ML20203P880
| ML20203P880 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/31/1985 |
| From: | PSE&G RESEARCH CORP. |
| To: | |
| Shared Package | |
| ML18092B141 | List: |
| References | |
| RTL-ENV-86-01, RTL-ENV-86-1, NUDOCS 8605080294 | |
| Download: ML20203P880 (166) | |
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4
I' RTL-ENV-86-01 ARTIFICIAL' ISLAND RADIOLOGICAL '
ENVIRONMENTAL MONITORING PROGRAM 1
1985 RADIOLOGICAL REPORT +
JANUARY l TO DECEMBER 31, 1985 Prepared for PUBLIC SERVICE ELECTRIC AND GAS COMPANY By PSE&G RESEARCH CORPORATION RESEARCH AND TESTING LABORATORY i i
APRIL 1986
=* - - .y-.- , - --- - - --
e , I
TABLE OF CONTENTS PAGE
SUMMARY
l INTRODUCTION 2 THE PROGRAM 3 Objectives 3 1985 Program Overview (Table-1) 4 Sample Collection 9 Data Interpretation 10 Quality Assurance Program 11 Program Changes 11 RESULTS AND DISCUSSION 12 Atmospheric 12 Direct Radiation 15 Terrestrial 16 Aquatic 23 '
PROGRAM DEVIATIONS 30 CONCLUSIONS 31 REFERENCES 32 APPENDIX A - PROGRAM
SUMMARY
35 APPENDIX B - SAMPLE DESIGNATION AND LOCATIONS 43
' APPENDIX C - 1985 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 i
i LIST OF FIGURES NUMBER PAGE
- 1. Comparison of Average Concentrations of Beta Emitters in Precipitation and in Air Particulates, 1973 through 1985.................................. 13 1A. Comparison of Average Concentrations of Beta Emitters in Precipitation and in Air Particulates, 1983 through 1985.................................. 14
- 2. Average Ambient Radiation Levels from Quarterly TLDs in the Vicinity of Artificial Island, 1973 through 1985....................................... 17 2A. Comparison of Ambient Radiation Levels of Off-Site Indicator Stations vs. Control Stations, 1982 through 1985....................................... 18
- 3. Average Concentrations of Iodine-131 in Milk in the Vicinity of Artificial Island, May 1974 through December 1985...................................... 19 3A. Average Concentrations of Iodine-131 in Milk in the Vicinity of Artificial Island, 1983 through 1985... 20
- 4. Average Concentrations of Beta Emitters and Potassium-40 in the Delaware River in the vicinity of Artificial Island, 1973 through 1985............ 25 4A. Average Concentrations of Beta Emitters and Potassium-40 in the Delaware River in the Vicinity of Artificial Island, 1983 through 1985............ 26 5.
Average Concentrations of Tritium in the Delaware River in the Vicinity of Artificial Island, 1973 through 1985....................................... 27 SA. Average Concentrations of Tritium in the Delaware River in the Vicinity of Artificial Island, 1983 through 1985....................................... 28 11
SUMMARY
During the period from January 1 through December 31, 1985, the Research and Testing Laboratory (RTL), PSE&G Research Corpora-tion, has been responsible for the collection and analysis of all samples and the maintenance of sampling equipment for SGS connected with the Operational Radiological Environmental Mon-itoring Program at Artificial Island, Salem County, New Jersey.
Salem Generating Station (SGS) Unit One became critical on December 11, 1976, thereby initiating the operational phase of the Radiological Environmental Monitoring Program (REMP). This program was designed to identify and quantify concentrations of radioactivity in various environmental media and to quantify ambient radiation levels in the environs of Artificial Island.
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, wi11 fulfill the requirements of the SGS Technical Specifications, and will provide background data for the Hope Creek Generating Station. This report presents the results of thermoluminescent dosimetry and radiological analyses of environmental samples collected during 1985.
A total of 4294 analyses were performed on 1620 environmental samples during the period covered by this report. Samples of air particulates, air iodine, surface, ground and drinking water, benthic organisms, sediment, milk, fish, crabs, vege-tables, game, fodder crops, meat, and precipitation were collected. Thermoluminescent dosimeters were used to measure ambient radiation levels.
A variety of radionuclides, both naturally-occurring and man-made, were found in the above samples. Subsequent sampling of the indicators in the estuarine food-chain were at levels similar to those found during the preoperational phase of this program. It can be concluded that the radiological character-istics of the environment around Artificial Island during 1985 were not adversely affected by the operation of SGS Units one and Two.
1
INTRODUCTION Artificial Island is the site of Salem and Hope Creek Generating Stations. The Salem Generating Station consists of two operat-ing pressurized water nuclear power reactors. Salem Unit One has a net rating of 1090 MWe (3338 MWt), and Salem Unit Two is rated at 1115 MWe (3411 MWt). The Hope Creek Generating Station is a boiling water nuclear power reactor under construction.
The Hope Creek Unit has a net rating of 1067 MWe (3293 MWt).
Artificial Island is a man-made peninsula on the east bank of the Delaware River and was created by the deposition of hydrau-lic fill from dredging operations. It is located in Lower Alloways Creek Township, Salem County, New Jersey. The environ-ment 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 [14]. More specific information on the demography, hydrology, meteorology, and land use of the area may be found in the Environmental Report [14],
Environmental Statement [15], and the Final Safety Analysis Report for SGS [16].
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 monitor-ing 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, con-ducted 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 analyces and TLD's.
This report summarizes the results from January 1 through December 31, 1985, for the Artificial Island Radiological Environmental Monitoring Program.
2
THE PROGRAM The operational phase of the REMP was conducted in accordance with Section 3.2 of the Environmental Technical Specifications for SGS Units 1 and 2 [17,18], until August 12, 1985, when the Technical Specifications were modified. From that date forward the REMP was conducted in accordance with Sections 3/4.12 and 6.9.1.10 of Appendix A to SGS Operating Licenses D15.-70 and DPR-75 [19,20].
An overview of the program is provided in Table 1. Radioanalyt-ical data from samples collected under this program were com-pared with results from the preoperational phase. Differences between these periods were examined statistically, where appli-cable, to determine the effects, if any, of station operations.
The REMP for the Artificial Island Site includes additional samples and analyses not specifically required by the Salem Technical Specifications. The summary tables in this report include these additional samples and analyses.
Objectives The objectives of the Operational Radiological Environmental Monitoring Program are:
- 1. To fulfill the obligations of the Radiological Surveil-lance sections of the Technical Specifications for 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 radio-active 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 environ-ment.
This report, as required by Section 6.9.1.10 of the Salem Technical Specifications, summarizes the findings of the 1985 REMP. Results of the four-year preoperational program have been summarized for purposes of comparison with subsequent operational reports [4].
3
TABLE 1 1985 ARTIFICIAL ISLAND RADIO!DGICAL ENVIROfMENTAL MONITORING PROGRAM STATION CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE / FREQUENCY
- OF ANALYSIS I. ATMOSPHERIC ENVIRole(ENT
- a. Air Particulate 2S2 SD1 16El IF1 3H3 Weekly Gross alpha / weekly SS1 10D1 2F2 Gross beta / weekly Sr-89 s -90/ quarterly Gamuna scan / quarterly
, b. Air Iodine 2S2 SD1 16El 1F1 3H3 Weekly Iodine-131/ weekly SSl 10D1 2F2
- c. Precipitation 2F2 Monthly Cross alpha / monthly Gross beta / monthly Tritium / monthly Sr-89 & -90/ quarterly Gamma scan / quarterly II. DIRECT RADIATION
- a. Thermoluminescent 2S2 SD1 2El 1F1 3G1 3H1 Monthly & Gamma dose / monthly Dosimeters SSl 10D1 3El 2F2 3H3 Quarterly Gamma dose / quarterly 6S2 14D1 13El 2F6 7S1 16El 5F1 10S1 6F1 11S1 7F2 llP1 13F4
TABLE 1 (cont'd) 1985 ARTIFICIAL ISLAND RADIOIDGICAL ENVIROlmENTAL MONI'IORING PROGRAM STATION CODE COLLECTION '
MEDIUM INDICA'IOR CONTROL FREQUENCY TYPE / FREQUENCY
- OF ANALYSIS
- a. Thermoluminescent 4D2 9El 2FS IG3 Quarterly Gamma dose / quarterly Dosimeters (cont'd) llE2 3F2 10G1 12E1 3F3 16G1 10F2 12F1 13F2 13F3 14F2
- 15F3 16F2 III. TERRESTRIAL ENVIRO! MENT
- a. Milk 13E3 2F4 Semi-monthly 3G1 Iodine-131/ semi-monthly 5F2 Sr-89 & -90/ monthly llF3** Gamma scan / monthly 14F1 15F1 f
- b. Well Water 2S3 SD1 3E1 Monthly Gross alpha / monthly Gross beta / monthly Potassium-40/ monthly Tritium / monthly Sr-89 & -90/ quarterly Gamma scan / quarterly
.T TABLE 1 (cont'd) 1985 ARTIFICIAL ISLAND RADIOIDGICAL ENVIROletENTAL MONIMRING PROGRAM STATION CODE COLLECTION MEDIUM INDICAMR 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 1F3 1G1 3H5 Annually Sr-89 & -90/on collection 4F1 2G1 (At Harvest) Gamma scan /on collection SF1 14F3
- e. Game 3El llD1 Semi- Sr-89 & -90 (bones)/on collection (Muskrat) annually Gamma scan (flesh)/on collection
- f. Beef 3El 14F1 Semi- Ganuna scan /on collection annually
- g. Bovine Thyroid 3El 14F1 Semi- Ganana scan /on collection annually
- h. Fodder Crops SDI 2F4 3G1 Annually Gamma scan /on collection SF2 IlF3 14F1
TABLE 1 (cont'd) 1985 ARTIFICIAL ISLAND RADIOIDGICAL ENVIROletENTAL MONIMRING PROGRAM STATION CODE COLLECTION MEDIUM INDICAMR CONTROL FREQUENCY TfPE/ FREQUENCY
- OF ANALYSIS l
IV. AQUATIC ENVIRONMENT l r
I a. Surface Water llAl 7El 1F2 12Cl Monthly Gross alpha / monthly 16F1 Gross beta / monthly Tritium / monthly Sr-89 & -90/ quarterly Gamma scan / monthly
'd
- b. Edible Fish llAl 7El 12Cl Semi- Tritium in 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
TABLE 1 (cont'd) 1985 ARTIFICIAL ISLAND RADIOIDGICAL ENVIRONMENTAL MONI*IORING PROGRAM STATION CODE COLLECTION MEDIUM INDICA'IOR CONTROL FREQUENCY TYPE / FREQUENCY
- OF ANALYSIS
- e. Sediment 11A1 7El 16F1 12Cl Semi- Sr-90/on collection 15Al annually Gamma scan /on collection 16Al oo
- Except for TLDs, the quarterly analysis is performed on a composite of individual samples collected during the quarter.
- Station llF3 replaced station 15F1 (terminated milk production) on October 7, 1985.
i
l Sample Collection
$ In. order to meet the stated objectives, an appropriate opera-tional REMP 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, Delaware 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 manifest station effects, if any exist; control samples are 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. Indi-cator and control station data are also evaluated relative to preoperational data, i
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 fil-ters. 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 Pre-d cipitation 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, i Samples were collected monthly and transferred to new polyeth-ylene bottles. The collector was rinsed with distilled water to include residual particulates in the precipitation _ samples.
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.
't 9
- _ ~. _.-. . - . _ - _ _ _ . _ _. _ . -- ,. __ - _ . -
. . -- .- _ _ _ _ _ _ ~ .
All estuarine samples were collected by V. J. Schuler Associ-ates, Inc. and delivered by PSE&G personnel. Surface water samples were collected in new containers ~which were rinsed twice with the sample medium prior to collection. Edible fish and crabs were taken by net, and frozen in sealed polyethylene con-tainers. . Benthos and sediment were taken with a bottom grab sampler.
Milk samples were taken semi-monthly in new polyethylene con-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.
4 Appendix A describes and summarizes, in accordance with Section 6.9.1.10 of the Salem TS, the entire operational program as performed in 1985. 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.
i Data Interpretation Results of all analyses wer.e 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 1 2 sigma. This represents the range of values into which 95% of repeated anal-yses 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 21. Thus, the 2 sigma deviations of the averaged data represent sample and not analytical variability. When a group of data was 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, how-ever, is only representative of the sampled medium for that specific location and instant of time. As a result, variation 10
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. '
f Quality Assurance Program PSE&G Research Corporation, Research and Testing Laboratory 1 (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 [22] and the Environmental Division Procedures Manual [23]. The internal quality control activity of the Laboratory includes the quality j control of instrumentation, equipment and reagents; the use of j reference standards in calibration, documentation of established procedures and computer programs, and analysis of duplicate and i 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 j E-1 through E-5 in Appendix E.
Program Changes An additional vegetable control location (2Gl) was added to the ,
4 program on May 2, 1985.
The first annual nearest residence survey, as required by Sec-tion 3.12.2 of the Technical Specifications, was conducted in August, 1985.
4 Two additional sediment locations (15Al and 16A1) were added to the program on September 23, 1985.
Location 15F1, from which milk and fodder crops were collected, terminated milk production in October and was replaced by loca- i tion 11F3. No samples were missed due to this change.
2 I a 11
RESULTS AND DISCUSSION The analytical results of the 1985 REMP samples are divided into categories based on exposure pathways: atmospheric, direct, terrestrial, and aquatic. The analytical results for the 1985 REMP are summarized in Appendix A. The data for individual samples are presented in Appendix C.
