; Bay View, Delaware

• • ID 2El' 4.4 mi. NNE of vent; local farm ID,FPV,E 2E2 4.4 mi. NNE of vent; local farm GM 3El 4.1 mi. NE of vent; local farm ID,THB,WW, GM,FPB 38

TABLE B-1 (CONT.)

7El 4.5 mi. SE of vent; 1 mi. Wof Mad Horse SW,ESF,ESP, Creek ESB,ESS 13El . 4.2 mi. Wof vent; Diehl House Lab ID 15El 4.1 mi. NW of vent; local farm FPV 16El 4.1 mi. NNW of vent; Port Penn ID,AP,AI,E lFl 5.8 mi. N of vent; Fort Elfsborg ID,AP,E 1F2 7.1 mi. N of vent; midpoint of Delaware SW River 2Fl 5.0 mi. NNE of vent; local farm E,V,M 2F2 8.7 mi. NNE of vent; Salem substation ID,AP,AI, RW,E 2F3 8.0 mi. NNE of vent; Salem Water Company PWR,P~H 5Fl 8.0 mi. E of Vent FPV,ID,E 5F2 7.0 mi. E of vent; local farm M,E,V 6Fl 6. 4 mi. ESE of vent; Stow !~eek Road ID 7F2 9.1 mi. SE of vent; Bayside, New Jersey ID 11Fl 5.*2 mi. SW of vent; Taylor's Bridge, ID Del aware 13Fl 9.8 mi. W of vent; Middletown, Delaware ID 14Fl 5.5 mi. WNH of vent; local farm V,M,FPIJ,THB,E 15Fl 5.2 mi. NW of vent; local farm ., V,M,E 16Fl 6.9 mi. NNW of vent; C &D Canal SW,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 ID,E,V,M 2Hl 34 mi. NNE of vent; RMC, Phila. ID 3Hl 32 mi. NE of vent; National Park, N.J. ID 3H3 110 mi. NE of vent; Maplewood Laboratories ID,AP,AI,E 3H4 18 mi. NE of vent; local farm FPV 39

MAP B-1 ON SITE SAM Pl ING LOCATIONS ARTIFICIAL ISLAND - 1977 0

SCALE Of f!LI LIS 40

MAP B-2 OFF SITE SAMPLING LOCATIONS ARTIFICIAL ISLAND 1977 0 1 2 3 ~ 5.

H- H I I -~,_I---'-I___.I SCALI Of MILIS 41

APPENDIX C DATA TABLES Appendix C presents the analytical results of the 1977 Artificial Island Radiological Environmental Monitoring Program for the period of January 1 to December 31.

TABLE TABLE TITLE PAGE NUMBER Aquatic Environment C-1 Concentrations of Tri ti um in Surface ~~ater ............... 48 C-2 Concentrations of Alpha Emitters in Surface Water ........ 49 C-3 Concentrations of Beta Emitters in Surface Water 50 C-4 Concentrations of Potassium-40 in Surface Water .......... 51 C-5 Concentrations of Strontium-89 and-90 in Surface Water **. 52 C-6 Concentrations of Garrma Emitters in Edible Fish *..*****.. 53 C-7 Concentrations of Strontium-89 and-90, and Tritium in Edible Fish .Samples . . . . . . . . . . *. . . . . . . . . . . . . . . . . . . . . . . . . . . 54 C-8 Concentrations of Gamma Emitters in Blue Crab Samples 55 C-9 Concentrations of Strontium-89 and-90, and Tritium in Blue Crab Samp 1es * * . * * *. * . * . . * * . . * . . . * . . . . . . . . * * *. * * . . ** . 56 C-10 Concentrations of Strontium-89 and-90, and Gamma Emitters

.in Prey Fish . . .. . .. . . ... .. .. . . .. .. . . .. ... .. .. . .. .. .. .. .. . 57 C-11 Concentrations of Gamma Emitters in Sediment **.****...*.. 58 C-12 Concentrations of Strontium-89 and-90 in Benthos and Sediment ................................................ . 59 Atmospheric Environment C-13 Concentrations Alpha Emitters in Air Particulates 60 C-14 Concentrations of Beta Emitters in Air Particulates *....* 62 C-15 Concentrations of Gamma Emitters in Quarterly Composites of* Air Particulate Samples *.**.******.**....*.**.****.*.. 64 45

TABLE TABLE TITLE (Cont.) PAGE NUMBER C-16 Concentrations of Strontium-89 and-90 in Quarterly Composites of Air Particulate Samp 1es * . . * * . . * * * . * . . . . . * * . * . * . . . * . . . . . * *

• 68 C-17 Concentrations of Iodine-131 in Filtered Air ................. 69

• C-18 Sampling Dates for Air Samples ............................... 71 C-19 Concentrations of Tritium, Alpha and Beta Emitters in Preci pi ta ti.on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 75 C-20 Concentrations of Stronti um-89 and-90 and Gamna Emitters in Quarterly Composites of Precipitation ..**..**.*...*...*.*..*. 76 Terrestrial Environment C-21 Concentrations of Tritium, Alpha and Beta Emitters, and Potassium-40 in Well Water ................................... 77 C-22 Concentrations of Strontium-89 and-90, and GaJJllla Emitters in Quarterly Composites of ~~el 1 ~~ater *.*.*..*.***...**.*..*.... 78 C~23 Concentrations of Tritium, Alpha and Beta Emitters~ and Potassium-40 in Raw and Treated Potable l4ater .**............ 79 C-24 Concentrations of Strontium-89 and-90, and Gamma Emitters in Quarterly Composites .of Potable Water .*.*..*****.****........ 80 C-25 Concentrations of Iodine-131 in Milk ......................... 81 C-26 Concentrations of Gamma Emitters and Strontium-89 and-90 in Mi 1k * * * * * . * * . * * * * * * * * . * * * . * . . . * . . . * . . * . . * * . . . . . . * . . * * * . . . . . . . 82 C-27 Sampling Dates for Milk Samples .............................. 83 C-28 Concentrations of Strontium-09 and-90, and Gamma Emitters in Meat and Game ................*..**.................*.*....... 85 C-29 Concentrations of Gamna Emitters in Bovine Thyroid .*..*.****. 86 C-30 Concentrations of Strontium-89 and-90, and Ga11111a Emitters in Food Products ..*...........................*.................. 87 C-31 Co~cen~rations of Gamma Emitters in Fodder Crop Samples *...*. 88 C-32 Concentrations of Strontium-90 and Gamma Emitters in Soil .... 89 C-33 Typical MDLs for Gamma Spectrometry *****.....**..*******.*... 90 46

TABLE TABLE TITLE (Cont.) PAGE NUMBER Direct Radiation C-34 Direct Radiation Measurements - Monthly TLD Results ....***..* 91 C-35 Direct Radiation Measurements - Quarterly TLD Results ...*.*.* 92 Special Tables C-36 Concentrations of Gamma Emitters in Special Weekly Composites of Air Particulate Samples .****.*****.**.*********..*...***.* 93 C-37 Comparison of Fourth Quarter Strontium-89 MDL Values in Milk Samples **.**.*.....*...*.........*.*..* w*~ *** ****************** 94 47

I~----

TABLE C-1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER

• Results in Units of pCi/l +/- 2 sigma STATION NO. 1-11-77 2-28-77 3-07-77 4-04-77 5-03-77 6-03-77 7-11-77 SA-SW-llAl * <80 140+/-68 87+/-65 124+/-55 166+/-73 90+/-65 SA-SW-12Cl

• 266+/-70 431+/-71 225+/-66 95+/-55 336+/-74 76+/-66 SA-SW-7El

• 292+/-68 460+/-71 65+/-65 <80 219+/-73 <80 SA-SW-1F2

• 272+/-70 144+/-68 76+/-65 103+/-55 251+/-73 78+/-64 SA-SW-16Fl

• 291+/-68 132+/-68 367+/-67 118+/-55 150+/-73 142+/-65

..p.

OJ . AVERAGE 240+/-181 261+/-337 164+/-262 104+/-35 224+/-149 93+/-56 ANNUAL STATION NO. 8-05-77 9-09-77 10-05-77 11-02-77 12-16-77 AVERAGE SA-SW-llAl 251+/-77 . 186+/-70(1) 188+/-76 214+/-74 <80 146+/-119 SA-SW-12Cl 400+/-78 138+/-71 184+/-76 125+/-73 <80 214+/-257 SA-SW-7El 236+/-77 159+/-70 175+/-76 168+/-74 <80 183+/-236 SA-SW-1F2 209+/-77 177+/-70 258+/-72 117+/-73 <80 160+/-153 SA-SW-16Fl 175+/-77 186+/-71 147+/-77 196+/-74 <80 180+/-164 AVERAGE 254+/-173 169+/-41 190+/-82 164+/-85 <80 177+/-191

• No sample collected because of icing conditions.

1 Sample date was 9-13-77.

TABLE C-2 CONCENTRATIONS OF ALPHA EMITTERS IN SURFACE WATER Results in Units of pCi/l +/- 2 sigma STATION NO. 1-11-77 2-28-77 3-07-77 4-04-77 5-03-77 6-03-77 SA-SW-llAl * <6.8 <16 <6.5 <14 <22 SA-SW-12Cl

• 14+/-13 <8.5 <2.5 <7.8 <19 SA-SW-7El * <9.0 <17 <18 <18 <15 SA-SW-1F2 * <11 <2.3 2.0+/-1.9 <2.3 <7.3

+=- SA-SW-16Fl <6.0 <9.4 <2.2 <3.8 <26 l.O STATION NO. 7-11-77 8-05-77 9-09-77 10-05-77 11-02-77 12-16-77 SA-SW-llAl <27 <20 <30(1) <9.4 <6.8 <7.8 SA-SW-12Cl <19 <20 <24 <7.2 <3.2 <6.3 SA-SW-7El <33 <29 <30 <9.4 <9.0 <16 SA-SW-1F2 <19 <16 <20 <3.7 <2.3 <4.5 SA-SW-16Fl <17 <16 <20 <3.1 <2.5 <5.0

• (1) No sample collected because of icing conditions.

Sample date was 9-13~77.

TABLE C-3 CONCENTRATIONS OF BETA EMITTERS IN SURFACE WATER Results in Units of pCi/l +/- 2 sigma STATION NO. 1-11-77 2-28-77 3-07-77 4-04-77 5-03-77 6-03-77 7-11-77 SA-SW-llAl

• 70+/-8 31+/-5 19+/-4 31+/-5 50+/-7 78+/-9 SA-SW-12Cl

• 56+/-7 16+/-3 8. 4+/-2. 9 17+/-4 52+/-7 73+/-8 SA-SW-7El ..

• 86+/-9' 38+/-5 50+/-7 35+/-5 55+/-6 140+/-14 SA..;SW-1F2

• 39+/-7 6.1+/-2.4 6.5+/-2.8 4.3+/-2.0 18+/-4 68+/-8 SA-SW-16Fl

• 49+/-6 19+/-4 9.1+/-3.0 7.4+/-2.2 61+/-8 61+/-7 AVERAGE 60+/-37 22+/-25 19+/-36 19+/-27 47+/-34 84+/-64 U1 0

ANNUAL STATION NO. 8-05-77 9-09-77 10-05-77 11-02-77 12-16-77 AVERAGE SA-SW-llAl 71+/-9 85+/-9(1) 47+/-5 51+/-6 21+/-4 50+/-46 SA-SW-12Cl 55+/-8 77+/-8 32+/-4 25+/-4 16+/-3 39+/-49 SA-SW-7El 85+/-10 110+/-11 49+/-5 77+/-8 41+/-5 70+/-67 SA-SW-1F2 41+/-6 56+/-6 15+/-3 16+/-3 11+/-3 26+/-44 SA-SW-16Fl 40+/-6 72+/-7 13+/-3 15+/-3 14+/-3 33+/-49 AVERAGE 58+/-39 80+/-40 31+/-34 37+/-54 21+/-24 43+/-59

• No sample collected because of icing conditions.

(1) Sample date was 9-13-77.

TABLE C-4 CONCENTRATIONS OF POTASSIUM-40* IN SURFACE WATER Results in Units of pCi/1 +/- 2 sigma RADIO-STA:rION NO. ACTIVITY 1-11-77 2-28-77 3-07-77 4-04-77 5-03-77 6-03-77 7-11-77 SA-SW-llAl K-40 ** 76+/-11 34+/-10 30+/-9 35+/-10 80+/-11 120+/-12 SA-SW-12Cl K-40 ** 73+/-10 22+/-9 13+/-9 18+/-9 78+/-10 76+/-11 SA-SW-7El K-40 ** 100+/-10 41+/-9 57+/-13 58+/-9 100+/-10 150+/-15 SA-SW-1F2 K-40 ** 23+/-9 <7.0 <7.0 <7.0 22+/-10 84+/-11 SA-SW-16Fl(2) K-40 ** 65+/-10 25+/-9 <7.0 <7.0 64+/-10 84+/-10 AVERAGE K-40 67+/-56 26+/-26 23+/-43 25+/-43 69+/-58 103+/-63 RADIO- ANNUAL STATION NO. ACTIVITY 8-05-77 9-09-77 10-05-77 11-02-77 12-16-77 AVERAGE SA-SW-llAl K-40 . 100+/-10 120+/-12(1) 60+/-10 66+/-9 27+/-10 68+/-70 SA-SW-12Cl K-40 98+/-11 100+/-10 37+/-10 35+/-10 12+/-9 51+/-69 SA-SW-7El K-40 110+/-11 170+/-17 66+/-10 87+/-10 41+/-9 89+/-85 SA-SW-1F2 (3) K-40 57+/-11 79+/-11 10+/-9 14+/-9 <9.0 29+/-59 SA-SW-16Fl K-40 65+/-10 78+/-11 11+/-9 33+/-10 27+/-10 42+/-59 AVERAGE K-40 86+/-47 109+/-76 37+/-53 47+/-58 23+/-26 56+/-79

• By ganma spectrometry. all other gamma emitters <MDL; typical MDL's are given in table C-33.

• • No sa""le* collected because of icy conditions.

(1) Sample collection date was 9-13-77.

(2) Cs-134 and Cs-137 were observed in the February samples from this station with the concentrations being 0.8+/-0.6 pCi/l and 2.1+/-1.3 pCi/l respectively.

(3) Cs-137 was observed in the November and December samples from this station with the concentrations being 1.0+/-0.7 pCi/l and 1.5+/-0.9 pCi/1 respectively.

51

TABLE C-S CONCENTRATIONS OF STRONTIUM-89 AND--90 IN SURFACE WATER Results* in Units of pCi/1 +/- 2 sigma 2-28-77**to 3-07-77 4-04-77 to 6-03-77 7-11-77 to 9-09-77 10-05-77 to 12-16-77 STATION NO. Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90

. <1. 0(1)

SA-SW-llAl <1.2 <0.6 <1.2 <O. 7 <0.5(1) <0.8 0.4+/-0.3*

SA-SW-12Cl <1.6 <0.9 . <0.6 <0.4 <0.9 0.4+/-0.3 <0.9 0.7+/-0.3 SA-SW-7El <1.5 <0.7 <1.1 <0.6 <1.0 <0.5 1.0+/-0.7 <0.6 U1 N

SA-SW-1F2 <1.4 <O. 7 . <O. 7 0.5+/-0.3 <1.1 0.4+/-0.3 <1.2 <0.7 SA-SW-16Fl <1.2 <0.6 <0.7 0.3+/-0.3 <0.8 <0.4 <1.3 <0.7

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

• • No samples collected prior to 2-28-77 because of icing conditions.

