ML20133J501

Artificial Island Radiological Environ Monitoring Program, 1984 Radiological Rept

ML20133J501
Person / Time
Site:	Salem
Issue date:	12/31/1984
From:	PSE&G RESEARCH CORP.
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References
RTL-ENV-85-01, RTL-ENV-85-1, NUDOCS 8510180474
Download: ML20133J501 (167)

Text

r RT -ENV-85-01 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRCNMENTAL MONITORING PROGRAM I

1984 RADIOLOGICAL REPORT JANUARY 1 TO DECEMBER 31, 1984 Prepared for PUBLIC SERVICE ELECTRIC AND GAS COMPANY By PSE&G RESEARCH CORPORATION RESEARCH AND TESTING LABORATORY I

MARCH 1985

[ok J h2 R

TABLE OF CONTENTS PAGE

SUMMARY

l INTRODUCTION 2 l THE PROGRAM 3 Objectives 3 1984 Program Overview (Table-1) 4 Sample Collection 8 Data Interpretation 9 Quality Assurance Program 10 Program Changes 10 RESULTS AND DISCUSSION 10 Atmospheric 11 .

Direct Radiation 14 Terrestrial 17 Aquatic 22 PROGRAM DEVIATIONS 29 CONCLUSIONS 29 REFERENCES 30 APPENDIX A - PROGRAM

SUMMARY

33 APPENDIX B - SAMPLE DESIGNATION AND LOCATIONS 43 APPENDIX C - 1984 DATA TABLES 51 APPENDIX D - SYNOPSIS OF ANALYTICAL PROCEDURES 101 APPENDIX E -

SUMMARY

OF USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDIES PROGRAM RESULTS 151 APPENDIX F - SYNOPSIS OF DAIRY AND VEGETABLE GARDEN SURVEY 161 1

LIST OF FIGURES I

NUMBER PAGE

1. Comparison of Average Concentrations of Beta - g Emitters in Precipitation and in Air Particulates, E 1973 through 1984.................................. 12 1A. Comparison of Average Concentrations of Beta Emitters in Precipitation and in Air Particulates, 1983 through 1984.................................. 13

2. Average Ambient Radiation Levels from Quarterly TLDs in the Vicinity of Artificial Island, 1973 through 1984....................................... 15 2A. Comparison of Ambient Radiation Levels of Off-Site Indicator Stations vs. Control Stations, 1982 through 1984....................................... 16

3. Average Concentrations of Iodine-131 in Milk in the Vicinity of Artificial Island, May 1974 through December 1984...................................... 18 3A. Average Concentrations of Iodine-131 in Milk in the Vicinity of Artificial Island, 1983 through 1984... 19

4. Average Concentrations of Beta Emitters and Potassium-40 in the Delaware River in the Vicinity of Artificial Island, 1973 through 1984............ 23 4A. Average Concentrations of Beta Emitters and Potassium-40 in the Delaware River in the Vicinity of Artificial Island, 1983 through 1984............ 24

5. Average Concentrations of Tritium in the Delaware River in the Vicinity of Artificial Island, 1973 through 1984....................................... 25 SA. Average Concentrations of Tritium in the Delaware River in the Vicinity of Artificial Island, 1983 through 1984....................................... 26 11

I I

SUMMARY

During the period from January 1 through December 31, 1984, the Research and Testing Laboratory (RTL), PSE&G Research Corpo-ration, has been responsible for the collection and analysis of I all samples and the maintenance of sampling equipment for SGS connected with the Operating Radiological Environmental Monitoring Program at Artificial Island, Salem County, New Jersey.

Galem Generating Station (SGS) Unit One became critical on December 11, 1976, thereby initiating the operational phase of I the Radiological Environmental Monitoring Program (REMP).

program was designed to identify and quantify concentrations of radioactivity in various environmental media and to quantify This ambient radiation levels in the environs of Artificial Island.

Unit Two achieved initial criticality on August 2, 1980. During the operational phase, the program will monitor the operations of SGS Units One and Two, will fulfill the requirements of the I SGS Environmental Technical Specifications, and will provide background data for the Hope Creek Generating Station. This report presents the results of thermoluminescent dosimetry and radiochemical analyses of environmental samples collected during I 1984.

A total of 4305 analyses were performed on 1626 environmental samples during the period covered by this report. Samples of air particulates, air iodine, surface, ground and drinking water, benthos, sediment, milk, fish, crabs, vegetables, game, fodder crops, meat, and precipitation were collected. Thermoluminescent dosimeters wn.re used to measure ambient radiation levels.

A variety of radionuclides, both naturally-occurring and manmade, were found in the above samples. \n.ejevated level of two radionuclides was found in one sediment / ben'ai..c crganism sample. Subsequent sampling of the indicators in the estuarine food-chain were at levels similar to those found during the peroperational phase of this program. It can be concluded that the radiological characteristics of the environment around Artificial Island during 1984 were not adversely affected by the operation of EGS Units One and Two.

1

I INTRODUCTION Artificial Island is the site of Salem Generating Station (SGS) which consists of two operating pressurized water nuclear power reactors. Unit One has a net rating of 1090 MWe (3338 MWt), and Unit Two is rated at 1115 MWe (3411 MWt).

Artificial Island is a man-made peninsula on the east bank of the Delaware River and was created by the deposition of hydraulic Il-l fill from dredging operations. It is located in Lower Alloways E Creek Township, Salem County, New Jersey. The environment 3 surrounding Artificial Island is characterized mainly by the Delaware River and Bay, extensive tidal marshlands, and low-lying meadowlands. 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 agriculture [13]. More specific information on the demography, hydrology, meteorology, and land use of the area may be found in the Environmental Report (13], Environmental Statement [14], and the Final Safety Analysis Report for SGS (15].

Since 1968 an off-site Radiological Environmental Monitoring Program (REMP) has been conducted at the Artificial Island site.

Starting in December 1972, more extensive radiological monitoring programs were initiated. The operational REMP was initiated in December 1976 when Unit 1 achieved criticality. The Research and Testing Laboratory (RTL), PSE&G Research Corporation, a wholly-owned subsidiary of Public Service Electric and Gas Company, has been involved in the REMP since its inception. The RTL is responsible for the collection of all radiological environmental samples, and, from 1973, through June, 1983, conducted a quality assurance program in which duplicates of a portion of those samples analyzed by the primary laboratory were also analyzed by the RTL.

From January 1973, through June 1983, Radiation Management Corporation (RMC) had primary responsibility for the analysis of all samples under the Artificial Island REMP and the annual reporting of results. RMC reports for the the preoperational phase from 1973 to 1976 and for the operational phase from 1976 through 1982 are referenced in this report [1-11]. On July 1, 1983, the RTL assumed primary responsibility for the analysis of all samples (except TLD's) and the reporting of results.

Teledyne Isotopes (TI), Westwood, NJ, at that time was made responsible for third-party QA analyses and TLD's.

This report summarizes the results from January 1 through December 31, 1984 for the Artificial Island Radiological l Environmental Monitoring Program. 3 2

I i

THE PROGRAM The operational phase of the REMP is conducted in accordance with section 3.2 of the Environmental Technical Specifications for SGS Units 1 and 2 (16,17]. An overview of this program is l provided in Table 1. Radioanalytical data from samples collected under this program were compared with results from the preoper-ational phase. Differences between these periods were examined statistically, where applicable, to determine the effects, if any, of station operations.

Objectives The objectives of the operational radiological environmental program are:

1. To fulfill the obligations of the Radiological Surveillance sections of the Environmental Technical Specifications for I Salem Generating Station (SGS).

2. To determine whether any significant increase occurs in the concentration of radionuclides in critical pathways.

3. To determine if SGS has caused an increase in the radioactive inventory of long lived radionuclides.

4. To detect any change in ambient gamma radiation levels.

5. To verify that SGS 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 Environ-mental Technical Specifications (ETS), summarizes the findings of the 1984 REMP. Results of the four-year preoperational program have been summarized for purposes of comparison with subsequent operational reports [4J.

I 3

TABLE -1 1984 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITT) RING PROGRAM STATION CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE / FREQUENCY

• OF ANALYSIS I. ATMOSPHERIC ENVIRONMENT

a. Air Particulate 2S2 SDI 16El IFl 3H3 Weekly Gross alpha / weekly SS1 10D1 2F2 Gross beta / weekly Sr-89 & -90/ quarterly Gamma scan /quartefly

b. Air Iodine 2S2 SD1 16El 1F1 3H3 Weekly Iodine-131/ weekly SSl 10D1 2F2 s

c. Precipitation 2F2 Monthly Gross alphs/ monthly Gross beta / monthly Tritium / monthly Sr-89 & -90/ quarterly Gamma scan / quarterly II. DIRECT RADIATION

a. Thermoluminesceat 2S2 SD1 2El 1F1 3G1 3H1 Monthly & Gamma dose / monthly Dosimeters 551 10D1 3El 2F2 3H3 Quarterly Gamma dose / quarterly 6S2 14D1 13El 2F6 7Sl 16El SF1 10S1 6F1 11S1 7F2 llF1

[ 13Fl/4 i

M M M M M M

m M M M M M M M M M M TABLE -1 (cont'd) 1984 ARTIFICIAL ISLAND RADIOIDGICAL ENVIRONMENTAL MONI'IORING PROGRAM STATION CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE / FREQUENCY

• OF ANALYSIS

a. Thermoluminescent 4D2 9El 2F5 1G3 Quarterly Gamma dose / quarterly Dosimeters (cont'd) 11E2 3F2 10G1 12El 3F3 16G1 10F2 12F1 13F2 13F3 14F2 15F3 m 16F2 III. TERRESTRIAL ENVIRONMENT

a. Milk 13E3 2F4 3G1 Semi-monthly Iodine-131/ semi-monthly SP2 Sr-89 & -90/ monthly 14F1 Gamma scan / monthly 15F1

b. Well Water 2S3 SD1 3El Monthly Gross alpha / monthly Cross beta / monthly Potassium-40/ monthly Tritium / monthly Sr-89 & -90/ quarterly Gamma scan / quarterly

i TABLE -1 (cont'd) 1984 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONI'IORING PROGRAM STATION CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE / FREQUENCY

• OF ANALYSIS

c. Potable Water 2F3 Monthly Gross alpha / monthly (Raw & Treated) (Composited Gross beta / monthly daily) Potassium-40/ monthly Tritium / monthly Sr-89 & -90/ quarterly Gamma Scan / quarterly

d. Vegetables SD1 2El IF3 IGl 3HS Annually Sr-89 & -90/on collection 4F1 (At Harvest) Gamma scan /on collection 05 SF1 14F3

e. Game 3El llD1 Semi- Sr-89 & -90 (bones)/on collection (Muskrat) annually Gamma scan (flesh)/on collection

f. Beef 3El Semi- Gamma scan /on collection annually

g. Bovine 'Ihyroid 3El Semi- Gamma scan /on collection annually

h. Fodder crops 3El 2F4 3G1 Annually Gamma scan /on collection SP2 14F1 15F1 m . -

m m M M M

l M

TABLE -1 (cont'd) 1984 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONI'IORING PROGRAM STATION CODE COLLECTION MEDIUM INDICA'IOR CONTROL FREQUENCY TYPE / FREQUENCY

• OF ANALYSIS IV. AQUATIC ENVIRONME!!T

a. Surface Water llAl 7El 1F2 12Cl Monthly Gross alpha / monthly 16F1 Gross beta / monthly Tritium / monthly Sr-89 & -90/ quarterly Gamma scan / monthly

b. Edible Fish 11A1 7El 12Cl Semi- Tritium in a annually Aqueous fraction /on collection Organic fraction /on collection Sr-89 & -90 (bones)/on collection Gamma scan (flesh)/on collection

c. Blue Crabs 11A1 12Cl Semi- Tritium (flesh)/on collection annually Sr-89 & -90 (shell)/on collection Sr-89 & -90 (flesh)/on collection Gamma scan (flesh)/on collection

d. Benthic Organisms llAl 7El 16F1 12Cl Semi- Sr-89 & -90/on collection annually Gamma scan /on collection

e. Sediment 11A1 7El 16F1 12C1 Semi- Sr-90/on collection annually Gamma scan /on collection

• Except for TLDs, the quarterly analysis is performed on a composite of individual samples collected during the quarter.

I Sample Collection In order to meet the stated ob]ectives, an appropriate oper-ational RE;4P was developed. Samples of various media were selected to obtain data for the evaluation of the radiation dose to man and other organisms. The selection of sample types was based on: (1) established critical pathways for the transfer of radionuclides through the environment to man, and (2) experience gained during the preoperational phase. Sampling locations were determined from site meteorology, Delawate estuarine hydrology, local demography, and land uses.

Sampling locations were divided into two classes - indicator and control. Indicator stations are those which are expected to g manifest station effects, if any exist; control samples are E collected at locations which are believed 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. Indicator and control station data are also evaluated relative to preoper-ational data. The REMP for the Artificial Island Site includes additional samples and analyses not specifically required by the Salem ETS. The summary tables in this report include these additional samples and analyses.

Air particulates were collected on Schleicher-Schuell No. 25 glass fiber filters with low-volume air samplers. Iodine was collected from air by adsorption on TEDA-impregnated charcoal cartridges connected in series after the air particulate filters.

Air sample volumes were measured with calibrated dry-gas meters and were corrected to standard temperature and pressure.

Precipitation was collected in a Wong Laboratory Automatic Precipitation Collector having a 95 square inch collection area.

The collector is automatically covered during periods of no precipitation to exclude fallout resulting from dry deposition.

Samples were collected monthly and transferred to new poly-ethylene bottles. The collector was rinsed with distilled water 3 to include residual particulates in the precipitation samples. l Tritium results were corrected for the tritium content of the distilled water.

Ambient radiation levels in the environs were measured with energy-compensated CaSO4 (Dy) thermoluminescent dosimeters (TLD's) supplied and read by Teledyne Isotopes. Packets for monthly and quarterly exposure were placed on and around the Artificial Island Site at various distances.

Well water samples were collected monthly by PSE&G personnel and separate raw and treated potable water samples were composited daily by personnel of the City of Salem water treatment plant.

New two-gallon polyethylene containers were used for all water samples.

8

I All estuarine samples were collected by V. J. Schuler Associates, Inc. (formerly Ichthyological Associates) and delivered by PSE&G personnel. Surface water samples were collected in new con-I tainers which were rinsed twice with the sample medium prior to collection. Edible fish and crabs were taken by net, and frozen in sealed polyethylene containers. Benthos and sediment were taken with a bottom grab sampler.

Milk samples were taken semi-monthly in new polyethylene con-I tainers. Food products, fodder crops, game, beef, and bovine thyroid were sealed in new plastic bags or jars. All perishable samples were transported in ice chests, and no preservatives were added.

Appendix A describes and summarizes, in the format of Table 5.6-1 of the Salem ETS, the entire operational program as performed in 1984. Appendix B describes the coding system which identifies sample type and location. Table B-1 lists the sampling stations and the types of samples collected at each station. These sampling stations are indicated on maps B-1 and B-2.

Data Interpretation Results of all analyses were grouped according to the analysis performed for each type of sample and are presented in the data tables in Appendix C. All results above the lower limit of detection (LLD) are at a confidence level of 2 2 sigma. This represents the range of values into which 95% of repeated analyses of the same sample should fall. As defined in Regulatory Guide 4.8, LLD is the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95%

probability with only 5% probability of falsely concluding that a blank observation represents a "real signal". LLD is normally calculated as 4.66 times one standard deviation of the background count or of the blank sample count as appropriate.

The grouped data were averaged and standard deviations calcu-lated in accordance with Appendix B of Reference 13. Thus, the 2 sigma deviations of the averaged data represent sample and not analytical variability. When a group of data were composed of 50% or more LLD values, averages were not calculated.

Grab sampling is a useful and acceptable procedure for taking environmental samples of a medium in which the concentration of radionuclides is expected to vary slowly with time or where intermittent sampling is deemed sufficient to establish the radiological characteristics of the medium. This method, however, is only representative of the sampled medium for that specific location and instant of time. As a result, variation 9

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 considered valid.

Quality Assurance Program PSE&G Research Corporation, Research and Testing Laboratory (RTL), has a quality assurance program designed to maximize confidence in the analytical procedures used. Approximately 20%

of the total analytical effort is spent on quality control, including process quality control, instrument quality control, interlaboratory cross-check analyses, and data review. The analytical methods utilized in this program are summarized in Appendix D.

The quality of the results obtained by the RTL is insured by the implementation of the Quality Assurance Program as described in the Environmental Division Quality Assurance Manual [19] and the Environmental Division Procedures Manual [20]. The internal quality control activity of the Laboratory includes the quality control of instrumentation, equipment, and reagents, the use of g reference standards in calibration, documentation of established g procedures and computer programs, and analysis of duplicate and spiked samples. The external quality control activity is implemented through participation in the USEPA Laboratory Inter-comparison Studies Program. These results are listed in Tables E-1 through E-6 in Appendix E.

Program Changes TLD location 13F1 was relocated to an adjacent site and designated 13F4 on March 27, 1984. This move became necessary when the new owners of the building upon which the TLD was mounted began renovation work.

An additional leafy vegetable location (14F1) became available in 1984 and was added to the program.

Vegetable control location 3H4 which is no longer growing crops was replaced by location 3H5.

RESULTS AND DISCUSSION The analytical results of the 1984 REMP samples are divided into categories based on exposure pathways: atmospheric, direct, terrestrial, and aquatic. The analytical results for the 1984 REMP are summarized in Appendix A. The data for individual samples are presented in Appendix C.

10

I This section discusses the data for samples collected under the REMP. It does not include the data from the quality assurance program discussed previously.

Atmospheric Air Particulates (Tables C-1, C-2, C-3)

Air particulate samples were analyzed for alpha and beta emitters, St-89 and -90, and gamma emitters. The weekly air particulate samples were analyzed for gross alpha and gross beta. Quarterly composites of the weekly samples from each station were analyzed for Sr-89, Sr-90 and specific gamma emitters.

Concentrations were detected in 366 of the 424 weekly samples analyzed for gross alpha emitters Taoleg-1). Alpha concentra-tions ranged from 0.7 to 4.7 x 10- pCi/ with the grand average for all stations being 1.9 x 10-g pCi/m3 Three analyses exhibited high uncertainties due to low sample volumes.

Analysis of weekly air particulate samples for gross beta (Table C-2gindicatedconcentrationsrangingfrom6.0x10-3 10- 3 with the grand average for all stations being 24 to 44 x x 10 gCi/m pCi/m 3. Figure 1 indicates the relation between gross beta activity in air particulates and precipitation for the preoperational and operational periods, including the effects of atmospheric weapons testing.

Of the 32 monthly-composited samples analyzed for strontium-89 onlygne pCi/m .

(control station) had a detectable level of 1.1 x 10-b TherewasnoSr-90detectableacgivity.3 I Sr-89 ranged from 0.2 x 10-3 to 2.0 x 10-Sr-90, from 0.1 x 10-3 to 0.6 x 10-3 pCi/m3, LLD's for pCi/m and, for Results of gamma spectrometry indicated detectable levels of B inalgofthe32monthlycompositeswithamaximumof79x10-g-7 PCi/m . Be-7 is a naturally occurring radionuclide attributed to cosmic ray activity in the atmosphere. Traces of Cr-51, Mn-54, Co-58, Fe-59, Te-129m, Ra-226 and Th-232 were detected in 5 samples; all of these activities were below the maximum LLD's for these radionuclides.

Air Iodine (Table C-4)

Cartridges for the adsorption of air iodine were connected in series after each of the air particulate filters. The adsorption media in these cartridges is triethylenediamine (TEDA) impreg- l natedcharcog1.

to <56 x 10- pCi/m .

AlgresultsforI-131rangedfrom<4.1x10-3 In addition, one did not meet minimum i

l sensitivity of 60 x 10-3 pCi/m3, 11

FIGURE I COMPARISON OF AVERAGE CONCENTRATIONS OF BETA EMITTERS IN PRECIPITATION AND IN AIR PARTICULATES,1973 THROUGH 1984 1000 Legend

. AIR 1E-3 pCi/m**3 a R AIN pCi/l

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EMITTERS IN PRECIPITATION AND IN AIR PARTICULATES 1983 THROUGH 1984 1000 Legend l 8 AIR IE-3 pCi/m"3 i - a RAIN pCi/l 10 0 1 . . n - >

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Precipitation (Tables C-6, C-7)

Although not required by the Salem ETS, precipitation samples were collected at 2F2 in the town of Salem. Monthly samples were analyzed for gross alpha, gross beta, and tritium. Alpha activities in 4 samples ranged from 0.8 to 2.4 pCi/L, with LLD's in 8 samples from 0.8 to 1.9 pCi/L. Beta activity in eleven of the monthly samples ranged from 1.0 to 4.0 pCi/L, with an LLD in one sample of <2.7 pCi/L. Tritium was detected in three samples at levels ranging from 140 to 150 pCi/L; this is below the required sensitivity of 200 pCi/L.

Quarterly composites were analyzed for radiostrontium and gamma g emitters. Neither Sr-89 nor Sr-90 was detected. Be-7 at g concentrations of 25 to 39 pCi/L was found in the quarterly samples. In addition, Ra-226 at 5.6 pCi/L and Th-232 at 7.8 pCi/L was seen in the fourth quarterly sample.

Direct Radiation (Tables C-8, C-9)

A total of 41 locations were monitored for direct radiation during 1984, including 6 on-site locations, 29 off-site locations within the 10 mile zone, and 6 control locations beyond 10 miles.

Monthly and quarterly measurements were made at the 6 on-site stations and at 15 off-site indicator stations, and 3 control l stations. An additional 14 quarterly measurements were taken at 5 schools and population centers with 3 additional controls beyond the 10 mile zone in Delaware.

Four readings fcr each TLD at each location were taken in order to obtain a more statistically valid result. The average dose rate for the 15 monthly off-site indicator TLD's was 5.8 millirads per standard month, and the corresponding averaged control dose rate was 6.4 millirada per standard month. The average dose rate for the 29 quarterly off-site indicator TLD's was 5.5 millirada per standard month, and the averaged control rate was 6.1. *For these measurements, the rad is considered equivalent to the rem, in accordance with 10CFR20.4.

In Figure 2, the average radiation levels are plotted for the 12 year period through 1984. Figure 2A shows the monthly averages of the off-site indicator stations and the control stations for 1982 through 1984. An increase in ambient radiation levels over those of 1983 for both indicator and control locations was noted for the months of February, May and June while the other months indicated a decrease. The annual averages for both off-site indicators and controls were slightly lower than those in 1983.

14

M M M M M M M M M M M M M M M M M M M FIGURE 2 AVERAGE AMBIENT RADIATION LEVELS FROM QUARTERLY TLDS IN THE VICINITY OF ARTIFICIAL ISLAND,1973 THROUGH 1984 10 Legend

. ALL STATIONS e CONTROL STATIONS 8-W

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FIGURE 2A COMPARISON OF AMBIENT RADIATION LEVELS OF OFF-SITE INDICATOR STATIONS VS. CONTROL STATIONS 1982 THROUGH 1984 to ,

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E g Terrestrial Milk (Tables C-10, C-11, C-12, C-13)

Milk samples were collected twice each month at six local dairy farms. Each sample was analyzed for I-131 and the first collec-I tion each month was also analyzed for Sr-89 and -90 and gamma emitters. Figure 3A indicates that I-131 was not detectec in any sample during 1984. Table C-10 lists the results and shows that sensitivities ranged from <0.1 to <0.2 pCi/L.

Strontium-89 was not detected in any of the samples; LLD values ranged from <0.8 to <2.0 pCi/L. Strontium-90 was found in all of the samples analyzed. The Sr-90 annual mean for the indicator locations was 2.4 pCi/L with a range of 1.2 to 5.3 pCi/L; annual mean for the control location was 3.2 pCi/L with a range of 2.2 to 4.9 pCi/L.

Gamma spectrometry showed detectable concentrations of K-40 in all samples and Cs-137 in eleven of the sixty indicator locations and none was detected in the twelve samples from the control location. The annual mean concentration of K-40 for the indi-cator locations was 1347 pCi/L with a range of 1200 to 1500 pCi/L; K-40 mean for the control location was 1330 pCi/L with a range of 1300 to 1500 pCi/L. The annual mean of Cs-137 for the indicator locations was 3.1 pCi/L with a range of 1.8 to 6.2 pCi/L; preoperational levels ranged from <0.4 to 14 pCi/L with I an average of 3.0 pCi/L. Traces of Na-22, Mn-54, La-140, Ra-226 and Th-232 was detected at levels near or below the LLD values in seven of the 72 samples analyzed.

Well Water (Tables C-14, C-15)

Well water samples were collected monthly from two indicator wells and one control well. Each sample was analyzed for gross I alpha, gross beta, tritium and potassium-40. Quarterly com-posites were analyzed for radiostrontium and gamma emitters.

Gross alpha concentrations f rom 0.9 to 2.0 pCi/L were detected in six of the indicator samples, with LLD sensitivities for the other analyses ranging from <0.6 to <1.9 pCi/L. Gross beta activity was detected in all of the samples. The mean activity I for the indicator locations was 10 pCi/L with a range of 2.9 to 17 pCi/L; mean activity for the control location was 8.4 pCi/L with a range of 6.0 to 10 pCi/L. K-40 in each monthly sample was determined by atomic absorption spectroscopy. Mean activity for the indicator locations was 11 pCi/L with a range of 2.8 to 28 pCi/L, and mean activity for the control location was 8.4 pCi/L with a range of 5.5 to 9.3 pCi/L. All tritium results were at LLD levels of <130 to <140.pci/L. Strontium-89 was detected in one indicator location sample at 0.9 pCi/L; LLD values ranged from <0.4 to <0.6 pCi/L. Sr-90 was not detected in any of the samples; LLD values ranged from <0.4 to <0.5 pCi/L.

17

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[14] United States Atomic Energy Commission. " Final Environmental Statement -

Salem Nuclear Generating Station, Units 1 and 2". Docket No. 50-272 and 50-311, 1973.

[15] Public Service Electric and Gas Company. " Updated Final Safety Analysis Report - Salem Nuclear Generating Station, Units 1 and 2". 1982. "

[16] Public Service Electric and Gas Company. " Environmental Technical g Specifications - Salem Nuclear Generating Station Units 1 and 2", 3 Appendix B to Operating License DPR-70, 1976 (through Amendment 58).

[17] Public Service Electric and Gas Company. " Environmental Technical Specifications - Salem Nuclear Generating Station Unit 2", Appendix B to Facility Operating License No. DPR-75, 1981 (through Amendment 27).

[18] U. S. Environmental Protection Agency. " Prescribed Procedures for Measurement of Radioactivity in Drinking Water." EPA-600/4-80-032, August, 1980.

[19] PSE&G Research Corporation, Research and Testing Laboratory. " Environ-mental Division Quality Assurance Manual." September, 1980.

[20] PSE&G Research Corporation, Research and Testing Laboratory. " Environ-mental Division Procedures Manual." February, 1981.

[21] Public Service Electric and Gas Company. " Radioactive Effluent Release Report, RERR Salem Generating Station, Units 1 and 2". 1984.

I I

31 I

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APPENDIX A .

PROGRAM

SUMMARY

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E ARTIFICIAL ISLAND RADIOIDGICAL ENVIROtSEENTAL MONITORING PROGRAM

SUMMARY

SALEM NUCLEAR GENERATING STATION DOCERT NO. 50-272/-311 SALEM CDUNTY, NEW JERSEY JANUARY 1, 1984 to DECEMBER 31, 1984 ANALYSIS AND IDWER NUMBER OF MEDILM OR PATHNAT 10TAL DRMBER LIMIT OF ALL INDICATOR IDCATIONS IDCATION WITN NIGHEST MEAN CONT 1tOL IDCATION(S) NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED ( LID) * (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Precipitation Alpha 12 0.8 1.5 (4/12) 2F2 8.7 mi NNE 1.5 (4/12) No Control 0 (pct /L) (0.0-2.4) (3.8-2.4) Incation Beta 12 2.7 2.0 (11/12) 2F2 8.7 mi NNE 2.0 (11/12) No CDntrol 0 (1.0-4.0) (1.0-4.0) location N-3 12 130 143 (3/12) 2F2 8.7 mi NNE 141 (3/12) No CDntrol 0 (140-150) (140-150) Iocation St-89 4 0.5 <LLD - (LIS No CDntrol 0 location Sr-90 4 0.4 <LLD - < LLD No (bntrol 0 location r:a mma pe-7 4 -

34 (4/4) 2r2 8.7 mi NME 34 (4/4) No CDntrol 0 (25-39) (25-39) location (J Ra-226 4 1.3 5.6 (1/4) 2r2 8.7 mi NME 5.6 (1/4) No Control 0 m (5.6) (5.6) Iocation th-232 4 2.2 7.8 (1/4) 2r2 8.7 mi NNE 7.8 (1/4) No CDntrol 0 (7.8) (7.8) Incation Direct Radiation Gamma 287 (arad/std. month) Dome (monthly) -

5.9 (251/251) 1181 0.09 mi Sw 6.8 (12/12) 6.4 (36/36) 0 (3.5-11.3) (4.7-11.31 (5.2-8.5)

Gaasna 163 Dose (qtriy.l -

5.5 (139/139) 1G319 mi N 6.7 (4/4) 6.1 (24/24) 0 (3.5-8.7) (6.0-7.2) (5.0-7.2)

ARTIFICIAL ISLAND RADIO 1DGICAL ENVIROMGNTAL MONITORING PROGRAM

SUMMARY

SALEM NUCI2AR GENERATING STATION DOCERT NO. 50-272/-311 SALEM COUNTY, NEN JERSEY JANUARY 1, 1984 to DECEMBER 31, 1984 ANALYSIS AND IDNER W M ER OF MEDIL30 OR PATHIO' TOTAL NEDtBER LIMIT OF ALL INDICA 10R IDCATIONS IDCATION NITH NIGHEST MEAN CONTROL IDCATION(S) NONROITTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN RE.NRTYD (UNIT OF M_***'_m "2 W)

_ PERFORMED ( Lib) * (RANGE) DISTANCE AND DIRECTION (RANGE) (RAkCE) MEASURIMENTS Air Particulates Alpha 424 0.6 2.0 (315/371) 16El 4.1 at NNN 2.2 (50/53) 2.0 (51/53) 0 (10*3 pC1/m3 ) (0.7-4.7) (0.8-4.7) (0. 0-s. 7)

Beta 424 3.0*** 24 (371/371) 16El 4.1 mi NNN 26 (53/53) 24 (53/53) 0 (10-44) (12-43) (6.0-41) 8r-69 32 0.2 < LLD 3N3 110 mi NE 1.1 (1/4) 1.1 (1/4) 0 (1.1) (1.1) 8r-90 32 0.1 <LLD -

< LLD < LIA 0 Gamma Be-7 32 -

64 (28/28) 501 3.5 mi E 73 (4/4) 60 (4/4) 0 (52-79) (63-79) (52-69)

Cr-51 28 1.9 2.0 (1/24) 282 0.4 mi NME 2.0 (1/4) < LLD 0 gg (2.0) (2.0) on Mn-54 32 0.1 0.7 (1/28) 16El 4.1 mi NNN 0.7 (1/4) < LLD 0 (0.7) (0.7) .

00-58 32 0.2 0.3 (1/28) 2S2 0.4 mi NME 0.3 (1/4) <LLD 0 (0.3) (0.3)

Fe-59 32 0.3 1.0 (1/28) 531 1.0 mi E 1.0 (1/4) <LLD 0 (1.0) (1.0)

Te-129m 28 2.5 15 (1/24) 581 1.0 mi E 15 (1/4) < LLD 0 (15) (15)

Ra-226 32 0.4 0.9 (1/28) 16El 4.1 mi NNN 0.9 (1/4) <LLD J (0.9) (0.9)

Th-232 28 1.0 1.4 (2/24) 16El 4.1 mi NNN 1.6 (1/4) <LLD 3 (1.3-1.6) (1.6)

Air Iodine 1-1 31 424 4.1 (LLD -

<LLD <LLD 0 (10-3 pC1/m3 )

M M M M Fm M M

I I REFERENCES I [1] Radiation Management Corporation. " Salem Nuclear Generating Station -

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

[2] Radiation Management Corporation. " Artificial Island Radiological Environmental Monitoring Program - 1974 Annual Report". RMC-TR-75-04, I 1975.