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 emit-ters, Sr-89 and Sr-90, and gamma emitters. The weekly air par-ticulate 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.
Total data recovery for the eight sampling stations during 1985 was 99.2 percent.
Concentrations were detected in 382 of the 414 weekly samples analyzed for gross alpha emitters (Table.C-l Alpha concen-trations ranged from 0.7 x 10-3 to 5.1 x 10 g. pCi/m3 with the grand average for all stations being 2.0 x 10-3 pCi/m3, Analysis of weekly air particulate samples for gross beta (Table C-2) indicated concentrations were detected in 413 of the 414 samples ranging from 11 x 10-3 to 45 x 10-3 p grand average for all stations being 24 x 10 gi/m3 ' pCi/mw th the 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.
Strontium-89wasnotdetectedinanyofthe31 monthly-comgosited to samples analyzed;3LLD
<3.0 x 10-3 Ci/m sensitivities Sr-90 ranged was detected from one in only <0.2sample x 10-pCi/m3; LLD sensitivities ranged from <0.1 x atg.4x10-to 10- <0.6 x 10-3 pCi/m3 ,
Results of gamma spectrometry indicated detectable levels of Be-7 in all of the 32 monthly composites with a maximum of 98 x 10-3 pCi/m3 . Be-7 is a naturally-occurring radionuclide attributed to cosmic ray activity in the atmosphere. Radium-226, alsonaturally-occurring,wasdetecgedinoneofthesamplesat a concentration of 1.0 x 10-3 pCi/m . This is near or below the LLD sensitivities for the other samples which ranged from
<0.6 x 10-3 to <8.0 x 10-3 pCi/m3, 12
FIGURE 1 COMPARISON OF AVERAGE CONCENTRATIONS OF BETA EMITTERS IN PRECIPITATION AND IN AIR PARTICULATES,1973 THROUGH 1985 1000 Legend
- AIR 1E-3 pCi/m**3 2 /1
. RAIN Ci
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nGURE1A COMPARISON OF AVERAGE CONCENTRATIONS OF BETA EMITTERS IN PRECIPITATION AND IN AIR PARTICULATES 1983 THROUGH 1985 1000 Legend
. AIR 1E-3 pCi/m**3 e RAIN2 Ci/l t
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Air Iodine (Table C-4)
Cartridges for the adsorption of air iodine were connected in series after,each of the air particulate filters. The-adsorp-tion media in these cartridges is triethylenediamine (TEDA) impregnated charcoal. Iodine-131 was detected in one indicator location sample at 24 x 10-3 pCi/m3 This is near or below the LLD values of the other samples. The LLD sensitivities ranged from <6.1 x 10-3 to <50 x 10-3 pCi/m3 In addi-tion one sample did not meet the minimum sensitivity of 70 x 10-3,pCi/m3 ,
Precipitation (Tables C-6, C-7)
Although not required by the Salem TS, precipitation samples were collected at location 2F2 in the town of Salem. Monthly samples were analyzed for gross alpha, gross beta, and tritium.
No. gross alpha or gross beta results are available for the first four months due to insufficient precipitation. A gross alpha concentration was detected in only one of the eight samples analyzed at 1.0 pCi/L. This is below the LLD sensitivities for the remaining samples which ranged from <1.2 to <2.8 pCi/L.
Beta activity was detected in all eight monthly samples and ranged from 0.8 to 7.3 pCi/L, with an average of 3.1 pCi/L.
Tritium was not detected in any of the twelve samples analyzed:
LLD sensitivities ranged from <130 to <150 pCi/L.
Quarterly composites for strontium-89 and -90 were performed only on the third and fourth quarters due to a lack of precipi-tation during the first two quarters. Neither Sr-89 nor Sr-90 was detected in either of the samples. Gamma analysis performed oon each of the four quarterly samples detected only Be-7 in each at concentrations ranging from 17 to 52 pCi/L.
Direct Radiation (Tables C-8, C-9)
A total of 41 locations were monitored for direct radiation during 1985, including 6 on-site locations, 29 off-site loca-tions 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 stations. An additional 14 quarterly measurements were
-taken at schools and population centers with 3 additional con-trols beyond the 10 mile zone in Delaware.
Four readings for 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 5.7 milli-rads per~ standard month, and the corresponding averaged control dose rate was 6.4 millirads per standard month. The average 15
dose rate for the 29 quarterly off-site indicator TLD's was 5.4 millirads 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 13 year period through 1985. Figure 2A shows the monthly aver-ages of the off-site indicator stations and the control stations for 1982 through 1985. Ambient radiation levels during 1985 were comparable to those obtained during 1984. The annual averages for the off-site indicators were slightly lower than those in 1984, while the controls remained the same.
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 col-lection each month was also analyzed for Sr-89 and Sr-90 and gamma emitters. Figure 3A indicates that I-131 was not detected in any sample during 1985. Table C-10 lists the results and shows that sensitivities ranged from <0.1 to <0.3 pCi/L.
Strontium-89 was detected in one indicator and one control location at concentrations of 1.1 pCi/L and 1.5 pCi/L respec-tively; LLD sensitivities ranged from <0.8 to <1.5 pCi/L.
Strontium-90 was found in all but on'e of the samples analyzed.
The Sr-90 annual mean for the indicator locations was 1.9 pCi/L with a range of 1.0 to 4.0 pCi/L; annual mean for the control location was 2.4 pCi/L with a range of. 1.5 to 3.2 pCi/L.
Gamma spectrometry showed detectable concentrations of K-40 in all samples. The annual mean concentration of K-40 for the indicator locations was 1357 pCi/L with a range of 1200 to 1400 pCi/L; K-40 mean for the control location was 1342 pCi/L with a range of 1300 to 1400 pCi/L. Cesium-137 was detected in three samples from one indicator station and in one control station sample. The indicator station concentrations ranged from 2.6 to 3.9 pCi/L and the control station value was 2.3 pCi/L. The Cs-137 LLDs for all stations ranged from <l.4 to <3.4 pCi/L.
Manganese-54 was detected in one control station sample at 3.5 pCi/L; LLD sensitivities ranged from <0.4 to <3.0. Radium-226 concentrations ranging from 3.3 to 14 pCi/L were detected in eight indicator station samples; LLD sensitivities ranged from
<2.5 to <6.5 pCi/L. Concentrations of naturally-occurring Th-232 were detected in three indicator station samples ranging from 8.0 to 13 pCi/L; LLDs ranged from <5.8 to <13 pCi/L for the.other samples.
16 1
RGURE 2 AVERAGE AMBIENT RADIATION LEVELS FROM QUARTERLY TLDS IN THE VICINITY OF ARTIFICIAL ISLAND,1973 THROUGH 1985 10 Legend
. ALL STATIONS
~
. CONTROL STATIONS 8
1 5
y 7-n..
H o e ,. . .
s /,/.\/ A p 4 Ifft n ,n\ .
1, . v . 4.. ? M..s,y .A % f.
d,_
.;.;e.:,17 4 9.
n 7,
.c,. .
4 i .
.. ./... .
A /
A
- :s : :=. :
, s
. t : :
Es E5 N E D 5 I& E5 2
b iS is i$ $3 i iS 9E 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986
RGURE 2A COMPARISON OF AMBIENT RADIATION LEVELS OF OFF-SITE INDICATOR STATIONS VS. CONTROL STATIONS 1982 THROUGH 1985 10 Legend
. OFF-SITE STATIONS s a CONTROL STATIONS l\
8 i
f =
.c 7
t
,0 e *i
=
i . n t
~ 7/1 ,,
ft V-@. h, Vaf.fW 4
3-JhhAh)JkbONbJhhAh)Jkh0kbJhhAh)Jk$0kbJkhAh)JkbONbJkhAh)Jk$0hb'J 1982 1983 1984 1985 1986 1987
6I pCi/l 2 - s 5 _
w , i i,,,i, , . Z
< ATMOSPHERIC WEAPONS TEST
-1
, 6 / 17/ 74 e
mt m Z
- ATMOSPHERIC WEAPONS TEST -
9/26/76
_Z ii -i G ii
~-
-< O N
ATMOSPHERIC WEAPONS TEST OO N <
w 9/ 7/77
________ ::==, i iiiii q Z G "*-__________ ATMOSPHERIC WEAPONS I I IIll O N-
)> m
--~~~
TEST
'3 3/14/ 7 8 yZ H --i G qZ g v s__ THREE MILE ISLAND -3 3/28/79 C ->j 3> O o- FZ
_ (n a
<____ P ERIC WEAPONS TEST g
z_ m e OO m
" g_ O N Z
=. ( (A R
$ 7 p g-l^
m -'
8
- O z-C G
OI I F=
$ _.a X e
G @
m U1 m ,
FIGURE 3A AVERAGE CONCENTRATIONS OF IODINE-131 IN MILK IN THE VICINITY OF ARTIFICIAL ISLAND,1983 THROUGH 1985 10 0 10 o ,
5 i
O., __ _ _ _ . v#'
JFMAMJJASONDJFMAMJJASONDJFMAMJJASONDJFMAMJJASONDJ 1983 1984 1985 1986 1987
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 alpha, gross beta, tritium and potassium-40. Quarterly compos-ites were analyzed for radiostrontium and gamma emitters.
Gross alpha concentrations from 1.4 to 2.2 pCi/L were detected in four of the indicator samples and one control sample, with LLD sensitivities for the other analyses ranging from <0.9 to <2.7 pCi/L. Gross beta activity was detected in all of the samples.
The mean activity for the indicator locations was 9.9 pCi/L with a range of 3.4 to 14 pCi/L; mean activity for the control loca-tion was 8.4 pCi/L with a range of 7.4 to 9.2 pCi/L. K-40 in each monthly sample was determined by atomic absorption spectro-scopy. Mean activity for the indicator locations was 11 pCi/L with a range of 3.7 to 18 pCi/L, and mean activity for the con-trol location was 9.3 pCi/L with a range of 8.4 to 12 pCi/L.
All tritium results were at LLD levels of <130 to <160 pCi/L.
Neither Sr-89 ncr Sr-90 was detected in any of the samples. The LLD sensitivities for Sr-89 ranged from <0.4 to <0.6 pCi/L, and from <0.4 to <0.5 pCi/L for Sr-90.
Gamma spectrometry showed detectable levels of K-40 in three of the eight indicator samples ranging from 10 to 18 pCi/L. Two control station samples had detectable concentrations of K-40 at 12 and 15 pCi/L; LLD values for the other two samples were <11 and <12 pCi/L. Ra-226 was detected in one control station sample at 1.3 pCi/L which was near or below LLD in the other eleven indicator and control station samples which ranged from <1.1 to
<1.5 pCi/L. Concentrations of Th-232 were detected in two indi-cator station samples at 1.8 and 2.7 pCi/L; LLD values for the other ten indicator and control station samples ranged from <1.7 to <2.7 pCi/L.
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 compos-ited into a monthly sample. The raw water source for this 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 water were analyzed for Sr-89, Sr-90, and gamma emitters.
Detectable alpha activity was noted in only two raw water samples at 1.6 and 4.2 pCi/L; LLD sensitivities ranged from <l.3 to <3.4 pCi/L (raw), and from <0.6 to <2.4 pCi/L (treated). Beta activ-ity was observed in 23 of the 24 monthly samples with ranges of 1.1 to 3.8 pCi/L (raw), and 1.0 to 3.8 (treated), and averages of 2.6 pCi/L (raw) and 2.3 pCi/L (treated). K-40 concentrations for raw and treated samples were practically identical and were 21
lower than the beta activity in all cases except for the one 1 sample which was <1.0 pCi/L. The K-40 average for both the raw and treated samples was 1.4 pCi/L. Tritium activity was observed in three of the twenty-four samples, ranging from 150 to 180 pCi/L.
Strontium-89 and -90 was not detected in any of the eight quar-terly composite water samples. LLD sensitivities ranged from
<0.6 to <0.8 pCi/L for Sr-89, and from <0.5 to <0.7 pCi/L for Sr-90. Gamma spectrometry detected Te-129m in one sample at 36 pCi/L, and Th-232 in two samples at 0.8 and 1.7 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, aspar-agus, cabbage, and tomatoes. Each sample was analyzed for Sr-89, Sr-90, and gamma emitters. Sr-89 was not found in any of the eighteen samples; Sr-89 LLDs ranged from <2.9 to <14 pCi/kg-wet.
Sr-90 was detected in three of the eighteen samples with activi-ties ranging from 2.4 to 27 pCi/kg-wet. These activities were detected in one tomato (control location), and two cabbage (indicator location) samples. St-90 LLDs ranged from <2.0 to
<9.8 pCi/kg-wet. All samples contained K-40 at concentrations from 1300 to 2900 pCi/kg-wet, with an average for all samples of 2100 pCi/kg-wet. A trace of Cs-137 was detected in one indicator station tomato sample at 1.5 pCi/kg-wet; this is equal to the lowest reported sensitivity value. LLD sensitivities ranged from
<1.5 to <18 pCi/kg-wet. Concentrations of Ra-226 were detected in three samples ranging from 4.6 to 8.4 pCi/kg-wet; this is near or below the sensitivities for the other 15 samples which ranged from <1.1 to <39 pCi/kg-wet.