(1) Sample dates were 7-11-77 to 9-13-77.

TABLE C-6 CONCENTRATIONS OF GAMMA EMITTERS* IN EDIBLE FISH Results in Units of pCi/g(wet) +/- 2 sigma SAMPLING STATION NO. DATE K-40 SA- ES F-1 lAl 6-07-77 to 4.2+/-0.4 6-25-77 8-09-77 to 3.8+/-0.4 8-31-77 SA-ESF-12Cl 6-07-77 to 3.1+/-0.3 6-25-77 8-09-77 to 4.3+/-0.4 8-31-77 SA-ESF-7El 6-07-77 to 3.3+/-0.3 6-25-77 8-09-77 to 4.2+/-0.4 8-31-77

• All other ganma emitters <MDL; typical MDLs are given in Table C-33.

53

TABLE C-7 CONCENTRATIONS OF STRONTIUM-89 AND-90, AND TRITIUM IN EDIBLE FISH SAMPLES SAMPLE TYPE FLESH FLESH BONES AQUEOUS FRACTION ORGANIC FRACTION (pCi/g(dry) +/- 2 sigma) {pCi/l +/- 2 sigma) (pCi/l +/- 2 sigma)

STATION NO. DATE Sr-89* Sr-90 H-3 H-3 SA-ESF-llAl 6-07-77 (J1 to 0.10+/-0.08 0.09+/-0.03 <80 358+/-67

..j:::> 6-25-77 8-09-77 to <2.2 <0.5 122+/-76 235+/-81 8-31-77 SA-ESF-12Cl 6-07-77 to + + 270+/-75 290+/-67 6-25-77 8-09-77 to <1. 7 <0.4 <80 . 175+/-81 8-31-77 SA-ESF-7El 6-07-77 to + + 119+/-74 142+/-66 6-25-77 8-09-77 to <8.8 <1.6 112+/-76 <84 8-31-77

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

+ Insufficient sample size.

TABLE C-8 CONCENTRATIONS OF GAMMA EMITTERS* IN BLUE CRAB SAMPLES Results in Units of pCi/g(wet) +/- 2 sigma STATION NO. DATE SAMPLE TYPE K-40 Cs-137 SA-ECH-llAl 6-28-77 Blue Crab (Hard Shell) 3. 3+/-0. 3 <0.008 8-09-77 to Blue Crab (Hard Shell) 2.2+/-0.2 <0.006 8-31-77 SA-ECH-12Cl 6-28-77 Blue Crab (Hard Shell) 2.9+/-0.3 0.02+/-0.01 8-09-77 to Blue Crab (Hard Shell) 2.6+/-0.3 <0.008

'a-31-77

• All other gamna emitters <MDL; typical MDLs are given in Table C-33.

55

TABLE C-9 CONCENTRATIONS OF STRONTIUM-89 AND-90, AND TRITIUM IN BLUE*CRAB SAMPLES Sr-89

• Sr-90 H-3 (EDIBLE PORTION)

STATION NO. DATE SAMPLE ( pCi I g +/- 2 s i gma) (pCi/g +/- 2 sigma) (pCi/l +/- 2 sigma)

SA-ECH-llAl 6-28-77 Flesh (wet) <0.03 <0.008 226+/-74 Shell (dry) 0.18+/-0.09 0.15+/-0.04 SA-ECH-llAl 8-09-77 Flesh (wet) <0.04 0.006+/-0.004 331+/-79 .

to Shell (dry) 0.3+/-0.2 0.33+/-0.04 8-31-77 SA-ECH-12Cl 6-28-77 Flesh (wet) * <0.03 <0.'007 184+/-73 Shell (dry) <0.1 0.21+/-0.04 U1

°' SA-ECH-12Cl 8-09-77 Flesh (wet) <0.04 0.006+/-0.004 83+/-77 to Shel 1 (dry) 0.4+/-0.2 0.32+/-0.04 8-31-77

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

TABLE C-10 CONCENTRATIONS OF STRONTIUM-89 AND-90, AND GAMMA EMITTERS* IN PREY FISH Results in Units of pCi/g(wet) +/- 2 sigma STATION NO. DATE Sr-89 ** Sr-90 K-40 SA-ESP-llAl 6-07-77 to <0.01 <0.004 3.1+/-0.3 6-25-77 8-09-77 to <0.2 <0.04 3.0+/-0.3 8-31-77 SA-ESP-12Cl 6-07-77 to <0.02 0. 004+/-0. 004 3.3+/-0.3 6-25-77 8-09-77 to <0.1 <0.03 2.5+/-0.3 8-31-77 SA-ESP-7El 6-07-77 to <0.02 <0.006 2. 7+/-0.3 6-25-77 8-09-77 to 0.13+/-0.09 <0.04 1. 9+/-0. 2 8-31-77

• All other gamma emitters <MDL; typical MDLs are given in Table C-33.

• • Sr-89 results* decay corrected to sample stop date.

57 '

TABLE C-11 CONCENTRATIONS OF GAMMA EMITTERS* IN SEDIMENT**

Results in Units of pCi/g(dry) +/- 2 sigma STATION NO. SA-ESS-llAl . SA-ESS-i2Cl SA-ESS-7El SA-ESS-16Fl DATE 6-08-77 9-12-77 6-08-77 9-12-77 6-08-77 9-12-77 6-08-77 9-12-77 NUCLIDE K-40 17+/-2(1) 16+/-2(2) 11+/-1 18+/-2(3) 13+/-1 11+/-1 18+/-2(4) 18+/-2 Nb-95 <0.02 0.04+/-0.03 0.02+/-0.01 <0.01 <0.01 o. 07+/-0. 03 <0.02 * <O. 02 U'i Cs-137 0.25+/-0.04 0.19+/-0.03 0.04+/-0.02 <0.01 0.05+/-0.02 0.07+/-0.03 o. 07+/-0. 03 o. 04+/-0. 03 0,,

Ra-226 0.81+/-0.08 0.70+/-0.07 1.0+/-0. l 0.75+/-0.08 0.72+/-0.07 0.71+/-0.07 o. 5+/-0.1 0.58+/-0.06 Th-232 0.8+/-0.2 0.46+/-0.06 0.69:!;0.07 o. 42+/-0. 07 0.73+/-0.07 0.38+/-0.07 0.8+/-0.1 0.54+/-0.08

• All other gamma emitters <MDL; typical MDLs are given in Table C-33.

• • Sediment samples included associated benthic organisms.

(1) Ru-103 was also observed in this sample with a concentration of 0.04+/-0.02 pCi/g(dry).

(2) Ce-144 was also observed in this sample with a concentration of 0.13+/-0.05 pCi/g(dry).

(3) - Mn-54 and Ce-141 were also-observed in this sample with a concentration of 0.02+/-0.01 pCi/g(dry) for both nuclides.

(4) Zr-95 and Sr-125 were also observed in this sample with a concentration of 0.04+/-0.03 pCi/g(dry) and 0.06+/-0.05 pCi/g(dry), respectively.

TABLE C-12 CONCENTRATIONS OF STRONTIUM-89* AND-90* IN BENTHOS AND SEDIMENT Results in Units of pCi/g {dry) +/- 2 sigma BEN TH OS SEDIMENT**

STATION NO. DATE Sr-89*** Sr-90 DATE Sr-90 SA-ESB-llAl 6-07-77 6-08-77 <0.05 to 20+/-11 <4.6 6-25-77 9-12-77 <0.04 9-12-77 <0.7 0.3+/-0.2 SA-ESB-12 Cl 6-07-77 6-08-77 <0.06 to <111 <31 6-25-77 9-12-77 <0.04 9-12-77 + +

SA-ESB-7El 6-07-77 6-08-77 <0.04 to <2.8 <0.8 6-25-77 9-12-77 <0.03 9-12-77 <0.5 0.1+/-0.1 SA-ESB-16Fl 6-07-77 6-08-77 <0.05 to <2370 <309 6-25-77 9-12-77 <0.04 9-12-77 + +

• High MDL values due to small sample size.

• • Sediment samples included associated benthic organisms.

+ Sample size too small to analyze.

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

59 .

TABLE C-13 CONCENTRATIONS OF ALPHA EMITTERS IN AIR PARTICULATES 3

Results in Units of 10- 3 pCi/m +/- 2 sigma STATION NO.

MONTH SA-AP-16El SA-AP-3H3 January 1.1+/-0. 6 2.1+/-0.8

1. 9+/-0. 6 2.1+/-0.6

<0.6 1. 4+/-0. 8 1.3+/-0. 7 0.5+/-0.5 February <0.2 <0.2

<1.8 <2. 3 1.2+/-0. 6 1. 4+/-0. 6

<0.6 1.8+/-1. 0 March 1. 0+/-0. 6 1. 6+/-0. 8

<0.3 2. 0+/-0.8 2.4+/-0.9 1.2+/-0.6 1.5+/-0. 6 0.5+/-0.4 0.6+/-0.5 1. 3+/-0. 6 April 1.3+/-0.7 o. 7+/-0. 7

1. 4+/-0. 9 o. 9+/-0. 7

<0.4 1.1+/-0. 7 1.4+/-0.8 1.1+/-0. 7 May 1.3+/-0.6 1.2+/-0.6 1.0+/-0.6 <0.4 0.8+/-0.5 1.8+/-0. 7 1.1+/-0.6 0.5+/-0.4 June 0.5+/-0.5 0.6+/-0.5 0.5+/-0.4 0.6+/-0.4

<0.3 1. 3+/-0. 6 0.8+/-0.5 0.9+/-0.5

1. 0+/-0. 6 1.1+/-0.6 6u i_

TABLE C-13 (CONT.)

CONCENTRATIONS OF ALPHA EMITTERS IN AIR PARTICULATES Results in Units of 10- 3 pCi/m3 +/- 2 sigma STATION NO.

MONTH SA-AP-16El SA-AP-3H3 July <0.5 1.2+/-0.8 0.8+/-0.5 0.9+/-0.6 1.6+/-0.8 1.5+/-0.8 0.9+/-0.7 2.1+/-0.9 August <0.9 <0.9 0.9+/-0.5 1.8+/-0. 7

<0.6 0.7+/-0.7 0.8+/-0.6 0.9+/-0.6 September 1.9+/-0. 7 2.6+/-0.8 0.9+/-0.7 1.4+/-0.8 0.9+/-0.5 1.0+/-0. 5 0.6+/-0.4 <0.6 October 0. 9+/-0. 6 1.4+/-0. 7 1.0+/-0.5 1.4+/-0. 6 1.0+/-0. 6 <0.3 1.6+/-0.6 1.2+/-0.5 0.9+/-0.6 1.6+/-0. 7 November 1.2+/-0.6 . 1.6+/-0. 7 0.6+/-0.4 1. 0+/-0. 6 0.7+/-0.5 1.1+/-0.6 0.8+/-0.5 0.7+/-0.6 December 0.9+/-0.6 0.7+/-0.6 1.2+/-0.6 0.7+/-0.5

<0.6 1.2+/-0.8 1.3+/-0.6 0.9+/-0.6 Average 1.0+/-0.9 1.2+/-1.1 61

TABLE C-14 CONCENTRATIONS OF BETA EMITTERS IN AIR PARTICULATES Results in Units of 10- 3 pCi/m3 +/- 2 sigma*

STATION NO.

MONTH SA-AP-2Sl SA-AP-5Sl SA-AP-501 SA-AP-1001 SA-AP-16El SA-AP-lFl SA-AP-2F2 SA-AP-3H3 AVERAGE January 55+/-6 58+/-6 53+/-6 62+/-6 58+/-6 64+/-6 59+/-6 51+/-6 58+/-9 62+/-7 63+/-7 55+/-6 64+/-7 59+/-7 57+/-7 67+/-7 62+/-7 61+/-8 35+/-6 27+/-6 27+/-5 29+/-6 30+/-6 31+/-6 37+/-6 23+/-5 30+/-9 33+/-5 31+/-5 53+/-6 28+/-5 31+/-6 30+/-5 25+/-5 31+/-6 33+/-17 February 32+/-6 30+/-5 28+/-5 29+/-5 27+/-5 28+/-5 27+/-5 26+/-5 28+/-4 (1) 47+/-6 45+/-6 43+/-5 42+/-5 38+/-5 46+/-6 38+/-6 43+/-7 36+/-4(2) 30+/-5 27+/-5 30+/-5 29+/-5 31+/-5 35+/-5 32+/-5 31+/-6 (1) 50+/-7 45+/-7 47+/-7 42+/-7 49+/-7 52+/-7 48+/-8 48+/-7 March 37+/-5(3) 35+/-7 36+/-6 41+/-6 31+/-6 39+/-6 40+/-6 79+/-9 42+/-30 55+/-7 52+/-7 55+/-7 48+/-6 50+/-6 51+/-7 57+/-7 65+/-8 54+/-11 60+/-7 62+/-8 58+/-7 60+/-8 53+/-8 54+/-7 53+/-7 55+/-7 57+/-7 54+/-7 52+/-7 53+/-6 53+/-7 46+/-7 50+/-6 54+/-7 46+/-7 51+/-7 o-.

'N 136+/-14 124+/-12 123+/-12 124+/-12 133+/-13 138+/-14 134+/-13 108+/-11 128+/-20 April . 76+/-8 78+/-8 78+/-8 81+/-8 79+/-8 71+/-7 63+/-7 72+/-8 75+/-12 203+/-20 194+/-19 176+/-18 210+/-21 248+/-25 204+/-20 205+/-21 183+/-18 203+/-43 178+/-18 187+/-19 190+/-19 155+/-16 156+/-16 186+/-19 194+/-19 170+/-17 177+/-30 177+/-18 159+/-16 150+/-15 188+/-19 175+/-18 159+/-16 158+/-16 118+/-12 161+/-43 May 242+/-24 260+/-26 238+/-24 236+/-24 224+/-22 248+/-25 261+/-26 218+/-22 241+/-31 254+/-25 286+/-29 259+/-26 268+/-27 286+/-29 263+/-26 274+/-27 253+/-25 268+/-26 356+/-36 351+/-35 348+/-35 285+/-29 350+/-35 289+/-29 330+/-33* 440+/-44 344+/-96 295+/-30 271+/-27 261+/-26 248+/-25 233+/-23 263+/-26 265+/-27 293+/-29 266+/-42 June 373+/-37 335+/-34 347+/-35 336+/-34 328+/-33 349+/-35 339+/-34 324+/-32 341+/-31 329+/-33 310+/-31 301+/-30 262+/-26 270+/-27 298+/-30 303+/-30 288+/-29 295+/-43 223+/-22 217+/-22 230+/-23 214+/-21 195+/-20 194+/-19 230+/-23 265+/-27 221+/-45 230+/-23 245+/-25 222+/-22 222+/-22 239+/-24 230+/-23 227+/-23 195+/-20 226+/-30 278+/-28 298+/-30 270+/-27 282+/-28 283+/-28 2!W+/-29 286+/-29 257+/-26 281+/-25

TABLE C-14 (CONT.)