Radiation Management Corporation. " Artificial Island Radiological

[3]

Environmental Monitoring Program - 1975 Annual Report". RMC-TR-76-04, 1976.

[4] Radiation Management Corporation. " Artificial Island Radiological I Environmental Monitoring Program - Preoperation Summary - 1973 through 1976". RMC-TR-77-03, 1978.

I [5] Radiation Management Corporation. " Artificial Island Radiological Environmental Monitoring Program - December 11 to December 31, 1976".

RMC-TR-77-02, 1977.

[6] Radiation Management Corporation. " Artificial Island Radiological Environmental Monitoring Program - 1977 Annual Report". RMC-TR-78-04A, 1978.

[7] Radiation Management Corporation. " Artificial Island Radiological Environmental Monitoring Program - 1978 Annual Report". RMC-TR-79-03, 1979.

[8] Radiation Management Corporation. " Artificial Island Radiological Environmental Monitoring Program - 1979 Annual Report". RMC-TR-80-03, 1980.

[9] Radiation Management Corporation. " Artificial Island Radiological I Environmental Monitoring Program - 1980 Annual Report".

1981.

RMC-TR-81-03,

[10] Radiation Management Corporation. " Artificial Island Radiological I Environmental Monitoring Program - 1981 Annual Report".

1982.

RMC-TR-82-01, I [11] Radiation Management Corporation. " Artificial Island Radiological Environmental Monitoring Program - 1982 Annual Report".

1983.

RMC-TR-83-03,

[12] PSE&G Research Corporation, Research and Testing Laboratory.

" Artificial Island Radiological Environmental Monitoring Program - 1983 Annual Report". RTL-ENV-84-01, 1984.

[13] Public Service Electric and Gas Company. " Environmental Report, Operating License Stage - Salem Nuclear Generating Station Units 1 and 2". 1971.

30 11

I PROGRAM DEVIATIONS The January surface water sample from all five locations was unavailable due to icing conditions on the river.

The second semi-annual collection of muskrat samples was not E obtained. Muskrats are normally trapped during November and E December each year. However, in 1984, because of weather con-ditions and the poor quality of the pelts, muskrats were not available from the trappers.

The second semi-annual collection of beef and bovine thyroid samples was not obtained. Farmers from whose animals the samples l are normally obtained did not slaughter from July through 5 December 1984.

Direct radiation measurement results from location 6S2 for September and the third quarter are unavailable; TLDs were missing from the field location.

I CONCLUSIONS The Radiological Environmental Monitoring Program for Salem Generating Station was conducted during 1984 in accordance with the SGS Environmental Technical Specifications. The objectives of the program were met during this period. The data collected assists in demonstrating that SGS Units One and Two were 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. Ambient radiation levels were relatively low, averaging about 6.0 mrad /std. month.

Except for the Co-58 and Co-60 seen in one sediment / benthic g organism sample which did not appear in subsequent analyses of 3 any of the estuarine samples, no unusual radiological character-istics were observed in the environs of Artifical Island. The operation of SGS Units #1 and #2 had no significant effect on the radiological characteristics of the environs of Artifical Island.

I l

I 29

Tritium activity in the aqueous fraction of the flesh was detected only in the second semi-annual samples at levels of 300 and 600 pCi/kg-wet with an average of 450 pCi/kg-dry.

Benthic Organisms and Sediment (Tables C-29, C-30)

As required by the Technical Specifications, benthic organisms I were separated from the bottom sediment and analyzed for Sr-89 and -90, and gamma emitters.

any of the samples.

Sr-89 and -90 were not detected in The gamma emitter Ra-226 was found in one sample. It should be noted that, due to the very small sample I sites for all salaples (0.1 gram to 0.25 gram dry), satisfactory strontium and gamma sensitivities could not be achieved. The small sample size was also responsible for the extremely high 2-sigma uncertainty for the gamma emitter found.

The benthos samples, which consist of sediment and associated benthic organisms, were collected at the same locations as the I bentnic organisms, and sample sizes are large enough to obtain more reliable results. Sediment was analyzed for Sr-90 and gamma emitters. The sensitivity requirements of the Salem Environmental Technical Specifications were met.

Levels of Sr-90 were below LLD (<19 to <39 pCi/kg-dry) in all eight samples analyzed. Results of gamma spectrometry indicated the presence of naturally-occurring K-40, Ra-226, and Th-232 in all eight samples with averages of 12000, 910, and 770 pCi/kg-dry respectively. Concentrations of the gamma emitters I Mn-54, Co-58, co-60 and Cs-137 were also detected. Trace quantities of these isotopes were found in releases from the Salem station during 1984 and reported in the semiannual Radioactive Effluent Release Report [21]. The concentrations of Co-58 and Co-60 at location 11A1 for the sample collected May 21, 1984 were 300 pCi/kg-dry and 520 pCi/kg-dry, respectively.

These levels were ten times higher than levels measured at control location 12C1, which were <29 pCi/kg-dry for Co-58 and 40 pCi/kg-dry for Co-60. In accordance with our Technical Specifications these results were reported to the USNRC after the results were confirmed by reanalysis. There was no indication of unusual levels of these radionuclides in any of the other estuarine samples for either semiannual period.

I I

I 28 i

Fish (Tables C-26, C-27)

Edible species of fish were collected semi-annually at three g locations and analyzed for tritium and gamma emitters (flesh) E and for strontium-89 and -90 (bones). Samples included spotted hake, channel catfish, white perch, summer flounder, brown bull-head, weakfish and bluefish.

Gamma spectrometry of these samples indicated K-40 in all six samples at an average concentration of 2400 pCi/kg-wet with a E range of 1200 to 3300 pCi/kg-wet. Cs-137 was noted in one sample 3 at 16 pCi/kg-wet, with LLD sensitivities for the other five samples from <6.2 to <14 pCi/kg-wet.

All six bone samples analyzed for Sr-89 were below LLD of <41 to

<190 pCi/kg-dry. Five of the six semi-annual samples analyzed for Sr-90 had detectable concentrations ranging from 62 to 1000 g PCi/kg-dry with an average of 380 pCi/kg-dry, the sixth sample E was <38 pCi/kg-ary. In 1983 the Sr-90 concentration for three of six samples ranged from 110 to 600 pCi/kg-dry with an average g of 347 pCi/kg-dry. The maximum level detected during the pro-operational period was 940 pCi/kg-dry with an average of 335 E pCi/kg-dry.

Tritium analyses were performed on both aqueous and organic fractions of the flesh portions of these samples. Three of the six samples analyzed for the aqueous fraction of tritium showed g detectable activity of 400 pCi/L at the outfall station: 11A1, E 400 pCi/L at the downstream station: 7El, and 300 pCi/L at the control station: 12C1. Only one sample, the control location, had a detectable concentration of tritium for the organic fraction with a result of 120 pCi/L. These results probably cannot be attributed to plant operation since the closest indicator station had a level of tritium in the aqueous fraction comparable to the other two stations and no detectable tritium in the organic fraction.

Blue Crab (Table C-28)

Blue crab samples, collected semi-annually at two locations, were analyzed for gamma emitters, Sr-89 and -90, and tritium in the aqueous fraction. The shells were also analyzed for Sr-89

, and -90.

l A trace of Co-60 in one sample and K-40 in all four samples were the only gamma emitters detected. K-40 levels ranged from 1900 l to 2300 pCi/kg-wet with an average of 2100 pCi/kg-wet. E l Sr-89 was not detected in either the flesh or the shell. Sr-90 was detected in all four of the shell samples at concentrations of 390 to 860 pCi/kg-dry with an average of 610 pCi/kg-dry, preoperational average for the shell was 614 pCi/kg-dry.

27 I

M M M M M M M M M M M M M M M M M M M FIGURE 5A AVERAGE CONCENTRATIONS OF TRITlUM IN THE DELAWARE RIVER IN THE VICINITY OF ARTIFICIAL ISLAND,1983 THROUGH 1984 1000 i l\

=

10 0 s/ LA-JhhAhJJk$0hbJhhAb)JkbOhbJhhAb)JkbONDJhhkhJ;kbOhbJ 1983 1984 1985 1986 1987

FIGURE 5 AVERAGE CONCENTRATIONS OF TRITIUM IN THE DELAWARE RIVER IN THE VICINITY OF ARTIFICIAL ISLAND,1973 THROUGH 1984 1000 j d

=

m

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1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 m M M M M M M M M M M M M M M M M M M

M M M M M M M M M M M M M M M M M M M RGURE 4A AVERAGE CONCENTRATIONS OF BETA EMITTERS AND POTASSIUM-40 IN THE DELAWARE RIVER IN THE VICINITY OF ARTIFICIAL ISLAND, 1983 THROUGH 1984 1000 Legend e GROSS BETA o P O TA5510 W -4 0 gg

~

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n JhbAbJJkbONbJhbAb)JkSONbJFbAbbJkSONbJhMAbJJAbONDJ 1983 1984 1985 1986 1987

nGURE 4 AVERAGE CONCENTRATIONS OF BETA EMITTERS AND POTASSIUM-40 IN THE DELAWARE RIVER IN THE VICINITY OF ARTIFICIAL ISLAND, 1973 THROUGH 1984 1000 Legend

. GROSS BETA o P O TA551U M -4 0 10 0- 7 ry ei

/d

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1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985

Aquatic Surface Water (Tables C-21, C-22, C-23, C-24, C-25)

Surface water samples were collected monthly at five locations I in the Delaware estuary, except for the January samples which were unavailable due to icing conditions on the river. One location is at the outfall area, another is downstream from the outfall area, and another is directly west of the outfall area at the mouth of the Appoquinimink River. Two upstream locations are in the Delaware River and at the mouth of the Chesapeake and Delaware Canal, the latter being sampled when the flow is from the Canal into the river. Station 12Cl, at the mouth of the Appoquinimink River, serves as the operational control. All surface water samples were analyzed monthly for gross alpha and I gross beta emitters, tritium, and gamma emitters. Quarterly composites were analyzed for Sr-89 and Sr-90.

Alpha concentrations were detected in eleven of the 44 indicator samples and in five of the eleven control samples. Levels ranged from 1.6 to 7.0 pCi/L. All the other samples were at or below the LLD, which ranged from <1.3 to <3.9. Beta concentrations for the indicator stations ranged from 3.2 pCi/L to 140 pCi/L with an average of 41 pCi/L, and, for the control station, from 4.3 pCi/L to 88 pCi/L with an average of 37 pCi/L. Nearly all of the beta activity was contributed by K-40, a natural component of salt.and brackish waters, as illustrated in Figure 4, which compares averaged gross beta and K-40 concentrations.

I Tritium analysis for the indicator stations ranged from 130 to 250 pCi/L. The average of the nine indicator samples with detectable levels of tritium was 164 pCi/L. Tritium was detected in two of the eleven control samples and ranged from 130 to 140 I pCi/L with an average of 135 pCi/L.

through 1984 are plotted in Figure 5.

Levels for the years 1973 I Gamma spectrometric analysis of surface water samples showed detectable concentrations in 44 of the 55 samples. The 3verage K-40 concentration at the indicator stations was 61 pCi/L eith a range of 9.7 to 140 pCi/L.

I Average K-40 concentration at the control station was 60 pCi/L with a range of 16 to 110 pCi/L.

Traces of Mn-54, Co-60, Cs-137, La-140, Ra-226 and Th-232 were detected at levels near or below the LLD in 15 of the 55 samples analyzed. ,

Strontium-89 was detected in one of sixteen indicator station samples at 1.3 pCi/L, none was detected in the four control station samples. The LLD sensitivities ranged from <0.5 to <1.4 pCi/L. Sr-90 was not detected in any of the twenty samples; LLD sensitivities ranged from <0.4 to <0.7 pCi/L.

22

I

\ll sacyles contained K-40 at concentrations from 1700 to 3000 pCi/kg-wet, with an average for all samples of 2100 pC1/kg-wet.

A trace of Ra-226 was seen in one control station pepper sample E and a trace of Th-232 was detected in an indicator station 5 cabbage sample. No other gamma emitters were detected in these food products.

I Game (Table C-19)

Two muskrat samples were collected in January. Bones from both samples were analyzed for Sr-89 and -90 while the flesh was analyzed for gamma emitters. Sr-89 was not found in either of the samples; Sr-89 LLD's were <100 and <160 pCi/kg-dry. Sr-90 was found in both samples at levels of 290 and 810 pCi/kg-dry.

These IcVels, while higher than in 1983, were significantly below those seen in the preoperational program. Gamma scans of the flesh indicated the presence of naturally-occurring K-40, in both samples at levels of 2400 and 3000 pCi/kg-wet; and Cs-137 in one sample at 5.6 pCi/kg-wet.

Beef and Bovine Thyroid (Table C-19)

One beef sample and the thyroid glands were collected in February. Analysis of the flesh for gamma emitters indicated only the presence of naturally-occurring K-40 at a concentration of 2500 pCi/kg-wet, and Ra-226 at a level of 9.3 pCi/kg-wet.

Analysis of the thyroid glands for gamma emitters indicated only K-40 at a concentration of 1200 pCi/kg-wet. No detectable concentrations of I-131 were found.

Fodder Crops (Table C-20)

Samples of crops normally used as cattle feed were collected at six locations where these products may be a significant element in the food-chain pathway. Five of the locations are milk sampling stations, and the sixth supplied a beef / thyroid sample.

Samples collected for wet gamma analysis included hay, corn silage, green chop, and soybeans.

K-40 was detected in all of the ten samples at concentrations from 2000 to 14000 pCi/kg-wet, with an average of 6700 pCi/ 3 kg-wet. Be-7, from the atmosphere, was found in seven of the E samples at concentrations from 260 to 1400 pCi/kg-wet, with an average of 390 pCi/kg-wet. Traces of Ra-226 or Th-232 were detected in hay, and soybeans at one indicator station. Nothing is known of the composition of fertilizers which may have been applied to the soil in which these crops were grown.

21

Gamma spectrometry showed detectable levels of K-40 in six of the eight indicator samples at an average concentration of 12 pCi/L with a range of 11 to 14 pCi/L. One control station sample had detectable K-40 at 6.3 pCi/L which was below the LLD values of <8.6 to <9.9 pCi/L. Traces of Ra-226 were detected in three samples at levels near or below the LLD values of the other nine samples.

Potable Water (Tables C-16, C-17)

Both raw and treated water samples were collected from the Salem water treatment plant. Each consisted of daily aliquots com-posited into a monthly sample. The raw water source for tnis plant is Laurel Lake and adjacent wells. Each sample was analyzed for gross alpha, gross beta, potassium-40, and tritium.

Quarterly composites of raw and treated were analyzed for Sr-89,

-90, and gamma emitters.

Detectacle alpha activity was noted in six raw and four treated water samples with ranges of 1.2 to 4.5 pCi/L (raw), and 1.0 to 1.6 pCi/L (treated). This resulted in an average activity of 2.4 pCi/L for the raw and 1.3 pCi/L for the treated potable waters. Beta activity was observed in all 24 of the monthly samples with ranges of 1.5 to 3.8 pC1/L (raw), and 1.7 to 3.4 (treated), and averages of 2.6 pCi/L (raw) and 2.4 pCi/L (treated). K-40 concentrations for raw and treated samples were practically identical and were lower than the beta activity in all cases. The K-40 average for both the raw and treated I samples was 1.5 pCi/L. Tcitium activity was observed in four of the twenty-four ranging from 140 to 250 pC1/L.

Sr-90 was observed in one of the quarterly raw water composites at 0.3 pCi/L; no Sr-89 was found. LLD's ranged from 0.4 to 0.9 pCi/L for Sr-89, and from 0.3 to 0.8 pCi/L for Sr-90. K-40 (via gamma spectrometry) was detected in the second quarter treated water composite at 7.4 pCi/L.

Food Products (Table C-18)

A variety of food products grown in the area for human consump-tion were sampled. These included sweet corn, peppers, aspara-gus, cabbage, and tomatoes. Each sample was analyzed for Sr-89, Sr-90, and gamma emitters. Sr-89 was not found in any of the seventeen samples; Sr-89 LLD's ranged from <2.8 to <20 pCi/kg-wet. Sr-90 was detected in eight of the seventeen samples with activities ranging from 1.8 to 32 pCi/kg-wet. These activities were detected in one sweet corn (control location), one pepper (control location), three cabbage (two indicator, one control location), and three tomatoe (two indicator, one control loca-tion) samples. Sr-90 LLD's ranged from <l.8 to <6.1 pCi/kg-wet.

20 I

FIGURE 3A AVERAGE CONCENTRATIONS OF 10 DINE-131 IN MILK IN THE VICINITY OF ARTIFICIAL ISLAND,1983 THROUGH 1984 10 0 10-5m I-0.1 ,, .,..,. .,..,. ,, ,, ,, ,, ,, ,, ,,,,, ,, ,,

JFMAMJJASONDJFMAMJJASONDJFMAMJJASONDJFMAMJJASONDJ 1983 1984 1985 1986 1987 m M M M M M M M M M M M M M M M M M M

ARTIFICIAL ISLAND RADIO!DGICAL ENVIRONMENTAI MONI10 RING PROGRAM

SUMMARY

SALEM NUCi. EAR GENERATING STATION DOCEET NO. 50-272/-311 SALEM COUNTY, NEW JERSEY JANUARY 1, 1984 to DECEMBER 31, 1984 ANALYSIS AND IDWER WUMBER OF MEDItm OR PATHWAY TOTAL NLMBER LIMIT OF ALL INDICA 10R IDCATIONS IDCATION NITH NIGHEST MEAN CONTROL IDCATION(S) NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREftENTS Milk I-131 144 0.1 < LID -

<LLD < LID 0 (pC1/L)

St-89 72 0.8 < LID -

<LLD < LID 0 St-90 72 -

2.4 (60/60) SF2 7.0 mi E 3.0 (12/12) 3.2 (12/12) 0 (1.2-5.3) (1.8-5.3) (2.2-4.9) i,amma Na-22 72 0.5 <LLD 3G1 17 mi NE 2.1 (1/12) 2.1 (1/12) 0 (2.1) (2.1)

E-40 72 -

1347 (60/60) 2F4 6.3 mi NNE 1383 (12/12) 1350 (12/12) 0 (1200-1500) (1300-1400) (1300-1500)

Mn-54 72 0.0 2.4 (1/60) 14F1 5.5 mi WNW 2.4 (1/12) < LID G (2.4) (2.4)

W Cm-137 72 1.3 3.1 (11/60) 5F2 7.0 mi E 3.4 (8/12) <LLD 0 4 (1.0-6.2) (1.8-6.2)

La-140 72 0.6 2.4 (1/60) 5F2 7.0 mi E 2.4 (1/12) < LID 0 (2.4) (2.4)

Ra-226 72 2.5 5.8 (3/60) 15F1 5.4 mi NW 6.5 (1/12) (LID 0 (5.1-6.5) (6.5)

Th-232 72 3.6 13 (1/60) Sr2 7.0 mi E 13 (1/12) (LLD 0 (13) (13)

Well water Alpha 36 0.6 1.4 (6/24) 2S3 700 ft NNE 1.5 (4/12) < LID 0 (pci/L) (0.9-2.0) (1.1-2.0)

Beta 36 1.0*** 10 (24/24) 5D1 3.5 mi E 13 (12/12) 8.4 (12/12) 0 (2.9-17) (12-)s' ( 6. 0-10)

E-40 36 -

11 (24/24) 5D1 3.5 mi E 14 (12/12) 8.4 (12/12) 0 (2.8-28) (6.4-28) (5.5-9.3)

N-3 36 130 < LID -

(LLD < LID 0 Sr-89 12 0.4 0.9 (1/0) 253 700 ft NNE 0.9 (1/4) < LID 0 (0.9) (0.9)

Sr-90 12 0.4 < LID -

< LID < LID 0 Gamma E-40 12 8.4 12 (6/8) 5D1 3.5 al E 13 (3/4) 6.3 (1/4) 0 (11-14) (12-14) ( 6. 3)

Ra-226 12 0.7 1.3 (3/8) 2$3 700 ft NNE 2.1 (1/4) 1.3 (1/4) 0 (0.6-2.1) (2.1) (1.3)

ARTIFICIAL ISLAND RADIO!DGICAL ENVIROletENTAL MONITORING FROGRAM SLBW4ARY SAIDI NUCLEAR GENERATING STATIOnt COCERT NO. 50-272/-311 SALEM COUnfrY, NEW JERSEY JANUARY 1, 1984 to DECEMBER 31, 1984 ANALYSIS AND IDWER NtMBER OF MEDIL30 OR FATUNAY TOTAL NLMBEA LINIT OF ALL INDICATOR EDCATIONS IACATIOk WITN HIGHEST MEAN CONTROL IDCATION(8) NONkOUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUk2 MENT) FERFORMED ( LIA) * (RANGE) D!$TANCE AND D!tECTION (RJJeGE) (RANGE) MEASUREMENTS potable tea ter Alpha 24 0.9 2.0 (10/24) 2F3 0.0 at NNE 2.0 (10/24) No Q)ntrol 0 Raw-Treated (1.0-4.5) (1. 0- 4. 5) Incation (pC1/L) Beta 24 1.0*** 2.5 (24/24) 2F3 8.0 et NME 2.5 (24/24) No Cbntrol 0 (1.5-3.0) (1.5-3.8) Iocatton E-40 24 - 1.5 (24/241 2F3 S.0 mi NME 1.5 (24/24) Ih' (bntrol 0 (1.1-2.0) (1.1-2.0) Incation n-3 24 120 172 (4/24) 2F3 0.0 mi NME 172 (4/24) No Q>ntrol 0 (140-250) (140-250) location St-89 8 0.4 <LLD -

< LIA No Cbatrol 0 Incation St-90 0 0.3 0.3 (1/0) 2F3 8.0 al NNE 0.3 (1/8) tio Q)ntrol 0 (0.3) (0.3) Iocation Gamma W E-40 8 5.9 7.4 (1/0) 2F3 4.0 mi NME 7.4 (1/0) No Cbatrol O

@ (7.43 (7.4) Iocation Fruit & Wgetables Sr-89 17 2.8 < LIA -

< LIA < LIA 0 (pci/kg-wet)

St-90 17 1.8 15 (4/10) 4F1 5.1 mi ENE 32 (1/2) 6.9 (4/7) 0 (2.7-32) (32) (1.4-12) f c -.

E-40 17 -

2140 (10/10) 4F1 5.1 mi ENE 2300 (2/2) 2114 (7/7) 0 (1700-2700) (1900-2700) (1700-3000) 14F3 5.4 mi WNW 2)00 (2/2)

(2000-2600)

Ra-226 17 1.0 <LLD 3N5 25 si NE 49 (1/4) 49 (1/7) 0 (49) (49)

Th-232 17 4.8 16 (1/10) erl 5.1 mi ENE 16 (1/2) <LLD 0 (16) (16)

M M EE .

M

ARTIFICIAL ISLAND RADIOthGICAL ENVIROletENTAL MONIIORING FROGRAM StD9tARY SALDE NUCLE.AR GENERATING STATION DOCKET NO. 50-272/-311 SALD4 COUNTY, NEN JERSEY JANUARY 1, 1984 to DECEMRER 31, 1984 ANALYSIS AND IhWER NUMBER OF MEDItst OR FATitiAY TOTAL BRDtBER LIMIT OF ALL INDICA 1DR IDCATIONS I4 CATION NITH MIGHEST MEAN CONTROL E/) CATION ($) NONROUTINE SAMFLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASURDtENT) FERFORMED (Lib) * (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Came St-89 2 100 < LLD -

< LIA <LLD 0 (pC1/kg-dry) (bones)

Sr-90 2 -

810 (1/1) 3E1 4.1 mi NE 810 (1/1) 290 (1/1) 0 (bone s) (810) (810) (290)

(pC1/kg-wet) e-.

(flesh)

E-40 2 -

3000 (1/1) 3E1 4.1 mi NE 3000 (1/1) 2400 (1/1) 0 (1000) (1000) (2400)

Cm-137 2 7. 7 < LIA 11D1 3.5 mi SN 5.6 (1/1) 5.6 (1/1) 0 (5.6) (5.6)

W seef Gamma (PC1/kg-wet) E-40 1 -

2500 (1/1) 3E1 4.1 mi NE 2500 (1/1) No Control 0 (2500) (2500) location Ra-226 1 -

9.3 (1/1) 3E1 4.1 mi NE 9.) (1/1) No Control 0 (9.3) (9.3) location Bovine Thyroid Gamma (pct /kg-wet) E-40 1 -

1200 (1/1) 3E1 4.1 mi NE 1200 (1/1) No Control 0 (12006 (12001 Incation Fodder Crope Gamma tpC1/kg-wet) re-7 10 130 527 (6/8) 15F1 5.4 at NW 830 (2/3) 260 (1/2) 0 (260-1400) (260-1400) (260)

E-40 10 -

6247 18/8) 3E1 4.1 mi NE 13000 (1/1) 8350 (2/2) 0 (2000-13000) (13000) (2700-14000)

Ra-226 10 14 41 (1/8) 15F1 5.4 31 NN 41 (1/3) < LIA 0 (41) (41)

Th-232 10 27 95 (1/8) 15F1 5.4 mi NN 95 (1/3) < LIA 0 (95) (95)

ARTIFICI AL ISLAND RADIOIDGICAL ENVIROMENTAL MONITORING PROGRAM SISMARY SALEM NUCLEAR GENERATING STATION DOCEET NO. 50-272/-311 SALEM CLtJNTY, NEW JERSET JANUAAT 1, 1984 to DECEMBER 31, 1984 ANALYSIS AND IDWER NtMBER 07 MEDILM OR PATWAY "JOTAL NLasBER LIMIT OF ALL INDICATOR IACATIONS IMCATION WITH MIGHEST MEAN CONTROL IDCATION(8) NONPi t *%

SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAM MEAN PEP'M.3 (UNIT OF M?i_c"" "*T) PERFORMED ( LID) * (RANGE) DISTANCE AND DIRECTION (RANCE) (RANGE) MEASUPJIME7-3 Surface water Alpha 55 1.3 3.1 (11/44) 12C1 2.5 at WSW 5.2 (5/11) 5.2 (5/11)  ?

(pci/L) (1.6-5.2) (3.4-7.0) (3.4-7.0)

Seta 55 3.0 41 (43/44) 7El 4.5 mi SE 57 (11/11) 37 (11/11) 6 (3.2-140) ( 8*. 3 -14 0) (4.3-88)

N-3 55 120 164 (9/44) Ir2 7.1 mi N 197 (3/11) 135 (2/11) o (130-250) (150-250) (130-140)

Sr-89 20 0.5 1.3 (1/16) 16F1 6.9 mi NNW 3.3 (1/4) < LIA 0 (1.33 (1.3)

Sr-9) 20 0.4 < LID - <LLD < Lla 0 Gamma 5-40 55 6.7 61 (34/44) 7El 4.5 mi SE 74 (10/11) 60 (7/11) 0 (9.7-140) (20-140) (16-110)

A Ma-54 55 0.3 0.7 (1/44) 11A1 0.2 mi SW 0.7 (1/11) < LID 0 O (0.7) (0.7) 00-60 55 0.2 0.6 (1/44) 7El 4.5 mi SE 0.6 (1/11) < L!s 0 (0.63 (0.6)

Ca-137 55 0.3 (LLD 12C1 2.5 mi WSW 0.5 (1/11) 0.5 (1/11) 0 (0.5) (0.5)

La-140 55 0.3 1.2 (1/44) 11A1 0.2 mi SN 1.2 (1/11) < lim 0

.(1.2) (1.2)

Ra-226 55 0.5 1.0 (6/44) 7El 4.5 mi SE 1.2 (2/11) 1.2 (2/11) 0 (0.6-1.5) (0.9-1.51 (1.0-1.3) 11A1 0.2 mi SW 1.2 (1/11)

(1.2) .

Th-232 55 1.3 1.7 (5/44) 1r2 7.1 mi N 2.0 (2/11) 1.6 (2/11) 0 (0.9-2.1) (2.0-2.1) (1.2-1.9) 7 m M M M M M M M M M M M M M

ARTIFICIAL ISLAND RADIO!4GICAL ENVIRODMENTAL MONITORING PROGRAM SlNMARY sal 2M NUCLEAR CENERATING STATION DOCKET NO. 50-272/-311 SALEM COUNTY, NEW JERSEY JANUARY 1, 1984 to DECEMBER 31, 1984 ANALYSIS AND I4WER NtMBER OF MEDItm OR PATHNAY TOTAL NLMBER LIMIT OF ALL INDICATOR IDCATIONS IDCATION WITH HIGHEST MEAN (TJNTROL IDCATION(S) NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED ( LID) * (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASURDIENTS Edible Fish St-89 6 41 < LIA -

<LLD < LID 0 (pct /kg-dry) (bones)

Sr-90 6 38 334 (3/4) 12c1 2.5 at wsw 615 (1/2) 615 (1/2) 0 (bones) (62-730) (230-1000) (230-1000)

(pci/kg-wet) s-3 6 50 400 (2/4) 7F1 4.5 mi SE 400 (1/2) 300 (1/2) c (aqueous) (400-400) (400) (300) 11A L 0.2 mi SW 400 (1/2)

(400)

M-3 6 50 < LLD 12C4 2.5 mi WSW 120 (1/2) 120 (1/2) 0 (organic) (120) (120)

Gamma R-40 6 -

2600 (4/4) 7El 4.5 mi SE 3300 (2/2) 1900 (2/2) 0 g (1200-3300) (3300-3300) (1400-2400)

W Cs-137 6 6.2 16 (1/4) 11A1 0.2 at SW 16 (1/2) < LIS 0 (16) (16)

Blue Crabs Sr-89 4 88 4 LID - <LLD < LID 0 (pC1/kg-dry) (shells)

Sr-90 4 -

600 (2/2) 12C1 2.5 at wsw 625 (2/2) 625 (2/2) 0 (shells) (580-620) (390-860) (390-860)

(pC1/kg-wet) H-3 4 50 600 (1/2) 1141 0.2 mi SW 600 (1/2) 300 (1/2) 0 (flesh) (600) (600) (300)

Sr-89 4 46 < LIA - < lim < LID 0 (flesh)

Sr-90 4 26 < LIA - <LLD + tsD 0 (flesh)

Gamma K-40 4 -

2200 (2/2) 11A1 0.2 mi SW 2200 (2f2s 1950 (2/2) 0 82100-2300) (2100-2300) (1900-2000)

CO-60 4 16 24 (1/2) 11A1 0.2 mi SW 24 (1/2) < LIA 0 (24) (24)

ARTIFICIAL ISIJ.ND RADIOIDGICAL ENVIRODMENTA. agDNITORING PROGRAM SLNMARY SALEM NUCLEAR GENERATING STATION DOCRET NO. 50-272/-311 SALDs CDUNTY, NEW JERSEY JANUARY 1,1984 to DECDtBER 31, 1984 ANALYSIS AND IDWER NUMBER OF MEDIIst OR PATHWAY TOTAL NLMBER LIMIT OF ALL INDICA 10R IMCATIONS II1 CATION WITH MICHEST MEAN CONTROL IDCATIOM(S( NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN AEPORTED (UNIT OF MEASUREMENT) PERFORMED (Lla)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Benthic Organisms Sr-89 8 2600 < Lib -

<LLD <LLD 0 (EC1/kg-dry)

St-90 8 1800 < LID - <LLD < LID 0 Gamma Ra-226 8 24000 23000 (1/6) 11A1 0.2 mi LJ 23000 (1/2) < LID 0 (23000) (23000)

Sediment Sr-90 8 19 < LIA -

<LLD < LID 0 (pC1/kg-dry)

, Gamma y Be-7 8 140 877 (3/6) 11A1 0.2 mi SW 1300 (1/2) (Lim 0 (330-1300) (1300)

E-40 8 -

11783 (6/6) 16F1 6.9 mi NNW 15000 (2/2) 13000 (2/2) 0 (4700-15000) (15000-15000) (12000-14000)

Mn-54 8 17 47 (3/6) 11A1 0.2 mi SW 87 (1/2) 25 (1/2) 0 (22-87) (87) (J5) 00-58 8 22 150 (3/6) 11A1 0.2 al SW 186 (2/2) < LIA 1 (73-300) (73-300) 00-60 8 32 184 (6/6) 11A1 0.2 mi SW 350 (2/2) 40 (1/2) 1 (22-520) (180-520) (40)

Co-137 8 20 108 (5/6) 11A1 0.2 mi SW 180 (1/2) 26 (2/2) 0 (26-180) (180) (19-32)

Ra-226 8 -

883 (6/6) 7El 4.5 mi SE 1140 (2/2) 995 (2/2) 0 (430-1300) (980-1300) (790-1200)

Th-232 8 -

742 (6/6) 16F1 6.9 mi NNW 930 (2/2) 845 (2/2) 0 (340-980) (900-960) (770-920)

• LIa listed is the lowest calculated LID during the reporting period.