Game (Table C-19)
Two muskrat samples were collected in January. Bones from both samples were analyzed for Sr-89 and Sr-90 while the flesh was analyzed for gamma emitters. Sr-89.was not found in either of the samples; Sr-89 LLD's were <72 and <140 pCi/kg-dry. Sr-90 was found in both samples at levels of 220 and 1300 pCi/kg-dry. The maximum Sr-90 concentration found in the preoperational program was 1800 pCi/kg-dry. Gamma scans of the flesh indicated the presence of naturally-occurring K-40 in both samples at concen-trations of.2800 pCi/kg-wet.
Beef and Bovine Thyroid (Table C-19)
Two beef samples and the thyroid glands from each were collected.
Analysis of the flesh for gamma emitters indicated the presence of naturally-occurring K-40 at concentrations of 1900 and 2000 PCi/kg-wet, and Cs-137 at 7.8 and 11 pCi/kg-wet.
22
Analysis of the thyroid glands for gamma emitters detected K-40 in the control location at 1500 pCi/kg-wet. The indicator loca-tion K-40 LLD was <1100 pCi/kg-wet.
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. Samples collected for wet gamma analysis included barley, feed corn, corn silage and soybeans.
Potassium-40 was detected in all of the eleven samples at con-centrations ranging from 2500 to 16000 pCi/kg-wet, with an average of 8100 pCi/kg-wet. Be-7, from the atmosphere, was found in five of the samples at concentrations ranging from 160 to 840 PCi/kg-wet.
Aquatic 5
Surface Water (Tables C-21, C-22, C-23, C-24, C-25)
Surface water samples were collected monthly at five locations in the Delaware estuary. One location is Et the outfall area, another is downstream'from the outfall area, and another is directly west of the outfall area at the mouth of the Appoquini-mink 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 12C1, at the mouth of the Appoquinimink River, serves as the operational control. All surface water samples we.ie analyzed monthly for gross alpha and 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 48 indicator samples and in one of.the twelve control samples, with levels ranging from 1.5 to 7.8 pCi/L; LLD sensitivities ranged from
<1.2 to <5.0. Beta concentrations for the indicator stations ranged from 4.5 to 120 pCi/L with an average of 55 pCi/L, and, for the control station, from 11 to 76 pCi/L with an average of 50 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
23
l Tritium concentrations for the indicator stations ranged from 130 to 1700 pCi/L. The average of the 25 indicator samples with detectable levels of tritium was 269 pCi/L. Tritium was detected in four of the twelve control samples and ranged from 140 to 190 pCi/L with an average of 160 pCi/L. Levels for the years 1973 through 1985 are plotted in Figure 5.
The tritium value of 1700 pCi/L was detected at outfall location, 11A1 and was most likely due to a liquid discharge from a radwaste (Chemical Volume Control) tank release from Salem Unit 2 which occurred on July 8, 1985. The result was ten times higher than the corresponding control station value. Because the result was ten times higher than the control station value, it was reported to the USNRC under our former Salem Environmental Technical Specifications which were in effect at that time. Our current Salem Technical Specifications establishes a tritium reporting level of 30,000 pCi/L. The 1700 pCi/L result should not be interpreted as representing a cignificant abnormality since the measurement obtained was within the range to be expected to exist during a liquid discharge.
Gamma spectrometric analysis of surface water samples showed detectable concentrations of K-40 in 58 of the 60 samples. The average K-40 concentration at the indicator stations was 67 pCi/L with a range of 21 to 140 pCi/L. Average K-40 concentration at the control station was 59 pCi/L with a range of 12 to 90 pCi/L.
Radium-226 was detected in eight indicator station samples with the values ranging from 0.6 to 1.7 pCi/L, and one control station sample at 1.3 pCi/L. This is near or below LLD sensitivities which ranged from <0.4 to <1.9 pCi/L. Concentrations of Th-232 in six indicator station samples were detected ranging from 0.8 to 3.7 pCi/L and two control samples at 1.9 and 3.1 pCi/L. LLD sensitivities for Th-232 ranged from <1.6 to <3.1 pCi/L.
Strontium-89 was detected in one of sixteen indicator station samples at 0.9 pCi/L; none was detected in the four control station samples. The LLD sensitivities ranged from <0.4 to <0.8 pCi/L. Sr-90 was not detected in any of the twenty samples; LLD sensitivities ranged from <0.4 to <0.6 pCi/L.
Fish (Tables C-26, C-27)
Edible species of fish were collected semi-annually at three locations and analyzed for tritium and gamma emitters (flesh) and for Sr-89 and Sr-90 (bones). Samples included channel catfish, summer flounder, weakfish and bluefish.
Gamma spectrometry of these samples indicated K-40 in all six samples at an average concentration of 3100 pCi/kg-wet with a range of 3000 to 3200 pCi/kg-wet. Four of the six samples had detectable concentrations of Cs-137 with an average of 10 pCi/kg-wet and a range of 4.8 to 11 pCi/kg-Vet. The LLD sensi-tivity for the other two samples was <11 and <13 pCi/kg-wet.
24 o
e
?
.x RGURE 4 AVERAGE CONCENTRATIONS OF BETA EMITTERS AND POTASSIUM-40 1
IN THE DELAWARE RIVER IN THE VICINITY 0F ARTIFICIAL ISLAND, 1973 THROUGH 1985 1000 Legend
. GROSS BETA _
o POTASSIUM-40 too c
- .b. . -
!$ vu N 9 m lII o#
- i b Ni \ fi o ll
?\ l h. ;. 22 M1 .1 \l 4. \ i4 i \ .~
= 1 '4. # AV \/ '. / l t ,Y
}" 'e. I 1
'\Lh'h/t V i I\ l
?'k
. fl' ;-
\.I ill
'V. .y ;
. "y P
10 ,
1 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986
RGURE 4A AVERAGE CONCENTRATIONS OF BETA EMITTERS AND POTASSIUM-40 IN THE DELAWARE RIVER IN THE VICINITY OF ARTIFICIAL ISLAND, 1983 THROUGH 1985 1000 Legend
. GROSS BETA o POTASSIUM-40
'cc
.n A - .
~
m j i 8
. t y ~. - ?' -
, n vy ;
y s i n :
\\ l D. H .
,, $f l 'c.l?
'l
..M JhhAhbJkbOhbJkhAh)JkbONbJkhAhbJkbOhbJhhAb)JkbONbJ 1983 1984 1985 1986 1987
FlGURE 5 AVERAGE CONCENTRATIONS OF TRITIUM IN THE DELAWARE RIVER IN THE VICINITY OF ARTIFICIAL ISLAND,1973 THROUGH 1985 1000 1 ,_
b
\..sp,j.I\
l'~. .
3m ,,,
Vs.j.s,/\/~s!.I'~I\*..*.)\. .*
- N 5 5 5C C 2]e zJ UE I
,, asy ass ,
1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986
FIGURE SA AVERAGE CONCENTRATIONS OF TRITIUM IN THE DELAWARE RIVER IN THE VICINITY OF ARTIFICIAL ISLAND,1983 THROUGH 1985 10000 1000 n l\
&' l\ n I \
I \l \. .I \
10 0
.....1' \.-. . . . . .. . . . . . . . .> ! \1L . _
JhhAh)JkbOhbJhhAh)JkbOhbJkhAh)JkbOhbJhhAh)JkbOhbJ 1983 1984 1985 1986 1987
Strontium-89 was detected in one of the six bone samples analyzed at a level of 70 pCi/kg-dry; the LLD sensitivities for the other five samples ranged from <26 to <36 pCi/kg-dry. Five of the six semi-annual samples analyzed for Sr-90 had detectable concentra-tions ranging from 24 to 350 pCi/kg-dry with an average of 93 pCi/kg-dry, and the sixth sample was <29 pCi/kg-dry. The maximum level detected during the preoperational period was 940 pCi/kg-dry with an average of 335 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 detectable activity of_400 pCi/L at the outfall station, 11Al; 200 pCi/L at the downstream station, 7E1; and 200 pCi/L at the control station, 12C1. Only one sample, indicator station 7El, had a detectable concentration of tritium for the organic frac-tion with a result of 90 pCi/L.
Blue Crab (Table C-28)
Blue crab samples, collected semi-annually at two locations, were analyzed for gamma emitters, Sr-89 and Sr-90, and tritium in the aqueous fraction. The shells were also analyzed for Sr-89 and Sr-90.
Potassium-40 in all four samples was the only gamma emitter detected. Potassium-40 levels ranged from 1700 to 2500 pCi/kg-wet with an average of 2200 pCi/kg-wet.
Strontium-89 was not detected in any of the four flesh samples; LLD sensitivities ranged from <27 to <40 pCi/kg-Wet. Both shell samples from the second semi-annual set had detectable levels of Sr-89 at 50 and 64 pCi/kg-dry; these are below the LLD sensitiv-ities for the first set of semi-annual samples which were <78 and
<120 pCi/kg-dry.
Strontium-90 was detected in one flesh sample (control location) at 28 pCi/kg-wet. The LLD sensitivitics for the other three samples ranged from <18 to <22 pCi/kg-wet. All four shell samples had detectable concentrations of Sr-90 ranging from 24 to 240 pCi/kg-dry with an average of 170 pCi/kg-dry.
Tritium activity in the aqueous fraction of the flesh was detec-ted only in the first semi-annual samples at levels of 200 pCi/kg-wet for each. The LLD sensitivity for both samples of the second semi-annual set was <50 pCi/kg-wet.
Benthic Organisms and Sediment (Tables C-29, C-30)
Benthic organisms were separated from the bottom sediment and analyzed for Sr-89 and Sr-90, and gamma emitters. Strontium-89 and Sr-90 was not detected in any of the samples. All gamma 29
emitters searched for were <LLD sensitivities. It should be noted that, due to the very small sample sizes for all samples (0.02 gram to 1.72 gram dry), satisfactory strontium and gamma sensitivities could not be achieved.
Sediment samples of sufficient size were available to enable sensitivity requirements for both Sr-90 and gamma emitters to be met. Levels of Sr-90 were below LLD (<19 to <23 pCi/kg-dry) in all ten samples analyzed. Results of gamma spectrometry indi-cated the presence of naturally-occurring K-40, Ra-226, and Th-232 in all ten samples with averages of 12000, 790, and 860 pCi/kg-dry respectively. Concentrations of the gamma emitters Be-7, Mn-54, Co-60, Cs-134 and Cs-137 were also detected. Be-7 was detected in one sample at 430 pCi/kg-dry; LLDs ranged from
<150 to <230 pCi/kg-dry. Mn-54 in one sample was detected at 38 pCi/kg-dry with LLDs ranging from <20 to <29 pCi/kg-dry. Con-centrations of Co-60 were detected in six samples ranging from 45 to 160 pCi/kg-dry, with the average being 64 pCi/kg-dry.
Co-60 LLD sensitivities for the remaining four samples ranged from <29 to <37 pCi/kg-dry. Cs-134 concentrations were detected in two samples at levels of 41 and 53 pCi/kg-dry, with LLDs ranging from <16 to <35 pCi/kg-dry. Cs-137 concentrations in six samples ranged from 16 to 88 pCi/kg-dry; LLD sensitivities ranged from <14 to <28 pCi/kg-dry.
PROGRAM DEVIATIONS Gross alpha and gross beta air particulate results from location 3H3 for the week beginning March 4, are unavailable due to a faulty sampling assembly.
Gross alpha and gross beta air particulate results, as well as iodine-131 filtered air results from location 16El for the week beginning August 27, are unavailable due to vandalism of the sampling assemblies.
Strontium-89 and -90 air particulate results for the third quarter from location 1F1 are unavailable due to a loss of sample during analysis.
Iodine-131 results from location 3H3, for the week beginning November 4, did not meet sensitivity due to a malfunction in the sampling equipment.
The second semi-annual collection of muskrat samples was not obtained. Muskrats are normally trapped during November and December each year. However, in 1985, because of weather condi-tions and the poor quality of the pelts, muskrats were not i available from the trappers.
1 l
30
Salem's former Environmental Technical Specifications required that gamma isotopic analysis be performed on milk samples once a month and that I-131 analyses be performed on each semimonthly milk sample collected. On August 12, 1985, the Station's Tech-nical Specifications were amended and the requirements for con-ducting the Radiological Environmental Monitoring Program were modified. The specifications now require that gamma isotopic analyses be performed semimonthly when cows are on pasture and monthly when they are not on pasture. According to the current Technical Specifications, gamma isotopic analysis and I-131 analysis are required to be performed at each milk location specified in Table 3.12-1. Gamma isotopic analyses were not performed on the second, semimonthly milk samples collected dur-ing August, September, October and November. Gamma isotopic analysis is currently being performed on each sample collected.
CONCLUSIONS The Radiological Environmental Monitoring Program for Salem Generating Station was conducted during 1985 in accordance with the SGS 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 com-pliance with 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 5.9 mrad /std. month.
! No unusual radiological characteristics were observed in the environs of Artificial Island. The operation of SGS Units One and Two had no significant effect on the radiological character-istics of the environs of Artificial Island.
- 31 l
y 1 n REFERENCES
[1] Radiation Management Corporation. "Salen 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, 1975.
[3] Radiation Management Corporation. " Artificial Island Radiological Environmental Monitoring Program - 1975 Annual Report". RMC-TR-76-04, 1976.
[4] Radiation Management Corporation. " Artificial Island Radiological Environmental Monitoring Program - Preoperation Summary - 1973 through 1976". RMC-TR-77-03, 1978.
[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 Environmental Monitoring Program - 1980 Annual Report". RMC-TR-81-03, 1981.
[10] Radiation Management Corporation. " Artificial Island Radiological Environmental Monitoring Program - 1981 Annual Report". RMC-TR-82-01, 1982.