CONCENTRATIONS OF BETA EMITTERS IN AIR PARTICULATES Results in Units of 10- 3 pCi/m3 +/- 2 sigma STATION NO.

MONTH SA-AP-2Sl SA-AP-5Sl SA-AP-5Dl SA-AP-lODl SA-AP-16El SA-AP-lFl SA-AP-2F2 SA-AP-3H3 AVERAGE July 151+/-15 148+/-15 143+/-14 130+/-13 133+/ 155+/-16 158+/-16 181+/-18 150+/-32 237+/-24 232+/-23 210+/-21 192+/-19 209+/-21 219+/-22 219+/-22 252+/-25 221+/-37 218+/-22 234+/-23 198+/-20 189+/-19 180+/-18 216+/-22 222+/-22 221+/-22 210+/-37 166+/-17 170+/-17 142+/-14 147+/-15 144+/-14 168+/-17 168+/-17 179+/-18 161+/-28 August 151+/-15 152+/-15 147+/-15 143+/-14 145+/-1'5 139+/-14 144+/-14 160+/-16 148+/-13

. 92+/-9 96+/-10

• 80+/-8 77+/-8 95+/-9 88+/-9 89+/-9 105+/-11 90+/-18 187+/-19 183+/-18 207+/-21 190+/-19 191+/-19 204+/-20 190+/-19 200+/-20 194+/-17 216+/-22 212+/-21 202+/-20 191+/-19 191+/-19 197+/-20 183+/-18 182+/-18 197+/-25 September 158+/-16 143+/-14 123+/-12 104+/-10 120+/-12 116+/-12 140+/-14 123+/-12 128+/-35 113+/-11 102+/-10 104+/-10 120+/-12 120+/-12 116+/-12 129+/-13 107+/-11 114+/-18 98+/-10 100+/-10 83+/-8 97+/-10 90+/-9 93+/-9 101+/-10 90+/-9 94+/-12 C-1 146+/-15 67+/-7 59+/-7 90+/-9 52+/-6 157+/-16 143+/-14 29+/-9 93+/-99 w

October 456+/-46 543+/-54 461+/-46 524+/-52 466+/-47 446+/-45 384+/-38 426+/-43 463+/-102 238+/-24 189+/-19 234+/-23 233+/-23 221+/-22 189+/-19 213+/-21 237+/-24 219+/-41 136+/-14 123+/-12 137+/-14 158+/-16 188+/-19 133+/-13 143+/-14 153+/-15 146+/-40 231+/-23 211+/-21 200+/-20 185+/-19 168+/-17 195+/-20 216+/-22 187+/-19 199+/-40 113+/-11 125+/-13 143+/-14 136+/-14 139+/-14 123+/-12 117+/-12 173+/-17 134+/-38 November 90+/-9 87+/-9 99+/-10 95+/-9 93+/-9 102+/-10 91+/-9 146+/-15 100+/-38 76+/-8 70+/-7 69+/-7 73+/-7 67+/-7 73+/-7 72+/-7 53+/-7 69+/-14 142+/-14 156+/-16 135+/-14 152+/-15 143+/-14 119+/-12 120+/-12 126+/-13 137+/-28 68+/-7 59+/-7 62+/-7 61+/-7 63+/-7 63+/-7 55+/-7 72+/-8 63+/-10 December 49+/-5 47+/-5 48+/-5 51+/-6 51+/-6 47+/-5 42+/-5 51+/-6 48+/-6 59+/-8 58+/-8 58+/-8 58+/-7 64+/-7 61+/-8 56+/-7 54+/-7 59+/-6 55+/-6 48+/-6 56+/-6 45+/-6 40+/-6 43+/-6 54+/-6 63+/-8 51+/-16 56+/-6 54+/-7 55+/-6 62+/-7 62+/-7 60+/-7 63+/-7 55+/-7 58+/-7 Average 153+/-204 146+/-215 141+/-198 140+/-198 140+/-197 142+/-192 144+/-189 144+/-204 144+/-198 (1) Unable to service air monitor due to poor weather conditions.

(2) Sample period was 2-07-77 to 2-22-77.

(3) Sample period was 2-22-77 to 3-07-77.

TABLE C-15 CONCENTRATIONS OF GAMMA EMITTERS* IN QUARTERLY .COMPOSITES OF AIR PARTICULATE SAMPLES Results** in Units of 10- 3 pCi/m3 +/- 2 sigma STATION NO.

AND DATE Be-7 Mn-54 Zr-95 Nb-95 Ru-103 Ru-106 Sb-125 . Cs-137 BaLa-140 Ce-141 Ce-144 SA-AP-2Sl 12-13-76 to 58+/-6 <0.1 2.8+/-0.5 3.5+/-0.4 1.8+/-0.3 <MDL <0.4 0.3+/-0.2 <0.9 1.8+/-0.4 2.1+/-1.0 3-29-77 3-29-77 to 98+/-10 <0.2 32+/-3 49+/-5 13+/-1 18+/-5 1.1+/-0.6 3.1+/-0.6 <2.7 7.4+/-0.8 48+/-5 6-27-77 6-27-77(1) to 58+/-10 <0.2 12+/-2 15+/-2 3.5+/-1.4 14+/-4 <0.8 2.3+/-0.5 <20 <1.4 45+/-5 9-27-77 9-27-77 to 97+/-18 <0.4 14+/-2 10+/-1 11+/-3 17+/-4 2.4+/-1.1 2.6+/-0.5 <173 13+/-3 35+/-4

a. 11-28-77 11-28-77 to 71+/-11 <0.4 2.7+/-1.3 3.8+/-0.9 1.3+/-0.8 <MDL <1.0 1.2+/-0.7 <4.4 <0.9 14+/-3 12-27-77 SA-AP-5Sl 12-13-76 to 69+/-7 <0.1 3.0+/-0.5 *4.2+/-0.4 2.3+/-0.3 <MDL <0.3 . 0.4+/-0. 2 <0.5 1.7+/-0.3 2.4+/-1.2 3-29-77 3-29-77 to 108+/-11 <0.2 35+/-3 49+/-5 14+/-1 17+/-3 1.5+/-0.6 2.8+/-0.4 <2.1 7.9+/-0.9 51+/-5 6-27-77 6-27-77 to 80+/-8 <0.2 14+/-1 18+/-2 3.4+/-0.6 15+/-3 1. 7+/-0.4 3.3+/-0.5 <6.0 1.8+/-0.6 37+/-4 9-26-77 9-26-77(2) to 101+/-20 <0.5 13+/-3 11+/-1 10+/-4 12+/-5 3.0+/-1.9 3.1+/-0.7 <277 16+/-9 30+/-4 11-28-77 11-28-77 to 76+/-20 <0.9 <3.0 3.1+/-1.2 <1.7 <MDL <3.1 1.1+/-0.9 11+/-11 <2.2 15+/-8 12-27-77

TABLE C-I5 (Cont.)

CONCENTRATIONS OF GAMMA EMITTERS* IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES Results**' in Units of 10- 3 pCi/m3' +/-. 2 sigma STATION NO.

AND DATE Be-7

• Mn-54 Zr-95 Nb-95 Ru-103

.. .. . .. Ru-106 Sb-I25 .Cs-I37 BaLa-I40 Ce-I4I Ce-I44 SA-AP-5DI I2-I3-76 to 63+/-6 <0.I 2.3+/-0.4 . 3.4+/-0.3 I.7+/-0.3 I.6+/-I.I <0.3 0.4+/-0.2 <0.7 I. 7+/-0.4 2.3+/-0.9 3-29-77 3-29-77 to 50+/-6 <0.2 I7+/-2 24+/-2 6.0+/-0.8 11+/-3 I.I+/-0.8 2.0+/-0.4 <2.3 4.0+/-0.7 24+/-2 6-27-77 6-27-77(3) to 69+/-7 0.3+/-0.2 I4+/-I 18+/-2 3.4+/-0.7 18+/-3 2.7+/-0.6 3.2+/-0.I <6.0 I. 7+/-0. 7 41+/-4 9-26-77 9-26-77 0) to 26+/-22 <0.3 16+/-4 7.3+/-I.O 4.6+/-3.2 <MDL <1.0 <0.4 <227 <5.6 36+/-6 01 11-28-77 11-28-77 to 78+/-I2 <0.4 3.I+/-I.I 4.3+/-0.9 <0.8 <MDL 1.6+/-1.4 2.5+/-0.8 <5.5 <I.6 18+/-5 I2-27-77 SA-AP-IODI I2-14-76 to 58+/-6 <0.I I.8+/-0.4 2.9+/-0.4 I.9+/-0.3 <MDL <0.3 0.2+/-0.2 <0.8 I.4+/-0.3 2.8+/-0.9 3-28-77 3-28-77 to 93+/-9 <0.2 30+/-3 43+/-4 11+/-1 16+/-3 1.6+/-0.6 2.2+/-0.3 <2.4 7.1+/-0.8 47+/-5 6-27-77 6-27-77 to 70+/-7 0.3+/-0.3 I3+/-1 16+/-2 2.7+/-0.9 15+/-4 1.7+/-0.6 3.1+/-0.5 <7.9 <I.2 48+/-5 9-26-77 9-26-77 to 87+/-20 <0.3 8.3+/-4.3 8.8+/-1.2 9.0+/-3.5 6.3+/-5.I <I.I 1.0+/-0. 7 <232 <5.2 31+/-6 11-28-77 11-28-77( 4) to 73+/-11 <0.4 1.9+/-1.2 3.1+/-0.9 <0.8 <MDL <I.0 1.6+/-0.8 <3.7 <0.9 15+/-4 12-28-77

TABLE C-15 (Cont.)

CONCENTRATIONS OF GAMMA EMITTERS* IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES Results** in Units of 10- 3 pCi/m 3 ~ 2 sigma STATION NO.

AND DATE Be-7 Mn-54 Zr-95 Nb-95 Ru-103 Ru-106 Sb-125 Cs-137 BaLa-140 Ce-141 Ce-144 SA-AP-16El 12-14-76 to 56+/-6 <0.1 1.7+/-0.5 2.8+/-0.3 1.6+/-0.*3 <MDL <0.3 0.5+/-0.2 <0.8 1.3+/-0.5 2.0+/-1.1 3-28-77 3-28-77 to 85+/-8 <:0.2 27+/-3 42+/-4 101+/-1 16+/-3 1.5+/-0.5 2.7+/-0.4 *<1.8_ 6.7+/-0.8 36+/-4 6-27-77 6-27-77 to 78+/-9 <0.3 15+/-2 19+/-2 3.5+/-0.9 17+/-3 2.0+/-0.6 3.4+/-0.5 <6.6 <0.9 51+/-5 9-26-77 9-26-77(5) to 91+/-16 <0.4 15+/-2 9.3+/-0.9 9.0+/-2.8 16+/-4 2.2+/-0.9 2.6+/-0.5 <232 15+/-4 33+/-3

"' 11-28-77 11-28-77(6) to 94+/-26 <1.1 <3.0 4.8+/-1.3 <1.7 <MDL <3.1 2.0+/-1.7 <15 <2.2 19+/-10 12-28-77 SA-AP:-lFl 12-13-76 to 57+/-6 <0.08 1.5+/-0.4 3.0+/-0.3 1.8+/-0.3 2. 7+/-1.1 <0.3 0.3+/-0.1 <0.7 1.3+/-0.4 2.4+/-1.0 3-29-77 3-29-77 to 97+/-10 <0.2 32+/-3 44+/-4 11+/-1 16+/-5 3.4+/-1.2 2.3+/-0.4 <2.7 6.8+/-0.8 41+/-4 6-27.-77 6-27-77 to 66+/-9 0.3+/-0.3 13+/-1 14+/-1 4.6+/-1.2 15+/-4(7) 1~7+/-0.9 3.2+/-0.6 . <25 <1.4 48+/-5.

9-27-77 9-27-77 to 86+/-15 <0.4 13+/-2 7.5+/-0.8 11+/-3 14+/-4 2.1+/-1.3 3.0+/-0.5 <220 13+/-3 31+/-3 11-28-77 11-28-77(8) to 83+/-13 <0.5 2.8+/-1.9 5.5+/-1.3 1.1+/-1.0 <MDL 39+/-37 2.4+/-1.1 <5.4 18+/-13 21+/-5 12-27-77

TABLE C-15 (Cont.)

CONCENTRATIONS OF GJIM.IA EMITTERS* IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES Results** in Units of 10- 3 pCi/m3 +/- 2 sigma STATION NO.

AND DATE Be-7 Mn-54 Zr-95 Nb-95 Ru-103 Ru-106 Sb-125 Cs-137 BaLa-140 Ce-141 Ce-144 SA-AP-2F2 12-13-76 to 67+/-7 <0.1 2.4+/-0.9 4.2+/-0.5 2.1+/-0.4 <MDL <0.4 0.4+/-0.2 <0.7 1. 5+/-0.4 2.3+/-0.9 3-29-77 3-29-77 to 94+/-9 <0.2 29+/-3 42+/-4 11+/-1 17+/-3 1. 5+/-0.6 2.8+/-0.4 <2.3 6.7+/-0.8 41+/-4 6-27-77 6-27-77 to 76+/-8 0.4+/-0.2 14+/-1 15+/-2 5. 5+/-1.1 18+/-3 2.0+/-0.6 3.2+/-0.4 <16 2.7+/-0.9 42+/-4 9-27-77 9-27-77 to 86+/-18 <0.5 15+/-3 10+/-1 11+/-4 16+/-7 3.8+/-1.5 3.3+/-0. 7 <293 15+/-8 42+/-4 11-28-77 11-28-77(9) to 87+/-24 <1.0 3.2+/-2.3 5.7+/-1.8 3.0+/-2.1 <MDL <2.0 1. 9+/-1.1 10+/-9 <2.0 18+/-8 12-27-77 SA-AP-3H3 12-13-76 to 73+/-7 <0.2 3.0+/-0.7 3.6+/-0.4 2.2+/-0.4 -<MDL <0.4 0.6+/-0.2 <1.2 1.7+/-0.4 1.3+/-0.9 3-28-77 3-28-77 to 93+/-9 <0.09 31+/-3 21+/-2 11+/-1 11+/-4 1.4+/-1. l 2.3+/-0.5 <3.0 5.5+/-0.7 41+/-4 6-27-77 6-27-77 to 74+/-8 <0.2 14+/-1 18+/-2 2.9+/-0.9 19+/-3 1.8+/-0. 6 3.3+/-0.4 <8.3 1. 6+/-0. 7 41+/-4 9-22-77 9-22-77 to 100+/-20 <0.5 18+/-4 10+/-1 12+/-5 22+/-9 <1.1 2.8+/-0.7 <309 13+/-9 37+/-5 11-28-77 11-28-77 to 78+/-13 <0.4 1.8+/-1.3 2.8+/-0.9 <1.0 <MDL <1.0 1.2+/-0.8 <5.5 <1.8 13+/-6 12-27-77

• All other gamma emitters <MDL; typical MDLs are found in Table C-33.

** .. Results corrected for decay to sample stop date with one exception.

The nuclide Nb-95 was not decayed.since it does not reach equilibrium.

( 1) K-40 was observed in this sample with a result of 0.024+/-0.006 pCi/cubi3 meter.

(2) Co-58 was observed in this sample with a result of 0.0013+/-0.0012 pCi/m *

(3) Co-58 was observed in this sample with a result of 0.0003+/-0.0003 pCigcubic meter.