• • Mean calculated using values above LIA only. Fraction of raasurements above LID are in parentheses.

• Typical LID value.

M M M M M M M M M M

I i

I i i

I I

I APPENDIX B I

l

SAMPLE DESIGNATION AND LOCATIONS I

I ,

i I

I I

I 43 I __- _- - _ _ - _ _ . _ . _.

I l APPENDIX B Sample Designation The PSE&G Research Corporation identifies samples by a three part code. The I first two letters are the power station identification code, in this case "SA". The next three letters are for the media sampled.

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

ECH = Hard Shell Blue Crab MLK = Milk ESB = Benthic Organisms PWR = Potable Water (Raw)

I ESF ESS FPB

=

=

=

Edible Fish Sediment Beef PWT =

RWA SWA

=

=

Ibtable Water (Treated)

Rain Water Surface Water FPV Food Products, Various THB = Bovine E yroid I

=

FPG = Grains VGT = Fodder Crops; Vegetation FPL = Green Leafy Vegetables WWA = Well Water I The last four symbols are a location code based on direction and distance I

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 clock-wise directions i.e., 2=NNE, 3=NE, 4=ENE, etc. ne 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 e,ff-site C = 2-3 miles off-site H = >20 miles off-site D = 3-4 miles off-site I The last number is the station numerical designation within each sector and zone; e.g., 1,2,3,... For example, the designation SA-WWA-5D1 would indicate a sample in the SGS program (SA), consisting of well water (WWA) , which had been collected in sector number 5, centered at 90* (due east) with respect to the reactor site at a radial distance of 3 to 4 miles off-site, (therefore, radial distance D). ne number 1 indicates that this is sampling station il in that particular sector.

I .

I l

45 I

I Sampling Locations All 1984 sampling locations and specific information about the individual locations are given in Table B-1. Maps B-1 and U-2 show the locations of sampling stations with respect to the site.

TABLE U-l STATION CODE STATION LOCATION SAMPLE TYPES 2S2 0.4 mi. NNE of vent AIO, APT,IDM 2S3 700 ft. NNE of vents fresh water holding tank WWA 5S1 1.0 mi. E of vents site access road AIO, APT,IDM 6S2 0.2 mi. ESE of vents observation bldg. IDM 7S1 0.12 mi. SE of venti station personnel gate IDM 10S1 0.14 mi. SSW of vents site shoreline IDM 1151 0.09 mi. SW of vent; site shoreline IDM 11A1 0.2 mi. SW of vents outfall area ECif , ESB , ES F, ESS,SWA 12Cl 2.5 mi. WSW of vents west bank of Delaware River ECll, ESB , ES F, ESS,SWA 4D2 3.7 mi. ENE of vent Alloway Creek Noct Road IDM SD1 3.5 mi. E of vent; local farm AIO, APT,FPV, IDM,WWA 10D1 3.9 mi. SSW of vents Taylor's Bridge Spur AIO, APT,IDM 1101 3.5 mi. SW of vent GAM 14DL 3.4 mi. WNW of vent; 3ey View, Delaware IDM 2El 4.4 mi. NNE of vent; local farm FPV,IDH 3El 4.1 mi. NE of vent; local farm FPD,FPG, GAM,IDM, TilD,WWA 7El 4.5 mi. SE of vent: 1 mi. W of Mad florse Creek ESB,ESF,ESS,SWA 9El 4.2 mi. S of vent IDM llE2 5.0 mi. SW of vent IDM 1

46 I

I I TABLE B-1 (cont'd)

I STATION CODE STATION LOCATION SAMPLE TYPES 12E1 4.4 mi. WSW of vent; Thomas Landing IDM 13El 4.2 mi. W of vent; Diehl House Lab IDM 13E3 4.9 mi. W of vent; local farm MLK 16El 4.1 mi. NNW of vent; Po t t . Penn AIO, APT,IDM 1F1 5.8 mi. N of vent; Fort Flfsborg AIO, APT,IDM 1F2 7.1 mi. N of vent; midpo ht of Delaware River SWA 1F3 5.9 mi. N of vent; local farm FPL,FPV 2F2 8.7 mi. NNE of vent; Salem Substation AIO, APT,IDM, RWA 2F3 8.0 mi. NNE of vent; Salem Water Company PWR,PWT 2F4 6.3 mi. NNE of vent; local farm MLK,VGT I 2F5 2F6 7.4 mi. NNE of vent; Salem High School 7.3 mi. NNE of vent; Southern Training Center IDM IDM I 3F2 5.1 mi. NE of vent Hancocks Bridge Municipal Building IDM 3F3 8.6 mi. NE of vent; Quinton Township School IDM 4F1 5.1 mi. ENE of vent; local farm FPL,FPV SFl 6.5 mi. E of vent FPV,IDM 5F2 7.0 mi. E of vent; local farm MLK,VGT I 6F1 6.4 mi. ESE of vent; Stow Neck Road IDM 7F2 9.1 mi. SE of vent; Bayside, New Jersey IDM 10E2 5.8 mi. SSW of vent IDM 11F1 6.2 mi. SW of vent; Taylor's Bridge Delaware IDM j 12F1 9.4 mi. WSW of vent; Townsend Elementary School IDM 1171 9.8 mi. W of vent; Middletown, Delaware IDM 13F2 6.5 mi. W of vent; Odessa, Delaware IDM 47 I -

I I TABLE B-1 (cont'd)

STATION CODE STATION LOCATION SAMPLE TYPES 13F3 9.3 mi. W of ver.t; Redding Middle School, IDM Middletown, DE 13F4 9.8 mi. W of vent; Middletown, Delaware IDM 14F1 5.5 mi. WNW of vent; local farm MLK,VGT 14F2 6.6 mi. WNW of vent; Boyds Corner IDM 14F3 5.4 mi. WNW of vent; local farm FPV 15F1 5.4 mi. NW of vent; local farm FPG,MLK,VGT 15F3 5.4 mi. NW of vent IDM 16F1 6.9 mi. NNW of vent; C&D Canal ESB,ESS,SWA 16F2 8.1 mi. NNW of vent; Delaware City Public School IDM 1G1 10.3 mi. N of vent; local farm FPV 1G3 19 mi. N of vent; Wilmington, DC. aware IDM 3G1 17 mi. NE of vents local farm FPG,IDM,MLK,VGT 10G1 12 mi. SSW of vent; Smyrna, Delaware IDM 16G1 15 mi. NNW of vent; Greater Wilmington Airport IDM 3H1 32 mi. NE of vent; National Par k, N.J. IDM 3H3 110 mi. NE of vent; Research and Testing AIO, APT,IDM Laboratory 3HS 25 mi. NE of vent; local farm FPL,FPV I

I I

48 I

I

MAP B-1 1

ON SITE SAMPLING LO C ATION S l ARTIFICI A L ISLAND l ) k u o

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I MAP B-2 0FF-SITE SAMPLING LOCATIONS ARTIFICIAL ISLAND I

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i l

1 l APPENDIX C 1984 DATA TABLES l

1

'I i f

i i

i I 51

DATA TABLES Appendix C presents the analytical results of the 1984 Artificial Island Radiological Environmental Monitoring Program for the period of January 1 to December 31, 1984.

TABLE OF CONTENTS TABLE NO. TABLE DESCRIPTION PAGE ATMOSPHERIC ENVIRONMENT AIR PARTICULATES C-1 1984 Concentrations of Gross Alpha Emitters.................... 56 C-2 1984 Concentrations of Gross Beta Emitters..................... 58 C-3 1984 Concentrations of Strontium-89 and -90 and Gamma Emitters in Quarterly Composites...................................... 60 AIR IODINE C-4 1984 Concentrations of Iodine-131.............................. 62 DATES C-5 1984 Sampling Dates for Air Samples............................ 64 PRECIPITATION C-6 1984 Concentrations of Gross Alpha and Gross Beta Emitters and Tritium...................................................... 69 C-7 1984 Concentrations of Strontium-89 and -90 and Gamma Emitters in Quarterly Composites...................................... 70 DIRECT RADIATION I THERMOLUMINESCENT DOSIMETERS C-8 1984 Quarterly TLD Results..................................... 71 C-9 1984 Monthly TLD Results....................................... 72 53

DATA TABLES (cont'd.)

TABLE NO. TABLE DESCRIPTION PAGE TERRESTRIAL ENVIRONMENT MILK C-10 1984 Concentrations of Iodine-131.............................. 74 C-11 1984 Concentrations of Strontium-89 and -90.................... 75 C-12 19 8 4 Conce n t ra t ions o f Ga mma Em i t te r s . . . . . . . . . . . . . . . . . . . . . . . . . . 76 C-13 1984 Sampling Dates for Milk Samples........................... 78 WELL WATER C-14 1984 Concentrations of Groas Alpha and Gross Beta Emitters; Potassium-40 and Tritium..................................... 80 C-15 1984 Concentrations of Strontium-89 and -90 and Gamma Emitters in Quarterly Composites...................................... 82 POTABLE WATER C-16 1984 Concentrations of Gross Alpha and Gross Deta Emitters; Potassium-40 and Tritium..................................... 83 C-17 1984 Concentrations of Strontium-89 and -90 and Gamma Emitters in Quarterly composites...................................... 84 FOOD PRODUCTS C-18 1984 Concentrations of Strontium-89 and -90 and Gamma Emitters in Vegetables................................................ 85 C-19 1984 Concentrations of Strontium-89 and -90 and Gamma Emitters in Game , Mea t and Bovine Thy r oid . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 86 FODDER CROPS C-20 19 8 4 Concent ra t ions of Gamma Emit te r s . . . . . . . . . . . . . . . . . . . . . . . . . . 87 l 54 t

l l

DATA TABLES (cont'd.)

TABLE NO. TABLE DESCRIPTION PAGE AQUATIC ENVIRONMENT SURFACE WATER C-21 198 4 Concentrations of Gross Alpha Emitters. . . . . . . . . . . . . . . . . . . . 88 C-22 1984 Concentrations of Gross Beta d 'mitters..................... 89 C-23 1984 Concentrations of Tritium................................. 90 C-24 198 4 Concentrations of S trontium-89 and -90. . . . . . . . . . . . . . . . . . . . 91 C-25 19 8 4 Concent ra t ions o f Gamma Emi tte r s . . . . . . . . . . . . . . . . . . . . . . . . . . 92 EDIBLE FISH C-26 1984 Concentrations of Strontium-89 and -90 and Tritium........ 94 C-27 1984 Concentrations of Gamma Emitters.......................... 95 BLUE CRABS C-28 1984 Concentrations of Strontium-89 and 90; Gamma Emitters and Tritium...................................................... 96 BENTHIC ORGANISMS C-29 1984 Concentrations of Strontium-89 and -90 and Gamma Emitters 97 SEDIMENT C-30 1984 Concentrations of Strontium-90 and Gamma Emitters. . . . . . . . . 98 SPECIAL TABLES LLDs C-31 1984 PSE&G Research Corporation LLDs for Gamma Spectrometry.... 99 i

55

TABLE C-1 1984 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN AIR PARTICULATES Results in Units of 10-3 pC1/m3 t 2 sigma STATION NO.

FONTH* SA-APT-2S2 SA-APT-5S1 SA-APT-5Dl** SA-APT-10D1 SA-APT-16El SA-APT-lF1 SA-APT-2F2 SA-APT-3H3 AVERAGE (Control)

JANUARY 2.620.8 1.620.6 1.221.0 1.420.6 1.510.6 2.0*0.7 2.220.8 1.920.7 1.8t0.9 2.821.0 1.910.8 <!.0 2.720.9 2.9ro.9 1.5*0.9 1.721.1 2.620.9 2.111.4

'2.5to.9 2.120.8 <2.0 2.421.0 2.711.0 <l.1 <1.4 1.620.7 2.021.1 4.021.0 3.720.9 2.421.2 3.421.0 4.721.0 3.621.0 4.321.0 2.720.9 3.621.5 1.610.7 1.420.6 <2.0 1.0t0.6 1.6 0.7 1.320.7 0.920.7 1.820.8 1.420.8 FEBRUARY 2.120.8 1.820.7 <0.8 1.020.8 <0.8 1.320.7 1.421.18I3 1.220.6 1.320.9 2.020.7 2.120.6 1.921.0 1.520.6 2.720.9 2.220.7 2.310.8 3.120.8 2.221.0 1.120.6 0.820.6 1.711.0 1.020.7 0.920.6 <l.0 <l.0 <0.8 1.020.6 1.720.8 1.320.7 1.020.9 <0.6 1.320.7 1.320.7 1.120.7 1.820.7 1.320.8 MARCH 1.220.6 1.3to.6 <l.0 <0.8 1.620.8 1.120.6 1.420.7 2.521.0 1.421.0 2.320.8 2.820.8 1.621.2 3.621.0 3.821.0 2.310.9 4.421.1 3.120.9 3.021.8 1.210.7 0.920.6 1.321.0 <l.0 1.6t0.8 1.620.8 1.110.8 1.410.7 1.320.5 g 1.520.8 1.120.7 2.121.1 1.220.7 1.6t0.8 1.020.7 1.720.8 1.4t0.8 1.420.7 cs APRIL 1.420.7 1.220.6 <2.0 <0.7 1.720.7 1.520.8 2.721.0 0.920.6 1.521.3 1.120.8 1.220.7 <l.0 <0.9 1.020.8 1.0t0.8 1.510.9 1.210.8 1.120.4 1.410.8 1.220.7 <1.0 1.520.9 <l.2 <l.0 1.420.8 1.720.8 1.320.5 1.020.6 1.320.6 <l.0 0.720.5 0.820.6 1.610.7 <0.7 1.020.6 1.0t0.6 1.620.9 1.720.7 <l.0 1.820.9 2.320.9 1.620.8 2.020.9 1.420.8 1.720.8 MAY 2.911.3 2.6*0.9 <l.0 2.420.9 2.820.9 2.821.0 2.110.9 1.410.7 2.221.4 2.6t!.0 1.620.7 <0.9 2.420.8 2.320.8 1.320.7 4.022.5III 2.020.7 2.121.9 2.410.8 2.920.8 <1.0 2.510.9 2.120.9 2.020.0 2.020.8 1.6t0.6 2.121.2 1.920.7 1.910.7 0.9t0.8 2.520.8 1.920.7 1.520.8 1.520.8 2.220.8 1.821.0 JUNE 1.520.8 2.120.9 <l.6 1.720.9 1.220.9 1.420.8 1.820.9 1.520.8 1.520.7 3.610.9 2.410.8 2.121.1 3.520.9 3.220.8 3.521.0 4.221.1 3.310.9 3.221.4 1.320.8 1.810.9 1.321.0 <!.2 2.3 1.1 1.420.9 1.4t0.9 1.410.8 1.520.7 2.020.8 1.820.7 1.411.0 1.6t0.8 2.310.8 1.020.7 <l.0 1.7t0.7 1.6to.9 1.710.8 1.920.s <!.0 1.210.8 2.521.0 1.720.9 1.9t0.9 2.021.0 J.7t0.9 M M -

M M TABLE C-1 (cont'd) 1984 CONCENTHATIONS OF GROSS ALPHA EMITTERS IN AIR PARTICULATES Results in Units of 10~3 541/m3

• 2 sigma STATION NO.

MONTH

• SA-APT-2S2 SA-APT-551 SA-APT-5DI** SA-APT-10D1 SA-APT-16El SA-APT-lF1 SA-APT-2F2 SA-APT-3H3 AVERAGE (Control)

JULY 2.620.8 1.820.7 <2.0 2.010.8 1.910.8 2.420.9 2.620.9 2.620.8 2.220.7 3.110.9 4.121.0 1.6t!.1 3.420.9 3.020.8 2.710.8 2.420.8 2.420.7 2.821.5 2.320.9 1.620.7 <l.0 <1.0 1.320.8 1.220.9 1.7t0.9 2.020.8 1.520.9

<l.1 <1.1 <!.0 <1.2 1.621.0 <1.3 1.621.0 1.020.7 -

AUGUST 2.520.9 1.420.7 1.311.1 1.320.9 2.0to.9 2.2t1.0 1.520.8 2.820.9 1.921.2 3.221.0 2.610.9 2.121.2 2.120.8 2.921.0 2.521.0 2.611.0 2.7t0.9 2.620.7 1.920.7 3.320.9 <0.8 1.910.9 3.021.0 2.711.0 2.621.0 2.220.7 2.3tl.6 1.520.6 1.920.7 <l.0 2.0t0.8 2.020.7 1.520.7 1.620.7 2.110.8 1.7t0.7 SEPTEMBER 3.320.9 2.310.7 2.0t!.3 2.820.9 3.120.9 2.520.8 2.010.8 2.920.8 2.6t1.0 1.520.8 <0.6 <2.0 0.920.6 1.320.7 0.920.6 1.420.8 0.820.6 1.220.9 1.620.6 1.210.6 <2.0 1.820.8 1.320.6 1.7to.7 1.820.8 1.320.6 1.620.6 1.420.6 1.720.7 <!.0 2.220.8 1.810.7 1.220.6 1.4 0.6 1.920.8 1.620.8 m 1.020.8 <0.9 1.6 1.1 <l.0 <1.0 1.220.8 1.220.9 2.020.8 1.220.8

-J OCTOBER 2.420.8 2.510.8 <l.0 3.211.0 1.520.8 2.220.8 2. ". 2 0. 8 3.420.9 2.321.6 3.021.0 2.621.0 1.220.9 3.6*1.1 4.221.3 2.821.1 2.921.1 3.121.0 2.921.7 2.921.0 2.921.0 <1.0 2.5 1.0 2.821.1 2.921.0 2.521.0 3.7tl.9(II 2.621.5 1.410.6 1.720.7 2.721.2 1.210.6 1.620.7 1.0t0.6 1.420.8 1.620.7 1.6t1.0 NOVEMSER 1.920.8 1.720.8 1.110.5 0.920.7 1.7t0.9 1.820.8 2.220.9 1.7+0.7 1.6t0.8 4.210.7 2.010.7 1.821.0 1.910.7 2.420.7 2.320.8 2.4to.8 1.7t0.6 2.120.5 3.111.1 3.421.2 1.821.1 2.320.9 3.021.0 1.620.9 3.621.2 2.6t0.9 2.721.5 2.420.9 3.021.1 3.021.3 3.221.0 4.321.1 2.821.0 2.421.0 2.220.8 2.921.3 DECEMBER 2.420.9 2.0to.9 <1.0 1.520.8 2.021.0 2.120.9 2.020.9 2.820.9 2.0t1.1 1.620.7 2.420.8 2.021.1 2.320.8 3.020.8 2.120.9 2.0 0.9 2.710.8 2.320.9 2.220.8 2.4to.8 <1.0 2.020.8 2.5 0.9 2.620.9 2.720.9 1.820.7 2.221.1 1.820.7 1.320.6 2.521.2 1.0t0.7 1.720.7 1.520.7 1.4t0.7 1.320.6 1.620.9

<l.1 1.220.8 <1.0 <l.0 1.6 0.8 <1.1 <1.0 <!.2 -

AVERAGE 2.021.5 1.9t!.5 -

1.8:1.7 2.111.8 1.821.4 2.021.7 2.021.4 Grand Avera9e 1.921.6

• Sampling dates can be found in Table C-5.

• • Resdits by Teledyne Isotopes.

(1) High uncertainty due to low sample voluse.

I l

i I

TABLE C-2 i

19C4 CONCEhTdATIONS OF CROSS BETA LMITTERS IN AIR PARf!CULATES Nesults in Units of 10-3 pct /m3 2 2 sigma t

I i

STATION NO.

MONTd* SA-APT-252 SA-APT-SS1 S A- A PT- 5 D 1 *

• SA-APT-10D1 SA-APT-16El SA-APT-IF1 SA-APT-2F2 SA-APT-3H3 AVEHACE (Control) i J ANU Aa r 3623 3723 3424 36:3 3923 36:3 4024 3623 37 4 35t3 35:3 3023 30t3 3123 3223 3514 3223 32r4 26:3 2613 21:3 29:3 3023 26t3 2724 2622 2625 I 3dr3 42 3 3924 39 3 42 3 40 3 4123 3813 40t3  ;

2523 2422 2123 23t3 23 3 27:3 2413 29 3 24 5 j FESxUARY 2322 23:2 16r3 22:3 23:3 23 3 2724 24 2 23r6 i 2413 2222 2123 22r2 262) 24t2 2423 2822 24t5 l 15 2 1422 1723 16 2 1622 14t2 1723 1622 1622 l 1923 1923 21:3 2013 1923 1923 2023 2123 20r2 .

I MARCH 1822 1522 1523 1723 14 3 1322 1523 1123 15t4 l 2623 28 3 30:3 29:3 3023 2923 2923 29:3 2922 2112 19t2 1st) 1612 2022 21r2 2123 1812 1924 n 1722 17 2 1823 1822 1922 1622 20t2 14r2 1724 APg1L 1322 1022 13r3 1122 1312 12r2 1423 622 1225 15r2 1522 1323 15r2 1622 14r2 1422 1422 1422 l 1422 1222 1323 1222 12r2 1322 1522 1322 13r2 13t2 1322 14r2 1322 1322 43r3 1222 1422 17:21 1623 1622 1623 1923 20r3 1623 1823 1512 1724 e

l MAy 2424 2323 20t3 22 3 2423 31 3 2423 2222 24r6 l 2423 13r2 21:3 1922 21:2 1722 1627(1) 1822 1925 2323 22:2 2423 24 3 2413 23t3 23t3 1922 23:3 2222 2222 19r2 1922 23r2 21r2 2122 20r2 21 3 JUNE 1523 17t3 12r3 1523 14t3 1723 1623 11 2 15r4 [

4123 41:3 35:3 3st) 43 3 42r3 43 3 41:3 40r5 2123 2112 23:3 1723 18r3 1923 20t3 2122 20r4 1 2222 2112 1713 2112 2422 21:3 23r3 1922 2124 l 20r3 1922 1923 18r3 1723 1723 2123 20r3 19t3 i i

l i  ;

i .

l t l

l E E E E E E E E E E E E E l L

M M M M M M M M M M TABLE C-2 (cont'd) 1984 CONCENTRATIONS OF GROSS BETA EMITTERS IN AIR PARTICULATES Results in Units of 10*I pC1/m3 2 2 sigma STATION NO.

MONTH

• SA-APT-2S2 SA-APT-5S! SA-APT-5DI** SA-APT-10D1 SA-APT-16El S)-APT-1F1 SA-APT-2F2 SA-APT-3H3 AVERAGE (Control)

JULY 2323 2422 1723 2213 24t3 23t3 22:3 2113 22t4 3223 3023 24t3 2923 30:3 2513 3223 2823 29t6 23 3 2022 2123 1723 1722 20t3 2023 2222 20t4 1522 1322 1723 1422 1813 1423 1423 1512 1513 A'JGUST 2122 20t2 2123 2123 24:3 212) 2323 3123 23t7 34 3 3213 3024 31:3 31:3 3523 3413 3123 3234 2423 25 2 2523 24t3 25t3 21 3 27:3 2412 2423 2012 2112 1923 1923 2312 1822 2323 1722 20t4 SEPTEMaER 36:3 3323 3223 34:3 4023 34t3 4024 3022 35t7 20t3 1923 21:3 1923 2223 1723 2223 17t2 20t4 2022 20t2 18t3 1813 2123 20t3 2423 2322 20t4 3023 332) 24:3 34 3 37:3 2923 3423 2923 3128 g3 2523 2323 26t3 20t3 2323 1823 2723 3223 2429 OCTOBER 27 3 27 3 232J 2623 3023 28 3 23 2 2412 2625 7123 3423 3313 3423 3714 3424 37 4 3423 3434 3323 2923 3114 3323 3524 3113 3523 3226III 3224 2222 24t3 2623 24:2 2522 2523 2713 3123 2625 NOVEMBER 2723 2823 26 2 2523 3324 25t3 28:3 2322 27t6 2122 26 2 25 3 2122 2322 23:2 2723 2322 24t4 3223 3114 28 4 26 3 32 3 32 3 3024 30 3 30:4 25:3 33t4 27:3 25t3 29:3 2323 2423 21 3 26t8 DECEMBER 32 3 31:3 33:4 2923 31:3 31t3 3523 3923 33t6 26:2 30:3 3123 3223 3523 2923 2923 3023 3025 4123 40 3 3814 3823 4123 3623 3723 3423 3825 4223 44 3 37:4 38t3 39:3 4023 3923 3713 4025 2123 1822 23t3 2012 21:2 2223 22*3 2223 21t3 AVERAGE 25 15 24216 23 14 24215 26t17 24216 26216 24t16 Grand Average 24216

• Sampling dates can be found in Table C-5.

• • Results by Teledyne Isotopes.

(1) utgh uncertataty due to low sample volume.

I i

1 J

I l

TABLE C-3 1984 CONCENTRATIOWS OF STRONTIDM-89* AmD -90 AND GAMMA EMITTERS ** IN QUARTERLY COMPOSITES OF AIR PARTICULATES l Results in Units of 10*3 pC1/m3 2 2 sigma l

i J

$ STATION MO. AND DATES St-89 St-90 se-7 Cr-51 Mn-54 Co-58 Fe-59 Te-129a Ra-226 Th-232 l.

SA-APT-252 12-27-83 to 3-26-84 <0.3 <0.2 5724 <2.8 <0.3 <0.4 <0.9 < 4.4 <0.7 <1.2 L

i 3-26-44 to 7-02-44 <0.6 <0.4 73 5 2.011.3 <0.4 0.320.2 <0.7 < 4.3 <0.9 <1.1 4 i

) 7-02-84 to 10-01-84 <0.3 <0.2 7125 <2.8 <0.3 <0.4 <0.9 <14 <1.0 <1.6 l

l 3

10-01-84 to 1-02-85 <0.2 <0.2 62 4 <2.5 <0.3 <0.3 <0.8 <12 <0.9 <1.5 l

i SA-APT-SSI 12-27-83 to 3-26-84 <0.3 <0.2 5224 <2.5 <0.4 <0.4 <0.6 15:10 <1.0 <1.6 3-26-84 to 7-02-84 <0.4 <0.3 69:5 <3.9 <0.3 <0.5 <0.9 <15 <1.1 <2.5

< 7-02-84 to 10-01-84 <0.3 <0.2 6425 <3.7 <0.3 <0.5 1.020.6 < 3.7 <1.1 1.320.8 l Ch C3 10-01-84 to 1-02-85 <0.2 <0.2 6525 <3.9 <0.4 <0.5 <0.9 <17 <1.0 <1.5 i SA-APT-5D1***

12-27-83 to 3-26-84 <1.0 <0.2 7329 (1) <0.4 <0.6 <2.0 (Il <9.6 (1) 3-26-84 to 7-02-84 <2.0 <0.2 78 5 (1) <0.3 <0.3 <0.8 (1) <5.0 (1) i I

7-02-84 to 10-01-84 <2.0 <0.4 7928 (1) <0.4 <0.4 <1.0 (1) <7.0 (1)  :

13-01-84 to 1-02-85 <0.7 <0.1 63t11 (la <0.8 <1.0 <2.0 (1) <10 (1)

S A- A PT-10 D1 12-27-8 3 to 3-27-84 <0.4 <0.3 55:5 <3.2 <0.3 <0.2 <0.9 <17 <1.1 <1.9 I'

3-27-84 to 7-03-84 <0.8 <0.6 6425 <2.2 <0.5 <0.4 <1.0 <11 <0.9 <2.0 7-0 3-64 to 10-02-0 4 <0.3 <0.2 63 5 <2.8 <0.3 <0.4 <0.3 <11 <1.0 <1.4 1

10-02-84 to 1-03-85 <0.2 <0.2 5425 <2.8 <0.4 <0.4 <0.9 <16 <1.1 <1.9 ,

I i

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l i ,

4 I

t-

i E E E E l

i

' TABLE C-3 (cont'd)

1984 ComCENTRATIONS OP STRONTIUM-89* AND -90 AND GAMMA EMITTESS** IN QUANTERLY COMPOSITES OF AIR PARTICULATES Results an Units of 10-3 pC1/m 3 2 2 sigma 1

1 STATION h0. AND DATES Sr-89 St-90 Be-7 Cr-51 Mn-54 Co-58 Fe-59 Te-129s Ra-226 Th-232 l

J SA-APT-16El 4

12-27-83 to 3-27-84 (0.4 <0.3 Se:S <3.7 0.720.3 <0.5 <1.0 <16 <1.0 <1.5 3-27-84 to 7-03-84 (0.4 <0.3 6625 <1.9 <0.3 <0.4 <1.1 < 6.3 <1.0 <1.6 i 7-03-8 4 to 10-02-8 4 <0.3 <0.2 6325 <2.5 <0.5 <0.2 <1.0 < 4.8 <1.2 <1.8 10-02-84 to 1-03-85 <0.2 <0.2 6525 <2.9 <0.4 <0.6 <0.6 <!5 0.920.5 1.621.0 SA-APT-Ir1 i

l j 12-27-8 3 t o 3-26-84 <0.3 <0.2 55t4 <3.0 <0.4 <0.4 <0.7 < 3.2 <1.0 <1.3 i i

3-26-84 to 7-02-84 <0.3 <0.2 6025 <4.6 <0.1 <0.4 <1.0 < 6.9 <1.0 <1.9 I 7-02-84 to 1G-01-84 <0.3 <0.2 65 6 <3.7 <0.3 <0.6 <0.8 <!! <1.0 <1.9 I l cs

Fa 10-01-84 to 1-02-85 <0.2 <0.2 5824 <2.6 <0.3 <0.4 <0.7 <13 <1.0 <1.2 t

l SA-APT-2P2

) 12-27-8 3 to 3-26-84 <0.4 <0.3 5625 <2.7 <0.5 <0.3 <1.0 <17 <1.0 <1.8 l 3-26-84 to 7-02-84 <0.4 <0.3 73tS <4.5 <0.5 <0.4 <1.0 < 4.8 <0.4 <1.7 i

j 7-02-84 to 10-01-84 <0.3 <0.3 7225 <4.7 <0.4 <0.4 <0.8 <15 <1.1 <1.7 10-01-a4 to 1-02-85 <0.3 <0.2 6025 <2.8 <0.4 <0.4 <0.7 <18 <1.0 <1.6 l

l SA-APT-3N3 tcontroll 12-27-8 3 to 3-26-84 <0.3 <0.2 5725 <2.1 <0.4 <0.4 <0.8 <!5 <0.9 <!.8 l 3-26-64 to 7-02-84 1.120.2 <0.3 62t4 <2.4 <0.3 <0.3 <0.8 < 2.5 <0.8 <1.4 l 7-02-84 to 10-01-84 <0.3 <0.2 6915 <2.8 <0.3 <0.2 <0.5 (15 <0.8 <!.4

] 10-01-84 to 1-02-85 <0.2 <0.2 52:3 <2.3 <0.3 <0.3 <0.6 <ll <0.6 <1.0 l i j AvEaAce - -

63t15 - - - - - - -

j

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

i

• • All other gassa esitters searched for were <LLDs typical LLDs are given in Table C-31.