[11] Radiation Management Corporation. " Artificial Island Radiological Environmental Monitoring Program - 1982 Annual Report". RMC-TR-83-03, 1983.
[12] PSE&G Research Corporation, Research and Testing Laboratory.
" Artificial Island Radiological Environmental Monitoring Program - 1983 Annual Report". RTL-ENV-84-01, 1984.
[13] PSE&G Research Corporation, Research and Testing Laboratory.
" Artificial Island Radiological Environmental Monitoring Program - 1984 Annual Report". RTL-ENV-85-01, 1985.
32
. u-REFERENCES (cont'd.)
[14] Public Service Electric and Gas Company. " Environmental Report, Operating License Stage - Salem Nuclear Generating Station Units 1 and 2". 1971.
[15] United States Atomic Energy Commission. '" Final Environmental Statement -
Salen Nuclear Generating Station, Units 1 and 2". Docket No. 50-272 and 50-311, 1973.
[16] Public Service Electric and Gas Company. " Updated Final Safety Analysis Report - Salem Nuclear Generating Station, Units 1 and 2". 1982.
[17] Public Service Electric and Gas Company. " Environmental Technical Specifications - Salen Nuclear Generating Station Units 1 and 2",
Appendix B to Operating License DPR-70,1976 (through Amendment 58) .
[18] 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) .
i (19] Public Service Electric and Gas Company. " Salem Nuclear Generating Station Unit 1 - Technical Specifications", Appendix A to Operating License No. DPR-70, 1976, Sections 3/4.12 and 6.9.1.10 (Amendment 59 jdi seq).
[20] Public Service Electric and Gas Company. " Salem Nuclear Generating Station Unit 2 . Technical Specifications", Appendix A to Operating License No. DPR-75, 1981, Sections 3/4.12 and 6.9.1.10 (Amendment 28 jdi seq).
[21] U. S. Environmental Protection Agency. " Prescribed Procedures for Measurement of Radioactivity in Drinking Water." EPA-600/4-80-032, August, 1980.
[22] PSE&G Research Corporation, Research and Testing Laboratory. " Environ-mental Division Quality Assurance Manual." September, 1980.
[23] PSE&G Research Corporation, Research and Testing Laboratory. " Environ-mental Division Procedures Manual." February, 1981.
i 33
p i
I APPENDIX A PROGRAM
SUMMARY
I a
i I.
9 35
n -,
ARTIFICIAL ISIAND RADIOIAGICAL ENVganamama'FAL NOMITORING PROGRAft SESWEARY SALBl NUCLEAR GENERATING STATION DOCERT NO. 50-272/-311 SALEN COUNTY, MSN JERSEY JANUARY 1, 1985 to DECBEBER 31, 1985 ANALYSIS AND IANER NtseER OF NEDIUM OR PATHNAY TOTAL 3RSIDER LIMIT OF ALL INDICATOR IACATIOGIS IACATION NITN WIGNRST 90 BAN CONTROL IACATIOW(8) amanegggg SANrLED OF ANALYSES DETECTION seEAN" NAsst seRAN IERAN REPORTED (out? Or NEASUREMENT) PERFORNED (LLD)* (RANGE) DISTANCE AND DIRSCT1005 (RANGE) (RANGE) _ _ _ _ . . . .
Air Particulates Alpha 414 0.8 2.1 (335/363) 1631 4.1 mi Neat 2.3 (48/51) 2.0 (47/51) 0 )
(10'3 pC1/m3 ) (0.7-5.13 (1.2-5.1) (1.2-3.6)
Beta 414 0.9 25 (363/363) SDI 3.5 mi E 25 (52/52) 24 (50/51) 0 (13-45) (14-43) (11-39)
St-89 31 0.2 < Lla - <LLD (Lla O St-90 31 0.1 0.4 (1/31) 581 1.0 mi E 0.4 (1/4) < LLD 0 Ga.ma Be-7 32 -
74 (28/24) 501 3.5 mi E 86 (4/4) 71 (4/4) 0 (58-98) (75-98) (56-81)
Ra-226 32 0.6 1.0 (1/28) 10D1 3.9 mi SSN 1.0 (1/4) < LLD 0 LJ (1.0) (1.0) 4 Air Iodine 1-131 415 6.1 24 (1/363) 2F2 8.7 al NME 24 (1/52) <!Ja 0 (10'3 pC1/m3 ) (24) (24)
Precipitation Alpha 8 1.2 1.0 (1/0) 2F2 8.7 mi inst 1.0 (1/0) Iso control 0 (pC1/L) (1.0) (1.0) Iocation Beta 8 1.0
- 3.1 (8/8) 2F2 8.7 al NME 3.1 (8/8) Ilo Ozatrol 0 (0.8-7.3) (0.8-7.3) Location a-3 12 130 <LLD - < LIA Ito Control 0 Incation Sr-49 2 0.5 < LIA - <LLD 100 Control 0
!acation Sr-90 2 0.5 < LIA - < Lta No Control 0 location Gamme
.se-7 4 -
24 (4/4) 2F2 0.7 mi NME 28 (4/4) No Q>ntrol 0 (17-52) (17-52) Incation Direct Radiation Gamma 288 - 5.8 (252/252) list 0.09 mi ser 6.9 (12/12) 6.4 (36/36) 0 (arad/std. month) Dose (monthly) (3.7-9.1) (4.0-9.1) (5.1-7.5) l Gemme 164 -
5.4 (140/140) 1G3 19 mi N 6.6 (4/4) 6.1 (24/24) 0 Dose (qtray.) ( 3. 6-7. 6 ) (5.8-7.2) (5.1-7.2)
N .
t ARTIFICIAL ISIAND RADIOIDGICAL ENygenamsamsfAL MONITORING PROGRAM StSSIARY SALEM NUCLEAR cameATING STATIOel DOCERT No. 50-272/-311 SAlme COUNTY, Mar JERSEY JANUARY 1,1985 to DeCastER 31, 1985 IRBSER OF A384 LYSIS AND IANER COef7RDL I4CATICII(S) annamnyr3 ggE LIMIT OF ALL IISICATOR ISCATIONS IDCATIOOB NITN WIGINST MEAN MEDILBt OR PATHNAY TOTAL IRBSER fERAN MEAN REPORTED MEAN" NAf8E SAMPLED OF AhALYSES DETECTION MEAsm'manuTS DISTANCE AIS DIRECT 1085 (RANGE) (RAIIGE)
(UNIT OF MEASURatENT) PERPOastED (LLD)* (RAaICE)
- (LLD < LID 0 Milk 1-131 144 0.1 (LLD (PC1/L) 1.5 (1/12) 1.5 (1/12) 0 Sr-89 72 0.8 1.1 (1/60) 3G1 17 mi NE (1.1) (1.5) (1.5) 3.1 (12/12) 2.4 (12/12) 0 Sr-90 72 0.0 1.9 (59/60) 5F2 7.0 mi E (1.0-4.0) -(2.4-4.0) (1.5-3.2)
Gamma 1392 (12/12) 1342 (12/123 0 E-40 72 - 1357 (60/60) 13E3 4.9 at W (1300-1400) (1300-1400)
(1200-1400) 3.5 (1/123 0 0.3 < Lla 3G1 17 mi NE 3.5 (1/12)
Mn-54 72 (3.5) (3.5?
3.4 (3/12) 2.3 (1/123 0 Cs-137 72 1.2 3.4 (3/60) SF2 7.0 at E (2.6-3.9) (2.3)
(2.6-3.9) <LLD 0 g 72 7.5 (8/60) 14F15.5 at wenf 10 (4/12)
Ra-226 2.5 m (3.3-14) (7.0-14) 0 14F1 5.5 mi enne 13 (1/12) (LLD th-232 72 58 10 (3/60)
(0.0-13) (13)
A 1.9 (4/24) Sol 3.5 mi E 2.1 (1/12) 1.4 (1/12) 0 Alpha 36 0.9 (1.4)
Nell Nater (1.6-2.23 (2.1)
(pC1/L) 12 (12/12) 8.4 (12/12) 0 36 1.0*" 9.9 (24/24) 501 3.5 mi E seta (3.4-14) (11-14) (7.4-9.2)
- 11 (24/24) 501 3.5 mi E 14 (12/12) 9.3 (12/12) 0 E-40 36 (0.4-12)
(3.7-18) (12-18)
- < LLD < LLD 0 a-3 36 130 < LIA
= <LLD <ILD 0 St-89 12 0.4 < !JA
- <LLD <LIa O Sr-90 12 04 < LIA Gamma 14 (2/4) 14 (2/4) 0 E-40 12 10 13 (3/8) 3E1 4.1 mi NE (12-15) (12-15)
(10-18) 1.3 (1/4) 0 1.1 <!1D 3E1 4.1 mi NE 1.3 (1/4)
Ra-226 12 (1.33 (1.3) 2.7 (1/4) (I4D 0 Th-232 12 1.7 2.2 (2/8) 283 700 ft lets (2.7)
(1.0-2.7)
ARTIFICIAL ISIAND RADIOIAGICAL ENVImam-TAL NOMITORING Fannem ggageARY
=
SAI24 NUCLEAR GENERATING STATION DOCERT No. 50-272/-311 SALat COUNTY, IsEN JERSEY JANUARY 1,1985 to DeCaenER 31, 1985 ANALYSIS AND IANER mamamme OF NEDIUM OR FATNNAT TOTAL BRasBER LIMIT OF ALL IllDICATOR IACATIONE IACATION NITE NIGISBT IgEAN CONTROL IACATION(3) ammanrsyggg SANFLED OF ANALYSES DETMCTION IIBAlf" NAf05 IEIAN IIEAN REFONTED (UNIT OF stEASURatENT) FERFOApeED . (LLD) * (RANGE) DISTANCE AND DIRACTION (RANGE) (RANGE) ..
rotable Mater Alpha 24 0.6 2.9 (2/24) 2F3 8.0 at InsE 2.9 (2/24) too cont'rol O Raw-Treated (1.6-4.2) (1.6-4.2) Incation (pC1/L) Beta 24 1.0 2.5 (23/24) 2F3 8.0 mi Inst 2.5 (23/24) No control 0 (1.1-3.4) (1.1-3.8) Iocation E-40 24 -
1.4 (24/24) 2F3 0.0 mi IAIE 1.4 (24/24) leo Cbntrol O
- (0.8-2.6) (0.0-2.6) location N-3 24 130 163 (3/24) 2F3 8.0 at NNE 163 (3/24) Iso control 0 (150-180) (150-100) location Sr-89 8 0.6 <LLD - <LLD 100 Control 0 location Sr-90 8 0.5 < LIA -
< LLD aso control 0 location G"""*
t) c Te-129m 8 13 34
. (1/8) 2F3 0.0 mi InsE 36 (1/0) Iso control 0
'(36) (36) Iocation th-2 32 8 1.6 1.2 (2/0) 2F3 8.0 mi anIE 1.2 (2/8) No Cbntrol 0 (0.8-1.7) (0.8-1.7) Incation Fruit 6 Vegetables Sr-89 18 2.9 < ILD - (ILD < IJD 0 (PC1/kg
- t)
Sr-90 18 2.0 19 (2/10) 4F1 5.1 mi BNE 27 (1/3) 2.4 (1/8) 0 (11-27) (27) (2.4)
Comma E-40 18 -
2250 (10/10) 2814.4 mi IRIE 2500 (1/1) 1950 (8/0) 0 (1700-2900) (2500) (1300-2500) co-137 18 1.5 1.5 (1/10) 14F3 5.4 mi anaf 1.5 (1/2) < IJA 0 (1.5) (1.5)
Ra-226 18 1.1 6.5 (2/10) 4F1 5.1 mi EME 8.4 (1/3) 6.2 (1/8) 0 (4.6-8.4) 8.4 (6.2)
Game St-89 2 72 <LLD - < LLD < IJE O (pci/kgwiry) (cones)
Sr-90 2 -
1300 (1/1) 3E1 4.1 mi NE 1300 (1/1) 220 (1/1) 0 (bones) (1300) 1300 (220)
(PC 1/kg-wet) Camma (flesh)
E-40 2 -
2000 (1/1) 3E1 4.1 mi NE 2000 (1/1) 2000 (1/1) 0 (2000) (2800) (2000) 1101 3.5 at SN 2000 (1/1)
(2000)
f 1 ARTIFICIAL ISIAND RADIOIDGICAL ENVIROISWIFFAL MONITORING P900BAII SIBOIARY SALBI NUCLEAR GENERATIIIG STATION DOCEST NO. 50-272/-311 SALDI COUltrY, Mas JERSEY JApunRY 1, 1995 to Deca eER 31, 1945 ammama CF AIIALYSIS AND :DNER COIrrtDL IDCATION(S) m ennygg LIMIT OF ALL IISICATOR IACATICIW IOCATION WITIf NIGERST ISAN IIEDIIBI OR FATuMAY TOTAL IRSSER SEAII ISA31 REFOATED ISAN** IIAIRE SAMPLED OF ANALYSES DETACTIOII mm %
DISTAIICE AND DIRSCTICII (RAIIGE) (RAIIGE)
(UNIT OF IIEASURRIIBIT) PERFORIBED (LLD)* (RA81GE)
Gamma 1900 (1/3) 0 Beef 2000 (1/1) 3E14.1 al IIE 2006 (1/1)
(pct /kg-wet) E-40 2 -
(1900)
(2000) (2000) 11 (1/1) 11 (1/1) 0 Ca-137 2 - 7.0 (1/3) 14F15.5 at IIInf (7.8) (11) (11)
Gaasna 0 Bovine thyroid
<!1D 14F15.5 mi MInf 1500 (1/1) 1500 (1/1)
(pct /k g-wet) E-40 2 1100 1500 1500 b
O Fo&Ser Crope Gasma 800 (1/2) 0 Se-7 11 130 490 (4/9) 14F1 S.5 mi Inmi 840 (1/1)
(pC1/kget) (640) (800)
(160-840) 10250 (2/2) 0 7633 (9/9) 3G1 17 mi NE 10250 (2/2)
E-40 11 -
(4500-16000)
(2500-16000) (4500-16000) 5.0 (4/12) 2.9 (1/123 0 Alpha 60 1.2 3.3 (11/40) 11A1 0.2 mi SN Surf ace IIater (2.7-7.8) (2.9)
(pC1/L) (1.5-7.8) 50 (12/12) 0 60 3.0*** 55 (48/48) 7El 4.5 el SE 01 (12/12) seta (27-120) (11-76)
(4.5-120) 160 (4/12) 1 130 269 (25/48) 11A1 0.2 mi SIf 420 (7/12) u-3 60 (140-190)
(130-1700) (140-1700)
<!1D 0 Sr-49 20 0.4 0.9 (1/16) 1F2 7.1 mi N 0.9 (1/4) j (0.9) (0.9) !