(4) I-131 was observed in this sample with a result of 0.014+/-0.010 pCi/m

• 3 The MDL for I-131 at the control station, 3H3, for this date was o.012 3pCi/m *

(5) Co-58 was observed in this sample with a result of 0.0015+/-0.0011 pCigm *

(6) Cr-51 was observed in this sample with a result of 0.021+/-0.018 pCi/m *

(7) This result is for RuRh-106.

~8) Co-60 was observed in this sample with a result of 0.0012+/-0.0008 pC~/m 3*

9) K-40 was observed in this sample with a result of 0.130+/-0.022 pCi/m

• 67

TABLE C-16 CONCENTRATIONS OF STRONTIUM-89* AND-90 IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES Results in Units of 10-J pCi/m3 +/- 2 sigma JAN to MAR APR to JUN JUL to SEP OCT to NOV DEC STATION NO. Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 SA-AP-251 1.6+/-0.6 <0.4 11+/-2 1.4+/-0.5 5.7+/-1.1 1.3+/-0.3 7.9+/-2.1 1.2+/-0.4 <1.6. 0.7+/-0.4 SA-AP-551 1.4+/-0.5 <0.3 13+/-2 0.9+/-0.6 4.6+/-1.2 1.4+/-0.3 8.6+/-2.1 1.0+/-0.4 <2.6 0.7+/-0.6 SA-AP-501 1. 7+/-0.5 <0~3 11+/-1 1.4+/-0.5 4.0+/-1.2 1. 7+/-0.3 5.3+/-2.3 1.4+/-0.4 <2.5 )~.9 SA-AP-1001 1.3+/-0.6 <0.5 11+/-1 0.9+/-0.5 5.3+/-1.3 1.1+/-0.3 6.5+/-2.1 1.2+/-0.4 <2.4 0.6+/-0.6 SA-AP-16El 1.6+/-0.5 <0.3 11+/-1 1.3+/-0.5 4.5+/-1.2 1.4+/-0~3 6.5+/-2.5 1.6+/-0.4 <2.4 <0.9 SA-AP-lFl l.6+/-0.5 0.3+/-0.2 7.9+/-2.1 1.1+/-0.7 3.8+/-1.1 2.0+/-0.3 5.7+/-2.4 1.3+/-0.4 <2.0 <0.8 0)

(X)

SA-AP-2F2 1.4+/-0.5 0.4+/-0.2 8.5+/-1.7 2.6+/-0.6 4.8+/-1.4 1.5+/-0.4 6.8+/-1.9 1.0+/-0.3 <2.2 <0.8 SA-AP-3H3 1.6+/-0;5 <0.3 10+/-2 1.3+/-0.5 4.4+/-1.5 1.4+/-0.4 6.3+/-2.6 1.1+/-0.4 <2.7 0.8+/-0.6

• Sr-89 results corrected to sample stop date.

TABLE C-17 CONCENTRATIONS OF IODINE-131 IN FILTERED AIR Results* in Units of 10- 3 pCi/m3 STATION NO.

MONTH SA-AI-2Sl SA-AI-5Sl SA-AI-501** SA-AI-1001 SA-AI-16El SA-AI-2F2 SA-AI-3H3 JAN 3.8+/-2.6 <2.7 <2.5 <2.9 <2.2 <3.5

<3.2 5.2+/-3.4 4.1+/-2.7 5.5+/-3.1 5.1+/-3.0 11+/-4

<2.6 <3.4 <3.2 <2.8 <2.8 <3.8

<3.0 3.8+/-2.7 6.0+/-3.1 <4.0 6.0+/-2.6 4.5+/-4.0 FEB <5.9 <5.9 <5.0 <5.5 <5.2 <5.9 (1) <5.3 <4.2 <4.7 <5.3 <6.8

<2.8(2) <4.4 - <4.7 <4.9 <4.6 <5.2 C'I (1) <6.0 <6.9 <7.4 <5.7 <8.9 c..o MAR <3.4(3) <6.0 <5.4 <5.3 <4.7 <6.4

<6.0 <6.3 <4.7 <5.4 <7.0 <7.4

<5.3 <5.7 <6.1 <6.6 <5.0 <5. 7

<4.6 <4.4 <5.l <4.8 <4.2 <5.1

<5.8 <5.9 <5.2 <5.2 <5.5 <5.3 APR <5.1 <5.3 <4.9 <5.0 <5.6 <6.0

<4.8 <5.1 <5.4 <6.1 <4.8 <5.4

<13 <5.1 <5.5 <4.6 <4.5 <5.4 <6.0

<5.6 <5.2 <5.2 <5.4 <6.0 <4.9 <5.9 MAY <5.9 <5.7 <6.1 <4.7 <5.0 <6.0 <6.2

<5.5 <5.6 <5.5 <6.0 <6.4 <5.4 <5. 7_

<5.8 <5.6 <6.1 <4.7 <4.8 <6.1 <6.2

<4.6 <4.3 <4.6 <4.9 <4.9 <4.5 <5. 3-JUN <6.8 <6.7 <7.3 <5.5 <5.4 <6.7 <7.1

<4.8 <4.9 <5.4 <5.1 <5.4 <5.0 <6.0

<5.9 <5.7 <5.6 <5.3 <5.4 <5.9 <6.5

<4.9 <5.1 <5.5 <6.0 <6.6 <5.5 <6.2

<4.9 <4.5 <4.8 <4.4 <4.6 <4.8 <5.1

TABLE C-17 (Cont.)

CONCENTRATIONS OF IODINE-131 IN FILTERED AIR Results* in Units of 10- 3 pCi/m3 STATION NO.

MONTH SA-AI-2Sl SA-AI-5Sl SA-AI-501 SA-AI-1001 SA-AI-16El SA-Al-2F2 SA-AI-3H3 JUL <6.3 <7.5 <6.9 <5.2 <5.0 <6.4 <6.8

<6.1 <5.4 <5.9 <5.6 <5.7 <5.7 <7.3

<5.7 <5.9 <6.5 <5.6 <4.9 <5.9 <5.9

<5.5 <6.3 <5."6 <6.1 (4) <4.8 <6.6 AUG <6.1 <5.8 <6.0 <5.4 <4.9 <6.6 <5.3

<5.6 <5.6 <6.5 <6.0 <5.7 <6.2 <5.9

<5.9 <6.0 <5.6 <4.8 <5.2 <5.6 <6.0

<5.5 <5.8 <5.9 <6.3 <6.0 <5.6 <6.6 SEP <5.0 <5.7 <5.2 <4.8 <4.0 <5.1 <5.2

<5.9 <5.8 <6.1 <5.8 <5.6 <6.6 <6.1

<5.0 <5.7 <5.7 <6.3 <6.3 <6.4 <6.3

<5.2 <5.8 <6.0 <6.3 <5.7 <5.4 <21 OCT 21+/-11 31+/-8 28+/-10 26+/-10 35+/-8 33+/-11 20+/-8 10+/-6 <4.9 <5.5 <5.8 <5.7 <5.2 <7.7

<6.1 <6.7 <7.2 <7.0 <6.9 <6.0 <7.5

<5.4 <5.7 <5.6 <4.7 <4.6 <5.8 <6.4

<5.3 (5.7 <5.5 <6.1 <6.1 <5.4 <6.9 NOV <5.4 <6.1 <7.6 <8.3 <7.6 <7.4 <5.9

<5.3 <5.5 <5.7 <4.4 <4.5 <5.4 <6.4

<4.8 <4.9 <5.6 <6.2 <5.9 <4.6 <6.4

<4.7 <5.1 <4.8 <4.9 <4.9 <5.5 <5.5 DEC <4.5 <4.6 <4.8 <6.3 <5.9 <4.5 . <6. 9

<5.8 <6.4 <6.0 <4.4 <4.8 <5."9 <6.4

<4.8 <5.0 <5.3 <5.1 <5.5 <5.0 <6.9

<4.4 <4.9 <4.6 <4.5 <5.0 <5.2 <5.7

• Results corrected for decay to sampling stop date.

• • Station 501 began weekly sampling on April 18, 1977.

(1) Unable to service air monitor due to poor weather conditions.

~2) Sampling period was 2-07-77 to 2-22-77.

3) Sampling period was 2-22-77 to 3-07-77.

(4) Cartridge was damaged in field; therefore it was not analyzed.

70

TABLE C-18 SAMPLING DATES FOR AIR SAMPLES STATION NO.

MONTH 2Sl 5Sl 501 1001 16El lFl 2F2 3H3 January 1-03-77 1-03-77 1-03-77 1-04-77 1-04-77 1-03-77 1-03-77 1-03-77 to to to to to to to to 1-11-77 1-11-77 1-11-77 1-12-77 1-12-77 1-11-77 1-11-77 1-11-77 1-11-77 1-11-77 1-11-77 1-12-77 1-12-77 1-11-77 1-11-77 1-11-77 to to to to to to to to 1-18-77 1-18-77 1-18-77 1-19-77 1-19-77 1-18-77 1-18-77 1-18-77 1-18-77 1-18-77 1-18-77 1-19-77 1-19-77 1-18-77 1-18-77 1-18-77 to to to to to to to to 1-24-77 1-24-77 1-24-77 1-25-77 1-25-77 1-24-77 1-24-77 1-24-77 1-24-77 1-24-77 1-24-77 1-25-77 1-25-77 1-24-77 1-24-77 1-24-77 to to to to to to to to 2-01-77 2-01-77 1-31-77 1-31-77 1-31-77 1-31-77 2-01-77 1-31-77 February 2-01-77 2-01-77 1-31-77 1-31-77 1-31-77 1-31-77 2-01-77 1-31-77 to to to to . to to to to 2-07-77 2-07-77 2-07-77 2-07-77 2-07-77 2-07-77 2-07-77 2-07-77 2-07-77 2-07-77 2-07-77 2-07-77 2-07-77 2-07-77 2-07-77 (1) to to to to to to to 2-14-77 2-14-77 2-15-77 2-15-77 2-14-77 2-14-77 2-14-77 2-07-77 2-14-77 2-14-77 2-15-77 2-15-77 2-14-77 2-14-77 2-14-77 to to to to to to to to 2-'?-2-77 2-22-77 2-22-77 2-22-77 2-22-77 2-22-77 2-22-77 2-22-77 2-22-77 2-22-77 2-22-77 2-22-77 2-22-77 2-22-77 2-22-77

( 1) to to. to to to to to 3-01-77 2-28-77 2-28-77 2-28-77 2-28-77 3-01-77 2-28-77 March 2-22-77 3-01-77 2-28-77 2-28-77 2-28-77 2-28-77 3-01-77 2-28-77 to to to to to to to to 3-07-77 3-07-77 3-07-77 3-07-77 3-07-77 3-07-77 3-08-77 3-07-77 3-07-77 3-07-77 3-07-77 3-07-77 3-07-77 3-07-77 3-08-77 3-07-77 to to to to to to to to 3-14-77 3-14-77 3-14-77 3-15-77 3-15-77 3-14-77 3-14-77 3-14-77 3-14-77 3-14-.77 3-14-77 3-15-77 3-15-77 3-14-77 3-14-77 3-14-77 to to to to to to to to 3-21-77 3-21-77 3-21-77 3-21-77 3-21-77 3-21-77 3-21-77 3-21-77 3-21-77 3-21-77 3-21-77 3-21-77 3-21-77 3-21-77 3-21-77 3-21-77 to to to to to to to to 3-29-77 3-29-77 3-29-77 3-28-77 3-28-77 3-29-77 3-29-77 3-28-77 3-29-77 3-29-77 3-29-77 3-28-77 3-28-77 3-29-77 3-29-77 3-28-77 to

• to to to to to . to to 4-04-77 4-04-77 4-04-77 4-04-77 4-04-77 4-04-77 4-04-77 4-04-77 71

TABLE C-18 (tont.)

SAMPLING DATE~ FOR AIR SAMPLES STATION NO.

MONTH 2Sl 5Sl SDI*. 1001 16El lFl 2F2 3H3 April 4-04-77 4-04-77 4-04-77 4-04-77 4-04-77 4-04-77 4-04-77 4-04-77 to to to. to to to to to 4-11-77 4-11-77 4-11-77 4-12-77 4-12-77 4-11-77 4-11-77 4-11-77 4-11-77 4-11-77 4-11-77 4-12-77 4-12-77 4-11-77 4-11-77 4-11-77 to to to to to to to to 4-18-77 4-18-77 4-18-77 4-18-77 4-18-77 4-18-77 4-18-77 4-18-77 4-18-77 4-18-77 4-18-77 4-18-77 4-18-77 4-18-77 4-18-77 4-18-77 to to to to to to to to 4-22-77 4-25-77 4-25-77 4-26-77. 4-26-77 4-25-77 4-25-77 4-25-77 4-26-77 4.:.25-77 4-25-77 4-26-77 4-26-77 4-25-77 4-25-77 4-25-77 to to to to to to to to 5-02-77 5-02-77 5-02-77 5-02-77 5-02-77 5-02-77 5-02-77 5-02-77 May 5-02-77 5-02-77 5-02-77 5-02-77 5-02-77 5-02-77 5-02-77 5-0~-77 to to to to to to to to 5-09-77 5-09-77 5-09-77 5-10-77 5-10-77 5-09-77 5-09-77 5-09-77 5-09-77 5;.09-77 5-09-77 5-10-77 5-10-77 5-09-77 5-09-77 5-09-77 to to to to to to to to 5-16-77 5-16-77 5-16-77 5-16-77 5-16-77 5-16-77 5-16-77 5-16-77 5-16-77 5-16-77 5-16-77 5-16-77 5-16-77 5-16-77 5-16-77 5-16-77 to to to to to to to to 5-23-77 5-23-77 5-23-77 5-24-77 5-24-77 5-23-77 5-23-77 5-23-77 5-23-77 5-23-77 5-23-77 5-24-77 5-24-77 5-23-77 5-23-77 5-23-77 to to to to to to to to 5-31-77 5-31-77 5-31-77 5-31-77 5-31-77 5-31-77 5-31-77 5-31-77 June 5-31-77 5-31-77 5-31-77 5-31-77 5-31-77 5-31-77 5-31-77 5-31-77 to to to to to to to to 6-06-77 6-06-77 6-06-77 6-07-77 6-07-77 6-06-77 6-06-77 6-06-77 6-06-77 6-.06-77 6-06-77 6-07-77 6-07-77 6-06-77 6-06-77 6-06-77 to to to to to to to to 6-13-77 6-13-77 6-13.:.77 . 6-14-77 6-14-77 6-13-77 6-13-77 6-13-77 6-13-77 6-13-77 6-13-77 6-14-77 6-14-77 6-13-77 6-13-77 6-13-77 to to to to to to to to 6-20-77 6-20-77 6-20-77 6-21-77 6-21-77 6-20-77 6-20-77 6-20-77 6-20-77 ',6-20-77 6-20-77 6-21-77 6-21-77 6-20-77 6-20-77 . 6-20-77 to to to to to to to to 6-27-77 6-27-77 6-27-77 6-27-77 6-27-77 6-27-77 6-27-77 6-27-77 6-27-77 ' *~-27-77 6-27-77 6-27-77 6-27-77 6-27-77 6-27-77 6-27-77 to . to to to to to to to 7-05-77 7-05-77 7-05-77 7-05-77 7-05-77 7-05-77 7-05-77. 7-05-77 72

TABLE.C-18 (Cont.)