• • • Results by Teledyne Isotopes.

j (1) Not analyzed my Toledyse Isotopes.

j i

i

)

1 I

Y

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

i L

TABLE C-4 1984 CONCENTRATIONS OF ICDINE-131* IN FILTERED AIR Results in Units of 10*3 pC1/m3 1

j STATION NO.

i I i RONTH** SA-AID-252 SA-AIO-SSI SA-AID-5DI*** SA-AIO-1031 SA-AIO-16El SA-AIO-lF1 SA-AIO-2F2 SA-AIO-393 j (Control)

JAncARY < 9.1 < 6.7 <40 < 6.2 < 7.7 < 6.4 <19 < 6.4

< 9.0 < 5.4 <20 < 7.4 < 7.6 < 9.6 <12 < 5.6

< 8.3 < 7.6 <20 < 9.9 < 8.4 < 9.8 <!2 < 4.1 l

<!3 (15 <20 <13 <!6 <28 <17 < 7.6

<16 <21 <20 (19 <33 <23 <26 <21 FEsa0ARY <17 <!3 <10 <22 <17 <15 <38(1) <17

<17 <17 <30 <!2 <23 <17 <21 <15

<!7 <!9 (20 <23 <!8 (17 <25 <16

<21 <!7 <10 <18 <26 <24 <26 <19 RARCu <15 <14 <10 <23 <25 <25 <18 <22

<!4 <16 (20 <15 <20 <18 <17 <12

<16 <!6 <30 <24 <17 <19 <21 <13 l

<14 <20 <13 <13 <18 C% < 8.9 <l8 <l4 PJ APRIL <17 <16 <50 <27 <24 <25 <21 < 7.1

<16 <20 <30 <18 <21 <26 <19 <!2

<14 < 5.0 <20 <19 (21 <16 <20 <13 (22 <16 <10 <l5 < 6.7 <17 <l5 < 5.7 i

<20 <11 <10 < 7.9 <17 <l5 <25 <14 i

MAY <20 <10 <20 < 7.8 <!9 (20 <18 <14

<21 < 6.1 (20 <!4 <17 <20 <110(l) <13 ,

<17 <13 <30 <20 <25 <13 <20 '19

! <ll < 8.2 <10 <!3 < 9.3 <i8 <16 < 2.4 i

JUNE <19 <21 (20 <23 <32 <19 <24 <!6 I <15 <12 <20 <16 (18 <27 <l5 <l3

<18 <12 <20 cl7 <21 (19 <14 <10

< 6.5 <13 <20 < 7.5 <14 <ll <24 <16

<l5 <1l <40 < 8.7 <20 <19 <lt <15 i t

i t 1

l 1

1 1

l M M M M M M M

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

S *

& M TABLE C-4 (cont'd) 1984 CONCENTRATIONS OF IOOINE-131' IN FILTEHED AIR kesults in Units of 10-3 pC1/m3 STATION NO.

RONTH** SA-AZO-2S2 SA-AIO-531 SA-AIO-5D1*** SA-AIO-1001 SA-AIO-16El SA-AIO-lF1 SA-AIO-2F2 SA-AIO-3H3 (Control)

JULY (17 <!8 <40 <24 <l6 <26 <26 (20

<19 <23 <20 <23 <18 <13 < 8.2 <15

<20 <19 <10 <l4 (16 < 9.1 <15 <l5

<11 <15 (50 < 8.0 <31 <27 (17 <21 AUGUST <12 <16 <30 <!8 <20 <19 <23 <16

<16 < 6.7 <20 <!7 <14 <12 <15 <17

<17 <12 <10 <20 <21 <20 <19 < 6.1

<12 <!6 (20 <14 <!8 <15 <!3 <16 SEPTEMBEa <17 <18 < 8.0 <20 <!7 <12 <13 <15

<18 <20 (10 <15 <!2 < 9.3 <28 <18

<15 <18 <10 <24 <21 <19 <20 <13

<15 < 8.5 <20 <!3 <14 < 5.7 <15 <!6 ch <!6 < 9.6 (20 <21 <23 <20 <25 <!3 tu OCTOBER <11 <!2 <20 <20 <14 < 5.9 < 5.9 <14

<21 <21 (20 < 7.0 <21 <18 <22 < 67 l

<10 <18 <40 <23 :22 <17 <15 <56 Ill l <15 <17 <20 <13 <13 <21 <l9 <15 NOVEMBER <17 <15 <20 <21 <!9 <14 < 7.4 <14

<17 <17 <20 < 6.2 <15 < 6.6 <!7 <14

<22 <24 <40 <20 <19 <!8 <24 < 5.7

<15 <16 < 9.0 < 6.7 <14 (17 <10 (18 DECEMdER (19 <26 (10 <19 <20 <18 <16 <14

<14 (21 <20 <20 < 5.3 <23 <13 <12

<!6 <15 < 9.0 <14 <!6 <26 <21 <!2 t

<11 < 6.3 (30 <16 <15 <21 <12 <14

<22 <19 <30 <10 <!4 <14 <13 <l5 l

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

• • Sampling dates can be found in Table C-5.

• • • aesults by Telecyne Isotopes. ,

(1) utgh LLD due to low sample volume. i l

l

TABLE C-5 1984 SAMPLING DA7ES FOR AIR SAMPLES STAF10N Ne nouTu 252 SSI 501 1001 t4El Ir1 2r2 3H3 J ANU ARY 12-27-83 12-27-83 12-27-83 12-27-83 12-27-83 12-27-83 12-27-83 12-27-83 to to to to to to to to 1-03-84 1-03-84 1-03-84 1-03-84 1-03-84 1-03-84 1-03-84 1-03-84 1-03-84 1-03-84 1-03-84 1-03-e4 1-03-84 1-03-84 1-03-84 1-03-84 to to to to to to to to 1-09-84 1-09-84 1-09-84 1-10-84 1-10-84 1-09-84 1-09-84 1-09-84 1-09-84 1-09-84 1-09-84 1-10-84 1-10-84 1-09-84 1-09-84 1-09-84 to to to to to to to to 1-16-84 1-16-84 1-16-me 1-16-84 1-16-84 1-16-84 1-16-84 1-16-84 1-16-84 1-16-84 1-16-84 1-16-84 1-16-84 1-16-84 1-16-84 1-16-84 to to to to to to to to 1-23-84 1-23-84 1-23-84 1-24-84 1-24-84 1-23-84 1-23-84 1-23-84 gg 1-23-84 1-23-84 1-23-84 1-24-84 1-24-84 1-23-84 1-23-84 1-23-84

,, to to to to to to to to 1-30-84 1-30-84 1-30-84 1-31-84 7-31-84 1-30-84 1-30-84 1-30-84 FESRUARY 1-30-84 1-30-84 1-30-84 1-31-84 .-31-o4 1-30-84 1-30-84 1-30-84 to to to to to to to to 2-06-84 2-06-84 2-06-84 2-06-84 2-06-84 2-06-84 2-03-84* 2-06-84 2-06-84 2-06-84 2-06-84 2-06-84 2-06-84 2-06-84 2-07-84 2-06-84 to to to to to to to to 2-14-84 2-14-84 2-14-84 2-14-84 2-14-84 2-14-84 2-14-84 2-14-84 2-14-84 2-14-84 2-14-84  ;-14-84 2-14-84 2-14-84 2-14-84 2-14-84 to to to to to to to to 2-21-84 2-21-84 2-21-84 2-21-84 2-21-84 2-21-84 2-21-84 2-21-84 2-21-84 2-21-84 2-21-84 2-21-84 2-21-84 2-21-84 2-21-84 2-21-84 to to to to to to to to 2-27-84 2-27-84 2-27-84 2-28-84 2-28-84 2-27-84 2-27-84 2-27-84 M AR CH 2-27-84 2-27-84 2-27-84 2-28-84 2-28-84 2-27-84 2-27-84 2-27-84 to to t, to to to to to 3-05-84 3-05-84 3-05-84 3-05-84 3-05-d4 3-05-64 3-05-84 3-05-84 3-05-84 3-05-84 3-05-84 3-05-84 3-05-84 3-05-84 3-05-84 3-05-84 to to to to to to to to 3-12-84 3-12-84 3-12-84 1-13-84 3-13-84 3-12-84 3-12-84 3-12-84 M M M M M M

M M M M M M M M TABLE C-5 (cont'd) 1984 SAMPLING DATES FOR AIR SAMPLES STATION NO.

MONTH 2S2 SSI SDI 10D1 15El IFl 2F2 3H3 MARCH 3-12-84 3-12-84 3-12-84 3-13-84 3-13-84 3-12-84 3-12-84 3-12-84 to to to to to to to to 3-19-84 3-19-84 3-19-84 3-19-84 3-19-84 3-19-84 3-19-84 3-19-84 3-19-84 3-19-84 3-19-84 3-19-64 3-19-84 3-19-84 3-19-84 3-19-84 to to to to to to to to 3-26-84 3-26-84 3-26-84 3-27-84 3-27-84 3-26-84 3-26-84 3-26-84 APRIL 3-26-84 3-26-84 3-26-84 3-27-84 3-27-84 3-26-84 3-26-84 3-26-84 to to to to to to to to 4-02-84 4-02-84 4-02-84 4-02-84 4-02-84 4-02-84 4-02-84 4-02-84 4-02-84 4-02-84 4-02-84 4-02-84 4-02-84 4-02-84 4-02-84 4-02-84 to to to to to to to to 4-09-84 4-09-84 4-09-84 4-10-84 4-10-84 4-09-84 4-09-84 4-09-84 4-09-84 4-09-84 4-09-84 4-10-84 4-10-84 4-09-84 4-09-84 4-09-84 O'

to to to to to to to to 4-16-84 4-16-84 4-16-84 4-16-84 4-16-84 4-16-84 4-16-84 4-16-84 4-16-84 4-16-84 4-16-84 4-16-84 4-16-84 4-16-84 4-16-84 4-16-84 to to to to to to to to 4-23-84 4-23-84 4-23-84 4-24-84 4-24-84 4-23-84 4-23-84 4-23-84 4-23-84 4-23-84 4-23-84 4-24-84 4-24-84 4-23-84 4-23-84 4-23-84 to to to to to to to to 4-30-84 4-30-84 4-30-84 4-30-84 4-30-84 4-30-84 4-30-84 4-30-84 MAY 4-30-84 4-30-84 4-30-84 4-30-84 4-30-84 4-30-84 4-30-84 4-30-84 to to to to to to to to 5-07-84 5-07-84 5-07-84 5-07-84 5-07-84 5-07-84 5-07-84 5-07-84 5-07-84 5-07-84 5-07-84 5-07-84 5-07-84 07-84 5-07-84 5-07-84 to to to to to to to to 5-14-84 5-14-84 5-14-84 5-15-84 5-15-84 5-14-84 5-10-84* 5-14-84 5-14-84 5-14-84 5-14-84 5-15-84 5-15-84 5-14-84 5-14-84. 5-14-84 to to to to to to to to 5-21-84 5-21-84 5-21-84 5-21-84 5-21-84 5-21-84 5-21-84 5-21-84 5-21-84 5-21-84 5-21-84 5-21-84 5-21-84 5-21-84 5-21-84 5-21-84 to to to to to to to to 5-29-84 5-29-84 5-29-84 5-30-84 5-30-84 5-29-84 5-29-84 5-29-84

TABLE C-5 (cont'd6 1984 SAMPLING DATES FOR A.k SAMPLES STATION NO.

MONTH 252 SSI SDI 1001 16El Irl 2fs 3H3 JUNE 5-29-84 5-29-84 5-29-84 5-30-84 5-30-84 5-29-84 5-29-84 5-29-84 to to to to to to to to 6-04-84 5-04-84 6-04-84 6-04-84 6-04-84 6-04-84 6-04-84 6-04-84 6-04-84 6-04-84 6-04-84 6-04-84 6-04-84 6-04-84 6-04-84 6-04-84 to to to to to to to to 6-11-84 6-11-84 6-11-84 6-12-84 6-12-84 6-11-84 6-11-84 6-11-84 6-11-84 6-11-84 6-11-84 6-12-84 6-12-84 6-11484 6-11-84 6-11-84 to to to to to to to to 6-18-84 6-18-84 6-18-84 6-18-84 6-18-84 6-18-84 6-18-84 6-18-84 6-18-84 6-18-84 6-18-84 6-18-84 6-18-84 6-13-84 6-18-84 6-18-84 to to to to t3 to to to 6-25-84 6-25-84 6-25-84 6-26-84 6-26-84 6-25-84 6-25-84 6-25-84 og 6-25-84 6-25-84 6-25-84 6-26-84 6-26-84 6-25-84 6-25-84 6-25-84 cs to to to to to to to to 7-02-84 7-02-84 7-02-84 7-03-84 7-03-84 7-02-84 7-02-84 7-02-84 JULY 7-02-84 7-02-84 7-02-d4 7-03-84 7-03-84 7-02-84 7-02-84 7-02-84 to to to to to to to to 7-09-84 7-09-84 7-03-84 7-09-84 7-09-84 7-09-84 7-09-84 7-09-84 7-09-84 7-09-84 7-09-84 7-09-84 7-09-84 7-09-84 7-09-84 7-09-84 to to to to to to to to 7-16-84 7-16-84 7-16-84 7-17-84 7-17-84 7-16-84 7-16-84 7-16-84 7-16-84 7-16-84 7-16-84 7-17-84 7-17-84 7-16-84 7-16-84 7-16-84 to to to to to to to to 7-23-84 7-23-84 7-23-84 7-24-84 7-24-84 7-23-84 7-23-84 7-23-04 7-23-84 7-23-84 7-23-84 7-24-84 7-24-84 7-23-84 7-23-84 7-23-84 to to to to to to to to 7-30-84 7-;0-84 7-30-84 7-31-84 7-31-84 7-30-84 7-30-84 7-30-84 AUGUST 7-30-84 7-30-84 7-30-84 7-31-84 7-31-84 7-30-84 7-30-84 7-30-84 to to to to to to to to 8-06-84 8-06-84 3-06-84 8-06-84 8-06-84 8-06-84 8-06-84 8-06-84 8-06-84 8-06-84 6-06-84 8-06-84 8-06-84 8-06-84 8-06-84 8-06-84 to to to to to to to to 8-13-84 8-13-84 8-13-84 8-14-84 8-14-84 8-13-84 8-13-84 8-13-84 m M M M M

M M M M M M M M TABLE C-5 (cont'd) 1984 SAMPLING DATES FOR AIR SAMPLES STATION NO.

MONTH 252 551 SD1 10D1 16El IFl 2F2 3H3 A'JGUST 8-13-84 8-13-84 8-13-84 8-14-84 8-14-84 8-13-84 8-13-84 8-13-84 to to to to to to to to 8-20-84 8-20-84 8-20-84 8-20-84 u-20-84 8-20-84 8-20-84 8-20-84 8-20-64 8-20-84 8-20-84 8-20-84 8-20-84 8-20-84 8-20-84 6-20-84 to to to to to to to to 8-28-84 6-28-84 8-28-84 8-29-84 8-29-84 8-28-84 8-28-84 8-27-84 SEPTEMBER 8-28-84 6-28-84 8-28-84 6-29-84 6-29-84 0-28-84 8-28-84 8-27-84 to to to to to to to to 9-04-84 9-04-84 9-04-84 9-04-84 9-04-84 9-04-84 9-04-84 9-04-84 9-04-84 9-04-84 9-04-84 9-04-84 9-04-84 9-04-84 9-04-84 9-04-84 to to to to to to to to 9-10-84 9-10-84 9-10-44 9-11-84 9-11-84 3-10-84 2-10-84 9-10-84

, 9-10-84 9-10-84 9-10-84 9-11-84 9-11-84 9-10-84 9-10-84 9-10-84 y to to to to to to to to 9-17-84 9-17-84 9-17-84 9-17-84 9-17-84 9-17-84 9-17-84 9-17-84 9-17-44 9-17-84 9-17-84 9-17-84 9-17-84 9-17-84 9-17-84 9-17-84 to to to to to to to to 9-25-84 9-25-84 9-25-84 9-26-84 9-26-84 9-25-84 9-25-84 9-24-84 9-25-84 9-25-84 9-25-84 9-26-84 9-26-84 9-25-84 9-25-84 9-24-84 to to to to to to to to 10-01-84 10-01-84 10-01-84 10-02-84 10-02-64 10-01-84 10-01-84 10-01-84 oCTonER 10-01-84 10-01-84 10-01-84 10-02-84 10-02-84 10-01-84 10-01-84 10-01-84 to to to to to to to to 10-09-84 10-09-84 10-09-84 10-09-84 10-10-84 10-09-84 10-09-84 10-09-84 10-09-84 10-09-84 10-09-84 10-09-84 10-10-84 10-09-84 10-09-84 10-09-84 to to to to to to to to 10-15-84 10-15-84 10-15-84 10-16-84 10-16-s4 10-15-84 10-15-84 10-15-84 10-15-84 10-15-84 10-15-84 10-16-84 10-16-84 10-15-84 10-15-84 10-15-64 to to to to to to to to 10-22-84 10-22-84 10-22-84 10-22-84 10-22-84 10-22-84 10-22-84 10-17-84*

10-22-84 10-22-84 10-22-84 10-22-84 10-22-84 10-22-84 10-22-84 10-22-84 to to to to to to to to 10-29-84 10-29-84 10-29-84 10-30-84 10-30-84 10-29-84 10-29-84 10-29-84

TABLE C-5 (cont'd) 1984 SAMPLING DATES FOR AIR SAMPLES STATION NO.

nONTH 2S2 5S1 SD1 10D1 16El IP1 2F2 3H3 NOVEMBER 10-29-84 10-29-84 10-29-84 10-30-84 10-30-84 10-29-84 10-29-84 10-29-84 to to to to to to to to 11-05-84 11-05-84 11-05-84 11-05-84 11-05-84 11-05-84 11-05-84 11-05-84 11-05-84 11-05-84 11-05-84 11-05-84 11-05-84 11-05-84 11-05-84 11-05-84 to to to to to to to to 11-13-84 11-13-84 11-13-84 11-13-84 11-13-84 11-13-84 11-13-84 11-13-84 11-13-84 11-13-84 11-13-84 11-13-84 11-13-84 11-13-84 11-13-84 11-13-84 to to to to to to to to 11-19-84 11-19-84 11-19-84 11-20-84 11-20-84 11-19-84 11-19-84 11-19-84 11-19-84 11-19-se 11-19-84 11-20-84 11-20-84 11-19-u4 11-19-84 11-19-84 to to to to to to to to 11-26-84 11-26-84 11-26-84 11-27-84 11-27-84 11-26-84 11-26-84 11-26-84 cn DECEMsER 11-26-84 11-26-84 11-26-84 11-27-84 11-27-84 11-26-84 11-26-84 11-26-84 as to to to to to to to to 12-03-84 12-03-84 12-03-84 12-03-84 12-03-84 12-03-84 12-03-84 12-03-84 12-03-84 12-03-84 12-03-84 12-03-84 12-03-84 12-03-84 12-03-84 12-03-84 to to to to to to to to 12-10-84 12-10-44 12-10-84 12-11-84 12-11-84 12-10-84 12-08-84* 12-10-84 12-10-84 12-10-84 12-10-84 12-11-84 12-11-84 12-10-84 12-11-84 12-10-84 to to to to to to to to 12-18-84 12-18-84 12-18-84 l'.-18-84 12-18-84 12-18-84 12-18-84 12-18-84 12-18-84 12-18-84 12-19-84 2-18-84 12-18-84 12-18-84 12-18-84 12-18-84 to to to to to to to to 12-26-84 12-26-84 12-26-84 12-26-84 12-26-84 12-26-84 12-26-84 12-26-84 12-26-44 12-26-84 12-26-84 12-26-84 12-26-84 12-26-84 12-26-84 12-26-84 to to to to to to to to 1-02-85 1-02-85 1-02-85 1-03-85 1-03-85 1-02-85 1-02-85 1-02-85

• Redaced samp1tng period due to instrument malfunction.

M M M

TABLE C-6 I 1984 CONCENTRATIONS OF GROSS ALPfiA AND GROSS BETA EMITTEHS, AND TRITIUM IN PRECIPITATION STATION NO. SA-RWA-2F2 Results in Units of pCi/L 2 2 sigma COLLECTION PERIOD ALPHA BETA TRITIUM 12-27-83 to 1-30-84 <0.8 <2.7 <130 1-30-84 to 2-27-84 1.120.8 3.520.7 <130 2-27-84 to 3-26-84 <1.4 3.220.7 140180 3-26-84 to 4-30-84 <0.9 3.720.7 <130 4-30-84 to 5-30-84 <1.5 1.820.6 <130 5-30-84 to 7-02-84 <1.0 2.820.7 140280 7-02-84 to 7-31-84 1.721.1 2.220.6 <130 7-31-84 to 8-28-84 <1.9 3.820.8 <140 8-28-84 to 10-02-84 2.421.2 4.020.8 150280 10-02-84 to 10-29-34 <1.0 1.020.5 <130 10-29-84 to 11-27-84 <1.0 3.221.2 <130 11-27-84 to 1-02-85 0.810.7 1.920.7 <140 AVERAGE -

2.821.8 -

I 69 I .

TABLE C-7 1984 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND GAMMA EMITTERS **

IN QUARTERLY COMPOSITi:S OF PRECIPITATION STATION NO. SA-RWA-2F2 Results in Unita of pCi/L t 2 sigma 12-27-33 3-26-84 7-02-84 10-02-84 NUCLIDE to to to to AVERAGE 3-26-84 7-02-84 10-02-84 10-29-84(1)

Sr-89 <0.5 <0.5 <0.5 <l.0 -

a O Sr-90 <0.4 <0.4 <0.4 <0.4 -

Be-7 3626 3524 2524 39221 34212 Ra-226 <1.5 <8.4 <l.3 5.622.4 -

Th-232 <2.4 <2.2 <2.5 7.8!4.5 -

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

• • All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-31.

(1) Results are only taken from the October sample due to insufficient rainfall in the remaining two months of the fourth quarter.

M M M M =

m M

TABLE C-8 I 1984 DIRECT RADIATION MEASUREMENTS - QUARTERLY TLD RESULTS Results in mead / standard month *

(Results by Teledyne Isotopes)

JANUARY APRIL JULY OC'IOBER STATION NC. to to to to AVERAGE MARCH JUNE SEPTEMBER DECEMBER SA-IDM-2S2 5.920.1 5.320.3 5.620.2 4.8t0.3 5.410.9 SA-IDM-SS1 4.920.2 4.420.3 5.0t0.4 4.520.2 4.7*0.6 SA-IDM-6S2 5.120.1 5.120.2 (1) 5.120.2 5.120.0 SA-IDH-7S1 6.220.2 5.920.2 6.6t0.2 6.220.2 6.220.6 SA-IDM-10S1 5.820.1 5.420.1 6.820.7 6.3t0.3 6.121.2 SA-IDM-llS1 4.910.1 4.720.1 6.7t0.2 8.7 0.3 6.223.7 SA-IDM-4D2 6.120.5 5.7t0.4 6.120.4 5.410.3 5.820.7 SA-IDM-5D1 5.3t0.2 5.120.1 5.820.2 5.120.1 5.310.7 SA-IDM-10D1 6.020.5 5.4 0.3 6.120.1 5.320.2 5.720.8 GA-IDH-14D1 5.320.3 5.410.3 6.120.2 5.120.2 5.520.9 SA-ICM-2El 5.510.1 5.120.5 6.020.6 5.220.6 5.420.8 SA-IDM-3El 5.210.2 5.020.3 5.620.4 4.910.3 5.220.6 EA-IDM-9El 6.6t0.2 6.220.8 6.820.5 6.120.1 6.420.7 SA-IDM-llE2 6.5t0.4 6.120.3 7.120.6 5.920.3 6.421.0 SA-IDM-12El 6.420.1 5.7t0.1 6.620.1 5.620.2 6.121.0 SA-IDM-13El 5.220.2 5.020.5 5.7t0.2 4.820.3 5.220.8 SA-IDM-16El 5.6t0.1 5.620.8 6.420.3 5.320.1 5.720.9 SA-IDH-lF1 5.020.5 5.1: 0. 6 6.020.3 5.220.1 5.32C.9 SA-IDM-2F2 4.220.1 4.820.5 4.820.2 3.820.1 4.4 1.0 SA-IDH-2F5 6.120.1 5.4t0.1 6.320.1 5.310.1 5.8 1.0 SA-IDM-2F6 5.520.3 5.120.2 6.010.3 5.020.1 5.420.9 SA-IDH-3F2 5.711.1 4.620.2 5.420.3 4.8t0.0 5.120.3 SA-IDM-3F3 5.320.2 4.420.2 5.520.1 4.5 0.1 4.910.9 SA-IDM-5P1 5.0t0.1 4.7t0.1 5.720.3 4.920.2 5.120.8 SA-IDM-6P1 4.520.2 4.220.0 5.120.3 4.020.2 4.421.0 SA-IDH-7F2 4.020.1 3.520.1 4.3t0.2 3.810.2 3.920.7 SA-IDM-10F2 6.320.1 5.5 0.5 6.720.1 5.8:0.2 6.ltl.1 SA-IDM-11F1 5.920.1 5.720.2 6.6t0.1 5.220.4 5.821.2 SA-IDM-12F1 6.210.1 5.220.3 6.220.1 4.910.3 5.621.4 SA-IDH-13F2 5.80.1 5.220.4 6.120.3 5.0 0.4 5.5tl.0 SA-IDM-13F3 6.220.2 5.5t0.2 6.4:0.2 5.220.2 5.821.1 SA-IDM-13F1/4** 5.6t0.1 5.420.4 6.120.1 5.320.2 5.6t0.7 SA-IDM-14F2 5.920.1 5.1 0.4 6.120.4 5.220.2 5.621.0 6.321.3 I SA-IDH-15F3 6.620.2 6.120.5 7.110.5 5.6t0.3 SA-IDM-16F2 5.7t0.1 4.8t0.5 5.720.3 4.7t0.0 5.2tl.1 SA-IDM-1G3 (C) 6.020.2 6.720.2 7.2t0.3 6.020.3 6.721.0 SA-IDM-3G1 (C) 5.620.1 5.820.3 6.720.3 5.320.2 5.821.2 SA-IDH-10G1 (C) 6.620.2 6.0 0.3 6.820.5 5.5t0.3 6.2tl.2 SA-IDM-16G1 (C) 6.920.2 6.120.3 7.220.3 5.9t0.2 6.521.2 SA-IDH-3H1 C) 5.5t0.2 5.020.6 6.6t0.2 5.4t0.2 5.621.4 SA-IDM-3H3 ((C) 5.7t0.2 5.720.2 6.520.3 5.420.2 5.810.9 AVERAGE 5.711.3 5.3tl.2 6.221.3 5.321.6 Grand Average 5.6tl.5

• 'Ihe standard month = 30.4 days.

• • Ef fective 3-27-84, loc.13F1 has been moved to a new location (13F4) .

(1) TLD missing from field location.

(C) Control station 71

TABLE C-9 1984 DIRECT RADIATION MEASUREMENTS - MONTHLY TLD RESULTS Results in mead / standard month *

(Results by Teledyne Isotopes)

STATION NO. JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-IDM-2S2 6.110.6 6.710.3 5.420.3 6.120.2 6.520.6 7.521.0 SA-IDH-SS1 4.320.2 6.120.1 4.620.1 4.920.1 5.820.2 6.320.3 SA-IDM-6S2 4.420.1 6.520.3 5.220.1 5.520.1 6.421.2 6.920.6 SA-IDM-7S1 5.320.2 7.720.1 5.920.4 6.620.5 7.020.2 7.820.2 SA-IDM-10S1 5.420.1 6.820.2 5.810.3 5.920.1 6.620.2 7.720.4 SA-IDH-llS1 4.820.8 5.720.1 4.720.1 5.420.6 5.820.4 6.820.9 SA-IDM-5D1 4.420.3 6.6t0.2 5.120.2 5.4to.2 6.220.2 7.020.2 SA-IDM-10D1 5.020.4 6.920.3 6.020.4 6.420.1 6.520.3 7.420.2 SA-IDM-14D1 5.420.1 6.820.5 5.420.2 6.220.3 6.520.3 7.620.2 SA-IDH-2El 5.420.4 6.720.2 5.110.3 5.520.1 6.320.4 7.411.5 SA-IDM-3E1 5.320.2 6.420.1 4.920.2 5.620.7 6.020.1 6.820.3 4 SA-IDH-13El 4.920.6 6.420.2 5.120.4 5.720.2 5.920.4 6.920.2 M SA-IDM-16El 5.220.8 7.220.3 5.720.3 6.020.2 6.320.5 7.520.1 SA-IDH-lF1 5.520.1 6.520.2 5.820.5 6.120.2 6.820.7 7.321.1 SA-IDM-2F2 4.620.1 5.620.2 4.520.9 4.420.1 5.221.0 6.020.2 SA-IDM-2F6 6.020.1 6.620.2 5.210.3 5.720.2 6.820.5 7.120.4 SA-IDH-5F1 4.320.3 6.220.1 4.820.2 5.220.2 5.920.2 6.620.3 SA-IDH-6F1 3.610.4 5.520.2 4.420.2 4.520.1 5.620.2 6.0t0.3 SA-IDM-7F2 3.520.2 5.620.5 3.820.2 4.320.3 4.920.3 5.5t0.4 SA-IDM-llF1 5.620.2 7.120.5 5.920.1 6.520.2 6.720.2 7.820.0 SA-IDM-13Fl/4** 5.320.4 6.520.2 5.420.2 6.220.3 6.620.2 7.6t0.9 SA-IDM-3G1 (C) 6.120.1 7.220.2 5.720.3 5.820.2 6.220.2 7.720.4 SA-IDH-3H1 (C) 6.020.3 6.920.2 5.320.2 5.820.1 7.020.2 7.320.2 SA-IDH-3H3 (C) 5.220.4 7.320.2 5.910.2 6.320.3 7.120.2 8.021.0 AVERAGE 5.121.4 6.621.1 5.221.1 5.721.3 6.321.1 7.121.3 K M

M M M M M M M M TABLE C-9 (cont'd) 1984 DIRECT RADIATION MEASUREMENTS - MONTHLY TLD RESULTS Results in mrad / standard month *

(Results by Teledyne Isotopes)

STATION NO. JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE SA-IDM-2S2 5.620.3 7.120.3 5.520.5 5.020.1 4.620.4 5.920.3 6.021.7 SA-IDH-SSl 5.320.3 6.620.7 5.120.2 4.820.2 4.820.8 5.520.2 5.321.4 SA-IDM-6S2 5.920.4 6.920.4 (1) 5.410.2 5.220.5 5.810.3 5.821.6 SA-IDM-7S1 6.520.4 8.120.4 6.720.2 6.420.2 6.320.6 6.920.5 6.821.6 SA-IDM-10S1 6.020.5 8.020.1 6.520.1 6.820.2 6.320.9 6.120.4 6.5 1.5 SA-IDM-11S1 5.410.6 8.520.4 8.310.5 11.320.6 9.322.4 5. 7* 0. 5 6.824.2 SA-IDM-5D1 5.720.5 7.020.5 5.620.2 5.020.3 4.R20.4 5.820.3 5.721.7 SA-IDM-10D1 6.420.3 8.120.4 6.320.1 5.720.2 5.520.5 6.120.6 6.421.7 SA-IDM-14D1 6.020.3 7.420.4 6.020.2 5.520.6 5.520.5 6.020.1 6.221.5 SA-IDM-2El 5.820.2 7.120.3 5.820.3 5.520.2 5.020.2 6.020.4 6.021.5 SA-IDM-3El 5.620.3 7.020.2 5.420.4 4.9 0.2 4.9tl.0 5.520.3 5.711.4 SA-IDM-13E1 5.920.2 7.120.1 5.921.2 5.120.4 4.920.4 5.720.4 5.821.5 d SA-IDM-16El 6.320.4 7.620.2 5.920.1 5.320.3 5.22 0.3 6.120.3 6.221.7 SA-IDM-lF1 5.820.3 7.620.2 6.021.0 5.420.3 5.020.3 5.720.4 6.121.6 SA-IDM-2F2 4.720.2 5.920.1 4.420.2 4.320.2 4.220.3 4.820.1 4.921.3 SA-IDH-2F6 6.220.5 7.120.4 5.520.3 5.420.2 5.120.2 6.lt0.3 6.121.4 SA-IDM-5F1 5.6t0.4 6.820.4 5.420.2 5.120.1 4.920.6 5.720.3 5.521.5 SA-IDH-6F1 5.020.2 6.110.2 4.720.4 4.620.1 4.820.3 5.0t0.1 5.021.4 SA-IDM-7F2 4.620.2 5.820.6 4.110.2 4.120.2 4.3 0.6 4.820.2 4.621.5 SA-IDH-llF1 6.310.2 8.210.6 6.120.4 6.020.3 5.820.3 6.120.4 6.521.6 JA-IDM-13F4 6.420.6 7.520.2 5.820.2 5.320.4 5.4t0.4 6.020.3 6.2t1.5 SA-IDH-3G1 (C) 6.320.8 7.720.3 6.421.1 5.720.1 5.520.4 6.120.3 6.421.5 SA-IDM-3H1 (C) 5.920.7 7.6.0.4 5.920.2 5.920.3 5.9-0.2 6.210.3 6.321.4 SA-IDM-3H3 (C) 6.620.9 8.520.2 6.110.3 5.820.3 6.320.3 6.520.3 6.611.9 AVERAGE 5.821.1 7.321.5 5.8t1.7 5.6i2.7 5.422.0 5.8tl.0 Grand Average 6.022.C

• The standard month = 30.4 days.