- <LLD <Ila 0 St-90 20 0.4 <ILD Gesuna 59 (12/12) 0 60 10 67 (46/48) 751 4.5 mi SE 98 (12/12)
E-40 (36-140) (12-90)
(23-140) 1.1 te/es) 16F16.9 al leaf 1.4 (3/12) 1.3 (1/12) 0 Ra-226 60 0.4 (1.2 1.7) (1.3)
(0.6-1.7) 0 2.2 (6/40) 751 4.5 mi SE 3.3 (2/12) 2.5 (2/12)
Th-232 60 16 12.9-3.7) (1.9-3.1)
(0.8-3.7)
ARTIFICIAL IStAND RADIOt4GICAL ENVI"""TAL MONITORING Penn StBSIARY SALan MUCLEAR GENERATING STATION 00 CERT NO. 50-272/-311 SAIJBI COUNTY, umI JERSEY JANUARY 1, 1985 to DecmIBER 31, 1985 ARIALYSIS AIID IANER NISSER OF MEDIt.Bt OR PATHIIAY TOTAL IltsesR LIMIT OF ALL IISICATOR I4CATICIS IDCATICII WITH NIGMST IISAN (XMrrRDL IACATICIIfS) IIGINIOUTIIE SAMP12D OF ARIALYSES DETECTICII IIRAII'
- IIAIIE MEAN MEAII REPORTED (UIIIT OF MEASURBIEIfT) PERFOSIIED (Llal* (RAIIGE) DISTAIICE AIID DIRACTICII (RAIIGE) (RAIIGE)
Edible Fish Sr-89 6 26 70 (1/4) 11A1 0.2 mi SW 70 (1/2) < LIA 0 (pC1 Ag-dry) (bonee) (70) (70)
St-90 6 29 135 (3/4) 11A1 0.2 mi SW 190 (2/2) 62 (2/2) 0 (bones) (24-350) (31-350) (30-95)
(pC1/kg-wet) u-3 6 50 300 (2/4) 11A1 0.2 at SW 400 (1/2) 200 (1/2) 0 (aqueous) (200-400) (400) (200) u-3 6 50 90 (1/4) 7El 4.5 mi SR 90 (1/2) < LIA 0 (organic) (90) (90)
Gamma E-40 6 -
3075 (4/4) 7El 4.5 mi SE 3150 (2/2) 3100 (2/2) 0 (3000-32003 (3100-32003 (3100-3100)
Cs-137 6 11 8.6 (3/4) 11A1 0.2 mi SW 10 (2/2) 10 (1/2) 0 4 (4.0-11) (10-11) (10)
V alue Crabs St-89 4 78 50 (1/2) 12C1 2.5 ml USN 64 (1/2) 64 (1/2) 0 (pci/kg-dry) (shells) (50) (64) (64)
St-90 4 -
215 (2/2) 11A1 0.2 mi Sw 215 (2/2) 132 (2/2) 0 (shells) (210-220) (210-220) (24-240)
(pC1/kg-wet) a-3 4 50 200 (1/2) 11A1 0.2 at SW 200 (1/2) 200 (1/2) 0 (flesh) (200) (200) (200) 12C1 2.5 mi IISW 200 (1/2)
(2003 Sr-89 4 27 < LIA - (LLD <LLD 0 (flesh)
Sr-90 4 18 < IJA 12C1 2.5 ml USW 28 (1/2) 28 (1/2) 0 (flesh) (28) (28)
Gamma E-40 4 -
2300 (2/2) 11A1 0.2 at Sw 2300 (2/2) 2100 (2/2) 0 (2100-2500) (2100-2500) (1700-2500)
] Benthic Organisms St-89 8 530 <t1D - (LLD <LLD 0 (pct /kg-dry)
St-90 8 200 < t1D - <!1D <!Ja 0*
Gamma 8 < LIA - 4 LIA <LLD 0
4 i ARTIFICIAL ISIJu1D RADIOIAGICAL ENVIROIsterrAL Be0NITORING PRDWAft StBetART SALEM IfUCLEAR GIRIERATIIBG STATION DOCERT NO. 50-272/-311 SAImt COUNTY, IssN JERSEY JAssunRT 1,1945 to DeCSEBER 31, 1985 NtBSER OF AleALTsgs AaID IAnfER CONTROL IDCATION($) NOM 0UTIM LIMIT OF ALL IISICATOR IACATIOes IDCATICII NITE NIGMT IGRAN MEDIIst OR PATansAT TOTAL IIL2eER SIEAN IIEAN 3BPORTED IEEAN** 30AftE SAMPLED OF AIIALYSES DETSCTIOtt psBASUReqENTS DISTANCE AND DIRACTICII (RANGE) (RAIIGE)
(UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE)
- (LLD <LLD 0 Sr-90 10 19 (LLD Sediment (pC1/kg-dry) comma 0 150 430 (1/0) 16F1 6.9 mi Inne 430 (1/2) < LLD se-7 10 (430)
(430) 0 10762 (0/0) 12C12 5 mi teser 15000 (2/2) 15000 (2/2)
E-40 10 -
(14000-16000)
(4500-14000) (14000-16000) 38 (1/1) <!1D 0 Mn-54 10 20 30 (1/8) 16Al O.7 mi tune (34) (34) 160 (1/1) < LLD 0 Cb-60 10 29 04 (6/S) 16Al 0 7 mi test (45-160) (160) 53 (1/2) 53 (1/2) 0 Cs-134 10 16 41 (1/0) 12C1 2.5 mi teset 8 (41) (53) (53) '
Jh 65 (2/2) 20 (1/2) 0 Cs-137 10 14 43 (5/0) 16F16.9 mi tems M (42-94) (20)
(16-88) 0 025 (8/s) 1641 0.7 mi anaf 1400 (1/1) 635 (2/2)
Re-226 10 -
(1400) (530-740)
(620-1400) 890 (0/0) 16Al 0.7 mi Mint 1600 (1/1) 765 (2/2) 0 Th-232 10 -
(Isan) (760-770)
(640-1600)
- G listed is the lowest calculated LIa during the reporting period.
- pesan calculated using values above LLD only. Fractions of measurements above LIa are in perentheses. *
- Typical LID value.
~~
. l l
1 APPENDIX B SAMPLE DESIGNATION AND LOCATIONS t
43
r - . . . . . . . . . .
f' -
APPENDIX B Sample Designation Re PSE&G Research Corporation identifies samples by a three part code. Se first two letters are the power station identification code, in this case "SA". He next three letters are for the media sampled.
AIO = Air Iodine IDM =
Immersion Dose (TLD)
APT = Air Particulates MLK = Milk ECH = Hard Shell Blue Crab PWR =
Potable Water (Raw)
ESB = Benthic Organisms PWT =
Potable Water (Treated)
ESF = Edible Fish RNA = Rain Water DSS = Sediment SWA = Surface Water FPB = Beef THB = Bovine hyroid FPV = Food Products, Various VGT = Fodder Crops; Vr getation FPL = Green Leafy Vegetables WWA = Well Water GAM = Game ne last four symbols are a location code based on direction and distance from the site. Of these, the first two represent each of the sixteen angular sectors of 22.5 degrees centered about the reactor site. Sector one is divided evenly by the north axis and other sectors are numbered in a clock-wise direction; i.e., 2=NNE, 3=NE, 4=ENE, etc. H e next digit is a letter which represents the radial distance from the plant S = On-site location E = 4-5 miles off-site A = 0-1 miles off-site F = 5-10 miles off-site B = 1-2 miles off-site G = 10-20 miles off-site C = 2-3 miles off-site H = >20 miles off-site D = 3-4 miles off-site The last number is the station numerical designation within each sector and zoner 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) . He number 1 indicates that this is sampling station il in that particular sector.
45
Sampling Locations All 1985 sampling locations and specific information about the individual locations are given in Table B-1. Maps B-1 and B-2 show the locations of sampling stations with respect to the site.
TABLE B-1 STATION CODE STATION LOCATION SAMPLE TYPES 2S2 0.4 mi. NNE of vent AIO, APT,IDM 2S3 700 ft. NNE of vent; fresh water holding tank WWA 1-SSl 1.0 mi. E of vent; site access road AIO, APT,IDM 6S2 0.2 mi. ESE of vent; observation bldg. IDM 7S1 0.12 mi. SE of vent; station personnel gate IDM 10S1 0.14 mi. SSW of vent; site shoreline IDM 11S1 0.09 mi. SW of vent; site shoreline IDM llAl 0.2 mi. SW of vents outfall area ECH,ESB, ESP, ESS,SWA 15Al 0.3 mi. NW of vent; cooling tower blowdown ESS discharge line outfall 16Al 0.7 mi. NNW of vent; south storm drain ESS discharge line 12Cl 2.5 mi. WSW of vent; west bank of Delaware River ECH,ESB, ESP, ESS,SWA 4D2 3.7 mi. ENE of vent; Alloway Creek Neck Road IDM SD1 3.5 mi. E of vent; local farm AIO, APT,FPV, IDM,VGT,WWA 10D1 3.9 mi. SSW of vent; Taylor's Bridge Spur AIO, APT,IDM llD1 3.5 mi. SW of vent GAM 14D1 3.4 mi. WNW of vent; Bay View, Delaware IDM 2El 4.4 mi. NNE of vent; local farm FPV,IDM 3El 4.1 mi. NE of vent; local farm FPB, GAM,IDM, THB,WWA l.
46
TABLE B-1 (cont'd)
.3TATION CODE STATION LOCATION SAMPLE TYPES 7El 4.5 mi. SE of vent; 1 mi. W of Mad Horse Creek ESB,ESF,ESS,SWA 9El 4.2 mi. S of vent IDM llE2 5.0 mi. SW of vent IDM 1251 4.4 mi. WSW of vent; Thomas Landing IDM '
1381 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; Port Penn AIO, APT,IDM 1F1 5.8 mi. N of vent; Fort Elfsborg AIO, APT,IDM 1F2 7.1 mi. N of vent; midpoint 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 2FS 7.4 mi. NNE of vent; Salem High School IDM 2F6 7.3 mi. NNE of vent; Southern Training Center IDM 3F2 5.1 mi. NE of vent; Hancocks Bridge Municipal IDM Building 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 SF2 7.0 mi. E of vent; local farm MLK,VGT 6F1 6.4 mi. ESE of vent; Stow Neck Road IDM 7F2 9.1 mi. SE of vent; Bayside, New Jersey IDM 10F2 5.8 mi. SSW of vent IDM l
11F1 6.2 mi. SW of vent; Taylor's Bridge Delaware IDM 47 i
I
. . , , . . . ~ _ , - , . -
TABLE B-1 (cont'd)
STATION CODE STATION LOCATION SAMPLE TYPES 11F3 5.3 mi. SW of vent; Townsend, Delaware MLK,VGT 12F1 9.4 mi. WSW of vent; Townsend Elementary School IDM 13F2 6.5 mi. W of vent; Odessa, Delaware IDM 13F3 9.3 mi. W of vent; Redding Middle School, IDM Middletown, Delaware 13F4 9.8 mi. W of vent; Middletown, Delaware IDM 14F1 5.5 mi. WNW of vent; local farm FPB,MLK,THB,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 MLK 15F3 5.4 mi. NW of vent IDM 16F1 6.9 mi. NNW of vent; C3D 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, Delaware IDM 2G1 12 mi. NNE of vent; Mannington Township, NJ FPV 3G1 17 mi. NE of vent; local farm 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 Park, New Jersey IDM 3H3 110 mi. NE of vent; Research and Testing AIO, APT,IDM Laboratory 3HS 25 mi. NE of vent; local farm FPL,FPV 48
-m3 mM. _ _->*am .2 __ _ _.a MAP B-1 ON SITE SAMpg gNG LOCATgang ARTIFICIAL ISLANO a
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APPENDIX C 1985 DATA TABLES 4
4 l
51
.- . .- .- __- - - _ - _ - ___ _. . _-- - -- . . _ _ _ _ - - . . - - - - - _ = _ - -
i t.
DATA TABLES Appendix C presents the analytical results of the 1985 Artificial Island Radiological Environmental Monitoring Program for the period of January 1 to December 31, 1985.