SAMPLING DATES FOR AIR SAMPLES STATION NO.

MONTH 2Sl 5Sl 501 1001 16El lFl 2F2 3H3 July 7-05-77 7-05-77 7-05-77 7-05-77 7-05-77 7-05-77 7-05-77 7-05-77 to to to to to to - to to 7-11-77 7-11-77 7-11-77 7-12-77 7-12-77 7-11-77 7-11-77 7-11-77 7-11-77 7-11-77 . 7-11-77 7-12-77 7-12-77 7-11-77 7-11-77 7-11-77 to to to to to to to to 7-18-77 7-18-77 7-18-77 7-19-77 7-19-77 7-18-77 7-18-77 7-18-77 7-18-77 7-18-77 7-18-77 7-19-77 7-19-77 7-18-77 7-18-77 7-18-77 to to to to to to to to 7-25-77 7-25-77 7-25-77 7-26-77 7-26-7'7 7-25-77 7-25-77 7-25-77 7-25-77 7-25-77 7-25-77 7-26-77 7-26-77 7-25-77 7-25-77 7-25-77 to to to to to to to to 8-02-77 8-01-77 8-01-77 8-01-77 8-02-77 8-01-77 8-02-77 8-01-77 August 8-02-77 8-01-77 8-01-77 8-02-77 8-02-77 8-01-77 8-02-77 8-01-77 to to to to to to_ to to 8-08-77 8-08-77 8-08-77 8-09-77 8-09-77 8-08-77 8-08-77 8-08-77 8-08-77 8-08-77 8-08-77 8-09-77 8-09-77 8-08-77 8-08-77 8-08-77 to to to to to to to to 8-15-77 8-15-77 8-15-77 8-16-77 8-16-77 8-15-77 8-15-77 8-15-77 8-15-77 8-15-77 8-15-77 8-16-77 8-16-77 8-15-77 8-15-77 8-15-77 to to to to to to to to 8-22-77 8-22-77 8-22-77 8-23-77 8-23-77 8-22-77 8-22-77 8-22-77 8-22-77 8-22-77 8-22-77 8-23-77 8-23-77 8-22-77 8-22-77 8-22-77 to to to to to to to to 8-29-77 8-29-77 8-29-77 8-29-77 8-29-77 8-29-77 8-29-77 8-29-77 September 8-29-77 8-29-77 8-29-77 8-30-77 8-29-77 8-29-77 8-29-77 8-29-77

. to to to to to to to to 9-06-77 9-06-77 9-06-77 9-07-77 9-07-77 9-06-77 9-06-77 9-06-77 9-06-77 9-06-77 9-06-77 9-07-77 9-07-77 9-06-77 9-06-77 9-06-77 to to to to to to to to 9-12-77 9-12-77 9-12-77 9-13-77 9-13-77 9-12-77 9-12-77 9-12-77 9-12-77 9-12-77 9-12-77 9-13-77 9-13-77 9-12-77 9-12-77 9-12-77 to to to to to to to to 9-19-77 9-19-77 9-19-77 9-19-77 9-19-77 9-19-77 9-19-77 9-19-77 9-19-77 9-19-77 9-19-77 9-19-77 9-19-77 9-19-77 9-19-77 9-19-77 to to to to to to to to 9-27~77 9-26-77 9-26-77 9-26-77 9-26-77 9-27-77 9-27-77 9-22-77 73

TABLE C-18 (Cont.)

SAMPLING DATES FOR AIR SAMPLES STATION NO.

MONTH 2Sl 5Sl 501 1001 16El lFl 2F2 3H3 October 9-27-77 . 9-26-77 9-26-77 9-26-77 9-26-77 9-27-77 9-27-77 9-26-77 to to to to to to to to 10-03-77 10-03-77 10-03-77 10-03-77 10-03-77 10-03-77 10-03-77 10-03-77 10-03-77 10-03-77 10-03-77 10-03-77 10-03-77 10-03-77 10-03-77 10-03-77 to to to to to to to to 10-11-77 10-11-77 10-11-77 10-11-77 10-11-77 10-11-77 10-11-77 10-11-77 10-11-77 10-11-77 10-11-77 10-11-77 10-11-77 10-11-77 10-11-77 10-11-77 to to to to to to to to 10-17-77 10-17-77 10-17-77 10-17-77 10-17-77 10-17-77 10-17-77 10-17-77 10-17-77 10-17-77 10-17-n 10-17-77 10-17-77 10-17-77 10-17-77 10-17-77 to to to to to to to to 10-24-77 10-24-77 10-24-77 10-25-77 10-25-77 10-24-77 10-24-77 10-24-77 10-24-77 10-24-77 10-24-77 10-25-77 10-25-77 10-24-77 10-24-77 10-24-77 to to to to to to to

• to 10-31-77 10-31-77 10-31-77 10-31-77 10-31-77 10-31-77 10-31-77 10-31-77 November 10-31-77 10-31-77 10-31-77 10-31-77 10-31-77 10-31-77 10-31-77 10-31-77 to to to to to to to to 11-07-77 11-07-77 11-07-77 11-07-77 11-07-77 11-07-77 11-07-77 11-07-77 11-07-77 11-07-77 11-07-77 11-07-77 11-07-77 11-07-77 11-07-77 11-07-77 to to .to to to to to to 11-14-77 11-14-77 11-14-77 11-15-77 11-15-77 11-14-77 11-14-77 11-14-77 11-14-77 11-14-77 11-14-77 11-15-77 11-15-77 11-14-77 11-14-77

• 11-14-77 to to. to to to to to to 11-21-77 11-21-77 11-21-77 11-21-77 11-21-77 11-22-77 11-22-77 11-21-77 11-21-77 11-21-77 11-21-77 11-21-77 11-21-77 11-22-77 11-22-77 11-21-77 to to to to to to to * *to

• 11-28-77 11-28-77 11-28-77 11-28-77 11-28-77 11-28-77 11-28-77 11-28-77 December 11-28-77 11-28-77 11-28-77 11-28-77 11-28-77 11-28-77 11-28-77 11-28-77 to to

• to to to to to to 12-06-77 12-06-77 12-06-77 12-05-77 12-05-77 12-06-77 12-06-77 12-05-77 12-06-77 12-06-77 12-06-77 12-05-77 12-05-77 12-06-77 12-06-77 12-05-77 to to to* to to to to to 12-12-77 12-12-77 12-12-77 12-13-77 12-13-77 12-12-77 12-12-77 12-12-77 12-12-77 12-12-77 12-12-77 12-13-77 12-13-77 12-12-77 12-12-77 12-12-77 to to to to to to to to 12-19-77 12-19-77 12-19-77 12-20-77 12-20-77 12-19-77 12-19-77 12-19-77 12-19-77 12-19-77 12-19-77 12-20-77 12-20-77 12-19-77 12-19-77 12-19-77 to to to to to to to to 12-27-77 12-27-77 12-27-77 12-28-77 12-28-77 12-27-77 12-27-77 12-27-77 (1) Unable to service air monitor due to poor weather conditions.

74

TABLE C-19 I

CONCENTRATIONS OF TRITIUM. ALPHA AND BETA EMITTERS IN PRECIPITATION I (Station: SA-RW-2F2)

Results in Units of pCi/1 +/- 2 sigma COLLECTION PERIOD H-3 ALPHA BETA 1-03-77 to 2-01-77 <80 6.3+/-1.1 <3.7 2-01-77 to 3-01-77 <80 <1.5 18+/-3 3-01-77 to 4-04-77 97+/-70 <1.5 39+/-5 4-04-77 to 5-03-77 85+/-55 <1.5 82+/-8 5-03-77 to 6-07-77 <80 12+/-4 776+/-78 6-07-77 to 7-05-77 195+/-73 0.7+/-0.7 98+/-10 7-05-77 to 8-02-77 128+/-75 <1.5 53+/-5 8-02-77 to 9-06-77 <80 <1.5 35+/-4 9-06-77 to 10-03-77 <80 <1.5 121+/-12 10-03-77 to 11-01-77 <80 0.7+/-0.5 28+/-3 I

11-01-77 to 12-06-77 <80 0.8+/-0.6 18+/-3 12-06-77 to 1-03-78 <80 <1.5 18+/-3 Average 107+/-427 75

TABLE C-20 CONCENTRATIONS OF STRONTIUM-89* AND-90, AND GAMMA EMITT,ERS**

IN QUARTERLY COMPOSITES OF PRECIPITATION ,

(Statfon: SA-RW-2F2)

Results in Units of pCi/1 +/- 2 sigma 1-03-77 4-04-77 7-05-77 10-03-77 to to to to NUCLIDE 4-04-77 7-05-77 10-03-77 1-03-78 Sr-89 <4.5 7.4+/-1.4 7.8+/-2.1 1.1+/-0.5 Sr-90 2.4+/-0.5 1. 4+/-0. 6 <1.0 <0~5 Be-7 <MDL 33+/-11 15+/-4 10+/-5 K-40. <30 <10 <9.0 58+/-12 ZrNb-95 <2.0 . 32+/-3 (1) (2)

Ru-103 <MDL 5.5+/-1.7 2.2+/-0.6 <0.5 Cs-137 <2.0 <1.0 0.8+/-0.5 <0.5 BaLa-140 <3.0 <1.0 1. 7+/-1.0 <0.9 Ce-141 <MDL <MDL 1.9+/-0.8. <0.7 Ce-144 <10 <6.0 5.7+/-1.9' <3.0

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

• • All other gamma emitters <MDL; typical MDLs are given in Table C-33.

(1) The activity for Zr-95 was 1.1+/-0.7, and for Nb-95 was 2.6+/-0.6.

(2) The activity for Zr-95 was 1.5+/-0.9, and for Nb-95 was 1.7+/-0.7.

76

TABLE C-21 CONCENTRATIONS OF TRITIUM. ALPHA AND BETA EMITTERS. AND POTASSIUM-40 IN WELL WATER Results in Units of pCi/l +/- 2 sigma STATION NO.

RADIOACTIVITY 1-11-77 2-14-77 3-14-77 4-11-77 5-09-77 6-13-77 SA-WW-4Sl H-3 <80 <80 <80 334+/-67 <80 100+/-73 Alpha <2.7 <1.5 <1.7 <1.5 <1.7 <1.5 Beta 7.2+/-3.6 8.9+/-2.9 10+/-3 13+/-3 10+/-3 <3.0 K-40

• 1.7+/-0.2 11+/-1 11+/-1 8.7+/-0.9 9.7+/-1.0 2.8+/-0.3 SA-WW-5Dl H-3* 236+/-74 <80 <80 <80 <80 167+/-73 Alpha <2.1 1.5+/-1.1 <1.5 <1.6 <1.6 <1.5 Beta <3.3 2.6+/-2.4 2.3+/-2.1 4.8+/-2.6 3. 6+/-1. 9 3.2+/-2.4 K-40 0.80+/-0.08 3.2+/-0.3 3.0+/-0.3 2.4+/-0.2 2.5+/-0.3 3.3+/-0.3 SA-WW-3El H-3 200+/-69 <80(1) 250+/-69 402+/-72 <80 77+/-72 Alpha <2.8 <1.5(1) <1.8 <1.5 <2.0 <1.6 Beta 5.3+/-3.5 6.5+/-2.8(1) 8.3+/-2.6 13+/-3 7.3+/-2.6 12+/-3

'-I K-40 1.4+/-0.1 8.4+/-0.8(1) 8.8+/-0.9 4.3+/-0.4 7.3+/-0.7 9.0+/-0. 9.

'-I STATION NO.

RADIOACTIVITY 7-11-77 8-08-77 9-12-77 10-11-77 11-14-77 12-12-77 AVERAGE SA-WW-4Sl H-3 <80 <80 <80 81+/-71 <80 <80(3)

Alpha <1.5 <1.5 <1.5 <1.5 <1.5 <1.5(3)

Beta 12+/-3 9.3+/-3.3 9.6+/-2.6 12+/-2 12+/-3 12+/-3(3) 9.9+/-5.5 K-40 7.6+/-0.8 11+/-1 9.5+/-1.0 12+/-1 12+/-1 11+/-1(3) 9. 0+/-6.8 SA-WW-5Dl H-3 <80(2) <80 <80 142+/-71 <80 <80 Alpha <1.5(2) <1.5 <1.5 <1.5 <1.5 <1.5 Beta 5.0+/-2.5(2) <3.0 <3.0 7.9+/-2.2 2.8+/-1.8 4.8+/-2.4 3.9+/-3.1 K-40 4.1+/-0.4(2) 1.6+/-0.2 1.1+/-0.1 3.5+/-0.4 2.8+/-0.3 3.1+/-0.3 2.6+/-2.0 SA-WW-3El H-3 <80 189+/-77 <80 <80 <80 <80 Alpha <1.5 <1.6 <1.5 <1.5 <1.5 <1.5 Beta 11+/-3 7.7+/-3.2 8.4+/-2.6 11+/-2 8.1+/-2.3 9.2+/-2.7 9.0+/-4.6 K-40 5.5+/-0.6 8.3+/-0.8 6.3+/-0.6 11+/-1 11+/-1 9.0+/-0.9 7.5+/-5.6 (1) Sampling date was 2-15-77.

(2) Sampling date was 7-12-77.

(3) Sampling date was 12-13-77.

TABLE C-22 CONCENTRATIONS OF STRONTIUM-89* AND-90, AND GAMMA EMITTERS**

IN QUARTERLY COMPOSITES OF WELL WATER Results in Units of pCi/l +/- 2 sigma 1-11-77 4-11-77 7-11-77 10-11-77 STATION NO. to to to to RADIOACTIVITY 3-14-77 6-13-77 9-12-77 12-12-77 SA-WW-4Sl (2)

Sr-89 <O. 7 0.4+/-0.4 <0.8 <0.5(2)

Sr-90 <0.4 <0.4 <0.4 <0.3(2)

K-40 16+/-10 <7.0 <8.0 10+/-8 SA-WW-501 (1)

Sr-89 <1.1 0.5+/-0.4 <0.7(1) <1.1 Sr-90 <0.6 <0.4 <0.4(1) <0.7 K-40 <6.0 <7.0 <7.0 <7.0 SA-WW-3El Sr-89 <1.1 <0.6 <0.9 <0.5 Sr-90 <0.6 0.6+/-0.3 <0.5 <0.3 K-40 <6.0 <7.0 13+/-9 <7.0

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

• • All other gamma emitters <MDL; typical MDLs are given in Table C-33.

(1) Collection dates were 7-12-77 to 9-12-77.

(2) Collection dates were 10-11-77 to 12-13-77.