• • Effective 3-27-84, Loc. 13F1 has been moved to a new location (13F4).

(1) TLD missing from field location.

(C) Control station .

TABLE C-10 1984 CONCENTRATIONS OF IODINE-Ill' IN MILE sesults in Units of pct /L STATION NO.** JANUARY (EBRUA2Y MARCH APRIL MAY JUNE SA-MLK-13E3 <0.1 <0.1 <0.1 <0.1 <0.1 <0.1

<0.2 <0.2 <0.1 <0.1 <0.1 <0.1 SA-MLK-2F4 <0.1 <0.2 <0.1 <0.1 <0.1 <0.1

<0.2 <0.2 <0.1 <0.1 <0.1 <0.1 SA-MLK-5F2 <0.1 <0.2 <0.1 <0.1 <0.1 <0.1

<0.2 <0.2 <0.1 <0.1 <0.1 P

<0.1 SA-MLK-14F1 <0.1 <0.2 <0.1 <0.1 <0.1 <0.1

<0.2 <0.2 <0.1 <0.1 <0.1 <0.1 SA-MLK-15F1 <0.1 <0.2 <0.1 <0,1 <0.1 <0.1

<0.2 <0.2 <0.1 <0.1 <0.1 <0.1 SA-MLK-3G1 <0.1 <0.1 <0.1 <0.1 <0.1 <0.1 (Control) <0.2 <0.2 <0.1 <0.1 <0.1 <0.1 a

STATION NO.** JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER l SA-MLK-13E3 <0.1 <0.1 <0.1 <0.1 <0.1 <0.2

! <0.1 <0.1 (0.2 <0.1 <0.1 <0.1 SA-MLK-2F4 <0.1 <0.2 <0.1 <0.1 <0.1 <0.2

<0.1 <0.1 <0.1 (0.1 <0.1 <0.1 l

SA-MLK-5F2 <0.1 <0.2 <0.1 <0.1 <0.1 <0.2 i

! <0.1 <0.1 <0.1 <0.1 <0.1 <0.1 4

i SA-MLK-14F1 <0.1 <0.2 <0.1 <0.1 <0.1 <0.2

<0.I <0.I <0.1 (O.I <0.I <0.1 SA-MLK-15F1 <0.1 <0.2 <0.1 <0.2 <0.1 (0.2

) <0.1 <0.1 <0.1 <0.1 <0.1 <0.1

! SA-MLK-3G1 (0.1 <0.1 <0.1 <0.1 (0.1 <0.2

) (Control) <0.1 <0.1 <0.1 <0.1 <0.1 <0.1  ;

I

}  !

i i j

• I-131 results are corrected for decay to midpoint of collection period.

,1

• • Sampling dates can be found in Table C-13.

I i

)

i I I I ,

M M M M M M TABLE C-11

?984 CONCENTRATIONS OF STRONTIUM-89* and -90 IN haLK Results in Units of pCi/L 2 2 sigma STATION NO.** NUCLIDE JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-MLK-13E3 St-89 <1.0 <1.2 <1.2 <1.3 <1.1 <1.4 St-90 2.520.4 2.910.5 2.620.5 3.220.6 2.410.4 2.720.6 SA-MLK-2F4 St-89 <1.0 <1.0 <1.1 <1.3 <1.1 <1.6 Sr-90 1.610.4 1.910.4 1.220.4 3.410.6 2.110.4 1.610.6 SA-MLK-5F2 Sr-89 <1.1 <1.2 <1.2 <1.2 <1.2 <1.7 St-90 2.720.4 3.810.5 3.210.4  !.820.5 4.120.5 5.320.7 SA-MLK-14F1 St-89 <1.2 <1.4 <1.2 <1.3 <1.1 <1.4 St-90 2.020.4 2.Sto.5 2.210.5 2.720.6 2.520.4 2.320.6 SA-MLK-15F1 St-89 <1.0 <1.4 (1.1 <1.2 <1.1 <1.3 St-90 1.410.4 2.620.6 1.820.4 2.320.5 1.420.4 2.010.5 SA-MLK-3G1 St-89 <1.2 <1.2 <1.3 <1.3 <1.2 <1.8 (Control) St-90 2.920.4 3.520.5 3.710.5 3.120.6 3.120.5 3.320.7 4

UI STATION NO.** NUCL1DE JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVf'AGB SA-MLK-13E3 St-89 <1.1 <1.0 (1.5 <1.1 <1.0 (0.8 -

Sr-90 2.120.5 2.120.4 2.210.6 2.210.4 2.0t0.4 1.920.4 2.420.8 SA-MLK-2F4 St-89 <1.0 <1.0 <1.5 <1.0 <1.0 <0.C -

St-90 1.320.4 1.320.4 1.210.4 1.510.4 1.820.4 1.5t0.3 1.721.2 SA-MLK-5F2 St-89 <1.4 <1.2 <1.7 <1.3 <1.4 <1.0 -

" Sr-90 4.910.6 4.2'O.6 4.310.7 4.510.6 4.410.6 2.5t0.4 3.8t2.1 SA-MLX-14F1 St-89 <l.1 <1.1 <1.4 <1.1 <1.1 <0.9 -

St-90 1.920.5 2.110.4 1.920.4 2.4t0.5 2.120.4 1.720.4 2.220.6 SA-MLK-15F1 Sr-89 <1.3 '

0 <2.0 <1.1 <1.1 <1.2 -

St-90 2.110.6 1.8.w.4 2.020.8 1.910.4 1.620.5 2.310.4 1.920.7 SA-MLK-3GL St-89 <1.3 <1.2 <1.6 <1.2 <1.2 <0.9 -

(Control) St-90 4.920.6 3.820.5 3.310.6 3.020.5 2.3t0.5 2.2 0.4 1.3:1.4 Grand Average St-89 -

Sr-90 2.511.9

• Sr-89 results are corrected for decay to midpoint of collection period.

• • Sampling dates can be found in Table C-13.

Strontium analysis performed only on first milk collection of each month.

TABLE C-12 1984 CONCENTRAT2ONS OF GAMMA ENITTER8* IN MILE l Results in Units of pC1/L e 2 sigma l l

1 NUCLIDE JANUARY FE830ARY MASCE AFRIL MAY JUNE j STATION NO.**

i SA-MLE-13E3 Ma-22 <2.1 <3.2 <2.9 <2.9 < 3. 5 <0.5 f E-40 1400:55 1400:68 1300:67 1200:57 1300:45 1300:58 l

Mn-54 <1.5 <2.1 <2.8 <1.9 < 2.1 <2.1 i

1 Co-137 2.3 1.5 <2.6 <2.4 <2.3 <2.3 <1.4 i::lf! l:8 5:fil.2

<9.3 li:1

<9.7

l:1 (7.6

!:1

<10

!:t

<8.0 Th-232 <7.3 SA-MLE-2F4 Ma-22 <3.1 <2.6 <2.2 <3.7 <3.6 <3.5 E-40 1400s61 1400:59 1400:55 1400 67 1400370 1400:59 Mn-54 <2.3 <2.5 <2.1 <2.3 <2.3 <2.3 Cs-137 <2.3 <2.5 <1.8 <2.6 <2.4 2.3s1.3 k::112 :l:1 :l:1  !:1 $!!;1.4 11:1 :l:t Th-232 <8.0 <7.4 49.1 <9.3 (9.3 <9.3 SA-MLE-5F2 Na-22 <3.0 <4.7 <2.7 <2 <3 5 <

E-40 1200s65 1200:53 1300:57 1400:)93 1400:59 14 0 h s. 953 Mn-54 <2.6 <2.2 <1.8 <0.9 <2.1 <2.7 Cs-137 <2.3 <3.7 <2.3 2.3s1.4 <2.1 4.3:1.7 La-140 <2.3 <2.3 <1.8 <2.1 <2.2 <1.5 Ra-226 <9.3 <9.0 (9.9 < 9. 0 <4.6 < 5. 8 Th-232 13s4 <11 <8.8 <8.2 <8.7 <9.0 SA-MLE-14F1 Ma-22 42.8 <2.9 <2.5 < 3.1 <1.6 <1.3 E-40 1400:56 1400:55 1400:55 1300:54 1300:58 1400:54

-J Ma-54 <2.6 <2.3 <2.1 <2.1 <1.0 <1.8 UI Cs-137 <2.8 <2.8 <2.7 <2.4 <2.2 <2.1 La-140 <2.6 <2.5 <2.0 <1.9 <1.2 <1.8 Ra-226 < 7. 2 <7.5 <?.9 <6.8 <4.2 44.6 Th-232 <11 <8.6 <10 <8.3 <10 <8.2 SA-MLE-15F1 Ma-22 < 3.1 < 3. 5 < 3. 4 <2.9 <1.7 <4.1 E-40 1300:58 1300 67 1300:67 1200s66 1300:66 1300s60 Mn-54 <2.2 <2.4 <2.1 <1.1 <2.4 <1.9 Cs-137 2.7s1.4 <2.0 <2.4 <2.5 <2.6 <3.3 La-140 <2.2 <3.0 <2.6 <3.3 <2.8 cl 7 Ra-226 <9.8 <9.6 <9.0 49.7 <t.4 6.5:3.4 Th-232 < 7.1 <8.6 <9.1 <8.2 <8.3 <8.3 SA-MLE-3G1 Ma-22 <3.5 <2.8 <3.0 2.1 1.2 <2.6 <1.5 E-40 1500:69 1300 68 1400:59 1400:68 1300:54 1300:57 (Control) <2.2 <1.7 <2.2 < 2. 4 <1.0 Ma-54 <2.3 Cs-137 <2.6 <2.2 <1.9 <2.7 <2.2 <1.8 k::112 21:f i:1

<10

l:1 49.2

l:t 49.3 11:1

<8.4

l:3

<6.7 Th-232 <9.3 AVERAGE E-40 1400:210 1300:160 1400:110 1300s200 1300:100 1400:110 m M M M M M M M M

M M M M M M M M M M M TABLE C-12 (cont'd) 1984 CONCENTR ATIONS OF G AMMA EMITTERS

• IN MILE Results in Units of_pC1/L a 2 sigma STATION NO.** NUCLIDE JULY AUGUST SEFTEMBER OCTOBER NOVEMBER DECEMBER AVEBAGE SA-MLE-1333 Ma-22 <3.0 <3.5 <1.6 <2.0 <2.7 <2.7 -

E-40 1300:58 1500a68 1400:54 1400460 1400459 1400:59 1400:160 Mn-54 <1.1 <2.3 <1.8 <1.7 <2.1 <0.9 -

Cs-137 <2.4 <2.6 <2.6 <2.4 <2.2 <2.5 -

La-140 <1 2 <2.4 <0.6 <l 3 <1 1 <2.1 -

Ra-226 44 7 <4.8 (4.4 <J 9 <3. 8 <4.4 -

Th-232 <8.2 <9.8 <3.6 <6.8 <9.6 <7.8 -

$A-MLE-2F4 Na-22 <3.2 < 3.1 <3.3 <2.9 <2.8 <3.3 -

E-40 1400a69 1400:49 1300s64 1400:59 1300s61 1400a68 1400a78 Mn-54 <1.2 <2.1 <2.3 <1.0 <2.3 <2.3 -

Cs-137 <2.5 <2.8 <2.4 <2.0 <2.6 <2.4 -

La-140 <2.1 <3.8 <2.3 <3.0 <2.9 <2.3 -

Ra-226 <5.5 < 5.1 44.8 (4.4 (4.8 <4.8 -

Th-232 48.2 <9.2 <$.9 <8.3 <8.9 <9.3 -

SA-MLE-5F2 Ma-22 <2.7 <2.4 <2.6 <3.5 <3.2 <2.3 -

E-40 1300:55 1400:58 1200:56 1300:46 1300s64 1300:52 1300:160 Mn-54 <0.8 <2.4 <2.3 <2.5 <2.5 <1.8 -

Co-137 4.2s1.7 3.1 1.9 6.2s1.9 3.0s1.7 2.1 1.3 1.0:1.0 3.le2.6 La-140 <1.4 2.4s! 4 <2.1 < 3.1 < 3. 0 <1.6 -

Ra-226 <5.7 <4.3 <3.9 <5.3 <4.4 <2.5 -

Th-232 < 7. 8 <8.8 c6.8 410 <8.9 <8.0 -

SA-MLE-14F1 Ma-22 <3.0 < 3. 0 <3.4 <2.7 <2.8 <2.8 -

,a E-40 1400:59 1300:54 1400a66 1400:54 1300:54 1500s60 1400 - 120 q Mn-54 2.4:1.4 <1.1 (2.3 <1.9 <1.8 <1.6 Cs-137 <2.4 <2.0 (2.6 <2.2 <2.0 <1.3 -

La-140 <3.3 <1.5 <2.6 <2.7 <1.1 <1.5 -

Ra-226 <4.8 <4.7 (4.8 <5.2 <5.0 c5.2 -

Th-232 <?.4 < 7. 9 <9.3 <8.6 <5.3 <3.2 -

SA-MLE-15F1 Na-22 <3.3 <2.5 <2.9 <1.4 <3.2 <3.6 -

E-40 1300:53 1400r68 1300:58 1400:55 1400s66 1200:53 1300:130 Mn-54 <1.8 <2.4 <1.1 <1.2 <2.3 <1.9 -

Cs=137 <1.9 <2.2 <2.0 <1.9 <2.6 <2.7 -

La-140 <2.6 <2.9 <2.0 <2.4 <2.7 <2.6 -

Ra-226 < S. 5 < 5. 4 <4.9 <4.1 <4.8 <5.6 -

Th-232 <9.0 <8.6 48.0 48.5 <9.3 <s.7 -

SA-MLE-3G1 Ma-22 < 3. 3 <2.3 <3.3 <3.7 1 <2.6 -

(Control) E-40 1300a67 1400:59 1300a67 1300a66 94 1400a69 1400:130 Mn-54 <2.2 <0.9 42.3 <16 e4 <2.5 -

Cs-137 <2.6 <2.3 <2.6 <2.1 , , *"' <22 -

La-140 <2.6 <1.7 (2.9 <2.4 . - < 3.1 -

Ra-226 <5.1 <4.9 45.1 < 5. 0 . 42 - <5.5 -

Th-232 <8.9 <7.6 <!2 <9.5 t i <3.4 -

AVERAGE E-40 1300:100 1400:130 1300:150 1400:100 c% *48 -

. g L *e v *' a , 1300:140

• All other gamma saltters searched for were <LLD typical LLDs are given in Table C-31.

• • Sampling dates can be found in Table C-13.

Gassa analysis performed only on first milk collection of each month.

TABLE C-13 I 1984 SAMPLING DATES FOR MILK SAMPLES l

STATION NO.

MONTH 13E3 2r4 5r2 14rl 15F1 3G1

. JANUARY 1-03-84 1-01-84 1-02-84 1-02-84 1-02-84 1-03-84 to to to to to to l l-04-84 1-03-84 1-03-84 1-03-84 1-03-84 1-04-84 l l-15-84 1-16-84 1-16-84 1-15-84 1-16-84 1-15-84 to to to to to to l

1-16-84 1-17-84 1-16-84 1-16-84 1-16-84 1-16-84 PEBRUARY 2-06-84 2-05-84 2-06-84 2-05-84 2-05-84 2-06-84 to to to to to to 2-07-84 2-06-84 2-07-84 2-06-84 2-06-84 2-07-84 2-20-84 2-21-84 2-21-84 2-21-84 2-21-84 2-20-84 to to to to to to 2-21-84 2-22-84 2-22-84 2-22-04 2-22-84 2-21-84 MARCH 3-05-84 3-04-84 3-03-84 3-04-84 3-04-84 3-05-64 to to to to to to y 3-05-84 3-06-84 3-06-84 3-05-84 3-05-84 3-05-84 03 3-19-84 3-18-84 3-18-84 3-18-84 3-18-84 3-19-64 to to to to to to 3-20-84 3-19-84 3-19-84 3-19-84 3-19-84 3-20-84 APRIL 4-02-84 4-01-84 4-01-84 4-01-84 4-01-84 4-02-84 to to to to to to 4-03-84 4-02-84 4-02-84 4-02-84 4-02-84 4-03-84 4-16-84 4-15-84 4-15-84 4-15-84 4-15-84 4-16-84 to to to to to to 4-17-84 4-16-84 4-16-84 4-16-84 4-16-84 4-17-84 MAY 5-06-84 5-07-84 5-07-84 5-07-84 5-07-84 5-06-84 to to to to to to 5-08-84 5-08-84 5-08-84 5-08-84 5-08-84 5-07-84 5-20-d4 5-21-84 5-21-84 5-21-84 5-21-84 5-20-84 to to to to to to 5-21 8a 5-22-84 5-22-84 5-22-84 5-22-84 5-21-84 JUNE 6-03-84 6-04-84 6-04-84 6-04-84 6-04-84 6-03-84 to to to to to to 6-04-84 6-05-84 6-05-84 6-05-84 6-05-84 6-04-84 6-17-84 6-18-84 6-18-84 6-18-84 6-18-84 6-17-84 to to to to to to 6-18 84 6-19-84 6-19-84 6-19-64 6-19-84 6-18-84 d

M M M M M M M M M M M TABLE C-13 (Cont'd) 1984 SAMPLING DATES FOR MILK SAMPLES STATION NO.

MONTH 13E3 2P4 5F2 14F1 15F1 3GI JULY 7-09-84 7-08-84 7-0S-84 7-08-84 7-08-84 7 iss-c 4 to to to to to ev 7-10-84 7-09-84 7-09-84 7-09-84 7-09-84 ,/-su-84 7-23-84 7-22-84 7-22-84 7-22-84 7-22-84 ' 7,23-84 to to to to to to 7-24-84 7-23-84 7-23-84 7-23-84 7-23-84 7-24-84 AucuST 8-06-84 8-05-84 8-05-84 8-05-84 8-05-84 8-06-84 to to to to to to 8-07-84 8-06-84 8-06-84 8-06-84 8-06-84 8-07-84 8-20-84 8-19-84 8-19-84 8-19-84 8-19-84 6-20-84 to to to to to to 8-21-84 8-20-84 8-20-84 8-20-84 8-20-84 8-21-84

' SEPTEMBER 9-03-84 9-04-84 9-04-84 9-04-84 9-04-84 9-03-84

-J to to to to to to u) 9-04-84 9-05-84 9-05-84 9-05-84 9-05-84 9-04-84 9-17-S4 9-16-84 9-16-84 9-16-84 9-16-84 9-17-84 to to to to to to 9-18-84 9-17-84 9-17-84 9-17-84 9-17-84 9-18-84 OCTOBER 10-09-84 10-08-84 10-08-84 10-08-84 10-08-84 10-09-84 to to to to to to 10-10-84 10-09-84 10-09-84 10-09-84 10-09-84 10-10-84 l

10-21-34 10-22-84 10-22-84 10-22-84 10-22-84 10-21-84 to to to to to to 10-22-84 10-23-84 10-23-84 10-23-84 10-23-84 10-22-84 NOVEMBER 11-04-34 11-03-84 11-03-84 11-03-84 11-03-84 11-04-84 to to to to to to 11-05-84 11-05-84 11-04-84 11-04-84 11-04-84 11-05-84 11-18-34 11-19-84 11-19-84 11-19-84 11-19-84 11-16-84 '

l to to to to to to 11-19 .J4 11-20-84 11-20-84 11-20-84 11-20-84 11-19-84 DECEMBER 12-02-84 12-03-84 12-03-84. 12-03-84 12-03-84 12-02-84 to to to to to to 12-03-84 12-04-84 12-04-84 12-04-84 12-04-84 12-03-84 12-18-84 12-17-84 12-17-84 12-17-84 12-17-84 12-16-84 to to to to to to 12-19-84 12-18-84 12-18-84 12-18-84 12-18-84 12-18-84

l .

TABLE C-14 1984 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, POTASSIUM-40 AND TRITIUM IN WELL WATER )

Results in Units of pCi/L i 2 sigma STATION NO.

RADIOACTIVITY 1-09-84 2-06-84 3-12-84 4-09-84 5-14-84 6-11-84 i

SA-WWA-2S3 l Alpha <1.1 <0.8 <1.1 <1.6 <1.4 <1.2 Beta 6.310.9 6.210.9 6.411.0 8.811.0 8.311.2 7.311.0 K-40 7.510.6 6.110.6 7.010.7 8.5!0.8 12 1 7.310.7 H-3 <130 <130 <130 <130 <130 <130 m SA-WWA-SD1 O

Alpha <1.1 <0.9(1) <1.1 <1.7 <1.2 <1.2 Beta 1411 1411 12 1 1211 1211 14 1 K-40 1311 1421 1311 13 1 1321 1311 H-3 <130 <130 <130 <130 <130 <130 SA-WWA-3El (Control)

Alpha <1.0 <1.0 <1.1 <1.7 <1.3 <1.3 Beta 8.6!1.0 8.311.0 8.811.1 8.711.0 6.011.1 10 1 K-40 9.3 0.9 9.310.9 8.810.9 8.7 0.9 8.920.9 8.8!0.9 H-3 <130 <130 <130 <130 <130 <130 M M M M M M M M M M M M M M M M M L __ ___ ..

M M M M M M M M M TABLE C-14 (cont'd) 1984 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, POTASSIUM-40 AND TRITIUM IN WELL WATER Results in Units of pCi/L 2 2 sigma STATION NO.

RADIOACTIVITY 7-16-84 8-13-84 9-10-84 10-15-84 11-13-84 12-10-84 AVEHAGE SA-WWA-2S3 Alpha <1.4 1.411.2 2.0 1.5 1.621.0(2) <1.2 1.1 0.9 -

Beta 4.710.8 2.910.7 7.711.0 1712 1311 5.320.9 7.827.6 K-40 3.7 0.4 2.810.3 7.4 0.7 1922 12 1 5.310.5 8.2 8.8 H-3 <133 <130 <140 <130 <140 <130 -

$ SA-WWA-5D1 Alpha <1.5 <1.5 <1.7 0.910.8 <1.1 1.4 1.0 -

Beta 13 1 1411 12 1 12!1 1411 1311 1312 K-40 6.410.6 28 3 14 1 14 1 13 1 1311 14210 H-3 <140 <140 <130 <140 <130 <140 -

SA-WWA-3El (Control)

Alpha <1.4 <1.5 <1.9 <0.6 <1.4 <1.1 -

Beta 9.611.1 8.211.0 8.3!1.' 8.111.0 8.3 1.0 8.5 1.0 8.4 1 . ')

K-40 5.520.6 7.810.8 7.6+0.8 9.1 0.9 8.510.8 8.3!0.8 8.422.1 H-3 <130 <140 <140 <130 <130 <140 -

(1) Station SA-WWA-SD1 was collected on 2-07-84.

(2) Station SA-WWA-2S3 was collected on 10-16-84.

i

TABLE C-15 1984 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND GAMMA EMITTERS ** {

l IN QUARTERLY COMPOSITES OF WELL WATER l

Results in Units of pCi/L i 2 sigma i

1-09-84 4-09-84 7-16-84 10-15-84 STATION NUMBER to to to to RADIOACTIVITY 3-12-84 6-11-84 9-10-84 12-10-84 SA-WWA-2S3 Sr-89 <0.5 <0.5 0.9 0.4 <0.4(1)

Sr-90 <0.5 <0.4 <0.5 <0.4 K-40 11 6 12 5 <9.4 14 6

! m Ra-226 <l.0 2.1 0.5 <6.8 <l.2 1

i SA-WWA-5D1 Sr-89 <0.5 <0.5 <0.6 <0.5 Sr-90 <0.4 <0.4 <0.4 <0.4 K-40 <8.4 12!6 1416 12!6 l Ra-226 1.2 0.6 <l.4 <l.4 0.610.4 SA-WWA-3El l (Control) l Sr-89 <0.5 <0.5 <0.6 <0.4 Sr-90 <0.4 <0.4 <0.4 <0.4 K-40 <8.6 <9.9 <9.0 6.324.1 Ra-226 <0.8 <l.3 1.320.7 <0.7

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

• • All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-31.

(1) Collection period for station SA-WWA-2S3 was 10-16-84 to 12-10-84.

1 1

1

M M M M l

TABLE C-16 1984 CONCENTRA110NS OF GROSS ALPHA AND GROSS BETA EMITTERS, POTASSIUM-40 AND TRITIUM IN RAW AND TREATED POTABLE WATER STATION NO. SA-PWR/T-2F3 Results in Units of pCi/L i 2 sigma RADIOACTIVITY JANUARY FEBRUARY MARCH APRIL MAY JUNE Alpha (Raw) <l.2 3.3tl.6 <2.0 <l.4 <1.7 1.921.6 (Treated) <1.2 <l.1 <l.6 1.311.0 1.621.2 <l.5 Beta (Raw) 3.8i0.7 2.320.7 3.020.6 3.5t0.7 3.110.7 3.020.7 (Treated) 3.4 0.7 2.420.7 2.520.6 2.120.6 2.520.6 2.620.7 K-40 (Raw) 2.020.2 1.510.2 1.420.1 1.520.2 1.720.2 1.920.2

, (Treated) 2.020.2 1.520.2 1.420.1 1.420.1 1.420.1 1.820.2 LD H-3 (Raw) <130 <130 <130 (130 <130 <130 (Treated) <140 <130 <130 250280 <120 140280 ~

RADIOACTIVITY JULY AUGUST SEPTEMBER OC'IOBER NOVEMBER DECEMBER AVERAGE Alpha (Raw) 4.St2.5 <2.6 2.221.6 <l.4 1.521.2 1.220.8 -

(Treated) 1.421.2 <l.9 1.010.7 <l.2 <l.0 <0.9 -

Beta (Raw) 2.920.7 2.220.7 1.910.6 2.420.6 2.120.6 1.Sio.7 2.621.4 (Treated) 2.520.7 1.720.6 1.820.6 2.620.6 2.120.6 2.720.8 2.410.9 K-40 (Raw) 1.620.2 1.1 0.1 1.420.1 1.220.1 1.420.1 1.420.1 1.510.5 (Treated) 1.620.2 1.320.1 1.520.2 1.420.1 1.520.1 1.6t0.2 1.520.4 H-3 (Raw) <130 <130 <140 140280 <140 <140 -

(Treated) <140 <130 <140 160180 <140 <140 -

i TABLE C-17 1984 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND GAMMA EMITTERS **

IN QUARTERLY COMPOSITES OF POTABLE WATER Results in Units of pCi/L i 2 sigma 1-01-84 4-01-84 7-01-84 10-01-84 STATION NUMBER to to to to RADIOACTIVITY 3-31-84 6-30-84 9-30-84 12-31-84 SA-PWR-2F3 (Raw)

Sr-89 <0.7 <0.7 <0.9 <0.4 Sr-90 <0.6 <0.6 <0.8 0.310.1 co

" K-40 <9.8 <9.1 <7.7 <5.9 SA-PWT-2F3 (Treated)

Sr-89 <0.8 <0.7 <0.6 <0.4 Sr-90 <0.7 <0.6 <0.5 <0.3 K-40 <8.9 7.4 3.0 <8.5 <7.0

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

• • All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-31.

l M M M - M M M l 1

c____ _.

M M M M TABLE C-18 1984 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND GAMMA EMITTERS ** IN VEGETABLES Results in Units of pCi/kg (wet)

• 2 sigma COLLECTION STATION NO. DATE(S) SAMPLE TYPE Sr-89 Sr-90 K-40 Ra-226 Th-232 SA-FPV-SD1 8-01-84 Corn < 6.2 < 3.7 24002290 <28 <81 SA-FPV-5D1 8-01-84 Tomatoes < 3.5 3.320.9 1800255 < 2.9 s 6.6 SA-FPV-2El 5-13-84 Asparagus < 4.1 < 3.0 2200277 < 4.0 <ll SA-FPL-lF3 8-01-84 Cab 5 age < 8.3 2112 22002120 <11 <20 SA-FPV-lF3 8-01-84 Peppers < 3.2 < 1.8 1700t190 <25 <42 SA-FPV-4F1 8-01-84 Peppers < 3.4 < 1.8 19002250 <30 <51 m SA-FPL-4F1 8-01-84 Cabbage < 9.9 3223 27001130 < 9.1 1629 SA-FPV-5F1 8-13-84 Tomatoes < 2.8 < l.9 1900256 < l.0 < 6.5 SA-FPV-14F3 8-01-84 Corn < 8.3 < 5.0 2600t280 <36 <60 SA-FPV-14F3 7-31 & 8-1-84 Tomatoes < 2.8 2.720.7 2000261 < 1.1 < 6. 4 SA-FPV-lGl (C) 8-01-84 Corn <20 1215 30002340 <44 <64 SA-PPV-lGl(C) 7-31 & 8-1-84 Peppers < 3.8 2.721.0 1800:210 <17 <47 SA-FPV-lGl(C) 7-31-84 Tomatoes < 2.9 1.820.7 1700243 <13 < 4.8 S A-FPV-3H5 (C) 8-01-84 Tomatoes < 4.1 < 2.4 2000254 < 3.0 < 5. 2 SA-FPV-3H5(C) 8-02-84 Corn <10 < 6.1 27002290 <41 <73 SA-FPV-3H5(C) 8-01-84 Peppers < 3.9 < 2.2 1700:210 49222 <55 SA-FPL-3H5(C) 8-01-84 Cabbage < 7.0 1122 1900297 <11 <17 AVERAGE - -

21002800 - -

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

• • All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-31.

(C) Control station

TABLE C-19 1984 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND GAMMA EMITTERS **

IN GAME, MEAT AND BOVINE THYROID Results in Units of Results in Units of pCi/kg (dry) t 2 sigma pCi/kg (wet) 2 sigma COLLECTION STATION NO. DATE(S) SAMPLE TYPE Sr-89 Sr-90 K-40 Cs-137 Ra-226 SA-GAM-llD1 1-27-84 Muskrat <100 290233 24002140 5.622.8 <9.6 (Control)

SA-GAM-3E1 1/12-16/84 Muskrat <160 810 46 30002180 <7.7 <14 SA-FPB-3E1 2-13-84 Beef (1) (1) 25002150 <6.7 9.3 5.7 S.'. -THB-3E1 2-13-84 Bovine inyroid (1) (1) 12002480 <39 <96 AVERAGE Muskrat -

5502740 27002850 - -

Beef - -

2510tl50 - -

Bovine Thyroid - -

12002480 - -

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

• • All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-31.

(1) Strontium-89 and -90 analysis not required. l l

l E -

E E E E E M M M

TABLE C-20 1984 CONCENTRATIONS OF GAMMA EMITTERS

• IN FODDER CROPS Results in Units of pCi/kg (wet) 1 2 sigma COLLECTION l STATION NO. DATE(S) SAMPLE TYPE Be-7 K-40 Ra-226 Th-232 ;

l SA-FPG-3E1 10-15-84 Soybean <130 130001530 <280 <69 l SA-VGT-2F4 9-04-84 Corn Silage 380!79 2300!200 <180 <37 SA-VGT-2F4 9-17-84 Sudex Hay 400160 3900 210 <14 <35 SA-VGT-5F2 10/06-07/84 Corn Silage 410192 2900 200 <15 <38 SA-VGT-14F1 9-05-84 Green Chop 310 79 2000 170 <140 <35 SA-VGT-15F1 9-04-84 Green Chop 260 67 4200 240 <18 <38 SA-VGT-15F1 9-08-84 Hay 1400 190 9000:480 41!24 <88 1

I SA-FPG-15F1 10-22-84 Soybean <180 130001580 <46 95156 SA-VCT-3G1(c) 9-04-84 Green Chop 260!59 27002170 <97 <27 SA-FPG-3G1(C) 10-21-84 Soybean <160 14000!640 <44 <92 AVERAGE 390 740 6700!10000 - -

• All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-31.