TABLE OF CONTENTS TABLE NO. TABLE DESCRIPTION PAGE ATMOSPHERIC ENVIRODMENT AIR PARTICULATES C-1 1985 Concentrations of Gross Alpha Emitters.................... 56 C-2 1985 Concentrations of Gross Beta Emitters..................... 58 C-3 1985 Concentrations of Strontium-89 and -90 and Gamma Emitters in Quarterly Composites................................... 60 AIR IODINE C-4 1985 Concentrations of Iodine-131.............................. 62 DATES C-5 1985 Sampling Dates for Air Samples............................ 64 PRECIPITATION C-6 1985 Concentrations of Gross Alpha and Gross Beta Emitters and Tritium................................................... 69 C-7 1985 Concentrations of Strontium-89 and -90 and Gamma Emitters in Quarterly Composites................................... 70 DIRECT RADIATION THERMOLUNINESCENT DOSIMETERS C-8 1985 Quarterly TLD Results..................................... 71 C-9 1985 Monthly TLD Results....................................... 72 .
i 53
DATA TABLES (cont'd.)
TABLE NO. TABLE DESCRIPTION PAGE TERRESTRIAL ENVIROIMENT MILK C-10 1985 Concentrations of Iodine-131.............................. 74 C-11 1985 Concentrations of Strontium-89 and -90.................... 75 C-12 19 8 5 Concentrations of Ganuma Emitters. . . . . . . . . . . . . . . . . . . . . . . . . . 76 C-13 1985 Sampling Dates for Milk Samples........................... 78 WELL WATER C-14 1985 Concentrations of Gross Alpha and Gross Beta Emitters; Potassium-40 and Tritium.................................. 80 C-15 1985 Concentrations of Strontium-89 and -90 and Ganuna Emitters in Quarterly Composites................................... 82 1
POTABLE WATER C-16 1985 Concentrations of Gross Alpha and Gross Beta Emitters; Potassium-40 and Tritium.................................. 83 C-17 1985 Concentrations of Strontium-89 and -90 and Gamma Emitters in Quarterly Composites................................... 84 FOOD PRODUCTS C-18 1985 Concentrations of Strontium-89 and -90 and Gamma Emitters in Vegetables............................................. 85 C-19 1985 Concentrations of Strontium-89 and -90 and Gamma Emitters in Game, Meat and Bovine Thyroid.......................... 86 FODDER CROPS C-20 1985 Concentrations of Gamma Emitters.......................... 87 l
1 i
54
e.
=
k *
)' DATA TABLES (cont'd.)
TABLE -
NO. TABLE DESCRIPTION PAGE
\
- t '
AQUATIC ENVIROletENT I SURFACE NATER C ~1985 Concentrations of Gross Alpha Emitters.................... 88 C-22. 1985 Concentrations of Gros's Beta Emitters..................... 89 i .
C 1985 Concentrations of' Tritium.................................- 90 C-24 1985 Concentrations of Strontium-89 and -90.................... 91 C-25 1985 Concentrations of Gamma Emitters.......................... 92 EDIBLE FISH C-26 1985 Concentrations of Strontium-89 and -90 and Tritium... .. . .. 94 C-27 1985 Concentrations of ca==a Emitters.......................... 95 BLUE CRABS C-28 1985 Concentrations of Strontium-89 and 90; Gar.aa Emitters and Tritium................................................... 96 BENTHIC ORGANISMS C-29 1985 Concentrations of Strontium-39 and -90 and Gamma Emitters 97 SEDIMENT C-30 1985 Concenty tions of Strontium-90 and Gamma Emitters......... 98 i
+
,SPECIAL TABLES t
LLDs t
- -31 1985 PSE&G Research Corporation LLDs for Gamma Spectrometry.... 99
\
i i
! t i
- 55
^$
-. . , . , _ _ _ - , . - _ _ - - . - . . . ~ . . - ,
TABLE C-1 1985 CONCENTRATIONS OF GROSS ALPHA ENITTERS IN AIR PARTICULATES Results in Units of 10-3 pC1/m3 2 2 sigma STATION NO.
MONTH
- SA-APT-2S2 SA-APT-5S1 SA-APT-5D1** SA-APT-10D1 SA-APT-16El SA-APT-lF1 SA-APT-2F2 SA-APT-353 AVERAGE (Control)
JANUARY 1.220.6 1.710.7 <2.0 1.310.7 2.010.8 1.620.7 1.920.8 1.520.6 1.620.6 1.420.8 1.210.7 <2.0 1.420.9 1.720.9 1.520.8 1.020.7. 1.520.8 1.520.6 1.720.6 1.920.7 3.021.3 2.420.9 1.420.6 1.220.6 1.720.6 1.210.6 1.821.2 2.020.9 1.610.8 <1.0 2.120.9 2.020.9 1.720.9 1.820.8 2.020.8 1.810.7 FEBRUARY 2.210.8 3.220.9 2.721.3 1.610.9 1.520.8 1.820.8 1.220.7 1.610.7 2.021.4 2.420.9 3.021.0 1.721.1 3.020.9 2.811.0 2.810.9 2.621.0 3.321.0 2.721.0 2.320.7 2.410.8 2.321.1 1.920.7 2.820.8 2.520.8 3.811.3 2.520.8 2.611.1 2.920.9 2.721.0 <1.0 1.220.7 2.320.9 1.720.9 2.120.9 3.221.1 ,2.121.6 MARCH 0.820.5 1.010.6 1.811.3 1.020.6 1.420.7 0.910.6 1.210.6 1.720.8 1.220.7 1.7s0.7 1.820.8 2.321.2 1.820.7 2.410.8 2.620.9 2.510.8 (1) 2.220.8 2.120.8 1.720.7 <1.0 2.120.9 1.220.8 1.620.7 1.420.0 2.020.8 1.620.8 2.520.8 1.010.7 <0.9 1.520.7 1.920.8 1.810.8 1.420.7 1.620.8 1.611.0 on 1.810.7 2.121.7 og 2.110.8 1.510.7 <1.0 2.720.9 3.811.0 1.720.0 2.110.8 APRIL 1.820.8 1.520.8 2.221.2 2.421.0 <0.9 2.220.9 1.620.8 1.320.7 1.821.0 4.211.0 3.410.9 1.511.0 3.020.9 3.720.9 3.6t0.9 3.520.9 3.010.8 3.221.6 2.820.9 2.611.0 3.821.8 2.211.0 2.721.0 2.210.9 2.210.8 1.920.8 2.621.2 2.120.9 1.720.9 2.021.1 2.321.0 1.520.8 1.820.9 1.521.0 1.520.8 1.820.6 MAY 1.410.7 2.120.9 <1.0 1.210.8 1.410.9 2.020.9 1.720.8 2.020.8 1.620.8 2.320.8 2.020.8 1.321.1 1.610.8 1.910.7 2.510.9 1.620.7 1.420.7 1.020.8 1.620.7 1.720.8 <1.0 1.820.8 2.020.8 1.510.8 1.920.8 1.320.7 1.620.6 2.620.8 2.610.9 0.920.8 2.721.0 1.910.8 2.410.9 1.710.8 1.810.7 2.121.2 JUNE 2.020.9 1.420.8 1.621.3 2.821.1 5.121.2 2.821.0 1.910.9 1.420.8 2.422.5 1.220.7 1.720.7 <1.0 1.310.9 2.310.9 1.010.9 2.120.9 2.120.9 1.721.0
<1.0 1.610.9 1.711.4 1.821.1 <1.2 <1.1 1.120.8 <1.0 -
0.820.6 1.620.7 <1.0 1.520.7 1.820.7 0.820.6 1.520.7 1.820.7 1.4*0.8 1.920.9 1.410.8 1.821.2 2.010.9 1.820.8 1.420.8 1.510.8 <0.8 1.610.8
. . _ _ _ _ - _ - - _ . - - . - - m
s [1 TABLE C-1 (cont'd) 1985 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN AIR PtRTICULATES %
Results in Units of 10-3 pC1/m3 1 2 signa STATION NO.
t sj MONTH
- SA-APT-2S2 SA-APT-5S1 SA-APT-5D1** SA-APT-10D1 SA-APT-16El SA-APT-lF1 SA-APT-2F2 SA-APT-3H3 AVERAGE (Control)
JULY 2.121.0 2.010.9 2.321.2 2.411.1 1.821.0 1.710.9 1.420.8 1.410.8 1.920.8 3.311.2 2.320.9 <1.0 1.720.8 1.720.0 1.720.8 1.920.8 1.420.7 1.921.4 1.410.9 2.720.9 2.221.3 2.321.0 1.720.9 2.220.9 3.221.0 2.620.9 2.321.1 2.421.0 2.120.8 <2.0 2.920.9 2.110.8 1.420.7 1.310.6 1.810.7 2.021.0 AUGUST 1.620.7 1.520.7 <0.8 2.610.9 2.020.8 1.320.7 1.220.7 2.120.8 1.621.1 1.820,3 <1.0 1.521.2 1.220.5 <1.0 f 1.0t0.7 <0.9 1.4 0.8 1.220.6 1.h20.8 2.410.9 2.321.3 2.511.0 2.721.0 2.220.9 1 2.Et1.0 2.020.8 2.320.7 1.620.8 1.820.8 1.521.0 1.210.8 1.310.8 1.920.9 , 1.220.9 1.420.8 1.510.5 2.220.9 3.020.9 1.220.8 2.421.1 (2) 2.821.0 74.221.3 1.920.0 2.521.9
- 1 SEPTEMBER, *+J.121.1 2.621.1 3.321.7 3.021.1 3.711.2 3.021.0 3.621'.2 2.220.9 3.121.0 1.310.7 1.910.8 1.320.9 1.410.7 1.910.7 , 8 1.920.8
- 1.720.8 2.520.8 1.720.8 on x.2.2tl.2 2.120.9 1.111.0 3.611.2 3.021.2 2.621.0 3.121.1 3.621.0 2.721.7
-J ~2.620.9 1.810.8 1.621.2 1.220.7 2.620.8 1.520.8 .2.2y9.9 1.720.7 1.921.0 OCTOBER 1.910.8 %- 1.910.8 1.421.1 1.820.9 2.411.0 1.520.7.' 2.220.9 2.020.8 1.910.7 2.710.8 2.920.8 1.321.0 3.020.9 3.620.9 2.420.8 3.220.9 1.620.7 2.621.6 2.520.9 ~2.921.3 2.321.3 1.8t1.0 2.521.0 2.320.9 <1.0 2.110.9 2.221.1 1.420.8 2.210.9 1.321.1 1.520.8 1.820.8 <1.0 <l.1 1.710.8 1.510.8 NOVEMBER 0.910.6 1.420.8 1.320.9 1.720.9 1.320.8 1.320.7 1.320.7 1.820.8 1.410.6 1.820.7 1.210.6 1.020.0 0.820.5 1.610.6 1.420.6 0.720.5 <2.1 1.321.0 1.610.9 1.611.0 <1.0 2.221.0 2.221.0 <1.3 <1.4 <1.2 -
2.621.0 2.6*0.9 1.320.9 2.620.9 2.020.7 2.520.9 2.820.9 2.810.9 2.421.0 1.420.9 1.920.9 1.921.2 <1.2 1.921.0 1.510.9 1.120.9 1.320.8 1.610.6 t DECEMBER 1.820.9 3.220.9 2.121.1 2.820.8 d.020.9 1.820.8 2.720.9 2.820.9 2.621.5 3.711.0 2.720.9 4.721.6 3.111.1 3.011.1 3.621.1 3.821.1 2.720.9 3.421.4 . i 3.421.0 2.610.8 2.421.1 2.921.0 2.820.8 2.910.9 3.120.9 3.010.8 2.920.6 2.320.9 1.910.8 2.621.2 2.811.0 2.110.8 3.211.0 2.620.9 2.120.8 2.420.9 AVERAGE 2.011.4 2.021.2 1.721.6 2.121.4 2.221.7 2.021.3 2.021.7 1.921.2 e ,
Grand Average 2.021.5 4
- Sampling dates can be found in Table C-5.
- Results by Teledyne Isotopes.
(1) No results due to faulty sampling assembly.
(2) No results due to vandalism of the sampling assembly.
-... - . . .. ,. - -_ ~ _ .. . .-. . . .
TABLE C-2 1985 CONCENTRATIONS OF GROSS BETA ENITTERS IN AIR PARTICULATES Results in Units of 10-3 pC1/m3 1 2 signa STATION NO.