78

TABLE C-23 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 RA DI OACTI VI TY JAN FEB MAR APR MAY JUN H-3 ~Raw) <80 173+/-69 102+/-70 <80 <80 254+/-72 Treated) <BO 175+/-69 161+/-70 <80 <80 143+/-71 Alpha (Raw) 1.0+/-0. 7 0.7+/-0.4 1.1+/-0. 5 1.0+/-0. 6 <1.0 0.4+/-0.4 (Treated) 1.0+/-0. 9 1.8+/-0. 8 0.8+/-0.5 1. 0+/-0. 7 . 0.7+/-0.5 1.2+/-0.7 Beta (Raw). 1.4+/-0.9 3.1+/-0.5 4.4+/-0.5 5.6+/-0.6 3.1+/-0.5 11+/-1 (Treated) <1.0 2.7+/-0.5 4.0+/-0.5 4.1+/-0.6 20+/-2 9.2+/-1.2 K-40 (Raw) 1.5+/-0.2 1.3+/-0. l .1.5+/-0.2 1.5+/-0.2 1. 4+/-0.1 0.61+/-0.06

~

(Treated) 1.5+/-0.2 1.3+/-0.1 1.6+/-0.2 2.2+/-0.2 1.3+/-0.1 0.76+/-0.08 RADIOACTIVITY JUL AUG SEP OCT NOV DEC AVERAGE H-3 (Raw) 178+/-77 204+/-72 302+/-72 94+/-73 <80 96+/-78 144+/-154 (Treated) 255+/-77 195+/-72 317+/-72 76+/-72 <80 79+/-78 143+/-161 Alpha (Raw) o. 7+/-0.4 0.4+/-0.4 <1.3 0.4+/-0.3 0.9+/-0.5 <0.4 0.8+/-0.6 (Treated) 1. 7+/-0.8 0.9+/-0.6 <1.0 <1.0 <1.0 <0.6 1.1+/-0.7 Beta (Raw) 3.8+/-0.5 3.2+/-0.5 2.9+/-0.7 3.6+/-0.5 5.6+/-0.8 6.0+/-0.6 4.5+/-4.9 (Treated) 3.6+/-0.5 2.4+/-0.4 3.0+/-0.6 2.5+/-0.4 3.7+/-0.7 4.5+/-0.5 5.1+/-10.2 K-40 (Raw) 1.7+/-0.2 1.3+/-0.1 1.2+/-0.1 1. 0+/-0.1 1.8+/-0.2 2.0+/-0.2 1.4+/-0. 7 (Treated) 2.1+/-0.2 1.8+/-0.2 3.2+/-0.3 1.1+/-0.1 1.8+/-0.2 2.0+/-0.2 1. 7+/-1.3

TABLE C-24 CONCENTRATIONS OF STRONTIUM-89*AND-90, AND GAMMA EMITTERS**

IN QUARTERLY COMPOSITES OF POTABLE WATER

{Sampled at location 2F3)

Results in Units of pCi/l +/- 2 sigma 1-01-77 4-01-77 7-01-77 10-01-77 to to to to SAMPLE 3-31-77 6-30-77 9-30-77 12-31-77 .

Raw Sr-89 1.2+/-1.2 <0.9 <1.1 <0.7 Sr-90 <0.6 1.0+/-0.3 0.7+/-0.3 0.6+/-0.3 Gamma Emitters All<MDL All<MDL All <MDL All<MDL Treated Sr-89 <1.9 0.8+/-0.6 <1.0 <0.7 Sr-90 0.5+/-0.4 0.6+/-0.3 0.5+/-0.3 0.4+/-0.3 Gamma Emitters All<MDL All <MDL All<MDL All <MDL

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

• • Typical MDLs are given in Table C-33.

ao

TABLE C-25 CONCENTRATIONS OF IODINE-131 IN MILK Results*in Units of pCi/l STATI'ON NO. JAN FEB MAR APR MAY JUN SA-M-2Fl <0.04 <0.03 <0.04 <0.05 <0.05 <0.06

<0.05 <0.04 <0.03 <0.04 <0.04 <0.05 SA-M-5F2 <0.05 <0.04 <0.03 <0.04 <0.05 <0.04

<0.05 <0.04 <0.04 <0.04 <0.05 <0.05 SA-M-14Fl <0.05 <0.05 <0.05 <0.05 <0.05 <0.07

<0.05 <0.04 <0.06 <0.05 <0.05 <0.08 SA-M-15Fl <0.06 <0.04 <0.04 <0.05 <0.06 <0.05

<0.05 <0.05 <0.05 <0.05 <0.06 <0.06 SA-M-3Gl <0.06 <0.04 <0.04 <0.03 <0.05 <0.05

<0.06 <0.04 <0.05 <0.04 <0.05 <0.06 STATION NO. JUL AUG SEP** OCT** NOV DEC SA-M-2Fl <0.07 <0.05 <0.03 25+/-3 1.4+/-0. l <0.04

<0.05 <0.04 <0.03 9. 9+/-1. 0 o. 30+/-0. 05 <0.07 1.4+/-0.1 3.9+/-0.4 SA-M-5F2 <0.07 <0.04 <0.04 23+/-2 0.9+/-0.l <0.04

. <0.05 <0.05 <0.04 8.4+/-0.8 0.21+/-0.07 <0.06 2.9+/-0.3 1. 6+/-0.2 SA-M-14Fl <0.07 <0.06 <0.04 15+/-2 0.45+/-0.08 0.07+/-0.03

<0.05 <0.06 <0.05 8.5+/-0. 9 0.13+/-0.06 <0.1 1.9+/-0.2 2.3+/-0.2 SA-M-15Fl <0.07 <0.05 <0.04 13+/-1 1.3+/-0.3 0.11+/-0.04

<0.04 <0.05 <0.06 6.3+/-0.6 0.31+/-0.07 <0.09 0.55+/-0.07 1.7+/-0.2 SA-M-3Gl <0.07 <0.04 <0.05 5.6+/-0.6 <0.07 <0.04

<0.06 <0.05 *<0.04 2.8+/-0.3 <0.08 <0.09 0.64+/-0.06 0.29+/-0.09

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

• • Additional samples taken in September and October following the nuclear weapon test by the People's Republic of China on September 17, 1977.

81

TABLE C-26 CONCENTRATIONS OF GAMMA EMITTERS* AND STRONTIUM-B9** AND-90 IN MILK Results in Units of pCi/l +/- 2 sigma STATION NO. NUCLIDE JAN FEB MAR APR MAY JUN SA-M-2Fl K-40 1300+/-130 1100+/-110 1200+/-120 1400+/-140 1600+/-160 1600+/-160 I-131 <0.5 <0.4 <0.5 <0.5 <0.5 <0.5 Cs-137 1. 9+/-0.8 1. 8+/-0.8 <0.7 1.9+/-0.9 5.1+/-1. 0 4.3+/-1.0 Sr-89 <2.2 <1.4 <0.9 <0.6 <0.7 <0.9 Sr-90 2.0+/-0.4 1. 3+/-0.6 1.1+/-0.3 <0.4 0.4+/-0.3 0.4+/-0.3 SA-M-5F2 K-40 1400+/-140 1000+/-100 1000+/-100 1500+/-150 1500+/-150 1700+/-170 I-131 <0.5 <0.4 <0.4 <0.5 <0.5 <0.5 Cs-137 1.3+/-0. 9 <0.6 1. 0+/-0. 7 1.6+/-0. 9 <0. 7 4.4+/-1.0 Sr-89 <2.0 <1.3 <0.9 <0.8 <0.7 <1.3 Sr-90 0.8+/-0.3 1.8+/-0.5 1.1+/-0.3 0.8+/-0.3 <0.4 0.6+/-0.4 SA-M-14Fl K-40 1400+/-140 1000+/-100 1200+/-120 1600+/-160 1500+/-150 1500+/-150 I-131 <0.5 <0.5 <0.4 <0.5 <0.5 <0.5 Cs-137 1.9+/-1.0 <0.6 <0.6 1.4+/-0.9 1. 9+/-0. 9 3.3+/-0.9 Sr-89 <1.5 <1.0 <1.4 <0.7 <0.8 <1.1 Sr-90 <0.6 1. 6+/-0.4 <O. 7 <0.4 0.3+/-0. 3 0.3+/-0.3 SA-M-15Fl K-40 1300+/-130 1200+/-120 1100+/-110 1800+/-180 1500+/-150 1600+/-160 I-131 <0.5 <0.5 <0.4 <0.5 <0.5 <0.5 Cs-137 1.2+/-0.8 1. 3+/-0.8 0.9+/-0.8 1. 3+/-1. 0 1. 8+/-0.9 2.0+/-1.0 Sr-89 <0.8 <1. 6 <1.0 <0.6 <0.5 <1.0 Sr-90 <0.4 1. 5+/-0. 7 <0.6 <0.4 <0.3 0.4+/-0. 3 SA-M-3Gl K-40 1600+/-160 1100+/-110 1100+/-110 1600+/-160 1400+/-140 1700+/-170 I-131 <0.5 <0.4 <0.5 <0.5 <0.5 <0.5 Cs-137 2.8+/-1.0 1. 7+/-0. 9 1. 7+/-0.8 2.1+/-0.9 2.2+/-0.9 3.2+/-1.0 Sr-89 <1.6 <1.9 <1.0 <0.7 <0.7 <1.0 Sr-90 0. 7+/-0.3 3.1+/-0.8 0.7+/-0.4 <0.4 <0.4 0.6+/-0.3 STATION NO. NUCLIDE JUL AUG . SEP OCT NOV DEC SA-M-2Fl K-40 1600+/-160 1600+/-160 1500+/-150 1500+/-150 1400+/-140 1300+/-130 I-131 <0.5 <0.5 <0.5 20+/-3 <0.5 <0.5 Cs-137 4. 7+/-1. 0 3.3+/-1.0 3.9+/-1.0 6. 2+/-1.1 2.9+/-0.9 3.6+/-0.9 Sr-89 <4.5 <2.9 <1.2 14+/-7 <44 (1) 4.3+/-2.9 Sr-90 5.2+/-1.1 2.4+/-0.8 1..3+/-0. 5 8.6+/-1.4 <15(1) 8.3+/-1.2 SA-M-5F2 K-40 1700+/-170 1500+/-150 1700+/-170 1600+/-160 1600+/-160 1600+/-160 I-131 <0.5 <0.5 <0.5 32+/-3 <0.5 <0.5 Cs-137 3.3+/-1.0 1. 9+/-0. 9 2.1+/-1. 0 5. 6+/-1.1 6.4+/-1.1 5.4+/-1.0 Sr-89 <4.1 <3.1 <3.1 9.0+/-8.9 <6.2 10+/-6 Sr-90 2.3+/-1.0 1.7+/-0.9 4.9+/-1.2 5. 0+/-1.8 6.4+/-0.9 4.2+/-2.4 SA-M-:-14Fl K-40 1500+/-150 1600+/-160 1800+/-180 1400+/-140 1400+/-140 1400+/-140 I-131 <0.5 <0.5 ' - <0". 5 . <:as* -zos*, -<as*

Cs-137 1.3+/-1.0 2.2+/-0.9 3. 5+/-1. 0 2.4+/-1. 0 3.3+/-0.9 4.7+/-1.1 Sr-89 2.1+/-1.2 <2.5 <2.1 <7.6 <7.7 5.7+/-4.5 Sr-90 1. 0+/-0. 7 1. 0+/-0. 7 1.2+/-0.8 3.6+/-2.8 4.2+/-1.7 2.7+/-1.7 SA-M-15Fl K-40 1700+/-170 1600+/-160 1800+/-180 1600+/-160 1600+/-160 1500+/-150 I-131 <0.5 <0.5 <0.5 14+/-3 <0.5 <0.5 Cs-137 1.1+/-0.9 1.9+/-1.0 4.0+/-1.1 4.2+/-1.0 3. 9+/-1.1 3.4+/-1.0 Sr-89 2.3+/-1.4 <2.6 <3.l <6.2 6.6+/-4.3 <4.4 Sr-90 2.2+/-0.8 <1.1 1. 2+/-1.1 3.7+/-2.3 2.5+/-0.9 3.1+/-0.9 SA-M-3Gl K-40 1700+/-170 1700+/-170 1500+/-150 1400+/-140 1700+/-170 1700+/-170 I-131 <0.5 <0.5 <0.5 45+/-5 <0.5 <0.5 Cs-137 3. 5+/-1. 0 3.4+/-1.0 3. 0+/-1. 0 7 .3+/-1. 0 3.9+/-1.1 4.1+/-1.0 Sr-89 <1.8 <2.8 <3.2 15+/-8 <9.1 <6.0 Sr-90 1. 4+/-0. 6 <1. 2 2.8+/-1.2 6.0+/-1. 6 2.3+/-1. 9 5.0+/-1.6

• All other gamma emitters <MDL; typical MDLs are given in Table C-33.

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

(1) This high MDL is a result of a low chemical yield.

82

TABLE C-27 SAMPLING DATES FOR MILK*SAM'LES STATION 'NO.

MONTH 2Fl 5F2 14Fl 15Fl 3Gl January 1-02-77 1-02-77 1-02-77 1-03-77 1-02-77 to to to to to 1-03-77 1-03-77 1-04-77 1-04-77 1-03-77 1-16-77 1-16-77 1-16-77 1-17-77 1-16-77 to to to to to 1-17-77 1-17-77 1-18-77 1-18-77 1-17-77 February 2-07-77 2-07-77 2-06-77 2-06-77 2-07-77 to to to to to 2-08-77 2-08-77 2-07-77 2-07-77 2-08-77 2-21-77 2-21-77 2-21-77 2-20-77 2-21-77 to to to to to 2-22-77 2-22-77 2-22-77 2-22-77 2-22-77 March 3-07-77 3-07-77 3-05-77 3-06-77 3-07-77 to to to to to 3-08-77 3-08-77 3-07-77 3-07-77 3-08-77 3-21-77 3-21-77 3-20-77 3-20-77 3-21-77 to to to to to 3-22-77 3-22-77 3-21-77 3-21-77 3-22-77

. Apri 1 4-04-77 4-04-77 4-03-77 4-03-77 4-04:..77 to to to to to 4-05-77 4-05-77 4-04-77 4-04-77 4-05-77 4-18-77 4-18-77 4-17-77 4-17-77 4-18-77 to to to to to 4-19-77 4-19-77 4-18-77 4-18-77 4-19-77 May 5-02-77 5-02-77 5-01-77 5-02-77 5-02-77 to to to to to 5-03-77 5-03-77 5-02-77 5-03-77 5-03-77 5-16-77 5-16-77 5-15-77 5-15-77 5-16-77 to to to to to 5-17-77 5-17-77 5-16-77 5-16-77 5-17-77 June 6-05-77 6-05-77 6-06-77 6-06-77 6-05-77 to to to to to 6-06-77 6-06-77 6-07-77 6-07-77 6-06-77 6-19-77 6-19-77 6-20-77 6-20-77 6-19-77 to to to to to 6-20-77 6-20-77 6-21-77 6-21-77 6-20-77 83

TABLE C-27 (Cont.)

SAMPLING DATES FOR MILK SAMPLES STATION rw.