(C) Control station

TABLE C-21 1984 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN SURFACE WATER Results in Units of pCi/L

• 2 sigma STATION NO. 1----84(1) 2-16-84 3-06-84 4-10-84 5-11-84 6-05-84 SA-SWA-llAl -

<2.3 <l.7 <l.7 4.822.7 <3.1 SA-SWA-12Cl -

6.623.8 4.422.8 <l.6 <2.1 <3.6 (Control)

SA-SWA-7El -

<3.1 1.6tl.3 <l.4 <l.8 <2.9 SA-SWA-lF2 -

<2.3 2.821.6 <l.7 <1.5 <2.5 SA-SWA-16F1 -

<3.9 3.622.3 5.242.7 <l.9 <2.0 AVERAGE - -

2.822.4 - - -

co

<n STATION NO. 7-12-84 8-06-84 9-07-84 10-10-84 11-06-84 12-03-84 SA-SWA-llAl <3.0 1.711.3 4.222.1 <l.6 <2.1 < 3. 5 SA-SWA-12C1 <2.6 3.422.4 7.023.6 <l.3 <2.9 4.922.6 (Control)

SA-SWA-7El <2.2 2.121.3 <2.1 <1.8 <l.8 <3.4 SA-SWA-lF2 <2.6 <l.6 <2.1 <1.4 <2.1 2.221.6 SA-SWA-16F1 <2.8 <1.7 <3.6 2.121.5 <2.3 4.023.0 AVERAGE -

2.121.3 - -

Grand Average 3.622.0 (1) Unable to collect January sample due to icing conditions on the river.

M M M M M

M M M M M TABLE C-22 1984 CONCENTRATIONS OF GROSS BETA EMITTERS IN SURFACE WATER Results in Units of pCi/L t 2 sigma STATION NO. 1----84(1) 2-16-84 3-06-84 4-10-84 5-11-84 6-05-84 SA-SWA-llAl -

5026 1423 1122 1423 1223 SA-SWA-12Cl -

4925 18t3 9.222.3 6.322.4 4.322.0 (Control)

SA-SWA-7El -

4626 3525 2524 1824 8.322.4 SA-SWA-lF2 -

2224 6.222.4 5.321.9 3.622.2 3.221.9 SA-SWA-16F1 -

2424 6.622.4 8.8t2.3 <3.0 3.721.9 AVERAGE -

38228 16t24 12115 9.0213 6.327.5 co STATION NO. 7-12-84 8-06-84 9-07-84 10-10-84 11-06-84 12-03-84 AVERAGE SA-SWA-llAl 1223 2224 9829 74210 110t10 110110 48t84 SA-SWA-12C1 7.0 2.2 3025 6427 5828 8829 7328 37261 (Control)

SA-SWA-7El 32t4 3825 98210 104212 140212 84210 57285 SA-SWA-lF2 3.821.9 9.922.9 4326 5828 6627 5226 25250 SA-SWA-16F1 4.421.9 1924 4826 5428 8128 7228 29258 AVERAGE 12223 24221 70153 70241 97258 78242 Grand Average 39271 (1) Unable to collect January sample due to icing conditions on the river.

TABLE C-23 1984 CONCENTRATIONS OF TRITIUM IN SURFACE WATER Results in Units of pCi/L 1 2 sigma STATION NO. 1----84(1) 2-16-84 3-06-84 4-10-84 5-11-84 6-05-84 SA-SWA-llAl -

130280 150280 <130 <l30 <120 SA-SWA-12Cl -

<130 <130 <130 <l30 <140 (Control)

SA-SWA-7El -

<130 <130 <130 <130 <130 SA-SWA-1F2 -

<130 <130 <130 190280 <130 o

O SA-SWA-16F1 -

<130 <130 <130 <120 <140 STATION NO. 7-12-84 8-06-84 9-07-84 10-10-84 11-06-84 12-03-84 SA-SWA-llAl <140 160280 <130 140200 <130 180280 SA-SWA-12C1 140280 <140 130280 <130 <140 <140 (Control)

SA-SWA-7El <130 130280 <l30 <140 <130 <130 SA-SWA-lF2 250280 <140 150t80 <140 <130 <130 SA-SWA-16F1 <140 <140 <140 <130 <130 <140 1

(1) Unable to collect January sample due to icing conditions on the river.

M M M M

M M M M M M M M M TABLE C-24 1984 CONCENTRATIONS OF STRONTIUM-89* AND -90 IN SURFACE WATER Results in Units of pCi/L 2 2 sigma 2-16-84** 4-10-84 7-12-84 10-10-84 STATION NO. to to to to 3-06-84 6-05-84 9-07-84 12-03-84 Sr-89 Sr-90 Cr-89 St-90 Sr-89 Sr-90 Sr-89 Sr-90 SA-SWA-11A1 <0.9 <0.6 <0.6 <0.5 <l.2 <0.5 <0.5 <0.4 SA-SWA-12Cl <1.0 <0.7 < 0. 6 <0.5 <l.4 <0.6 <0.6 <0.5 (Control) e H

SA-SWA-7El <0.8 <0.6 <0.6 <0.4 <0.8 <0.4 < 0. 5 < 0. 4 SA-SWA-lF2 <0.6 <0.5 <0.6 <0.5 <0.8 <0.5 <0.5 <0.4 SA-SWA-16F1 <0.6 <0.5 <0.6 <0.5 1.320.4 <0.5 <0.6 < 0. 5

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

• • Unable to collect January sample due to icing conditions on the river.

I TABLE C-25 1984 CONCENTRATIONS OF GAMMA EMITTERS

• IN SUHFACE WATER Results in Units of pC1/L 2 2 sigma STATION NO. NUCLIDE 1----84(II 2 16-84 3-06-84 4-10-84 5-11-84 6-05-84 53t8 2126 11t5 1416 1425 SA-SWA-llAl K-40 -

<0.5 <0.5 Mn-54 - <0.6 <0.5 0.7t0.3

<0.6 <0.6 <0.6 <0.8 <0.7 Co-60 -

<0.6 <0.5 Cs-137 - <0.6 <0.5 <0.5 La-140 - <2.9 <1.4 <0.9 <0.9 <1.3 Ra-226 - :11 <1.0 <1.0 <1.0 <1.0

<l.8 <l.9 2.121.1 <2.4 1.420.8 Th-232 -

K-40 - 3928 1627 <8.1 <7.1 <8.8 SA-SWA-12Cl <0.5 <0.5 <0.4 (Control) Mn-54 - <0.5 <0.6 Co-60 - <0.6 <0.6 <0.6 <0.5 <0.7

<0.6 <0.3 <0.4 <0.5 <0.4 Cs- 13 7 -

<1.1 La-140 - <1.2 <0.8 <1.4 <0.6 Ra-226 - <1.2 1.310.6 <l.2 <0.8 <8.2

<1.9 <1.9 1.921.0 <1.7 <2.3 Th-232 -

K-40 8829 4719 2827 20t6 <9.3 SA-SWA 'El -

<0.5 <0.6 <0.3 <0.5 Mn-54 - <0.6 y)

Co-60 - <0.7 0.6*0.4 <0.7 <0.5 <0.6 g3 Cs-137 - <0.6 <0.6 <0.4 <0.5 <0.3 La-140 - <2.1 <2.3 <1.3 <0.5 <1.7 Ra-226 - <13 0.910.6 <1.0 <1.1 <l.2 Th-232 - <3.1 <1.6 <2.4 <1.7 <1.7 K-40 - 3117 <8.3 <6.7 <10 <9.6 SL-SWA-1F2 <0.4 <0.6 <0.4 Mn-54 - <0.4 <0.4

<0.7 <0.2 <0.5 <0.8 <0.5 Co-60 -

Cs-137 - <0.4 <0.5 <0.5 <0.6 <0.4 La-140 - <1.1 <2.1 <l.6 <1.0 <0.6

<9.1 <0.9 1.110.6 <l.2 <8.2 Ra-226 -

<2.3 <2.2 Th-232 - <2.3 <1.3 <l.6 K-40 - 2317 <ll 9.725.4 <8.7 <10 SA-SWA-16F1 Mn-54 - <0.7 <0.5 <0.5 <0.4 <0.6 Co-60 - <0.7 <0.5 <0.6 <0.7 <0.4 Cs-137 - <0.9 <0.6 <0.5 <0.4 <0.6

<3.2 <1.0 <1.2 <0.3 <1.7 La-140 -

<1.0 <1.1 Ra-226 - <l.2 <l.1 0.820.4 Th-232 - <2.4 <2.2 0.920.6 <2.0 <2.0 AVERAGE K-40 - 47251 21 31 13:17 - -

I m m m m m m m m m

M M M M M M M TABLE C-25 (cont'd) 1984 CONCENTRATIONS OF GAMMA EMITTERS

• IN SURFACE WATER Results in Units of pC1/L t 2 sigma STATION NO. NUCLIDE 7-12-84 8-06-84 9-07-84 10-10-84 11-06-84 12-03-84 AVERAGE SA-SWA-llAl K-40 1924 4716 8719 130210 120211 120112 58296 Mn-54 <0.5 <0.5 <0.3 <0.4 <0.5 <0.6 -

Co-60 <0.6 <0.6 <0.3 <0.7 <0.8 <0.4 -

Cs-137 <0.5 <0.5 <0.6 <0.6 <0.7 <0.5 -

La-140 <0.7 <1.3 1.210.6 <0.4 <l.0 <1.4 -

Ra-226 <0.5 <0,5 <8.6 <9.0 1.220.7 <l.3 -

Th-232 <1.9 <l.9 <2.3 <l.9 <2.8 <2.2 - l l

SA-SWA-12Cl K-40 <10 2917 65t9 8229 110110 7629 41273 (Control) Mn-54 <0.. <0.6 <0.6 <0.6 <0.5 <0.5 -

Co-60 <0.4 <0.9 <0.5 <0.9 <0.7 <0.7 -

Cs-137 <0.5 <0.6 0.520.3 <0.6 <0.5 <0.5 -

La-140 <l.2 <l.0 <l.1 <l.2 <l.3 <0.8 -

Ra-226 <l.3 <l2 <9.8 <l.3 1.020.4 <1.3 -

Th-232 <1.5 <3.0 <2.0 <2.0 1.220.7 <l.9 -

SA-SWA-7El K-40 4226 5629 110110 81210 140212 130t9 68189 y) Mn-54 <0.5 <0.6 <0.6 <0.6 <0.4 <0.5 -

La Co-60 <0.7 <0.6 <0.7 <0.5 <0.7 <0.6 -

Cs-137 <0.5 <0.5 <0.6 <0.5 <0.3 <0.4 -

La-140 <l.3 <l.1 <0.4 <l.1 <0.9 <0.7 -

Ra-226 <0.5 <l.2 <l.2 <l.1 1.520.7 <0.5 -

Th-232 <l.9 <t.0 <2.0 <2.3 <2.0 <l.6 -

SA-SWA-lF2 K-40 <9.5 21 5 5823 86210 8619 5918 35163 Mn-54 <0.4 <0.6 <0.3 <0.5 <0.3 <0.5 -

Co-60 <0.6 <0.6 <0.6 <0.7 <0.2 <0.7 -

Cs-137 (0.5 <0.5 <0.4 <0.5 <0.6 <0.5 -

La-140 <0.8 <1.1 <0.9 <l.3 <l.2 <0.7 -

Ra-226 <1.2 <0.5 <1.2 <1.0 <l.1 <l.0 -

Th-232 2.111.3 <1.9 <l.9 <l.9 2.021.2 <l.9 -

SA-SWA-16F1 K-40 <!2 2427 55t8 84110 84210 7917 3(t65 I

Mn-54 <0.5 <0.5 <0.5 <0.6 <0.4 <0.5 -

co-60 <0.5 <0.6 <0.7 <0.7 <0.6 <0.6 -

Cs-137 <0.8 <0.5 <0.5 <0.5 <0.6 <0.4 -

La-140 <1.0 <0.9 <l.1 <1.0 <l.0 <0.6 -

l Ra-226 <l.4 <1.1 <1.0 0.6to.3 <l.0 <0.5 -

Th-232 (2.2 (2.2 <!.9 <l.9 <l.8 <l.6 -

AVERAGE K-40 - 35231 75246 93142 108:47 93261 l

Grand Average K-40 48180

• All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-II.

(1) Unable to collect January sample due to icing conditions on the river.

TABLE C-26 1984 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND TRITIUM IN EDIBLE FISII TRITIUM (FLESH)**

STRONTIUM (DONES) AQUEOUS FRACTION ORGANIC FRACTION pCi/kg (dry) t 2 sigma pCi/kg (wet) 2 2 sigma STATION NO. COLLECTION PERIOD Sr-89 Sr-90 11 - 3 11 - 3 SA-ESF-llAl 6-04-84 to 6-11-84 <190 730257 <50 <100 9-04-84 to 10-29-84 <67 210:20 4002100 <50

, SA-ESF-12C1 6-08-84 to 6-25-84 <140 1000250 <50 <100 A (Control) 9-89-84 to 10-18-84 <120 230231 3002100 120250 SA-ESF-7El 6-21-84 to 6-22-84 <54 <38 <50 <100 l

9-09-84 to 10-18-84 <41 62210 400t100 <50 AVERAGE -

3802790 - -

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

• • Tritium results by Controls for Environmental Pollution, Inc.

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M M M M M M M M TAELE C-27 1984 CONCENTRATIONS OF GAMMA EMITTERS

• IN EDIBLE FISH Results in Units of pCi/kg (wet) ! 2 sigma STATION NO. COLLECTION PERIOD K-40 Cs-137 SA-ESF-11A1 06-04-84 to 06-11-84 2600!220 1618 09-04-84 to 10-29-84 12001110 < 6.2

• SA-ESF-12C1 06-08-84 to 06-25-84 24002240 <13 (Control) 09-09-84 to 10-18-84 1400 110 < 6.6 l SA-ESF-7El 06-21-84 to 06-22-84 33001230 <14 09-09-84 to 10-18-84 3300!230 <13 AVERAGE 240021800 -

• All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-31.

TABLE C-28 1984 CONCENTRATIONS OF STRONTIUM-89* AND -90, GAMMA EMITTERS ** AND TRITIUM IN BLUE CRABS l

Results in Unitr. of pCi/kg (wet)

• 2 sigma COLLECTION AQUEDUS FRACTION STATION NO. PERIOD SAMPLE St-89 Sr-90 K-40 Co-60 H-3***

SA-ECH-llAl 6/18-19/84 Flesh <57 <26 21001340 <28 <50 Shell(l) <110 620140 (2) (2) (2) 10/25-26/84 Flesh <46 <28 23002230 24tl2 600t300 Shell III <89 580229 (2) (2) (2) e o

SA-ECH-12Cl 6/18-19/84 Flesh <59 <28 19002300 <27 <50 (Control) Shell(l) <120 860246 (2) (2) (2) 10/22-23/84 Flesh <49 <28 20002200 <16 3001100 Shell(l) <88 390227 (2) (2) (2)

AVERAGE Flesh - -

21002340 - -

Shell -

6101390 - - -

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

• • All other gamma emitters searched for were < LID; typical LLDs are given in Table C-31.

• • • Tritium results by Controls for Environmental Pollution, Inc.

(1) Strontium results in units of pCi/kg (dry).

(2) Gamma and tritium analysis not required.

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M M M M TABLE C-29 1984 CONCENTRATIONS OF SR-89* AND -90 AND GAMMA EMITTERS ** I ti BENTHIC ORGANISMS Results in Units of pCi/kg (dry) i 2 signa COLLECTION STATION NO. DAT3 Sr-89 Sr-90 Ra-226 SA-ESB-llAl 5-21-84 <7900 <5100 <43000 10-17-84 <9400 <5600 23000114000 SA-ESB-12Cl 5-21-84 <2600 <1800 <24000

• (Control) 10-17-84 <13000 <8000 <42000 SA-ESB-7El 5-21-84 <3400 <2100 <51000 10-17-84 <7800 <4600 <40000 SA-ESB-16F1 5-21-84 <8800 <6000 <66000 10-17-84 <14000 <8700 <47000 NOTE: Analyses performed on benthic organisms have extremely high uncertainties and sensitivities due to the unavailability of an adequate sample.

Sample sizes ranged from approximately 0.1 grams to 0.25 grams dry.

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

• • All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-31.

TABLE C-30 1984 CONCENTRATIONS OF STRONTIUM-90 AND GAMMA EMITTERS

• IN SEDIMENT **

Results in Units of pC1/kg (dry) t 2 sigma STATION NO. Co-58 Co-60 Cs '.27 Ra-226 Th-232 DATE St-90 Be-7 K-40 Mn-54 SA-ESS-IIAI

<32 13002220 150002600 87222 300230 520t29 180230 8902370 750:100 5-21-84

<22 <1(3 470nt300 <17 73t15 180216 <20 4301210 340253 10-17-84 SA-ESS-12Cl (Control)

<30 s230 12000:490 25tl5 <29 40114 32217 1200:320 770282 5-21-84

<21 <160 14000:530 <22 <22 <32 19 11 7901240 920272 10-17-84 CD SA-ESS-7El 5-21-84 <39 <!80 1000ut450 22:13 <26 53120 35 19 1300:300 980281

<19 <160 11000 470 <20 (22 22 13 26210 9801210 520259 10-17-84 SA-ESS-16PI

<35 3301200 15000:590 <31 <30 69t18 150224 9102360 960t92 5-21-84

<25 1000:140 150001520 32:18 100220 260221 150123 7901310 900282 10-17-84 AVERAGE - - 1200027100 - -

150:340 762140 9102530 7701460

• All other gamma emitters searched for were <LLD* typical LLDs are given in Table C-31.

• • Sediment samples which include benthic organisms constitute t hs benthos sample.

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--_.A---h - - - + . - - - - * -a-4-a4 h------h----A -h--- - ----A- - - - - - - - - - - - - - + - - - - - - - - - -*-4 - - - - - - ~ + - - --- -- - - - ' - - - -- ~~~ -

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TABLE C-31 l

1984 PSE6G HESEARCH COHPOHATION LLDa FOR GAMMA SPECTROMETHY I .

I AIR WELL/ POTABLE FOOD MEAT AND FODDER PRECIPITATION MILK WATER PRODUCTS GAME CHOPS

, PARTCULATgS (pCi/kg-wetI (pC1/kg-wet) (pci/kg-wet 1 NUCLIDES (10~ pC1/m ) (PC1/L) (PC1/L) (PC1/L) i GEOMETHY: 13 Filters 100ml 3.5 Liter 10M1 100ml 400ml 100ml 100ml 1

Be-7 3.0 4.3 14 4.0 8.0 120 43 78 l

' 0.50 1.2 15 6.0 10 Na-22 0.54 0.62 1.8

K-40 - -

Cr-51 2.6 5.2 12 4.6 9.5 140 54 100 i

i Mn-54 0.38 0.51 1.4 0.41 1.0 14 5.0 8.5 co-58 0.39 0.52 1.6 0.43 0.99 15 5.0 9.3 1 Fe-59 0.83 1.2 3.2 1.1 2.4 32 12 23 I

Co-60 0.46 0.57 2.0 0.52 1.1 16 5.5 9,4 J

1.0 3.3 0.93 2.0 31 10 17

) Zn-65 0.86 0.59 1.7 0.53 1.1 16 6.0 11 l Nb-95 0.43 L

e gr-95 0.71 1.0 3.0 0.93 2.0 28 10 19 Mo '39 12 55 20 48 51 1300 990 6800 Nu-103 0.39 0.57 1.4 0.50 1.0 16 5.7 11 Ru-106 4.0 4.9 14 4.4 10 130 47 81 A9-110m 0.67 0.82 1.5 0.72 1.6 14 8.0 14 i Sb-125 0.90 1.4 4.1 1.2 2.6 39 13 22 j Te-129m 14 22 63 19 40 620 220 410

, I-131 0.46 1.1 1.8 1.0 1.7 30 13 37 j

I Te-132 0.89 3.8 2.1 3.4 3.9 99 62 340 Cs-134 0.51 0.65 1.7 0.56 1.3 13 6.3 11 Cs-136 0.49 0.78 1.9 0.70 1.3 22 8.5 20 Cs-137 0.35 0.50 1.7 0.43 1.0 17 4.8 8.0 l Ba-140 1.6 3.0 6.2 2.7 5.0 82 33 76 La-140 0.73 1.3 2.3 1.1 2.2 J2 14 83 Ce-141 0.42 0.65 2.4 0.59 1.2 19 6.7 13 Ce-144 1.4 2.1 10 1.7 4.1 79 20 35 Ha-226 0.86 1.2 4.0 1.0 2.2 32 11 19 Th-232 1.7 2.0 6.8 i.8 3.8 54 19 33 l

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= n .

TABLE C-31 (cont'd) 1984 PSE6G RESEARCH COMPORATION LLDs DUM GAMMA SPECTROMETHY SHELLFISH SEDIMENT AIR SURFACE FISH IODINE WATER (10*3pC1/m3)

(pC1/kg-wet) (pC3/kg-wet) (pC&/kg-dry) NUCLIDES NUCLIDES (pC1/L) 100ml 400ml 100ml 400ml 100ml 100ml GEOMETRY: 100ml 92 142 85 120 I-131 15 Be-7 4.1 37 0.59 5.3 11 21 10 14 1-132 26 Na-22

- - - - I-133 39 E-40 - -

5.1 45 107 170 91 150 1-135 1.2 Cr-51 4.4 10 17 10 13 Mn-54 0.48 0.50 4.5 11 18 10 14 Co-58 1.2 10 24 41 22 36 Fe-59 5.0 11 19 11 15 Co-60 0.54 0.99 9.0 22 35 22 25 Zn-65 0.58 5.0 12 19 10 15 g Nb-95 C) 1.0 8.8 21 35 20 26 3r-95

[ O 2400 1200 530 13000 Mo-99 68 370 0.55 4.9 12 19 11 14 ku-103 4.6 42 98 160 97 120 ku-106 7.2 11 28 10 19 Ag-110m 0.79 12 27 46 27 28 Sb-125 1.3 183 480 720 430 600 Te-129m 21 1.2 9.0 30 33 18 52 1-131 18 26 170 85 49 650 Te-132 5.7 9.3 22 9 12 Cs-134 0.62 0.78 6.4 20 24 14 31 Cs-136 4.4 12 17 12 12 Cs-137 0.47 ba-140 3.0 25 71 94 51 105 11 28 41 20 52 La-140 1.3 5.6 15 22 13 17 Ce-141 0.64 n 2.0 18 57 73 56 55 Ce-144 1.1 10 23 40 23 230 ha-226 1.8 17 40 69 40 48 Th-232

- Indicates a positive concentratton was measured in all samples analyzed.

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__ - - - - - - - - _ . - _ _ _ - 4_ . _ . , _ . _m _ -.. _ m a I

APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES i

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l SYNOPSIS OF ANALYTICAL PROCEDURES Appendix D presents a synopsis of the analytical procedures utilized by various laboratories for analyzing the 1984 Artificial Island Radiological Environmental Monitoring Program samples.

TABLE OF CONTENTS LAB

• PROCEDURE DESCRIPTION PAGE GROSS ALPHA PSE&G Analysis of Air Particulates.................... 105 TI Analysis of Air Particulates.................... 107 PSE&G Analysis of Water............................... 108 GROSS BETA PSE&G Analysis of Air Particulates.................... 109 TI Analysis of Air Particulates.................... 111 PSE&G Analysis of Water............................... 112 POTASSIUM-40 PSE&G Analysis of Water............................... 113 TRITIUM PSE&G Analysis of Water............................... 114 CEP Analysis of Aqueous Fraction of Fish and Crab... 115 CEP Analysis of Organic Fraction of Fish and Crab... 116 I IODINE-131 PSE&G Analysis of Filtered Air........................ 117 TI Analysis of Filtered Air........................ 118 PSE&G Analysis of Raw Milk............................ 119 PSE&G Analysis of Bovine Thyroid...................... 121 I

103

SYNOPSIS OF ANALYTICAL PROCEDURES (cont'd)

TABLE OF CONTENTS LAB

• PROCEDURE DESCRIPTION PAGE STRONTIUM-89 AND -90 PSE&G Analysis of Air Pa r ticula tes . . . . . . . . . . . . . . . . . . . . 122 TI Analysis of Air Particulates.................... 125 PSE&G Analysis of Raw Milk............................ 127 PSE&G Analysis of Water............................... 130 PSE&G Analysis of Vegetation, Meat and Aquatic Samples 133 PSE&G Analysis of Bone and Shel1...................... 136 PSE&G Analysis of Soil and Sediment................... 139 PSE&G Analysis of Samples for Stable Strontium........ 142 GAMMA SPECTROMETRY PSE&G Analysis of Air Particulates.................... 144 TI Analysis of Air Particulates.................... 145 PSE&G Analysis of Raw Milk............................ 146 PSE&G Analysis of Water............................... 147 PSE&G Analysis of Solids (combined procedures)........ 148 ENVIRONMENTAL DOSIMETRY TI Analysis of Thermoluminescent Dosimeters........ 150

• PSE&G - PSE&G Research Correa?. on TI - Teledyne Isotopeo CEP - Controls for Ent y e uc. -al Pollution, Inc.

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SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE t GROSS ALPHA ANALYSIS OF AIR PARTICULATE SAMPLES Af ter allowing at least a three-day (extending from the sample stop date to the sample count time) period for the short-lived radionuclides to decay out, I air pa.ticulate samples are ccunted for gross alpha activity on a low back-ground gas proportional counter. Along with a set of air particulate samples, a clean air filter is included as a blank with an 241 Am air filter geometry I alpha counting standard.

The specific alpha activity is computed on the basis of total corrected air flow sampled during the collection period. This corrected air flow takes I into account the air pressure correction due to the vacuum being drawn, the correction factor of the temperature-corrected gas meter as well as the gas meter efficiency itself.

Calculation of Gross Alpha Activity:

I Air flow is corrected first by using the following equations:

P= (B-V)/29.92 P = Pressure correction factor B = Time-averaged barometric I _

pressure during sampling period, "Hg V = Time-averaged vacuum during sampling period, "Hg 29.92 = Stancard atmospheric pressure at 32*F, "Hg V= F*P*O.946*0.0283 E F = Uncorrected air flow, ft3 0.946 = Temperature correction factor j from 60*F to 32'F 0.0283 = Cubic meters per cubic foot E = Gas meter ef ficiency (= %

efficiency /100)

I V = Corrected air flow, m3 P = Presuure correction factor I Using these corrected air flows, the gross alpha activity is computed as follows:

Result (pCi/m 3) = (G-B)/T (2.2 2) * (E) * (V) G = Sample gross counts B = Background counts (from blank filter)

T = Count time of sample and blank,

. mins.

E = Fractional 241 Am counting I

efficiency V = Corrected air flow of sample, m3 2.22 = No. of dpm per pCi 105 fIl I

2-sigma error (pci/m )3 = (1.96* (G+B)1/2)

• A (G-B)

A = Gross alpha activity, pCi/m 3 G = Sample gross counts B = Background counts (from blank filter)

Calculation of lower limit of detection:

A sample activity is assumed to be LLD if the sample net count is less than 4.66 times the standard deviation of the count on the blank.

LLD(pCi/m 3) = 4.66 * (B)1/2

( 2.22) * (E) * (V) * (T)

B = Background counts (from blank filter)

E = Fractional 241 Am counting efficiency V = Corrected air flow of sample, m3 T = Count time of blank, mins.

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I SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE I ANALYSIS OF AIR PARTICULATE FILTERS FOR GROSS ALPFA AND BETA The air filter is first stored for 2 to 5 days from date of receipt to allow I

for decay of the radon-thoron daughters. It is then placed in a stainless steel planchet which has been coated in the center with rubber cement. The filter is then counted for beta activity and subsequently repeat counted for alpha activity (at a different voltage setting) in a Beckman-Sharp Wide Beta II automatic alpha-beta counter.

Gross alpha and beta activity (pCi/m 3) are computed as follows:

A= (G/T -B) t Om* ((G/T +B)/T)1/2 (2.22*V*Y*D*E) (2.22*V*Y*D*E)

Where G = Total sample counts B *- Background counts per minute l T = Sample count time, mins. l 2.22 = dpm/pCi

'I V = Sample volume, m3 Y = Chemical yield (Y = 1 in this case)

D = Decay factor from collection to count date (D = 1 in this case)

E = Counter ef ficiency om = Multiples of counting error l

If the net activity (G/T -B) is equal to or less than the counting error, then the activity is considered to be the minimum detectable level, or MDL.

I where MDL = 3* (2*B/T) l/2 (2.22*V*Y*D*E)

Variables are as previously defined I

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SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE GROSS ALPHA ANALYSIS OF WATER SAMPLES The sample is thoroughly mixed. Then, a 250ml portion of sample and an equal volume of deionized water blank are acidified with dilute sulfuric acid.

Barium carrier is added and the sample heated to 50*C in order to help precipitate barium sulfate. Maintaining the same temperature for the remainder of the procedure, iron carrier is then introduced. After a 30 minute equilibration period, the sample is neutralized with dilute ammonium hydroxide to precipitate ferric hydroxide. The mixed precipitates are then I

5 filtered onto a membrane filter, dried under an infrared heat lamp, weighed and mounted on a stainless steel planchet. The sample is then alpha-counted for 100 minutes on a low' background gas proportional counter, along with a 238 U source of the same geometry. The blank is treated in the same manner as the sample.

Calculation of Gross Alpha Activity:

Result (pCi/L) =

(G-B)/T (2.2 2) * (E) * (V) * (S)

G = Sample gross counts B = Background counts (from blank sample)

T = Count time of sample and blank l

5 E = Fractional counting ef ficiency from 238 U source V = Sample volume, liters S = Normalized efficiency regression equation as a function of thick-ness 2.22 = No. of dpm per pCi 2-sigma error (pCi/L) =

(1. 96* (G+B) 1/2) *A (G-B)

A = Gross alpha activity, pCi/L G = Sample gross counts B = Background counts (from blank sample)

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I I SYNOPSIS OF PSE&G RESEARCH CORPOPATION PROCEDURE GROSS BETA ANALYSIS OF AIR PARTICULATE SAMPLES After allowing at least a three-day (extending from the sample stop date to the sample count time) period for the short-lived radionuclides to decay out, I air particulate samples are counted for gross beta activity on a low back-ground gas proportional counter. Along with a set of air particulate samples, a clean air filter is included as a blank with an 90 Sr air filter geometry beta counting standard.

The gross beta activity is computed on the basis of total corrected air flow I sampled during the collection period. This corrected air flow takes into account the air pressure correction due to the vacuum being drawn, the correction factor of the temperature-corrected gas meter as well as the gas meter efficiency itself.

Calculation of Grv:: Beta Activity: l l

Air flow is corrected first by using the following equations:

P= (B-V) /29. 92 P = pressure correction factor D = Time-averaged barometric I pressure during sampling period, "Hg

_V = Time-averaged vacuum during sampling period, 'Hg 29.92 = Standard atmospheric pressure at 32*F, "Hg I V= F*P*0.946*0.0283 E F = Uncorrected air flow, ft3 0.946 = Temperature correction factor e

from 60*F to 32*F 0.0283 = Cubic meters per cubic foot E = Gas meter ef ficiency (= %

efficiency /100)

V = Corrected air flow, m3 P = Pressure correction factor I

Using these corrected air flows, the gross beta activity is computed as follows:

Result (pci/b 3) (G-B)/T I

=

(2.22) * (E) * (V) G = Sample gross counts B = Background counts (from blank filter)

T = Count time of sample and blank, mins.