MONTH
- SA-APT-2S2 SA-APT-SSI SA-APT-5D1** SA-APT-10D1 SA-APT-16El SA-APT-lF1 SA-APT-2F2 SA-APT-3M3 AVE 3 AGE (Control)
JANUARY 2323 2223 2724 2513 2423 2013 22 3 2322 2314 1723 16t3 2013 2023 1723 1823 1923 1723 1923 2712 2823 2823 2913 2623 3123 26 2 3123 2814 2123 2023 2223 1923 2123 2123 1723 2513 2115 FEBRUARY 2222 2012 2323 2824 1923 1923 20t3 22:3 2226 3623 3423 3614 3023 3823 3423 3523 3323 3425 2922 3113 2923 2823 3123 2913 2524 3013 2924 1923 2013 2023 1723 1923 1923 2213 2523 2025 1
) MARCH 3423 3723 2423 22t3 2213 3523 2423 2623 28t12
- 23 2 24 3 2723 25 3 2523 3013 2723 (1) 26 5 1
2222 2113 22 3 1723 2023 2023 2123 2123 2023 23 2 2223 2023 2323 2222 2423 2323 2613 2323 Ln 1722 1912 1923
. og 1822 1822 2013 1813 2223 1923 APRIL 1922 1822 2423 2223 2123 1823 1722 1922 2025 30 3 2823 2723 2923 28:2 2813 30 3 2022 2826 2723 2523 2214 3724 3023 2513 2523 2623 2729 2222 22:3 2423 1923 20t2 2623 1923 1612 2126 MAY 2222 1922 22 3 2023 2023 1913 2223 2213 21:3 2613 2523 2623 2323 24 2 2523 2423 2523 2522 l 1722 1822 1723 1823 1812 1722 1923 1722 1811 1 2812 2622 2713 2513 2722 2523 2623 23:2 2623 JUNE 2323 2523 2924 2824 2523 24:3 2423 1923 2526 4 2122 2112 2413 28 3 2113 2223 2223 2222 2325
.I 20t2 1922 4923 2123 1713 2223 2022 1522 1914 2413 2423 2223 2523 2422 1923 2423 2423 2324 1
1622 1422 20t3 1623 1612 1512 1622 1122 1615 i
TABLE C-2 (cont'd) 1985 CONCENTRATIONS OF GROSS BETA EMITTERS IN AIR PARTICULATES Results in Units of 10-3 PC1/m3 2 2 sigma STATION NO.
MONTH
- SA-APT-2S2 SA-APT-SSI SA-APT-5DI** SA-APT-10D1 SA-APT-16El SA-APT-lF1 SA-APT-2F2 SA-APT-3H3 AVERAGE (Control)
JULY 2724 2423 2723 2714 3124 2323 2213 2623 2626 2424 2423 2714 2423 2823 2623 2523 1922 2525 2924 2913 3124 2923 2923 2823 2923 2813 29 2 2223 1913 2123 23 3 1823 1923 1822 1822 2024 AUGUST 1922 1913 2123 20t3 1622 1913 1923 2012 1923 1622 1522 1923 1423 1523 1422 1422 1622 1523 3413 3423 3414 3623 4013 3013 . 3523 3423 3526 2823 2323 2523 2423 2523 2323 23t3 2022 2414 3523 3013 3023 3623 (2) 2723 3923 2722 3229 SEPTEMBER 3924 3714 4325 3924 3624 4124 3824 3423 3826 2223 2013 2223 2413 2422 22 3 2223 1822 2224 Ln 3824 3623 2923 3323 4024 3423 3523 3913 3617 y3 2623 2112 2523 2222 2422 2213 2423 2422 2423 OCTOBER 2222 20t3 2123 1923 2123 2213 2123 2023 2112 2612 2812 2623 2823 2922 2722 2623 2812 2722 2723 2923 3024 2724 2823 2823 29 3 2213 2825 1722 1922 2123 1822 1922 2023 1923 2112 1923 NOVEMBER 1612 1623 1422 1323 1623 1722 1722 1522 1623 1722 1922 '1812 1722 1722 1422 1722 <8.9 1626 2323 2323 1923 2423 2623 1923 2423 20t3 2215 2923 3323 3223 3113 3123 3023 3423 3323 3223 2223 2223 2523 2023 1913 2423 2023 1913 2124 DECEMBER 3724 3623 3223 3623 4523 3223 4013 38t3 3718 3823 3913 4024 38 4 3823 4013 3913 3623 3823 3113 2822 3123 3613 3123 3123 3323 3223 3224 2523 2422 2613 3123 2522 2923 2713 2222 2626 AVERAGE 25212 24t13 25211 25213 25:14 24212 24213 23:13 s Grand Average 24213
.
- Sampling dates can be found in Table C-5.
6
- Results by Teledyne Isotopes.
(1) No results due to faulty sampling assembly.
(2) No results due to vandalism of sampling assembly.
TABLE C-3 1985 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND GAMMA EMITTERS **
IN QUARTERLY COMPOSITES OF AIR PARTICULATES Results in Units of 10-3 pCi/m3 2 2 sigma STATION NO. AND DATES Sr-89 Sr-90 Be-7 Ra-226 SA-APT-2S2 1-02-85 to 4-dl-85 <0.3 <0.2 70 5 <0.9 4-01-85 to 7-01-85 <0.2 <0.2 86 5 <0.9 7-01-85 to 9-30-85 <0.5 <0.3 8225 <1.1 9-30-85 to 12-30-85 <0.3 <0.3 6125 <1.0 SA-APT-SSI 1-02-85 to 4-01-85 <0.3 <0.2 71 4 <0.6 4-01-85 to 7-01-85 <0.2 <0.2 71 4 <0.6 7-01-85 to 9-30-85 <0.5 0.4 0.1 73 5 <1.0 9-30-85 to 12-30-85 <0.3 <0.2 67 5 <1.0 SA-APT-SDl***
1 1-02-85 to 4-01-85 <0.6 <0.2 86 9 <8.0 4-01-85 to 7-01-85 <2.0 <0.1 98!10 <6.0-7-01-85 to 9-30-85 <3.0 <0.2 75 7 <8.0 9-30-85 to 12-30-85 <1.0 <0.2 8528 <8.0 SA-APT-10D1 1-03-85 to 4-02-85 <0.4 <0.2 71 6 <1.2 4-02-85 to 7-02-85 <0.3 <0.2 79 6 1.0 0.6 7-02-85 to 10-01-85 <0.4 <0.3 80 5 <1.1 10-01-85 to 12-31-85 <0.3 <0.2 58 5 <1.0 1
s 60
TABLE C-3 (cont'd) 1985 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND GAMMA EMITTERS **
IN QUARTERLY COMPOSITES OF AIR PARTICULATES Results in Units of 10-3 pCi/m3 2 sigma STATION NO. AND DATES Sr-89 Sr-90 Be-7 Ra-226 SA-APT-16El 1-03-85 to 4-02-85 <0.3 <0.2 71 5 <0.8 4-02-85 to 7-02-85 <0.2 <0.2 90 6 <1.2 7-02-85 to 10-01-85(1) <0.8 <0.5 74 4 <l.1 10-01-85 to 12-31-85 <0.3 <0.2 5824 <0.6 SA-APT-lF1 1-02-85 to 4-01-85 <0.3 <0.2 7325 <0.8 4-01-85 to 7-01-85 <0.2 <0.2 79 5 <0.8 7-01-85 to 9-30-85 (3) (3) 72 5 <l.0 9-30-85 to 12-30-85 <0.3 <0.2 67 5 <0.9 SA-APT-2F2 1-02-85 to 4-01-85 <0.3 <0.2 7116 <l.1 4-01-85 to 7-01-85 <0.3 <0.2 86 6 <l.1 7-01-85 to 9-30-85 <0.4 <0.3 74 6 <1.2 9-30-85 to 12-30-85 <0.7 <0.5 60 5 <1.3 SA-APT-3H3 (Control) 1-02-85 to 4-01-85(2) <0.3 <0.2 73 5 <1.0 4-01-85 to 7-01-85 <0.2 <0.2 81 6 <l.0 7-01-85 to 9-30-85 <0.6 <0.3 7514 <0.6 9-30-85 to 12-30-85 <0.8 <0.6 56 5 <0.8 AVERAGE - -
74120 -
- St-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.
- Results by Teledyne Isotopes.
(1)-Quarterly composite of all weekly filters except for the second week in March, which was unavailable due to a faulty sampling assembly.
(2) Quarterly composite of all weekly filters except for the fifth week in August, which was unavailable due to vandalism of the sampling assembly.
(3) Sample lost during analysis.
61
.~ . - . . . . . . . . . - - .
TABLE C-4 1985 CONCENTRATIONS OF IODINE-131* IN FILTERED AIR
! Results in Units of'10-3 pCi/m3 STATION NO.
MONTH ** SA-AIO-2S2 SA-AIO-5S1 SA-AIO-5DI*** SA-AIO-10D1 CA-AIO-16El SA-AIO-1F1 SA-AIO-2F2 SA-AIO-3H3 (Control)
JANUARY <18 <18 <30 <28 <20 <22 <20 <12
<22 <23 <20 <22 <15 <16 <16 <18
<12 <15 < 7.0 <28 <l5 <19 <21 <16
< 7.5 <15 <50 <13 <17 <22 <18 <10
- FEBRUARY <12 <18 <20 <23 <22 <24 <19 <13
- <13 <17 <20 <19 <l5 <19 24 13 <17
<11 <12 <20 <19 <l5 <10 <17 <13
<l5 <20 <20 <17 <21 <21 <17 <19 MARCH <13 <17 <20 <26 <20 <15 < 7.6 <12
<14 <11 <20 <17 <19 < 6.9 <21 <12
+ <14 <11 <40 <21 <13 <22 <21 <10
<16 <13 <20 <20 <14 <20 <19 <18 ch <16 t
og <12 <11 <40 <17 <14 < 7.2 < 8.6 APRIL <12 <18 <30 <29 <15 <15 <13 < 6.1
<16 <14 <20 <16 <17 <!9 < 9.5 <14
<13 < 9.0 <20 <25 <17 <17 <12 <14
<18 <23 <20 <13 <13 <21 <l5 <13 MAY <16 <14 <20 <18 <25 <19 <19 <18
<10 <21 <20 <17 <12 <14 <14 <14
<13 <22 <20 <16 <12 <27 <15 <18
< 9.3 <20 <20 <26 <15 < 8.0 <14 <17 JUNE <10 <20 <30 <24 <25 <23 <17 <19
<16 <12 <40 <19 <18 <19 <15 <19
<20 <23 <20 <21 <18 <19 <16 <12
<14 <14 <20 <22 <20 <21 < 9.1 <20
<18 <17 <20 <23 <13 <17 <23 <15
.~ .. . - . . . .~- .- _. . _
TABLE C-4 (cont'd) 1985 CONCENTRATIONS OF IODINE-131* IN FILTERED AIR ,
I Hesults in Units of 10-3 pC1/m3 STATION NO.
I MONTH ** SA-AIO-!S2 SA-AIO-SSI SA-AIO-5DI*** SA-AIO-10D1 SA-AIO-16El SA-AIO-1F1 SA-AIO-2F2 SA-AIO-3N3 (Control)
JULY <25 <20 <20 <25 <17 <18 <12 <17
<21 <15 <30 < 9.2 <l5 <20 <24 <l5
<l5 <22 <20 <17 <28 <18 <14 <19
<28 <17 <20 < 14 - <14 <19 <17 <13 AUGUST <18 <21 < 9.0 <14 <12 <21 <13 <20
<17 <12 <20 <!4 <20 <21 <19 <ll
<16 <16 <40 <17 <20 <20 <21 <15
. <14 <19 <20 <12 <17 <16 <23 <17
<12 <16 <20 <l5 (1) <13 <19 <17 SEPTEMBER <17 <28 <20 <23 <30 <20 <29 <22
<12 <18 <20 <14 <16 <20 <17 <17 .
ch <24 <26 <20 <27 <18 <18 <14 <21 ba <14 <20 <20 <12 <18 <14 <22 <14 OCTOBER <18 <22 <20 <20 <18 <23 <22 <16
<19 <20 <10 <13 <11 < 8.1 <13 <13
<22 <20 <20 <33 <18 <22 <17 <20
<17 < 7.9 <20 <23 <22 <16 <14 <17 NOVEMBER <17 <20 <30 <17 <15 <16 <l5 < 9.8 i <17 <11 <10 <18 < 6.3 <18 <15 <120(2)
<13 <26 <20 <21 <14 <32 <16 <17
<13 <27 <20 <22 <20 <14 <13 <16
<l5 <16 <10 <20 <13 <21 <20 <13 DECEMBER <20 <10 <20 <20 <19 <19 <17 <16
<24 <28 <40 <22 <30 <19 <19 <ll
<20 <20 <20 <19 <20 <26 <20 < 7.0
<23 <13 <20 <22 <18 <19 <13 <19
'e
- I-131 results are corrected for decay to sample stop date.
- Sampling dates can be found in Table C-5. .
- *
- Result s by Teledyne Isotopes.
(1) No results due to vandalism of the sampling assembly.
(2) High LLD due to low sample volume, i
m _ _ _ m . _ __ _ . _. _ m . . <
TABLE C 1985 SAMPLING DATES FOR AIR SAMPLES STATION NO.