MONTH 2Fl 5F2 14Fl 15Fl 3Gl July 7-05-77 7-05-77 . 7-04-77 7-04-77 7-05-77 to to to to to 7-06-77 7-06-77 7-05-77 7-05-77 7-06-77 7-17-77 7-17-77 7-18-77 7-18-77 7-17-77 to to to to to 7-18-77 . 7-18-77 7-19-77 7-19-77 7-18-77 August 7-31-77 7-31-77 8-01-77 8-01-77 7-31-77 to to to to to 8-01-77 8-01-77 8-02-77 8-02-77 8-01-77 8-14-77 8-14-77 8-15-77 8-15-77 8-14-77 to to to to to 8-15-77 8-15-77 8-16-77 8-16-77 8-15-77 September 9-05-77 9-05-77 9-06-77 9-06-77 9-05-77 to to to to to 9-06-77 9-06-77 9-07-77 9-07-77 9-06-77 9-19-77 9-19-77 9-19-77 9-19-77 9-19-77 to to to to to 9-20-77 9-20-77 9-20-77 9-20-77 9-20-77

. 9-25-77 9-25-77 9-25-77 9-25-77 9..,25-77 to to to to to 9-26-77 9-26-77 9-26-77 .9-26-77 9-26-77 October 10-03-77 10-03-77 10-03-77 10-03-77 10-03-77 to to to to to 10-04-77 10-04-77 10-04-77 10-04-77 10-04-77 10-17-77 10-17-77 10-17-77 10-17-77 10..;17-77 to to to to to 10-18-77 10-18-77 10-18-77 10-18-77 10-18-77 10-31-77 10-31-77 10-31-77 10-31-77 10-31-77 to to to to to 11-01-77 11-01-77 11-01-77 11-01-.77 11-01-77 November 11-06-77 11-06-77 11-06~77 11-06-77 11-06-77 to to to to to 11-07-77 11-07-77 11-07-77 11-07-77 11-07-77 11-20-77 11-20-77 11-20-77 11-20-77 11-20-77 to to to to to 11-21-77 11-21-77 11-21-77 11-21-77 11-21-77 December 12-04-77 12-04-77 12-04-77 12-04-77 12-04-77 to to to to to 12-05-77 12-05-77 12-05-77 12-05-77 12-05-77 12-18-77 12-18-77 12-19-77 12-19-77 12-18-77 to

• to to to to 12-19-77 12-19-77 12-20-77 12-20-77 12-19-77 84

TABLE C-28

. CONCENTRATIONS OF STRONTIUM-89 AND-90*, AND GAMMA EMITTERS** IN MEAT AND GAME Results in Units of pCi/g(wet) +/- 2 sigma STATION NO. DATE SAMPLE TYPE K-40 Sr-89 Sr-90 Cs-137 SA-FPB-14Fl 2-15-77 Beef 0.63+/-0.06 <0.002 SA-FPB-3El 3-16-77 Beef 2.7+/-0.3 0.017+/-0.006 SA-FPB-3El 11-03-77 Beef 3.4+/-0.3 0.02+/-0.01 SA-GM-llDl 2-25-77 Muskrat 3.4+/-0.3 0.9+/-0.1 1. 0+/-0. 1 <0.005 co CJ1 SA-GM-3El 2-21-77 Muskrat o. 72+/-0. 07 0.62+/-0.07 0.80+/-0.05 <0.002 SA-GM-3El 12-09-77 Muskrat 3. 7+/-0. 4 0.9+/-0.3 0.5+/-0.1 0.028+/-0.009 SA-GM-1101 12-12-77 Muskrat 3.2+/-0.3 1. 2+/-0. 4 0.5+/-0.1 <0.007 SA-GD-2E2 12-00-77 ( 1) Deer 3.0+/-0.3 0.021+/-0.008

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

• • All other gamma emitters <MDL; typical MDLs are given in Table C-33.

(1) Deer sample obtained on approximately 12-09-77.

TABLE C-29 CONCENTRATIONS OF GAMMA EMITTERS* IN BOVINE THYROID Results in Units of pCi/g (wet) +/- 2 sigma STATION NO. DATE I-131 K-40 SA-THB-14Fl 2-15-77 <0.05 <0.8 SA-THB-3El 3-16-77 <0.05 <0.8 SA-THB-3El 11-03-77 2.3+/-0.2 0.9+/-0.8

• All other garrma emitters <MDL; typical MDLs are given in Table C-33.

86

TABLE C-30 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-lGl 4-19-77 Asparagus 2.8+/-0.3 <0.005 <0.003 SA-FPV-2El 5-01-77 Asparagus (1) 3.0+/-0.3 <0.006 0.004+/-0.003 SA-FPV-3H4 7-25-77 Corn 3.5+/-0.4 <0.03 <0.01 SA-FPV-3H4 7-25-77 Peppers 2. 5+/-0. 3 <0.02 <0.008 SA-FPV-3H4 7-25-77 Tomatoes 2.2+/-0.2 <0.02 <0.01 SA-FPV-2El 7-25-77 Green Peppers 2.4+/-0.2 <0.03 <0.007 SA-FPV-lGl 7-25-77 Corn 2.7+/-0.3 <0.03 <0.01 SA-FPV-lGl 7-26-77 *Tomatoes 3.3+/-0.3 <0.03 <0.01 SA-FPV-15El 7-26-77 Corn 3.3+/-0.3 <0.04 <0.02 SA-FPV-1G2 8-22-77 Squash(2) 1. 0+/-0.1 <0.01 <0.007 SA-FPV-3H4 8-22-77 Cucumbers 1. 3+/-0.1 <0.01 <0.006 SA-FPV-5Fl 8-22-77 Tomatoes 2.3+/-0.2 <0.009 <0.005 SA-FPV-3H4 8-22-77 Eggplant 2.3+/-0.2 <0.009 <0.005 SA-FPV-lGl 8-23-77 Eggplant 2.5+/-0.3 <0.008 <0.004

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

All other gamma emitters <MDL; typical MDLs are given in Table C-33.

(1) ZrNb-95 was also observed in this sample with a concentration of 0.013+/-0.003 pCi/g(wet).

(2) Cs-137 was also observed in this sample with a concentration of 0.004+/-0.002 pCi/g(wet).

87

TABLE C-31 CONCENTRATIONS OF GAMMA EMITTERS* IN FODDER CROP SAMPLES Results in units of pCi/g(dry) +/- 2 sigma STATION NO. DATE SAMPLE TYPE Be-7 K-40 Mn-54 Zr-95(2) Nb-95 Ru-103 SA-V-3Gl 9-12-77 Corn Silage 0.8+/-0.1 8.2+/-0.8 <0.01 0.09+/-0.02 0.19+/-0. 02 <0.009 SA-V-2Fl 9-14-77 Grass 4.3+/-0.4 13+/-1 0.03+/-0.02 0.51+/-0.05 1.0+/-0.1 0.06+/-0.02 SA-V-3Gl 9-14-77 Green Chop 1.3+/-0.2 7.0+/-0.7 <0.02 0.08+/-0. 03 0.17+/-0.03 <0.02 SA-V-5F2 9-14-77 Grass 7.2+/-0. 7 18+/-2 0.03+/-0.02 0.52+/-0.05 1.1+/-0.1 *0.07+/-0.02 SA-V-14Fl 9-15-77 Grass 4.2+/-0.4 14+/-1 0.01+/-0.01 0.39+/-0.04 0.83+/-0.08 0.06+/-0.02 SA-V-15Fl 9-15-77 Grass 2.9+/-0.3 23+/-2 0.02+/-0.01 0.27+/-0.03 o. 64+/-0. 06 0.05+/-0.02 SA-V-15Fl 9-15-77 Silage <MDL 19+/-2 <0.02 0.19+/-0.03(1) <MDL SA-V-lBl 9-28-77 Corn Silage <MDL 3.4+/-0.4 <0.02 <0.02 <MDL SA-C-3Gl 10-23-77 Soybeans <MDL 19+/-2 <0.02 <0.02 - <MDL SA-V-5Dl 10-24-77 Soybeans <MDL 19+/-2 <0.02 <0.02 <MDL SA-V-15Fl 10-24-77 Soybeans <MDL 19+/-2 <0.02 <0.02 <MDL STATION NO. DATE SAMPLE TYPE . Ru-106(3) Sb-125 Cs-137 Ce-141 Ce-144 Ra-226 SA-V-3Gl 9-12-77 Corn Silage <0.08 <0.02 0.03+/-0.01 <0.01 0.37+/-0. 06 <0.03 SA-V-2Fl 9-14-77 Grass <0.30 <0.07 0.12+/-0.03 <0.03 <0.10 <0.06 SA-V-3Gl 9-14-77 Green Chop <0.20 <0.05 0.03+/-0.02 <0.02 0.6+/-0.1 <0.04 SA-V-5F2 9-14-77 Grass 0.6+/-0.2 0.07+/-0.04 0.13+/-0.02 0.06+/-0.03 2.4+/-0.2 <0.03 SA-V-14Fl 9-15-77 Grass 0.4+/-0.1 0.06+/-0.03 0.08+/-0.02 0.02+/-0.01 1.5+/-0.2 0.10+/-0.04 SA-V-lSFl 9-15-77 Grass 0.4+/-0.1 0.05+/-0.04 0.08+/-0.02 <0.0l 1.2+/-0.l o. 07+/-0. 04 SA-V-15Fl 9-15-77 Silage <0.09 <MDL <0.02 <MDL <0.10 <0.04 SA-V-lBl 9-28-77 Corn Sil age <0.09 <MDL <0.02 <MDL <0.10 <0.04 SA-V-3Gl 10-23-77 So~beans <0.10 <MDL o. 04+/-0. 03 ' <MDL * <0.10 <0.04 SA-V-5Dl 10-24-77 Soybeans <0.09 <MDL <0.02 <MDL <0.10 <0.04 SA-V-15Fl 10-24-77 soyl>eans <0.09 <MDL <0.02 <MDL <0.10 <0.04

• All other gaillna emitters <MDL; typical MDLs are given in Table C-33.

~l) . This result is for Zr~b-95.

2) The MDL 1 s are for ZrNb-95.

(3) The MDL 1 s are for RliRh-106.

88

TABLE C-32 CONCENTRATIONS OF STRONTIUM-90 AND GAMMA EMITTERS* IN SOIL Results in Units of pCi/g (dry) +/- 2 sigma STATION NO. DATE Sr-90 K-40 Ru-103 Cs-137 Ra-226 Th-232 SA-E-6Sl 4-06-77 0.13+/-0.03 8.4+/-0.8 0.02+/-0.01 0.11+/-0. 03 0.53+/-0.05 0.42+/-0.06 SA-E-5Dl 4-06-77 0.29+/-0.05 6.6+/-0.7 <0.02 0.55+/-0.06 0.70+/-0.07 0.64+/-0.07 SA-E-1001 4-05-77 0.26+/-0.04 9.5+/-1.0 <0.01 0.56+/-0.06 0.90+/-0.09 0.5+/-0.1 SA-E-2El 4-04-77 0.17+/-0.03 8.1+/-0.8 <0.01 0.46+/-0.05 0.84+/-0.08 0.66+/-0.07 SA-E-16El 4-05-77 0.16+/-0.04 14+/-1 <0.01 0.27+/-0.03 1. 0+/-0.1 0.8+/-0.2 SA-E-lFl 4-04-77 0.25+/-0.04 5.6+/-0.6 <0.01 3.7+/-0.4 0.55+/-0.06 0.40+/-0.07 00 ID SA-E-2Fl 4-04-77 0.31+/-0.05 10+/-1 <0.01 0.46+/-0.05 1.1+/-0.1 0.6+/-0.2 SA-E-2F2 4-04-77 0.06+/-0.03 9.3+/-0.9 <0.01 0.22+/-0.03 0.48+/-0.05 0.39+/-0.06 SA-E-5Fl 4-05-77 0.30+/-0.04 6.1+/-0.6 <0.01 0.83+/-0.08 0.58+/-0.06 0.45+/-0.05 SA-E-5F2 4-05-77 0.15+/-0.03 4.8+/-0.5 -<0.01 0.42+/-0.04 0.55+/-0.06 0.45+/-0.05 SA-E-14Fl 4-05-77 0.19+/-0.04 15+/-2 <0.02 0.26+/-0.03 1.1+/-0.1 1. 0+/-0.1 SA-E-15Fl 4-05-77 0.42+/-0.05 13+/-1 <0.02 0. 71+/-0. 07 1. 2+/-0.1 1. 0+/-0.1 SA-E-3Gl 4-06-77 0.17+/-0.04 11+/-1 <0.01 0.41+/-0.04 1.1+/-0.1 0.8+/-0.1 SA-E-3H3 4-07-77 0.68+/-0.06 9.1+/-0.9 <0.02 0.82+/-0.08 1.0+/-0.1 0. 77+/-0. 08

• All other gamma emitters <MDL; typical MDLs are given in Table C-33.

TABLE C-33 TYPICAL MDLs FOR GAf41A SPECTROMETRY*.

SURFACE FISH AIR WELL/POTABLE FOOD FODDER BOVINE WATER SHELLFISH SEDIMENT PARTICULATES PRECIPITATION WATER MILK PRODUCTS CROPS GAME THYROIDS SOIL NUCLIDE (pCi/l) (pCi/kg) (pCi/g) ( 10- 3pCi /m 3) (pCi/l) (pCi/l) (pCi/l) (pCi/kg-wet)

(pCi/kg-dry) (pCi/kg) (pCi /kg) (pCi/g)

Na-22 0.2 2 0.02 0.2 0.6 0.2 0.3 0.7 10 3 30 0.02 K-40 Cr-51 7

3 30 0.1 3

2 10 7

7 4 5 10 100 40 800 400 0.1 Mn-54 0.5 8 0.02 0.2 1 0.5 0.7 2 20 7 60 0.01 Co-58 0.5 4 0.02 0.1 1 0.5 0.7 2 20 2 60 0.01 Fe-59 1 10 0.02 0.3 2 1 2 4 50 10 100 0.02 Co-60 0.6 10 0.02 0.3 1 0.6 1 3 30 9 70 0.02 Zn-65 1 20 0.03 0.3 2 1 2 5 60 20 100 0.03 ZrNb-95 0.5 6 0.04 1 1 0.5 0.6 1 20 6 60 0.03 Mo-99 4 50 0.1 1 10 4 5 10 200 50 500 0.1 RuRh-106 2 30 0.1 3 5 2 3 6 90 30 300 0.1 Ag-llOm 0.5 7 0.04 0.4 1 0.5 0.7 1 20 6 60 0.05 Te-129m 7 100 0.3 2 20 8 10 20 300 100 900 0.2

~ 1-131 0.4 3 0.01 0.2 0.8 0.4 0.5 9 20 5 50 0.01 Te-132 0.4 3 0.01 0.2 0.8 0.4 0.4 1 20 4 40 0.01 1-133 0.5 4 0.01 0.2 1 0.5 0.6 2 20 6 50 0.01 Cs-134 0.5 4 0.02 0.2 2 0.5 0.7 2 20 2 60 0.02 Cs-136 0.7 10 0.03 0.2 1 0.7 1 3 30 10 80 0.02 Cs-137 0.5 4 0.01 2 1 0.5 0.6 2 20 2 60 BaLa-140 0.6 9 0.02 0.4 1 0.6 0.6 2 20 8 70 0.03 Ce-144 3 40 0.1 20 6 3 3 30 100 30 300 0.1 Ra-226 0.9 10 - 0.6 2 0.9 1 3 40 10 100 Th-232 2 20 - 0.6 4 2 3 6 80 20 200

• At time of analysis.