E = Fractional 90 Sr counting I efficiency V = Corrected air flow of sample, m3 2.22 = No. of dpm per pCi 109 11

I 2-sigma error (pci/m )3 = (1. 96* (G+B) l/2) *A (G-B)

A = Gross beta activity, pCi/m3 G = Sample gross counts B = Background counts (from blank filter)

Calculation of lower limit of detection:

A sample activity is assumed to be LLD if the sample net count is less than 4.66 times the standard deviation of the count on the blank.

LLD(pCi/m 3) = 4.66 * (B)l/2

( 2.22) * (E) * (V) * (T)

B = Background counts (from blank filter)

E = Fractional 90 Sr counting efficiency V = Corrected air flow of sample, m3 T = Count time of blank, mins.

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SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE ANALYSIS OF AIR PARTICULATE FILTERS FOR GROSS ALPIIA AND BETA h e air filter is first stored for 2 to 5 days from date of receipt to allow I for decay of the radon-thoron. daughters. It is then placed in a stainless steel planchet which has been coated in the center with rubber cement. We filter is then counted for beta activity and subsequently repeat counted for alpha activity (at a different voltage setting) in a Beckman-Sharp Wide Beta II automatic alpha-beta counter.

Gross alpha and beta activity (pCi/m 3) are computed as follows:

A= (G/T -B) t Um* ((G/T +B)/T)1/2

( 2. 2 2*V*Y*D* E) ( 2. 2 2*V* Y*D* E)

Where G = Total sample counts i B = Background counts per minute T = Sample count time, mins.

2.22 = dpm/pCi I V = Sample volume, m3

! 3 l Y = Chemical yield (Y = 1 in this case)

D = Decay factor from collection to count date (D = 1 in this case)

E = Counter ef ficiency om = Multiples of counting error If the net activity (G/T -B) is equal to or less than the counting error, l then the activity is considered to be the minimum detectable level, or MDL.

where MDL = 3* (2*B/T) 1/2

( 2. 2 2*V*Y*D*E) l Variables are as previously defined I

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SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE GROSS BETA ANALYSIS OF WATER SAMPLES The sample is mixed thoroughly. 'Ihen, a 1.0 liter portion is removed f rom the potable, rain or well water container and 250ml taken from each surface water. A deionized water blank is prepared for each different volume of l sample (e.g.1.0 liter blank for 1.0 liter samples and 250ml for 250ml

• samples). All samples and blanks are then evaporated on a hotplate until the volume approaches 20 to 25ml. At that point, the samples and blanks are g transferred to tared stainless steel ribbed planchets and evaporated to dry- 3 ness under an infrared heat lamp. They are subsequently cooled in a desic-cator, weighed and counted on a low background gas proportional counter along with an 90 Sr source of the same geometry.

Calculation of Gross Beta Activity:

Result (pCi/L) = (G-B)/T (2.22) * (E) *V) * (S)

G = Sample gross counts g B = Background counts (from blank sample) I T = Count time of sample and blank E = Fractional counting efficiency l from 90 Sr source 5 V = Sample volume, liters S

• Normalized efficiency regression g equation as a function of thick- g ness 2.22 = No. of dpm per pCi 2-sigma error (pci/L) =

(1.9 6* (G+B) 1/2)

• A I

(G-B)

A = Gross beta activity, pCi/L G = Sample gross counts B = Background counts (from blank sample)

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SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE ANALYSIS OF WATER FOR POTASSIUM 40 Water samples (with the exception of rain water) received by the Research and Testing Laboratory are routinely analyzed for potassium by the Chemical Division. 'the results, reported in parts per million (ppm), are converted to pCi/L by means of a computer program, i Calculation of 40 K Activity:

40 K Activity (pCi/L) = 0.85*C 0.85 = Proportionality constant for converting ppm to pCi/L C = Potassium concentration, ppm

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SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE ANALYSIS OF WATER FOR TRITIUM Approximately 50ml of raw sample is mixed with sodium hydroxide and potassium permanganate and is distilled under vacuum. Eight ml of distilled sample is mixed with 10ml of InstagelO liquid scintillation solution, and placed in the liquid scintillation spectrometer for counting. An internal standard is prepared by mixing eight ml of sample, 10 ml of Instagel, and 0.1ml of a standard with known activity. Se efficiency is determined from this. Also prepared is a blank consisting of eight ml of distilled low-tritiated water and 10ml of Instagel, to be used for a background determination. This is done for each pair of samples to be counted.

Activity is computed as follows: I A (pci/L) = (G-B)*(1000) 2.2 2* (E) * (V) * (T)

A = Activity B = Background count of sample G = Gross count of sample E = Counting Efficiency V = Aliquot volume (ml)

T = Count time (min) 2.22 = DPM/pCi 1000 = Number of ml per L Ef ficiency (E) is computed as follows:

E= (N) * (D)

A' l

N = Net CPM of spikt7d sample B D = Decay factor of spike N is determined as follows:

N = C-(G/T)

C = CPM of spiked sample G = Gross counts of sample T = Count time (min) ne associated error is expressed at 95% confidence limit, as follows:

l 1.96*(G/T2+B/T2 )1/2*(1000) 2.22* (V) * (E)

Samples are designated LLD if the activity is less than the following value:

LLD (pCi/L) = ( 4. 6 6) * (B) l/2 * (1000) l

2. 2 2* (V) * (E) * (T) r 114

I I SYNOPSIS OF CONTROLS EVR ENVIRONMENTAL POLLUTION, INC., PROCEDURE TRITILH ANALYSIS OF AQUECUS FRACTION OF BIOLOGICAL MATERIALS An aliquot of fish or crab flesh is placed in a round bottom flask, along with 200 ml of benzene, and the water removed via azeotropic distillation.

Three milliliters of the extracted water is then mixed with aguasol cocktail (NEF-934 AguasofE cocktail, manufactured by New England Nuclear Corpora-tion).

ne resultant mixture is comprised of nineteen percent sample in a clear gel-type aguasol and provides a tritium counting efficiency of approximately thirty percent, when counted on a Beckman LS-100 Liquid Scintillation Spec-trometer. The efficiency of the counting system is determined by placing six I tritium standards (certified by NBS) before each set of water samples to be counted. The counting ef ficiency is determined f rom these standards which I are equal in activity but vary in the amount of quenching. All samples are counted for 500 minutes each.

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SYNOPSIS OF CONTROLS EVR ENVIRONMENTAL POLLUTION, INC., PROCEDURE TRITIUM ANALYSIS OF ORGANIC FRACTION OF BIOLOGICAL MATERI ALS An aliquot of fish or crab is first oxidized by heating in the presence of oxygen, with the off-gas passing over heated copper oxide. The resulting converted water is then mixed with aqaasol cocktail (NEF-934 Aguaso18 cock-tail, manufactured by New England Nuclear Corporation) .

The resultant mixture is comprised of nineteen percent sample in a clear g gel-type aguasol and provides a tritium counting efficiency of approximately m thirty percent when counted on a Beckman LS-100 Liquid Scintillation Spectro-meter. The of ficiency of the counting system is determined by placing six tritium standards (certified by NBS) before each set of water samples to be counted. The counting ef ficiency is determined f rom these standards which are equal in activity but vary in the an.ount of quenching. All samples are counted for 500 minutes each.

A second method, used to verify results, is the wet oxidation method using hydrogen peroxide and the same counting method as described above.

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SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE GAMMA ANALYSIS OF AIR IODINE Approximately 300m3 of air is drawn through a 50ml bed of triethylenedismine (TEDA)-impregnated charcoal granules at a rate which closely corresponds to the breathing rate of an adult male. The contents of the exposed air iodine cartridge are emptied into an aluminum sample can containing 50ml of fresh TEDA-impregnated charcoal. The can is hermetically sealed and then counted on a gamma detector.

Calculation of Gamma Activity:

The following are the calculations performed for the gamma activity, 2-sigma error and LLD:

Result (pci/m 3) = NaD =R (2.22) * (E) * ( A) * (T) * (V)

N = Net counts under photopeak D = Decay correction factor At1*EXP(At2) 1-EXP(-Atl) t1 = Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition A = 0.693/nuclide half life E = Detector efficiency A = Gamma abundance factor (no. of photons per disintegration)

T = Acquisition live time, mins.

V = Sample volume, m 3 2.22 = No. of dpm per pCi I 2-sigma error (pCi/m 3) = 1.96*(GC+BC)l/2*R N

GC = Gross counts BC = Background counts All other variables are as defined earlier.

The LLD (pci/m 3) = 4.66*(GC)l/2 0 (2.22) * (E) * ( A) * (T) * (V) 117

SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE ANALYSIS OF CHARCOAL FILTERS FOR IODINE-131 Charcoal cartridges are analyzed for I-131 using a lithium-drifted germanium detector interfaced with a 2048 channel pulse height analyzer calibrated at 1.0 Kev per channel. Teledyne Isotopes employs one of three possible data acquisition and computation systems. The first, a Data General NOVA mini-computer, in series with the pulse height analyzer, calculates the number of counts (and the standard deviation) in the peak region by performing a linearly-interpolated background subtraction. If no peak is observed, then only the background is used (along with sample volume, collection date and length of count) to determine the detection limit. The activity or MDL of each nuclide is computed on an IBM 360. This semi-automatic system is in contrast with the other two data acquisition and computation systems, namely, a Tracor Northern TN-ll and a Nuclear Data 6620, which perform all the above computations automatically. All resultant spectra are stored on magnetic tape.

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SYNOPSIS OF PSE&G RESEARCH CORFCRATION PFOCEDURE ANALYSIS OF RAW MILK FOR IODINE-131 Stable iodine carrier is equilibrated in a 4-liter volume of raw milk before two separate batches of anion exchange resin are introduced to extract iodine.

The iodine is removed from the resin and converted to free iodine. The f ree iodine is then extracted into carbon tetrachloride and reduced to iodide with sodium bisulfite when back-extracted into water. Then cuprous chloride is added to precipitate cuprous iodide, which is mounted on a membrane filter, sealed in a cut-down x-ray cell, vacuum dried and counted for 120 minutes on

{

a beta-gamma coincidence system. j 1

l On the same day the above analysis is performed, a stable iodide analysis is also run, using a digital voltmeter, lodide specific ion electrode and double junction reference electrode. Using the known addition technique, fixed quantities of a dilute sodium iodide standard solution are added to 100ml of raw milk. For each addition, the millivolt reading from the meter is plotted vs. amount of stable iodine added, using Gran's plot paper. The concentration of stable iodide in the sample can be found by plotting a line through the points and extending it to the concentration axis. The chemical recovery of iodide for the radiochemical analysis is then computed on the basis of both carrier iodide and intrinsic stable iodide measured in the sample.

Calculation of 131 I Activity:

131I Results (pci/L) = (G-n)/T

' (2.2 2) * (E) * (V) * (Y) * (1.05) * (H)

G = Sample gross counts B = Dackground counts (from blank j sample)

T = Count time of sample and blank I E = E0 *EXP(-A*M) = efficiency equation where E0 = counting efficiency at zero sample thickness A = Self-absorption coefficient M = sample thickness, mg/cm2 V = Sample volume, liters I Y = Chemical recovery =

R Rl+R2 where R = mg of I~ recovered R1 = mg of I~ carrier -

added R2 = mg of intrinsic stable I" measured in sample 1.05 = Correction factor for protein-bound iodine 119

H = J/ (1-K)

• EXP (L) = correction factor for 131 I decay during counting period E

J= (0. 693/8. 0 5) * ( R/14 40) g R = Count time, minutes

' 1440 = No. of minutes per day 8.05 = Half-life of 131 I, days j K = EXP(-J) j L= (0. 693/8.05) *N N = Elapsed time (days) from mid-point of collection period to beginning of count time.

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I SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE ANALYSIS OF BOVINE THYROID FOR IODINE-131 The thyroid sample is first weighed and then, in combination with ethyl alcohol and 3.0ml iodine carrier, pureed in a blender in order to achieve a reasonably homogeneous sample. The contents are transferred to a sample can and additional alcohol added until the total sample volume reaches 100ml.

The can is then hermetically sealed and counted on a gamma detector.

Calculation of 131 I Activity:

The following are the calculations performed for the gamma activity, 2-sigma error and LLD:

Result (pCi/kg wet) = N*D =R (2.22) * (E) * ( A) * (T) * (V)

N = Net counts under photopeak D = Decay correction factor I Atl*EXP(It2) 1-EXP(-Atl) tl = Acquisition live time t2 = Elapsed time f rom sample collec-tion to start of acquisition A = 0.693/nuclide half life E = Detector efficiency I A = Gamma abundance factor (no. of photons per disintegration)

T = Acquisition live time, mins.

I V = Sample quantity, kg wet 2.22 = No. of dpm per pCi 2-sigma error (pci/kg wet) = 1.96* (GC+BC)l/2* R I N l

i GC = Gross counts BC = Background counts All other variables are as defined earlier.

The LLD (pCi/kg wet) = 4.66*(GC)1/2*D (2.2 2) * (E) * ( A) * (T) * (V)

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I SYlh'CS OF PSE&G RESEARCH CORPORATION PROCEDURE RADIOSTRONTIUM ANALYSIS OF AIR FILTERS The air filters are placed in a small beaker and just enough fuming nitric acid is added to cover the filters. A blank, composed of the same number of clean air filters, is prepared in the same way. Stable strontium carrier is then htroduced into each sample and several fuming nitric acid leachings are carried out to remove the radiostrontium from the filter media. Once this is done, the resultant nitrates are dissolved in distilled water and the filter residue is filtered out. Radioactive interferences are stripped out by coprecipitation on ferric hydroxide (yttrium strip) followed by e barium chromate strip. h e strontium is precipitated as a carbonate, which is dried and weighed. ne samples and blank are then counteu on a low background gas proportional counter and, again, at least 14 days later. The basis for this two count method is that 90Sr and 89 Sr are both unknown quantities requiring two simultaneous equations to solve for them.

Calculation of 90 Sr Activity:

90Sr Results (pci/m3) = N4/R

( 2.2 2) * (E) * (E (15)/E') * (S6) * (V) * (U)

= W2 where S6 = A + B*M + C*M2 (h is is the general form of the normalized 90 Sr efficiency regression equation for one particular gas proportional counter, where A, B and C are regression coefficlents.)

M = nickness density of strontium carbonate precipitate, mg/cm2 E(15)/E' = Ratio of 90 Sr efficiency at thickness value of 15mg/cm2 to 90 Sr counting standard efficiency run at the time of instrument calibration (21s standard is run with each group of environmental strontium samples)

E . 90Sr counting standard efficiency V = Sample quantity (m 33 U = Chemical yield N4 = (N2 - Fl*N1)/W1 = net counts due to 90 Sr only W1 = ((1 + Rl*I2) - (1 + Rl*II) *F1)

Il = 1 - EXP ((-0.693/2.667) *tl)

I2 = 1 - EXP ( (-0. 693/2. 667)

• t 2) tl = Elapsed time from 90 Y strip to first count t2 = Elapsed time from 90 Y strip to second count 122 I

I I 2.667 = Half-life of 90Y , days R1 = D + E*M + F*M2 (h is is the general form of the regression equation for 90y eggeyj90Sr eff'y ratio for one particular gas proportional counter, where D, E and F are regression coefficients.)

N2 = X - Y, where X and Y are recount gross counts and background counts, respectively N1 = X1 - Yl, where X1 and Y1 are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi F1 = EXP ((-0.693/2.667) *t2)

R = Count time of sample and blank Using the same variable definitions as above, the 2-sigma error for 90Sr (pCi/m 3) .

2* M + fX1+Yl)*F1 2"1/2* (Wl*W2)

W12 w12 ,

(N2-Fl*N1)

Again, keepin the same variable definitions, the LLD for 9 Sr (pCi/m3) .

4.66* (X+Y) + (X1+Yl)*F12 1/2 W12 W12 Calculation of 89Sr Activity:

89Sr Results (pci/m3) = N6/R (2.2 2) * (E) * (E (15) /E') * (S7) * (V) * (U) * (F9)

= W3 S7 = G + H*M + I*M2 (his is the general form of the normalized I 89 Sr efficiency regression equation for one particular gas proportional counter where G, H and I are regression coef ficients.)

N6 = N1 - N7* (1 + Rl*II)

N7 = (N2 - Fl*N1)/W1 (%is 6epresents counts due to 90 Sr)

I E(15)/E' = Ratio of 89 Sr ef ficiency at thickness value of 15mg/cm2 to 90 Sr counting standard efficiency run at the time of instrument calibration (his standard is run with each group of environmental strontium samples)

F9 = EXP ((-0.693/50.5) *t)

I 123 I

I t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount.

50.5 = Half-life of 09Sr, days All other quantities are as previously defined.

'Ihe 2-sigma error for 89Sr (pci/m3 ) = 2* (S8 2+39 32 1/2 *W3 (N1 - N7* (1+Rl* II)

S8 = (X+Y) + (X1+Yl)*F1 1/2 W12 wt2 S9 = (X1+Yl)1/2 All other variables are as previously defined.

Keeping the same variable definitions, the LLD for 09 Sr (pCi/m 3) ,

4.66*(S62 +392 )l/2 I

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I I SYNOPSIS OF TELEDYNE ISO'IOPES PROCEDURE ANALYSIS OF COMPOSITED AIR PARIICULATE FILTERS FOR RADIOSTRONTIUM The composited air filters are leached with concentrated nitric acid, with I heating, in the presence of strontium carrier. After adding deionized water, the sample is gravity filtered through a paper filter and the filtcate diluted further with additional deionized water, before being split into two equal parts. One part is put aside for gross alpha analysis and the other part I evaporated on a hotplate to a small volume. 'Ihe sample is transferred to a centrifuge tube and luming nitric acid added to form the strontium nitrate precipitate. After centrifuging and pouring off the supernate, the precipi-I tate is dissolved in deionized water and an iron scavenge performed. Th is marks the beginning of<the 90 Y ingrowth period. Centrifuging and discarding the precipitate, standardized yttrium carrier is added to the supernate and the sample is set aside for 5 to 7 days. After this period, the sample is I alkalinized with ammonium hydroxide and heated in a hot water bath to form yttrium hydroxide. After cooling, the sample is centrifuged and the supernate saved for 89 Sr determination. The precipitate is dissolved with dilute nitric and hydrochloric acids, and the yttrium precipitated as oxalate using saturated ammonium oxalate solution. The yttrium oxalate is mounted on a tared paper filter, oven dried, weighed and counted on a gas proportional counter. The sample is then recounted the following day to confirm the decay I of 90y, The supernate, saved for 89 Sr determination, is treated with saturated I sodium carbonate solution to precipitate strontium carbonate which is filtered on a tared glass fiber filter, oven-dried and likewise counted 200 minutes on a gas proportional counter. These samples, however, are covered with an 2 90 80ngfem 9 aluminum absorber to stop the Sr beta emissions, thus allowing the Sr betas to be counted alone.

The 89 Sr activity (pci/m 3 ) is computed as follows:

A= (G/T-Be -Ba ) *U m * ((G/T+B e +B a )/T)l/2 (2.22*V*Y*D*E) (2.22*V*Y*D*E) '

If the net activity (G/T -B) is less than or equal to the 20 counting error, the activity is considered MDL I where MDL = 2* (2* B/T) 1/2

( 2. 2 2*V*Y*D* E) where G = Tbtal sample counts T = Sample count time, mins.

D c = Background rate of counterb 9 cpm Ba = Background addition from Sr and ingrowth of 90 y I 2.22 =

V =

Y =

dpm/pci Sample volume, m 3 Chemical yield of strontium D = 89Sr decay factor from midpoint of collection period to counting date.

E = 99Sr counting efficiency with 80 mg/cm 2aluminum absorber cm = Multiples of counting error I 125

I The 90 3r activity (pci/m 3) is computed as follows:

A= (G/T-B) 2 O m *((G/T+B)/T)1/2 (2.22*V*Y*D*E) (2.22*V*Y*D*E) M Y = Chemical yield of the mount or sample counted E

D = Decay factor from the co?.lection to the counting date g E = Cbunter efficiency All other variables are as previously defined.

If the net activity (G/T-B) is less than or equal to the 20 counting error, the activity is considered MDL where MDL = 2* (2 *B/T) I/2 (2.2 2*V*Y1*Y2 *I *D*E)

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I SYNOPSIS OF PSE&G RESEARCH CORPORATION PkOCEDURE RADIOSTRONTIUM ANALYSIS OF RAW MILK Stable strontium carrier is first introduced into a milk sample and into a distilled water sample of equal volume to be used as a blank. The sample (s)

[ and blank are passed through cation resin columns which adsorb strontium, E calcium, magnesium and other cations. These cations are then eluted off with a TRIS-buffered 4N sodium chloride solution into a beaker and precipitated as carbonates. He carbonates are converted to nitrates with 6N nitric acid I and, by acidifying further to an overall concentration of 70% nitric acid, strontium is forced out of solution somewhat ahead of calcium. Barium chromate precipitation is then performed to remove any traces of radium I and radiobarium. Strontium recrystallization is carried out to remove re idual calcium which may have been coprecipitated with the initial strontium precipitation. Another recrystallization removes ingrown 90 Y, marking the tima of the yttrium strip. The strontium is precipitated as its carbonate, filtered, dried and weighed to determine strontium recovery. The samples and blank are then counted on a low backgrourd gas proportional counter and, again,atleast14dayslater.

9 Sr and 09 The basis for this two-count method is that Sr are both unknown quantities requiring two simultaneous equations to solve for them.

Calculation of 90 Sr Activity:

90Sr Results (pCi/L) = N4/R

( 2.2 2) * (E) * (E (15) /E') * (S6) * (V) * (U)

= W2 where S6 = A + B*M + C*M2 (his is the general form of the normalized 90 Sr efficiency regression equation for one particular gas proportional counter, where A, B and C are regression coefficients.)

M = nickness density of strontium carbonate precipitate, mg/cm2 E(15)/E' = Ratio of 90Sr ef ficiency at thickness value of 15mg/cm2 to ,

90 Sr counting standard efficiency run at the time of instrument '

calibration (2 1s standard is run with each group of environmental strontium samples) y . 90Sr counting standard efficiency v = Sarple quantity (liters)

U = Chemical yield N4 = (N2 - Fl*N1)/W1 = net counts due to 90Sr only W1 = ((1 + Bl*I2) - (1 + Rl*II' *F1)

Il = 1 - EXP ((-0.693/2.667)'tl) 12 = 1 - EXP ( (-0. 69 3/2. 6 67)

• t 2) 127 I

I t1 = Elapsed time from 90 Y strip to first count t2 = Elapsed time from 90 Y strip to second count 2.667 = Half-life of 90Y , days R1 = D + E*H + F*M2 (h is is the general form of the regression l equation for 90y eggeyj90Sr eff'y ratio for one particular gas um proportional counter, where D, E and F are regression coefficients.)

N2 = X - Y, where X and Y are recount gross counts and background counts, respectively N1 = XI - Yl, where XI and Y1 are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi F1 = EXP ( (-0. 693/2. 6 67)

• t 2)

R = Count time of sample and blank Using the same variable definitions as above, the 2-sigma error for 90 Sr (pCi/L) =

~

2* + (X1+Yl)*P1 f 1/2* (W1*W2)

W1 W12 (N2-Fl*N1)

- . 5 Again, keepin the same variable definitions, the LLD for 9 Sr (pci/L) =

4.66* + fX 1)*P1 f 1/2 i

Calculation of 89 Sr Activity:

89Sr Results (pCi/L) = N6/R

( 2. 2 2) * (E) * (E (15) /E') * (S7) * (V) * (U) * (F9)

= W3 S7 = G + H*M + I*M2 (Wis is the general form of the normalized 89 Sr efficiency regression equation for one particular gas proportional counter where G, H and I are regression coefficients.)

N6 = N1 - N7* (1 + R1*II)

~

N7 = (N2 - Fl*N1)/H1 (This represents counts due to 90Sr) 128 I

I I E(15)/E' = Ratio of 09 Sr efficiency at thickness value of 15mg/cm 2 to 90 Sr counting standard efficiency run at the time of instrument l calibration ('1his standard is run with each group of environmental I

strontium samples)

F9 = EXP ((-0.693/50.5) *t) t = Elapsed time frca midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount.

50.5 = Half-life of 89 Sr, days All other quantities are as previously defined.

The 2-sigma error for 89Sr (pCi/L) = 2* (S82 +S92 )1/2 *W3 (N1 - N7* (1+Rl* II)

~

S8 = (X+Y) + ( XI+Yl)

• F12 1/2 I

W12 W12 S9 = (X1+Yl)1/2 All other variables are as previously defined.

Keeping the same variable definitions, the LLD for 89Sr (pC1/L) =

2 2 4.66*(S8 +S9 )1/2 I

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SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE I

RADIOSTRO*lTIUM ANALYSIS OF WATER Stable strontium carrier is introduced into a water sample and into a distilled water sample of the same volume which is used as a blank. We sample (s) and blank are then made alkaline and heated to near boiling before precipitating the :arbonates. n e carbonates are converted to nitrates by fuming nitric acid recrystallization which acts to purify the sample cf nost of the calcium. Radioactive interferences are stripped out by coprecipita-tion on ferric hydroxide (yttrium strip) followed by a barium chromate strip.

ne strontium is precipitated as a carbonate before being dried and weighed.

The samples and blank are then counted on a low background gas proportional counter and, again, at least 14 days later. he basis for this two count l

5 method is that 90 Sr and 89 Sr are both unknown quantities requiring two simultaneous equations to solve for them.

Since surface waters, as well as some drinking water samples, have been found to contain significant amounts of stable strontium, a separate aliquot f rom each sample is analyzed for stable strontium. These results are used in correcting the chemical recovery of strontium to its true value.

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Calculation of 90 Sr Activity:

90Sr Results (pCi/L) =

N4/R (2.2 2) * (E) * (E(15)/E') * (S6) * (V) * (U)

= W2 where S6 = A + B*M + C*M2 (h is is the general form of the r.ormalized 90 Sr efficiency regression equation for one particular gas E 3

proportional counter, where A, B and C are regression coefficients.)

M = nickness density of strontium carbonate precipitate, mg/cm2 E(15)/E' = Ratio of 90Sr efficiency at thickness value of 15mg/cm2 to 90 Sr counting standard efficiency run at the time of instrument E 3

calibration (mis standard is run with each group of environmental strontium samples)

E = 90Sr counting standard efficiency V = Sample quantity (liters)

U = Chemical yield 90 Sr only N4 = (N2 - Fl*N1)/W1 = net counts due to W1 = ((1 + Rl*I2) - (1 + Rl*II) *F1)

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Il = 1 - EXP ( (-0. 69 3/2. 66 7)

• tl)

I I2 = 1 - EXP ( (-0. 693/2. 667)

• t 2) tl = Elapsed time from 90 Y strip to first count t2 = Elapsed time from 90 Y strip to second count 2.667 = Half-life of 90Y , days R1 = D + E*M + F*M2 (h is is the general form of the regression equat. ion for 90y effeyf 90 sr eff'y ratio for one particular gas I

proportional counter, where D, E and F are regression coefficients.)

N2 = X - Y, where X and Y are recount gross counts and background counts, respectively N1 = X1 - Yl, where X1 and Y1 are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi F1 = EXP ( (-0. 693/2. 667)

• t2)

R = Count tine of sample and blank Using the same variable definitions as above, the 2-sigma error for 90Sr (pCi/L) =

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~

2* (X+Y) + (X1+Yl)*F12 1/2* (Wl*W2)

W12 W12 (N2-Fl*N1)

I Again, keeping the same variable definitions, the LLD for 90Sr (pCi/L) =

4.66* (X+Y) + (X1+Yl)*F12 1/2 W12 w12 Calculation of 89 Sr Activity:

89 Sr Results (pCi/L)

= N6/R

( 2. 2 2) * (E) * (E (15) /E ')

• iS7) * (V) * (U) * (F9)

= W3 S7 = G + H*H + I*M2 (his is the general form of the normalized 89 Sr efficiency regression equation for one particular gas -

proportional counter where G, H and I are regression coefficients.)

N6 = N1 - N7* (1 + Rl*II)

N7 = (N2 - Fl*N1)/W1 (his represents counts due to 90Sr) 131

E(15)/E' = Ratio of 89 Sr ef ficiency at thickness value of 15mg/cm 2 to 90 Sr counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium sampleo I F9 = EXP ((-0.693/50.5) *t) t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount.

50.5 = Half-life of 89 Sr, days ,

l All other quantitles are is previously defined. j The 2-sigma error for 09Sr (pCi/L) = 2* (S82+39 32 1/2 *W3 (N1 - N7* (1+Rl*II)

~

S8 = (X+Y) + (XI+Yl)*Fl Y 1/2 Wld Wld l

S9 = (X1+Yl)1/2 E All other variables are as previously defined.

Keeping the same variable definitions, the LLD for 89 5r (pCi/L) =

4.66*(S82 +s92 )1/2 I

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SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE RADIOSTRONTIUM ANALYSIS OF VEGETATION, MEAT AND AQUATIC SAMPLES The samples are weighed (recorded as " wet" weight) as received, before being placed in an oven to dry at 100*C. At the completion of the drying period, samples are again weighed (recorded as

• dry

• weight) and then pulverized. A measured amount (quantity dependent on desired sensitivity) of the pulverized sample is first charred over a Bunsen burner and then ashed in a muffle furnace. Tre ash is fused with 409 sodium carbonate, along with 20mg strontium cactier, at 900*C for 1/2 hour. After removal from the furnace, the melt is cooled, pulverized and added to 500ml distilled water and heated to near boiling for 30 minutes, with stirring. The sample is filtered (filtrate discarded) and the carbonates on the filter dissolved with 1:1 nitric acid (HNO 3). The resultant nitrates are heated to dryness and are dissolved in 20ml distilled water before adding 60ml fuming HNO3 . After I calcium removal with anhydrous acetone, radioactive interferences are stripped out by coprecipitation on ferric hydroxide followed by coprecipitation on barium chromate. The strontium is precipitated as its carbonate, which is I dried and weighed. The samples are then counted on a low background gas proportional counter and, again, at least 14 days later.

two-count method is that 90Sr and 89Sr are both unknown quantities The basis for this requiring two simultaneous equations to solve for them.

Calculation of 90Sr Activity:

I 90Sr Results (pCi/kg wet) = N4/R (2.2 2) * (E) * (E (15) /E ') * (S6) * (V) * (U)

= W2 where S6 = A + B*M + C*M2 (This is the general form of the normalized 90 Sr efficiency regression equation for one particular gas I proportional counter, where A, B and C are regression coefficients.)

M = Thickness density of strontium carbonate precipitate, mg/cm2 E(15)/E' = Ratio of 90Sr efficiency at thickness value of 15mg/cm2 to 90 Sr counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)

E . 90Sr counting standard efficiency V = Sample quantity (kg wet)

U = Chemical yield N4 = (N2 - Fl*N1)/W1 = net counts due to 90Sr only W1 = ((1 + Rl*I2) - (1 + Rl*II) *F1) 133

1 l

Il = 1 - EXP ( (-0. 693/2. 667)

• tl)

I2 = 1 - EXP ( (-0. 69 3/2. 6 67)

• t 2 )

tl = Elapsed time from 90 Y strip to first count t2 = Elapsed time from 90 Y strip to second count 2.667 = Half-life of 90Y , days R1 = D + E*M + F*M2 (h is is the general form of the regression equation for 90y eggeyj90Sr eff'y ratio for one particular gas proportional counter, where D, E and F are regression coefficients.)

N2 = X - Y, where X and Y are recount gross counts and background counts, respectively N1 = XI - Y1, where XI and Y1 are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi F1 = EXP ( (-0. 69 3/2. 667)

• t2 )

R = Count time of sample and blank Using the same variable definitions as a Mve, the 2-sigma error for 90 Sr (pCi/kg wet) =

2* (X+Y) + (X1+Yl)*F1 2" 1/2* (Wl*W2)

, Wl Wl d ,

(N2-Fl* N1)

Again, keepin the same variable definitions, the LLD for 9 Sr (pCi/kg wet) =

l E

4.66* (X+Y) + (X1+Yl)*F1 2"l/2 W12 w12 Calculation of 89Sr Activity:

89 Sr Results (pCi/kg wet) = N6/R (2. 2 2) * (E) * (E (15) /E') * (S7) * (V) * (U) * (F9)

W3 S7 = G + H*M + I*M2 (% is is the general form of the normalized 89 Sr efficiency regression equation for one particular gas

proportional counter where G, H and I are regression coef ficients.)