TABLE C-34 DIRECT RADIATION MEASUREMENTS - MONTHLY TLD RESULTS mrad/standard month*

STATION NO. JAN FEB MAR APR MAY JUN SA-ID-2Sl 3.94+/-0.30 3.76+/-0.46 4.45+/-0.29 4.01+/-0.12 4.07+/-0.42 3.94+/-0.20 SA-ID-5Sl 3.81+/-0.23 4.20+/-0.37 4.45+/-0.24 4.34+/-0.28 4.62+/-0.35 4.01+/-0.47 SA-ID-6Sl 4.94+/-0.28 5.31+/-0.46 5.26+/-0.57 5.49+/-0.48 5.33+/-0.64 5.44+/-0.38 SA-ID-7Sl 5.41+/-0.91 5.36+/-0.55 6.16+/-0.39 5.57+/-0.28 *6.00+/-0.64 5.77+/-0.57 SA-ID-lOSl 5.05+/-0.44 5.33+/-0.09 5.54+/-0.20 5.81+/-0,96 5.67+/-0.57 5.21+/-0.64 SA-ID-1151 4.13+/-0.37 4.01+/-0.32 4.06+/-0.33 4. 21+/-0.40 4.24+/-0.33 4.05+/-0.35 SA-ID-501 4.63+/-0.47 4.53+/-0.28 4.83+/-0.36 4.93+/-0.27 5. 24+/-0. 77 5.03+/-0.74 5A-ID-10Dl 5.87+/-1.11 5.49+/-0.40 5.83+/-0.30 5.99+/-0.55 7.83+/-2.74 6.19+/-0.29 SA-ID-1401 5.27+/-0.39 5.05+/-0.27 5.24+/-0.36 5.46+/-0.33 5.71+/-0.40 5.38+/-0.43 5A-ID-2El 5.02+/-0.58 4.84+/-0.39 4.97+/-0.41 5.10+/-0.05 5.64+/-0.40 5.78+/-0.60 SA-ID-3El 5.07+/-0.09 4.93+/-0.27 4.95+/-0.66 5 .13+/-0. 32 5.31+/-0.70 5.21+/-0.63 5A-ID-13El 4.81+/-0.62 4.86+/-0.39 5.11+/-0.35 5 .15+/-0.14 5.34+/-0.55 5.12+/-0.21 SA-ID-16El . 5.06+/-0.54 5.10+/-0.30 5.52+/-0.49 5 .12+/-1. 30 5.40+/-0.38 5.50+/-0.50 5A-ID-1Fl 5.35+/-0.28 5.30+/-0.38 5.39+/-0.22 5.82+/-0.79 5.77+/-0. 26 5.58+/-0.44 5A-ID-2F2 4.23+/-0.30 3.98+/-0.36 4.09+/-0.51 4.61+/-0.33 5.24+/-0.77 4.38+/-0.50 5A-ID-5Fl . 4.71+/-0.49 4.76+/-0.38 5.53+/-0.33 5.21£0.63 5.15+/-0.71 5.30+/-0.63 SA-ID-6Fl 4.06+/-0.12 4.29+/-0.21 4.41+/-0.31 4.22+/-0.89 4.51+/-0. 34 4.30+/-0.21 5A-ID-7F2 3.65+/-0.24 3.80+/-0.30 3.96+/-0. 23 3.75+/-0.47 4.25+/-0.53 3.93+/-0.47 SA-ID-llFl 5.42+/-0.25 5.79+/-0 *. 27 5.59+/-0.54 6.16+/-0. 50 6.50+/-0.38 6.40+/-1.50 SA-ID-13Fl 4.73+/-0.36 5.07+/-0.14 4.61+/-1.72 5.25+/-0.52 5.28+/-0.25 5.11+/-0.28 5A-ID-3Gl 5.41+/-0.28 5.53+/-0.54 5.58+/-0.42 5.83+/-0.77 6.40+/-0.29 6.58+/-0.76 5A-ID-2Hl 5.17+/-0.65 5.86+/-0.53 5.72+/-0.50 5.47+/-0.32 5.76+/-0.57 5.68+/-0.55 SA-ID-3Hl 5.31+/-0.40 5.88+/-0.43 5.58+/-0.24 5.68+/-0.47 5.92+/-0.40 5.67+/-0.82 5A-ID-3H3 5.46+/-0.40 5.22+/-0.21 5.48+/-0.33 5.45+/-0.37 6.07+/-0.31 6.03+/-0.61 AVERAGE 4.85+/-1.20 4.93+/-1.28 5.10+/-1.23 5 .16+/-1. 32 5.47+/-1.64 5.23+/-1.56 STATION NO. JUL AUG SEP OCT NOV DEC AVERAGE 5A-ID-2Sl 5.02+/-0.29 5.21+/-0.14 5.05+/-0.18 5.52+/-0.16 6.00+/-0.18 6.21+/-0.33 4.76+/-1.71 5A-ID-551 4 .18+/-0. 38 4.17+/-0.40 4.21+/-0.58 4.27+/-0.41 4.69+/-0.42 4.55+/-0.26 4.29+/-0.51 5A-ID-651 5.22+/-0.44 4.76+/-0.15 5.20+/-0.53 5.47+/-0.42 5. 92+/-1. 05 5.48+/-0.51 5.32+/-0.58 SA-ID-751 5.37+/-0.52 4.86+/-0.44 5.40+/-0.33 5.33+/-0.37 5.57+/-0.46 6.05+/-0.43 5.57+/-0.74 SA-ID-1051 4.90+/-0.36 4.65+/-0.11 4.69+/-0.34 5.29+/-0.35 5.41+/-0.19 5.31+/-0.43 5.24+/-0.73 5A-ID-1151 3.82+/-0.24 3.56+/-0.23 3.99+/-0.26 4.17+/-0.34 4.33+/-0.45 4.61+/-0.18 4: 10+/-0.52 5A-ID-5Dl 4.72+/-0.48 4.17+/-0.40 4.75+/-0.12 4.58+/-0.22 4.88+/-0.36 5.26+/-0.26 4.80+/-0. 62 5A-ID-10Dl 5.61+/-0.37 5.52+/-0.08 5.49+/-0.37 5.58+/-0.37 5.63+/-0.42 5.78+/-0.44 5. 90+/-1.29 5A-ID-14Dl 5.12+/-0.22 4.99+/-0.32 5.07+/-0.49 5.20+/-0.13 5.32+/-0.26 5.48+/-0.22 5.27+/-0.42 5A-ID-2El 4.73+/-0.43 4.63+/-0.37 4.79+/-0.53 5.31+/-0.46 5.12+/-0.05 5.59+/-0.43 5.13+/-0.76 5A-ID-3El 4.81+/-0.30 4.73+/-0.40 4.45+/-0.40 5.12+/-0.35 4.62+/-0.23 5.09+/-0.37 4.95+/-0.51 5A-ID-13El 4.76+/-0.20 4.85+/-0.26 4.64+/-0.28 4.93+/-0.21 5.16+/-0.66 4.98+/-0.27 4.97+/-0.41 5A-ID-16El 5.51+/-0.44 5.10+/-0.20 5.08+/-0.21 5.03+/-0.26 5.32+/-0. 71 5.52+/-0.31 5.27+/-0.42 5A-ID-1Fl 5.47+/-0.46 4.83+/-0.32 5.25+/-0.50 5.43+/-0.35 5.41+/-0.37 5.94+/-0.27 5.46+/-0.59 5A-ID-2F2 4.27+/-0.56 3.91+/-0.06 3.89+/-0.23 4.43+/-0.41 4.40+/-0.36 4.80+/-0.26 4.35+/-0.79 5A-ID-5Fl 5.15+/-0.43 4.55+/-0.04 4.99+/-0.20 4.89+/-0.47 4.80+/-0.16 5.22+/-0.38 5.02+/-0.57 5A-ID-6Fl 5.25+/-1.00 3.79+/-0.15 4.16+/-0.17 4.33+/-0.15 4.23+/-0.41 4.47+/-0.36 4.33+/-0.69 5A-ID-7F2 4.20+/-0.25 3.29+/-0.13 4.00+/-0.23 3.86+/-0.14 4.05+/-0.12 4.57+/-0.38 3.94+/-0.65 5A-ID-11Fl 5.86+/-0.64 5.31+/-0.27 5.65+/-0.28 5.73+/-0.13 5.58+/-0.59 5.55+/-0.38 5.79+/-0.75 5A-I.D-13Fl 4.84+/-0. 22 4.86+/-0. 25 4.99+/-0.25 5.26+/-0.19 4.93+/-0.29 5.29+/-0.31 5.02+/-0.46 5A-ID-3Gl 5.86+/-1.02 5.51+/-0.41 5.76+/-0,92 5.63+/-0.33 5.83+/-0.25 6.16+/-0.55 5.84+/-0.73 5A-ID-2Hl 5.12+/-0.48 5.03+/-0.25 5.01+/-0.43 5.57+/-0.21. 4. 96+/-0. 38 5.77+/-0.57 5.43+/-0.69 5A-ID-3Hl 5.78+/-0.47 5.02+/-0.51 5.14+/-0.46 5.45+/-0.39 6.54+/-1.57 6.42+/-0.93 5.70+/-0.92 SA-ID-3H3 5.37+/-0.45 5.07+/-0.58 5.38+/-0.31 5.54+/-0.56 5.64+/-0.21 6.43+/-0.68 5.59+/-0.78 AVERAGE 5.04+/-1.09 4.68+/-1.18 4.88+/-1.07 5.08+/-1.06 5 .18+/-1.24 5.44+/-1.18 5.09+/-1.32

• The standard JTK)nth = 30.4 days.

91

TABLE C-35 DIRECT RADIATION MEASUREMENTS - QUARTERLY TLD RESULTS mrad/standard month*

STATION NO. JAN-MAR APR-JUN JUL-SEP OCT-DEC AVERAGE SA*ID-2Sl 3.95+/-0.39. 3.95+/-0.27 5.04+/-0.11 5.61+/-0.88 4.64+/-1.65 SA-ID-5Sl 4.12+/-0.70 3.95+/-0.57 4.10+/-0. 27 4.49+/-0.39 4.16+/-0.46 SA-ID-6Sl 5.16+/-0.32 5.17+/-0.23 4.86+/-0.21 5.28+/-0.54 5.12+/-0.36 SA-ID-7Sl 5.41+/-0.45 5.60+/-0.37 5.13+/-0.40 5.47+/-0.27 5.40+/-0.40 SA-ID-lOSl 5.03+/-0.38 5.29+/-0.41 4.70+/-0.28 4.84+/-0.22 4. 96+/-0. 51 SA-ID-llSl 3. 77+/-0. 25 4.00+/-0. 71 3.74+/-0.34 4.01+/-0.42 3.88+/-0.29 SA-ID-5Dl 4.56+/-0.48 4.98+/-0.25 4.64+/-0.36 4.73+/-0.64 4.73+/-0.36 SA-ID-1001 5.44+/-0.33 5.61+/-0.36 5.31+/-0.23 5.23+/-0.21 5.40+/-0.33 l.O N

SA-ID-1401 5.11+/-0.31 4.99+/-0.57 4.93+/-0.32 5.20+/-0.51 5.06+/-0.24 SA-ID-2El 5.02+/-0.30 4.97+/-0.72 5.04+/-0.30 5.52+/-0.42 5.14+/-0.51 SA-ID-3El 4.73+/-0.41 5 .48+/-1.36 4.47+/-0.25 4.93+/-0.46 4.90+/-0.86 SA-ID-13El 4. 77+/-0. 44 4.69+/-0.60 4.72+/-0.13 4.93+/-0.23 4. 78+/-0. 21 SA-ID-16El 5.02+/-0.39 5.08+/-0.40 5.02+/-0.35 5.41+/-0. 51 5.13+/-0.37 SA-ID-lFl 4.93+/-0. 45 4.94+/-1.39 5.02+/-0.21 5.21+/-0.70 5.02+/-0.26 SA-ID-2F2 4.08+/-0.38 4.26+/-0.05 3.73+/-0.36 4.25+/-0.56 4.08+/-0.50 SA-ID-5Fl 4.64+/-0.32 5.08+/-0.29 4.69+/-0.47 4.62+/-0.23 4. 76+/-0.43 SA-ID-6Fl 4.19+/-0. 29 4.08+/-0.64 4.01+/-0.38 4.00+/-0.11 4.07+/-0.18 SA-ID-7F2 3.96+/-0.21 3.82+/-0.18 3.55+/-0.09 3.70+/-0.22 3.76+/-0.35 SA-ID-llFl 5.43+/-0.27 5.62+/-0.27 5.67+/-0.30 5.60+/-0.55 5.58+/-0.21 SA-ID-13Fl . 4.89+/-0. 27 5.21+/-0.78 4.87+/-0.30 5.05+/-0.32 5.00+/-0.32 SA-ID-2Hl 5. 77+/-0. 25 5.56+/-0.35 5.29+/-0.44 5.75+/-0.13 5.59+/-0.45 SA-ID-3Hl 5.44+/-0.41 5.46+/-0.36 5.09+/-0.28 5.73+/-0.37 5.43+/-0.53 SA-ID-3H3 5.46+/-0.54 5 .90+/-1.28 5.33+/-0.65 5.22+/-0.40 5.48+/-0.60 SA-ID-3Gl 5.27+/-0.82 5.56+/-0.31 5.46+/-0.46 5.68+/-0.44 5.49+/-0.35 Average 4.84+/-1.14 4.97+/-1.27 4. 77+/-1.14 5 .02+/-1.18 4.90+/-1.18

• .The standard month = 30.4 days.

TABLE C-36 CONCENTRATIONS OF GAMMA EMITTERS IN SPECIAL WEEKLY COMPOSITES.

- OF AIR PARTICULATE SAMPLES Results* in Units of 10- 3 pCi/m3 +/- 2 sigma STATION NO.

AND DATE Be-7 Zr-95 Nb-95 Ru-103 1-131 Cs-137 BaLa...;140 Ce-141 Ce-144 SA-AP-251 9-19-77 to 62+/-21 13+/-5 15+/-3 24+/-4 47+/-27 <2 34+/-16 21+/-4 16+/-6 9-27-77 l.D . SA-AP-lFl w

9-19-77 to 69+/-28 19+/-6 18+/-4 25+/-5 <26 3+/-2 45+/-22 32+/-7 <22 9-27-77 SA-AP-2F2 9-19-77 to <30 19+/-6 6.7+/-2.4 19+/-4 <14 <2 36+/-16 25+/-5 11+/-7 9-27-77

• All results are decay corrected to sample stop date.

TABLE C-37

• COMPARISON OF FOURTH QUARTER STRONTIUM-89 MDL VALUES IN MILK SAMPLES Results in Units of pCi/l +/- 2 sigma DATE MDL AT TIME MDL DECAY CORRECTED SAMPLE LOCATIONS OF ANALYSIS TO SAMPLE STOP DATE October SA-M-2Fl *

• SA-M-5F2 *

• SA-M-14Fl <6.2 <7.6 SA-M-15Fl <5.1 <6.2 SA-M-3Gl *

• November SA-M-2Fl <20{1) <44 SA-M-5F2 <1.8 <6.2 SA-M-14Fl <3.5 <7.7 SA-M-15Fl *

• SA-M-3Gl <4.1 <9.1 December I SA-M-2Fl *

• SA-M-5F2 *

• SA-M-14Fl *

• SA-M-15Fl {2)

SA-M-3Gl <3.3 <6.0

• Indicates positive value was detected.

{l) .This higher than normal MDL at the time of analysis is a result of a low chemical yield.

{2) MDL {4.4 pCi/l) is within the required sensitivi.ty *.

94