N6 = N1 - N7*(1 + Rl*II)

N7 = (N2 - Fl*N1)/W1 (his represents counts due to 90 Sr) 134 I

i E(15)/E' = Ratio of 89 Sr efficiency at thickness value of 15mg/cm 2 to 90 Sr counting standard efficiency run at the time of instrument ,

calibration (This standard is run with each group of environmental I strontium samples)

F9 = EXP ((-0.693/50.5) *t) t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount.

50.5 = Half-life of 89Sr, days All other quantities are as previously defined.

The 2-sigma error for 89Sr (pCi/kg wet) = 2* (S82 +392 )l/2 *W3 (N1 - N7*(1+Rl*II) 58 = (X+Y) + (X1+Yl)*F12 1/2 Wld Wld S9 = (X1+Yl)l/2 All other variables are as previously defined.

Keeping the same variable definitions, the LLD for 09Sr (pCi/kg wet) =

4.66*(S82 +s92 )l/2 135

SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE RADIOSTRONTIUM ANALYSIS OF BONE AND SHELL The bone or shell is first physically separated from the rest of the sample before being broken up and boiled in 6N sodium hydroxide (NaOH) solution for a brief time to digest remaining flesh / collagen material adhering to the sample.

After multiple rinses with distilled water, the bone /shell is then oven dried and pulverized. An aliquot of the sample is removed, weighed and ashed in a muffle furnace. Then, in the presence of strontium carrier and cesium holdback carrier, the radiostrontium is leached out of the ash by b(siling in diluted nitric acid, after which the sample is filtered.

The sample is then treated with concentrated (70%) nitric acid and boiled until strontium nitrate crystallizes out. W e strontium nitrate is freed of calcium =

by repeated fuming nitric acid recrystallizations. From this point on, any radiological impurities are removed by coprecipitation with ferric hydroxide g followed by coprecipitation with barium chromate. The strontium is precipi- g tated as strontium carbonate, which is dried, weighed, then beta-counted on a low background gas proportional counter. A second count isgerformedatleast 14 days later. The basis for this two-count method is that OSr and 89Sr are both unknown quantities requiring two simultaneous equations to solve for them.

Calculation of 90Sr Activity:

90 Sr Results (pCi/kg dry) = N4/R (2.2 2) * (E) * (E(15)/E') * (S6) * (V) * (U)

= W2 where S6 = A + B*M + C*M2 (his is the general form of the normalized 90Sr efficiency regression equation for one particular gas proportional counter, where A, B and C are regression coefficients.)

M = W ickness density of strontium carbonate precipitate, mg/cm 2 E(15)/E' = Ratio of 90Sr efficiency at thickness value of 15mg/cm2 to 90 Sr counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)

E = 90Sr counting standard efficiency V = Sample quantity (kg dry)

U = Chemical yield 90Sr only N4 = (N2 - Fl*N1)/W1 = net counts due to W1 = ((1 + Rl*I2) - (1 + Rl*II) *F1) 136 I

I Il = 1 - EXP ( (-0. 693/2. 667)

• tl) 12 = 1 - EXP ( 1-0. 693/2. 667)

• t 2) tl = Elapsed time from 90 Y strip to first count t2 = Elapsed time from 90Y strip to second count 2.667 = Half-life of 90Y , days R1 = D + E*M + F*M2 (his is the general form of the regression equation for 90y eggeyj90Sr eff'y ratio for one particular gas proportional counter, where D, E and F are regression coefficients.)

N2 = X - Y, where X and Y are recount gross counts and background counts, respectively N1 = XI - Yl, where Xl and Y1 are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi F1 = EXP ( (-0. 693/2. 667)

• t 2 )

R = Count time of sample and blank Using the same variable definitions as above, the 2-sigma error for 90Sr (pCi/kg dry) =

I 2* (X+Y) + (X1+Yl)

• F12 1/2* (W1*W2)

Wld Wld (N2-Fl*N1)

Again, keepi the same variable definitions, the LLD for Sr (pCi/kg dry) =

4.66* (X+Y) + (X1+Y1)

• F12 1/2 W12 W12 Calculation of 89 Sr Activity:

89 Sr Results (pCi/kg dry) =

N6/R (2.2 2) * (E) * (E(15) /E') * (S7) * (V) * (U) * (F9)

= W3 I S7 = G + H*M + I*M2 (h is is the general form of the normalized 89 Sr efficiency regression equation for one particular gas proportional counter where G, H and I are regression coefficients.)

N6 = N1 - N7* (1 + Rl*II)

N7 = (N2 - Fl*N1)/W1 (his represents counts due to 90Sr) 137 I

E(15)/E' = Ratio of 69Sr efficiency at thickness value of 15mg/cm 2 to 90 Sr counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental 3 strontium samples) g F9 = EXP ( (-0.693/50.5) *t) t = Elapsed time f rom midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount.

50.5 = Half-life of 09 Sr, days All other quantities are as previously defined.

The 2-sigma error for 89 Sr (pCi/kg dry) = 2* (S82 +392 )l/2 *W3

~

S8 = (X+Y) + (XI+Yl)*P12 1/2 W12 w12 S9 = (XI+Yl)1/2 All other variables are as previously defined.

Keeping the same variable definitions, the LLD for 89Sr (pci/kg dry) =

4.66*(S82 +392 )1/2 I

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SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE RADIOSTRONTIUM ANALYSIS OF SOIL AND SEDIMENT After the soil or sediment sample has been dried and pulverized, a 50gm aliquot l

I is added to approximately 1/3 - liter concentrated hydrochloric acid (hcl),

containing Sm1 of strontium carrier (10mg St++/ml) . A blank containing only 1/3 - liter concentrated hcl and Sml strontium carrier is run in parallel with the sample. We samples are stirred vigorously for at least 30 minutes and I

then filtered. The filtrate is then diluted to a known volume and aliquots removed for stable strontium. We remaining sample is alkalinized with ammonium hydroxide to precipitate all the transitional ele.3ents. After filter-ing out these interferences, the filtrate is heated and sodium carbonate added to precipitate strontium and calcium carbonate. These carbonates are first filtered and then digested with 6N HNO 3. Two fuming (90%) HNO3 recrystal-lizations are then performed to remove calcium. Subsequently, radicactive I impurities are removed by two precipitation steps, using ferric hydroxide and barium chromate as carriers. he strontiur.is precipitated as strontium carbonate before being dried and weighed. The samples are counted for beta activity in a low background gas proport.onal counter (Count time will vary, I depending on the desired sensitivity.). There is a second count st least 14 days later. We basis for this two-count method is that 90Sr and 895r are both unknown quantities requiring two simultaneous equations to solve for them.

Calculation of 90 Sr Activity:

90Sr Results (pCi/kg dry) = N4/R I (2.22) * (E) * (E(15)/E') * (S6) * (V) * (U)

= W2 where S6 = A + B*M + C*M2 (This is the general form of the normalized 90Sr efficiency regression equation for one particular gas proportional counter, where A, B and O are regression coefficients.)

M = Wickness density of strontium carbonate precipitate, mg/cm2 I E(lS)/E' = Ratio of 90 Sr efficiency e' thickness value of 15mg/cm2 to 90 Sr counting standard efficiency run at the time of instrt' ment calibration (his standard is run with each group of environmental strontium samples)

E = 90Sr counting standard officiency i l

l V = Sample quantity (kg dry)

U = Chemical yield 90 Sr only N4 = (N2 - Fl*N1)/W1 = net counts due to W1 = ((1 + Rl*I2) - (1 + Rl*II) *F1)

I 139

Il = 1 - EXP ( (-0. 69 3/2. 667)

• tl)

I2 = 1 - EXP ( (-0. 693/2. 667)

• t2) tl = Elapsed time from 90 Y strip to first count t2 = Elapsed time from 90 Y strip to second count 2.667 = Half-life of 90Y , days El = D + E*M + F*M2 (This is the general form of the regression equation for 90y eggeyj90Sr eff'y ratio for one particular gas proportional counter, where D, E and F are _ regression coefficients.)

N2 = X - Y, where X and Y are recount gross counts and background counts, respectively N1 = XI - Yl, where XI and Y1 are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi F1 = EXP ( (-0.693/2.667) *t2)

R = Count time of sample and blank Using the same variable definitions as above, the 2-sigma error for 90 Sr (pci/kg dry) =

2* MiXL + (X1+Yl) *Fl b 1/2* (W1*W2)

W12 Wl d (N2-Fl*N1) -

Again, keeping the same variable definitions, l the LLD for 9USr (pCi/kg dry) = 5 4.66* (X+Y) + (X1+Yl)

• P1 2 1/2 W12 w12 Calculation of 99 Sr Activity:

89Sr Results (pCi/kg dry) =

N6/R (2. 2 2) * (E) * (E (15) /E' ) * (S7) * (V) * (U) * (F9)

= W3 S7 = G + H*M + I*M2 (This is the general form of the normalized 89 Sr efficiency regression equation for one particular gcs "

proportional counter where G, H and I are regression coefficients.)

N6 = N1 - N7* (1 + Rl*II) l l N7 = (N2 - Fl*N1)/W1 (This represents counts due to 90Sr) l 140 I

l l

I E(15)/E' = Ratio of 09Sr efficiency at thickness value of 15mg/cm 2 to 90 Sr counting standard efficiency run at the time of instrument calibration (h is standard is run with each group of environmental strontium samples)

F9 = EXP ( (-0. 693/50. 5) *t)

I t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount.

50.5 = Half-life of 89 Sr, days All other quantities are as previously defined.

The 2-sigma error for 89Sr (pci/kg dry) = 2* (S82 +392 )l/2 *W3

~

S8 = (X+Y) + (XI+Y1)

• Pl f 1/2 W12 w12 I S9 = (X1+Yl)1/2 All other variables are as previously defined.

Keeping the same variable definitions, the LLD for 89Sr (pCi/kg dry) =

4.66*(S8 +39 2 32 1/2 I

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_ _ _ _ _ _ _ . . _ _ _ ___m_ _ _ _ _ _ _ _ _ . . _ . _ _ _ _ _ _ _ _

I SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE ANALYSIS OF ENVIRONMENTAL SAMPLES FOR STABLE STRONTIUM It has been the practice of tFe Environmental Division to perform a stable strontium determination on any samples to be analyzed for strontium 90 and 89, if they are likely to contain significant amounts of the stable isotopes. l For water samples, this involves removal of a 60-ml aliquot of sample. How- E ever, mineral and biological media require acid leaching and/or ashing steps to extract the element (s) of interest. The removal of the aliquot is done early in the course of the radiostrontium analysis and involves the withdrawl of 25ml of diluted leachate (in the case of soil or sediment) which is then transferred to a flask. Bone and shell are prepared by ashing 2g of sample, digesting in 20ml 6N hcl, filtering out insoluble residues and then trans-ferring to a flask. All samples are sent to Chemical Division for analysis.

ne results (reported as milligrams strontium per liter) are then used to find the true chemical recovery of strontium based on both the amount of carrier added (only in the case of soil and sediment) and the quantity of strontium intrinsic to the sample.

Sample Calculation of Corrected Chemical Recovery of Strontium in Soil and I

Sediment:

Reported concentration of stable strontium (mg/L) :119 Volume of specimen (ml):25 (removed f rom 1000ml of diluted leachate)

Proportion of sample used for aliquot: 0.025 Milligrams Strontium in 25m1 flask = (119mg/L) x (.025L/25ml) x (25ml)

2.98mg Sr Since 2.98mg Sr represents the quantity of stable strontium in 2 1/2 percent of the sample, total strontium (stable + carrier) in the full sample

2.98mg Sr = 119 mg 0.025 Net weight of SrCO3 precipitate (mg) : 125 Percent of Sr in precipitate: 59.35 Quantity of strontium recovered = (125mg) x (.5935) = 74.2 Corrected Chemical Recovery of strontium = 74.2 = 0.623 119 he calculations follow the same sequence for bone and shell samples.

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I Sample Calculation of Corrected Chemical Recovery of Strontium in Water:

Reported concentrations of stable strontium (mg/L): 1.65 Volume of radiochemical water sample (liters) : 2.0 I I Stable strontium in 2 liter sample = (1.65mg/L) x (2.0L)

= 3.30mg Quantity of strontium carrier added to sample (mg) : 20.0 Total amount of strontium in sample (mg) : 20.0 + 3.30 = 23.3mg Net weight of SrCO3 Precipitate (mg): 28.9 I Percent of Sr in precipitate: 59.35 Quantity of strentium recovered = (28.9mg) x (.5935) = 17. 2 rg Corrected Chemical Recovery of Strontium = 17.2mg = .738 I 23.3mg I

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I SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE GAMMA ANALYSIS OF AIR PARTICULATE COMPOSITES At the end of each calendar quarter, 13 weekly air filters from a given location are stacked in a two inch diameter Petri dish in chronological order, with the oldest filter at the bottom, nearest the detector, and the l E

newest one on top. The Petri dish is closed and the sample counted on a gamma detector.

The following are the calculations performed for the gamma activity, 2-sigma error and LLD:

Result (pCi/m 3) = N*D =R (2.22) * (E) * ( A) * (T) * (V)

N = Net counts under photopeak E

D = Decay correction factor 3 A tl*EXP ( A t2 )

1-EXP(-Atl) tl = Acquisition live time t2 = Elapsed time from sample collection to start of acquisition g A = 0.693/nuclide half life 5 E = Detector efficiency A = Gamma abundance factor (no. of g photons per disintegration) g T = Acquisition live time, mins.

V = Sample volume, m 3 2.22 = No. of dpm per pCi 2-sigma error (pCi/m 3) = 1.96*fGC+BC)1/2*R N

GC = Gross counts BC = Background counts All other variables are as defined earlier.

The LLD (pci/m 3) = 4.66*(GC)l/2*D (2.22) * (E) * (A) * (T) * (V)

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SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE ANALYSIS OF AIR PARTICULATE FILTERS FOR CAMMA I

Air particulate filters are analyzed for gamma using a lithium-drifted germanium detector interfaced with a 2048 channel pulse height analyzer

)

calibrated at 1.0 Kev per channel. Teledyne Isotopes employs one of three possible data acquisition and computation systems. The first, a Data General I NOVA minicomputer, in series with the pulse height analyzer, calculates the nurter of counts (and a one standard deviation) in the peak region by performing a linearly-interpolated background subtraction. If no peak is observed, then only the background is used (along with sample volume, collec-tion date and length of count) to determine the detection limit. The activity or MDL of each nuclide is computed on an IBM 360. This semi-automatic system is in contrast with the other two data acquisition and computation systems, namely, a Tracor Northern TN-ll and Nuclear Data 6620 which perform all the above computations automatically. All resultant spectra are stored on magnetic tape.

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SYNOPSIS OF PSE&G RESEARCli CORPORATION PROCEDURE GAMMA ANALYSIS OF RAW MILK A well mixed 3.5-liter sample of raw milk is poured into a calibrated Marinelli beaker along with 20ml of 37% formaldehyde solution (used as a preservative). After stirring, the sample is allowed to reach ambient temperature and then counted on a gamma detector for 1000 minutes.

Calculation of Gamma Activity:

The following are the calculations performed for the gamma activity, 2-sigma error and LLD:

Result (pCi/L) = N*D =R (2.22) * (E) * ( A) * (T) * (V)

N = Net counts under photopeak D = Decay correction factor Atl*EXP( At2) 1-EXP(- Atl) tl = Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition A = 0.693/nuclide half life E = Detector efficiency A = Gamma abundance factor (no of photons per disintegration)

T = Acquisition live time, mins.

V = Sample volume, liters 2.22 = No. of dpm per pCi 2-sigma error (pCi/L) = 1.96*(GC+BC)1/2*R GC = Gross counts BC = Background counts All other variables are as defined earlier.

'Ihe LLD (pCi/L) = 4. 66* (GC) l/2* D E (2.2 2) * (E) * ( A) * ( s') * (V) g 146 I

SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE GAMMA ANALYSIS OF WATER A 4-liter sample of water is added to a brown glass jug. Then, a bent glass tube is connected to the open end of the jug by means of a rubber stopper I inserted into it. The other end of the glass tube (which is flared) is closed with a small cork. This assembly is inverted and mounted in a ring stand.

An aluminuo can is positioned on a hotplate underneath the end of the glass The cork is removed with the aid of a forceps and the water flows into I

tube.

the can until the water level meets the tip of the glass tube. The height of the glass tube is critical and is adjusted up or down until the water level automatically reaches the 100ml mark scribed on the inside of the can. After all tne sample has left the jug, any salts which have crept up the inside of the can, are pushed back into the sample by means of a rubber policeman.

Also, the jug and glass tube are rinsed with distilled water and the rinsing I added to the can. The water level is then adjusted back to the 100ml level by additional evaporation.

temperature before sealing the can and then counting on a gamma detector for The sample is finally lef t to cool to room 1000 minutes.

Calculation of Gamma Activity:

The following are the calculations performed for the gamma activity, 2-sigma error and LLD:

Result (pCi/L) = N*D =R (2. 22) * (E) * ( A) * (T) * (V)

N = Net counts under photopeak D = Decay correction factor Atl*EXP( A t2) 1-EXP(-Atl) tl = Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition A = 0.693/nuclide half life E = Detector efficiency A = Gamma abundance factor (no. of photons per disintegration)

T = Acquisition live time, mins.

V = Sample volume, liters 2.22 = No. of dpm per pCi 2-sigma error (pCi/L) = 1. 9 6* (GC+BC) 1/2* R I "

GC = Gross counts BC = Background counts All other variables are as defined earlier.

I The LLD (pCi/L) =

(2.2 2) * (E) * ( A) * (T) * (V) 4.66*(GC)1/2*D 147

I SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE GAMMA ANALYSIS OF SOLIDS Several methods are employed in preparing solids for gamma analysis, depending on the type of sample or sensitivity required. For high sensitivity analysis of vegetation, meat and seafood, the sample is first weighed, then oven-dried to a constant weight. A ratio of wet-to-dry weight is computed before the sample is ground and compressed to un1L density (lg/cm3 ), whenever possible, in a tared aluminum can. The can is weighed and then hermetically sealed and counted on a gamma detector.

When sample size or time is limited, a wet sample can be prepared (assuming sensitivity can be met) by using a food processor to puree it. The sample is then poured into a calibrated and tared clear plastic container until a standard volume is reached. The sample is weighed and then sealed with a screw cap before gamma counting.

Soil and sediment samples are first oven dried until a constant weight is achieved and then pulverized. The sample is added to a tared aluminum can, compacted to a standard volume and weighed. It is hermetically sealed and gamma counted.

Benthic organisms are oven dried, followed by the physical removal of any obvious impurities (such as shells or twigs) . The dried organisms are weighed and then wet-ashed with concentrated nitric acid. After all solids have been digested, the sample is evaporated to near dryness and the residual salts taken up with distilled water. The sample is filtered and the filtrate added to an aluminum can. The sample volume is brought up to the standard geometry with distilled water and the can hermetically sealed before gamma counting.

Calculation of Gamma Activity:

The following are the calculations performed for the gamma activity, 2-sigma error and LLD:

Result (pCi/kg) = N*D =R (2.22) * (E) * ( A) * (T) * (V)

N = Net counts under photopeak D = Decay correction factor A tl*EXP ( A t2 )

l-EXP(-ltl)

E g

t1 = Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition A = 0.693/nuclide half life E = Detector efficiency A = Gamma abundance factor (no. of photons per disintegration)

T = Acquisition live time, mins.

V = Sample volume, liters 2.22 = No. of dpm per pCi 148

2-sigma error (pCi/kg) = 1.96* (GC+BC) l/2* R N

GC = Gross counts BC = Background counts All other variables are as defined earlier.

The LLD (pCi/kg) = 4.66*(GC)1/2*D (2.22) * (E) * ( A) * (T) * (V)

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)

SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE ANALYSIS OF TELEDYNE ISOTOPES THERMOLUMINESCENT DOSIMLTERS These devices are rectangular Teflon wafers impregnated with 25% CaSO 4 :Dy phosphor. They are first annealed in a 250*C oven prior to exposure in the field. Following field exposure (for a 1-month or 3-month period) four l separate areas of the dosimeter are read in a Teledyne Isotopes model 8300 E TLD reader. The dosimeter is then re-irradiated by a standardized Cs-137 source and the four areas are read again. Calculation of the environmental exposure is performed by computer, using the re-irradiation readings to determine the sensitivity of each area of the dosimeter. The readings of control dosimeters are subtracted to allow for transit dose and system back-ground.

The results are computed as follows:

For any given area of the dosimeter, the dose in mR is calculated by the following formula:

DOSE = R * (REDOSE/RR) -AVC R = Initial reading of the area RR = Second reading of the area g (af ter re-irradiation) g REDOSE = Re-irradiation dose, mR AVC = Average of control values, mR 4N where AVC = E CDOSE/4N i=1 l

N = Tbtal number of control dosi-meters l

l CPOSE = CR* (CREDOSE/CRR) E CDOSE = Control area dose, mR CR = Initial reading of control area CRR = Second reading of the control area (af ter re-irradiation)

CREDOSE = Re-irradiation dose of the control dosimeter, mR l

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I APPENDIX E

SUMMARY

OF USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDIES PROGRAM RESULTS I l 151

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SUMMARY

OF USEPA INTERCOMPARISON STUDIES PROGRAM l

Appendix E presents a summary of the analytical results for the 1984 USEPA Environmental Radioactivity Laboratory Intercomparison Studies Program.

l TABLE OF CONTENTS TABLE l NO. TABLE DESCRIPTION PAGE E-1 Gross Alph; and Gross Beta Emitters in Water and Air Particulates.............................. 154 E-2 Gamma Emitters in Milk, Water, Air Particulates and Food Products............................. 155 E-3 Tritium in Water................................ 157 E-4 Iodine in Water and Milk........................ 158 E-5 Strontium-89 and -90 in Air Particulates, Milk, Water and Food Products....................... 159 E-6 Radium-226 and -228 in Water.................... 160 I

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l IlI TABLE E-1 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Gross Alpha and Gross Beta Analysis of Water (pCi/1.)

and Air Particulate (pCi/ filter)

PSE&G EPA GRAND AVG I

PSE& G DATE ENV ID NUMBER MEDIUM ANALYSIS Mean t s.d. Mean i s.d. Mean 2 s.d.

1/84 EPA-WAT-AB85 Water Alpha 3323 1025 1023 84-116 Beta 1121 1225 1323 3/84 EPA-WAT-AB91 Water Alpha 521 St5 622 84-363 Beta 1821 20 5 2023 3/84 EPA-APT-GABS 92 APT Alpha 1821 1525 1623 84-364 Eeta 6922 5125 56*6 5/84 EPA-BLD-P95 Water Alpha 3524 (1) (1)84-612 Beta 11922 (1) (1) 5/84 EPA-WAT-AB97 Water Alpha 321 3t5 3tl 84-740 Beta 521 625 722 7/84 EPA-WAT-AB102 Water Alpha 721 6t5 522 84-1007 Beta 1221 1325 1323 8/84 EPA-APT-GABS 106 APT Alpha 1921 17t5 1723 84-1144 Beta 5822 5125 5226 9/84 EPA-WAT-ABil3 Water Alpha 61 525 522 84-1368 Beta 1321 16t6 1523 11/84 EPA-WAT-AB122 Water Alpha 721 725 722 84-1680 Beta 1821 2025 2123 11/84 EPA-WAT-Pil6 Water Alpha 1121 14 5 13t4 84-1542 Beta 22 1 6425 6027 11/84 EPA-APT-GABS 123 APT Alpha 1721 (1) (1) 84-1681 Beta 6321 (1) (1)

I (1) Results not received from EPA.

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!I TABLE E-2 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Gamma Analysis of Milk, Water (pC1/L), Air Particulate (pCi/ filter) and Food Products (Pci/kg) 1 PSE&G PSE& G EPA GRAND AVG ,

DATE ENV ID NUMBER MEDIUM NUCLIDE Mean 2 s.d. Mean 2 s.d. Mean s.d. l 2/84 EPA-WAT-G87 Water Cr-51 4624 4025 4028 I 84-177 Co-60 Zn-65 Ru-106 1121 5323 65 10 1025 5025 6125 1122 5028 5529 Cs-134 3023 3125 2923 Cs-137 1622 1625 16t3 3/84 EPA-ORG-GS 8 6 Food I-131 1922 2026 2024 84-117 Cs-137 2122 20t5 2123 K(*) 2510280 27202140 26652250 3/84 EPA-APT-GABS 92 APT Cs-137 1021 1025 1223 84-364 5/84 EPA-WAT-P95 Water 0o-60 2922 (1) (1)84-612 Cs-134 3022 (1) (1)

Cs-137 2621 (1) (1) 6/84 EPA-MLK-GS101 Milk I-131 4321 4326 4324 84-819 Cs-137 3621 3515 3623 K(*) 1530220 7496175 1560297 6/84 EPA-WAT-G98 Water Cr-51 73212 6625 64213 84-741 Co-60 3223 3125 3124 Zn-65 6625 6325 63 9 Ru-106 3427 2925 30211 Cs-134 4422 4725 4426 Cs-137 3721 3725 3724 7/84 EPA-ORG-GS103 Food I-131 3922 3926 3925 84-985 Cs-137 2522 2525 2723 K (*) 2!.90290 26052130 2571t229 8/84 EPA-APT-GABS 106 APT CS-137 1421 1525 1724 84-1144 I

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TABLE E-2 (cont'd)

USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Gamma Analysis of Milk, Water (pCi/L), Air Particulate (pCi/ filter) and Food Products (Pci/kg)

PSE&G PSE& G EPA GRAND AVG DATE ENV ID NUMBER MEDIUM NUCLIDE Mean 2 s.d. Mean 1 s.d. Mean t s.d.

10/84 EPA-WAT-Gil4 Water Cr-51 5029 4025 3828 84-1479 Co-60 2021 2025 20r3 Zn-65 1421 14727 149212 Ru-106 4021 4725 4529 Cs-13 4 3021 3125 2923 Cs-137 25 1 2425 2523 10/84 EPA-MLK-GSil7 Milk I-131 62222 4226 4025 84-1579 Cs-137 31:2 3225 3223 g K(*) 1265216 1517276 14982143 5 11/84 EPA-WAT-Pil6 Water 00-60 1621 1415 1622 84-1542 Cs-134 221 215 322 Cs-137 1522 1425 1622 11/84 EPA-APT-GABS 123 APT Cs-137 1021 (1) (1) g 84-1681 g I

(*) Reported as mg/L of Potassium g (1) Results not received from EPA. 3 I

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I TABLE E-3 USEPA ENVIRONMENTAL RADIOACTIVITY LABORA'IORY INTERCOMPARSION STUDY PROGRAM Tritium Analysis of Water (pCi/L)

PSE&G PSE&G EPA GRAND AVG DATE ENV ID NUMBER MEDIUM NUCLIDE Mean i s.d. Mean i s.d. Mean t s.d.

2/84 EPA-WAT-H88 Water H-3 2370280 23832351 23662247 84-178 4/84 EPA-WAT-H94 Water H-3 33602100 35082364 34612288 84-472 6/84 EPA-WAT-H99 Water H-3 2920240 30512359 30392235 84-785 8/84 EPA-WAT-H105 Water H-3 2780220 28172356 2842r251 84-1029 10/84 EPA-WAT-Hil5 Water H-3 2760220 28102356 2814t213 84-1480 ,

12/84 EPA-WAT-E125 Water H-3 3280270 31822360 32062236 84-1783 I .

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I TABLE E-4 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Iodine Analysis of Water and Milk (pCi/L)

PSE&G PSE&G EPA GRAND AVG DATE ENV ID NUMBER MEDIUM NUCLIDE Mean s.d. Mean t s.d. Mean 1 s.d.

3/84 EPA-MLK-I89 ( * *) Milk I-131 621 621 6tl 84-265 4/84 EPA-WAT-193 Water I-131 621 621 622 84-426 8/84 EPA-WAT-Il04 Water I-131 36 1 3426 3625 84-1028 3626 3625 12/84 EPA-WAT-Il24 Water I-131 32tl E 84-1688 E

(**) Special EPA /NRC low level study I

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TABLE E-5 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM  ;

Strontium-89 and -90 Analysis of Air Particulates (pCi/ filter) ,

Milk, Water (pCi/L) and Food Froducts (pCi/kg)

PSE&G PSE& G EPA GRAND AVG l DATE ENV ID NUMBER MEDIUM NUCLIDE Mean 2 s.d. Mean t s.d. Mean 2 s.d.

1/84 EPA-WAT-S84 Water Sr-89 4121 3C5 3629 l 84-94 Sr-90 24 1 2422 2323 3/84 EPA-ORG-GS86 Food Sr-89 2721 3425 3125 84-117 Sr-90 2122 20t5 20t4 3/84 EPA-APT-GABS 92 APT St-90 1821 2122 1922 84-364 5/84 EPA-BLD-P95 Water Sr-89 22 1 (1) (1)84-612 St-90 2621 (1) (1) 5/84 EPA-WAT-S96 Water Sr-89 2422 2525 2424 84-683 St-90 4tl 522 521 I 6/84 EPA-MLK-GS101 84-819 Milk St-89 Sr-90 LT4 LT2 2525 1721.5 2125 1522 I 7/84 EPA-ORG-GS103 Food Sr-89 (2)- - 84-985 Sr-90 (2) - -

8/84 EPA-WAT-GABS 106 APT Sr-90 16t; 1821.5 1722 84-1144 9/84 EPA-WAT-S107 Water Sr-89 3222 34 5 3028 84-1174 Sr-90 1711 1921.5 1823 10/84 EPA-MLK-GS117 Milk Sr-89 1823 2225 1924 84-1579 Sr-90 1221 1621.5 1522 I 11/84 EPA-WAT-Pil6 84-1542 Water Sr-89 St-90 1022 1121 1125 1221.5 1124 1323 11/84 EPA-APT-GABS 123 APT Sr-90 1721 (1) (1) 84-1681 I

(1) Results not received from EPA.

(2) No analysis results due to equipment failure.

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TABLE E-6 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Radium-226 and -228 Analysis of Water (pCi/L)

PSE&G PSE&G EPA GRAND AVG DATE ENV ID NUMBER MEDIUM NUCLIDE Mean 2 s.d. Mean i s.d. Mean i s.d.

3/84 EPA-WAT-R90 Water Ra-226 5.421 4.121 3.821 84-331 Ra-228 1.721 2.021 2.421 5/84 EPA-BLD-P95 Water Ra-226 1521 (1) (1)84-612 Ra-228 9.820.6 (1) (1) 6/84 EPA-WAT-R100 Water Ra-226 5.520.1 3.520.5 3.520.5 84-785 Ra-228 1.820.4 2.020.3 2.220.9 9/84 EPA-WAT-Ril2 Water Ra-226 (2) - -

84-1367 Ra-228 (2) - - E g

12/84 EPA-WAT-R126 Water Ra-226 (2) - -

84-1784 Ra-228 (2) - -

(1) Results not received from EPA.

(2) Analysis cancelled by PSE&G.

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APPENDIX F SYNOPSIS OF DAIRY' AND VEGETABLE GARDEN SURVEY i I

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APPENDIX F SYNOPSIS OF 1984 MILK ANIMAL AND VEGETABLE GARDEN SURVEYS MILK ANIMAL SURVEY A survey of dairy farms conducted out to a distance of five miles from the Salem Generating Station (SGS) was performed in May and September, 1984.

The results of the May survey were as follows:

One dairy farm, situated 4.9 miles West of SGS was located.

The results of the September survey were as follows:

No change from the May survey.

VEGETABLE GARDEN SURVEY A survey of vegetable gardens conducted out to a distance of one mile of the SGS was performed in September 1984.

I No vegetable gardens were found within this area.

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I RTL-ENV-85-01 l

I ARTIFICIAL ISLAND RADIOLOGICAL

' I ENVIRONMENTAL MONITORING PROGRAM I

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I 1984 RADIOLOGICAL REPORT JANUARY 1 TO DECEMBER 31,1984 I

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. Prepared for l PUBLIC SERVICE ELECTRIC AND GAS COMPANY By PSE&G RESEARCH CORPORATION RESEARCH AND TESTING LABORATORY MARCH 1985 I

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