MONTH 2S2 5SI 5D1 10D1 16El IF1 2F2 3H3 JANUARY 1-02-85 1-02-85 1-02-85 1-03-85 1-03-85 1-02-85 1-02-85 1-02-85' to to to to to to to to 1-08-85 1-08-85 1-08-85 1-09-85 1-09-85 1-08-85 1-08-85 1-09-85 1-08-85 1-08-85 1-08-85 1-09-85 1-09-85 1-08-85 1-08-85 1-09-85 to to to to to to to to 1-14-85 1-14-85 1-14-85 1-15-85 1-15-85 1-14-85 1-14-85 1-14-85 i
. 1-14-85 1-14-85 1-14-85 1-15-85 1-15-85 1-14-85 1-14-85 1-14-85 l to to to to to to to to 1-22-85 1-22-85 1-22-85 1-22-85 1-22-85 1-22-85 1-22-85 1-21-85 1-22-85 1-22-85 1-22-85 1-22-85 1-22-85 1-22-85 1-22-85 1-21-85 to to to to to to to to 1-28-85 1-28-85 1-28-85 1-29-85 1-29-85 1-28-85 1-28-85 1-28-85
- 8
- FEBRUARY 1-28-85 1-28-85 1-28-85 1-29-85 1-29-85 1-28-85 1-28-85 1-28-85 to to to to to to to to 2-04-85 2-04-85 2-04-85 2-04-85 2-04-85 2-04-85 2-04-85 2-04-85 2-04-85 2-04-85 2-04-85 2-04-85 2-04-85 2-04-85 2-04-85 2-04-85 i to to to to to to to to 2-11-85 2-11-85 2-11-85 2-11-85 2-11-85 2-11-85 2-11-85 2-11-85 2-11-85 2-11-85 2-11-85 2-11-85 2-11-85 2-11-85 2-11-85 2-11-85 to to to to to to to to 2-19-85 2-19-85 2-19-85 2-19-85 2-1S-85 2-19-85 2-19-85 2-19-85 2-19-85 2-19-85 2-19-85 2-19-85 2-19-85 2-19-85 2-19-85 2-19-85 to to to to to to to to 2-25-85 2-25-85 2-25-85 2-26-85 2-26-85 2-25-85 2-25-85 2-25-85 MARCH
- 2-25-85 2-25-85 2-25-85 2-26-85 2-26-85 2-25-85 2-25-85 2-25-85 i to to to to to to to to 1 3-04-85 3-04-85 3-04-85 3-04-85 3-04-85 3-04-85 3-04-85 3-04-85 i 3-04-85 3-04-85 3-04-85 3-04-85 3-04-85 3-04-85 ?-04-85 3-04-85 to to to
- to to to to to 3-11-85 3-11-85 3-11-85 3-12-85 3-12-85 3-11-85 3-11-85 11-85 3-11-85 3-11-85 3-11-85 3-12-85 3-12-85 3-11-85 3-11-85 3-11-85 to to to to to to to to 3-18-85 3-18-85 3-18-85 3-18-85 3-18-85 3-18-85 3-18-85 3-18-85 '
, . _ _ m .-
TABLE C-5 (cont'd) 1985 SAMPLING DATES FOR AIR SAMPLES STATION NO.
MONTH 2S2 SSI Sul 10D1 16El IF1 2r2 3H3 MARCH 3-18-85 3-18-85 3-18-85 3-18-85 3-18-85 3-18-85 3-18-85 3-18-85 to to to to to to to to 3-25-85 3-25-85 3-25-85 3-26-85 3-26-85 3-25-85 3-25-85 3-25-85 3-25-85 3-25-85 3-25-85 3-26-85 3-26-85 3-25-85 3-25-85 3-25-85 to to to to to to to to 4-01-85 4-01-85 4-01-85 4-02-85 4-02-85 4-01-85 4-01-85 4-01-85 t
APRIL 4-01-85 4-01-85 4-01-85 4-02-85 4-02-85 4-01-85 4-01-85 4-01-85 to to to to to to to to 4-08-85 4-08-85 4-08-85 4-08-85 4-08-85 4-08-85 4-08-85 4-08-85 4-08-85 4-08-85 4-08-85 4-08-85 4-08-85 4-08-85 4-08-85 4-08-85 to to to to to to to to 4-15-85 4-15-85 4-15-85 4-16-85 4-16-85 4-15-85 4-15-85 4-15-85 m
LR 4-15-85 4-15-85 4-15-85 4-16-85 4-16-85 4-15-85 4-15-85 4-15-85 to to to to to to to to 4-22-85 4-22-85 4-22-85 4-22-85 4-22-85 4-22-85 4-22-85 4-22-85 4-22-85 4-22-85 4-22-85 4-22-85 4-22-85 4-22-85 4-22-85 4-22-85 1 to to to to to to to to 4-29-85 4-29-85 4-29-85 4-30-85 4-30-85 4-29-85 4-29-85 4-29-85 MAY 4-29-85 4-29-85 4-29-85 4-30-85 4-30-85 4-29-85 4-29-85 4-29-85 to to to to to to to to .
5-06-85 5-06-85 5-06-85 5-06-85 5-06-85 5-06-85 5-06-85 5-06-85 5-06-85 5-06-85 5-06-85 5-06-85 5-06-85 5-06-85 5-06-85 5-06-85 to to to to to to to to 5-13-85 5-13-85 5-13-85 5-14-85 5-14-85 5-13-85 5-13-85 5-13-85 5-13-85 5-13-85 5-13-85 5-14-85 5-14-85 5-13-85 5-13-85 5-13-85 to to to to to to to to 5-20-85 5-20-85 5-20-85 5-21-85 5-21-85 5-20-85 5-20-85 5-20-85 5-20-85 5-20-85 5-20-85 5-21-85 5-21-85 5-20-85 5-20-85 5-20-85 to to to to to to to to 5-28-85 5-28-85 5-28-85 5-29-85 5-29-85 5-28-85 5-28-85 5-28-85 ,
I
. . .. . . . - .- = .- .- - - -- . ,<
t.
,i
. TABLE C-5 (cont'd) 1 1985 SAMPLING DATES FOR AIR SAMPLES STATION NO. .
MONTH 2S2 SSI SDI 10D1 16El IF1 2F2 3H3 JUNE' 5-28-85 5-28-85 5-28-85 5-29-85 5-29-85 5-28-85 5-28-85 5-28-85 to to to to to to to to 6-03-85 6-03-85 6-03-85 6-04-85 6-04-85 6-03-85 6-03-85 6-03-05 6-03-85 6-03-85 6-03-85 6-04-85 6-04-85 6-03-85 6-03-85 6-03-85 to to to to to to to .
to 6-10-85 6-10-85 6-10-85 6-11-85 6-11-85 6-10-85 6-10-85 6-10-85 6-10-85 6-10-85 6-10-85 6-11-85 6-11-85 6-10-85 6-10-85 6-10-85 to to to to to to to to 1
6-17-85 6-17-85 6-17-85 6-17-85 6-17-85 6-17-85 6-17-85 6-17-85 6-17-85 6-17-85 6-17-85 6-17-85 5-17-85 6-17-85 6-17-85 6-17-85 to to to to to to to to 6-24-85 6-24-85 6-24-85 6-25-85 6-25-85 6-24-85 6-24-85 6-24-85 Os 04 6-24-85 6-24-85 6-24-85 6-25-85 6-25-85 6-24-85 6-24-85 6-24-85 l to to to to to to to to l 7-01-85 7-01-85 7-01-85 7-02-85 7-02-85 7-01-85 7-01-85 7-01-85 4
JULY 7-01-85 7-01-85 7-01-85 7-02-85 7-02-85 7-01-85 7-01-85 7-01-85 to to to to to to to to
! 7-08-85 7-08-85 7-08-85 7-08-85 7-09-85 7-08-85 7-08-85 7-08-85 l 7-08-85 7-08-85 7-08-85 7-08-85 7-09-85 7-08-85 7-08-85 7-08-85 to to to to to to to to 7-15-85 7-15-85 7-15-85 7-16-85 7-16-85 7-15-85 7-15-85 7-15-85
,i j 7-15-85 7-15-85 7-15-85 7-16-85 7-16-85 7-15-85 7-15-85 7-15-85 L to to to to to to to to 7-22-85 7-22-85 7-22-85 7-22-85 7-22-85 7-22-85 7-22-85 7-22-85 7-22-85 7-22-85 7-22-85 7-22-85 7-22-85 7-22-85 7-22-85 7-22-85 to to to to to to to to 7-29-85 7-29-85 7-29-85 7-30-85 7-30-85 7-29-85 7-29-85 7-29-85 AUGUST . 7-29-85 7-29-85 7-29-85 7-30-85 7-30-85 7-29-85 7-29-85 7-29-85 to to to to to to to to
, 8-05-85 b-05-85 8-05-85 8-06-85 8-06-85 8-05-85 8-05-85 8-05-85 i
j 8-05-85 8-05-85 8-05-85 8-06-85 8-06-85 8-05-85 8-05-85 8-05-85 to to to to to to to to 8-12-85 8-12-85 8-12-85 8-13-85 8-13-85 8-12-85 8-12-85 8-12-85 i
TABLE C-5 (cont'd) 1985 SAMPLING DATES FOR AIR SAMPLES STATION NO.
MONTH 2S2 SSI SD1 10D1 16El IF1 2F2 3H3 AUGUST 8-12-85 8-12-85 8-12-85 8-13-85 8-13-85 8-12-85 8-12-85 8-12-85 to to to to to to to to 8-19-85 8-19-85 8-19-85 8-19-85 8-19-85 8-19-85 8-19-85 8-19-85 8-19-85 6-19-85 8-19-85 8-19-85 8-19-85 8-19-85 8-19-85 8-19-85 to to to to to to to to 8-26-85 8-26-85 u-26-85 8-27-85 8-27-85 8-26-85 8-25-85* 8-26-85 8-26-85 8-26-85 8-26-85 8-27-85 8-26-85 8-27-85 8-26-85 to to to to (1) to to to 9-03-85 9-03-85 9-03-85 9-03-85 9-03-85 9-03-85 9-03-85 SEPTEMBER 9-03-85 9-03-85 9-03-85 9-03-85 9-03-85 9-03-85 9-03-85 9-03-85 to to to to to to to to 9-09-85 9-09-85 9-09-85 9-09-85 9-09-85 9-09-85 9-09-85 9-09-85 04
-J 9-09-85 9-09-85 9-09-85 9-09-85 9-09-85 9-09-85 9-09-85 9-09-85 to to to to to to to to 9-16-85 9-16-85 9-16-85 9-17-85 9-17-85 9-16-85 9-16-85 9-16-85 9-16-85 9-16-85 9-16-85 9-17-85 9-17-85 9-16-85 9-16-85 9-16-85 to to to to to to to to 9-20-85* 9-23-85 9-23-85 9-23-85 9-23-85 9-23-85 9-23-85 9-23-85 9-24-85 9-23-85 9-23-85 9-23-85 9-23-85 9-23-85 9-23-85 9-23-85 to to to to to to to to 9-30-85 9-30-85 9-30-85 10-01-85 10-01-85 9-30-85 9-30-85 9-30-85 OCTOBER 9-30-85 9-30-85 9-30-85 10-01-85 10-01-85 9-30-85 9-30-85 9-30-85 to to to to to to to to 10-07-85 10-07-85 10-07-85 10-07-85 10-07-85 10-07-85 10-07-85 10-07-85 10-07-85 10-07-85 10-07-85 10-07-85 10-07-85 10-07-85 10-07-85 10-07-85 to' to to to to to to to 10-15-85 10-15-85 10-15-85 10-16-85 10-16-85 10-15-85 10-15-85 10-15-85 10-15-85 10-15-85 10-15-85 10-16-85 10-16-85 10-15-85 10-15-85 10-15-85 to to to to to to to to 10-21-85 10-21-85 10-21-85 10-21-85 10-21-85 10-21-85 10-21-85 10-21-85 10-21-85 10-21-85 10-21-85 10-21-85 10-21-85 10-21-85 10-21-85 10-21-85 to to to to to to to to 10-28-85 10-28-85 10-28-85 10-29-85 10-29-85 10-28-85 10-28-85 10-28,85
i TABLE C-5 (cont-J) 1985 SAMPLING DATES FOR AIR SAMPLES STATION NO.
MONTH 2S2 SSI 5D1 10D1 16El IFl 2F2 3H3 NOVEMBER 10-28-85 10-28-85 10-28-85 10-29-85 10-29-85 10-28-85 10-28-85 10-28-85 i to to to to to to to to l 11-04-85 11-04-85 11-04-85 11-04-85 11-04-85 11-04-85 11-04-85 11-04-85 11-04-85 11-04-85 11-04-85 11-04-85 11-04-85 11-04-85 11-04-85 11-04-85 to to to- to to to to to 11-12-85 11-12-85 11-12-85 11-12-85 11-12-85 11-12-85 11-12-85 11-06-85*
11-12-85 11-12-85 11-12-85 11-12-85 11-12-85 11-12-85 11-12-85 11-12-85 to to to to to to to to 11-18-85 11-18-85 11-18-85 11-19-85 11-19-85 11-18-85 11-18-85 11-18-85 11-18-85 11-18-85 11-18-85 11-19-85 11-19-85 11-18-85 11-18-85 11-18-85 to to to to to to to to i
j 11-25-85 11-25-85 11-25-85 11-26-85 11-26-85 11-25-85 11-25-85 11-25-85 t Ch 1 03 11-25-85 11-25-85 11-25-85 11-26-85 11-26-85 11-25-85 11-25-85 11-25-85 I
to to to to i to to to to 12-02-85 12-02-85 12-02-85 12-02-85 12-02-85 12-02-85 12-02-85 12-02-85 DECEMBER 12-02-85 12-02-85 12-02-85 12-02-85 12-02-85 12-02-85 12-02-85 12-02-85 to to to to to to to to i 12-09-85 12-09-85 12-09-85 12-10-85 12-10-85 12-09-85 12-09-85 12-09-85 12-09-85 12-09-85 12-09-85 12-10-85 12-10-85 12-09-85 12-09-85 12-09-85 to to to to to to to to 12-16-85 12-16-85 12-16-85 12-16-85 12-16-85 12-16-85 12-16-85 12-16-85 I
12-16-85 12-16-85 12-16-85 12-16-85 12-16-85 12-16-85 12-16-85 12-16-85
-; to to to to to to to to 12-23-85 12-23-85 12-23-85 12-23-85 12-23-85 12-23-85 12-23-85 12-23-85 12-23-85 12-23-85 12-23-85 12-23-85 12-23-85 12-23-85 12-23-85 12-23-85 to to to to to to to to 12-30-85 12-30-85 12-30-85 12-31-85 12-31-85 12-30-85 12-30-85 12-30-85 1
- Heduced sampling period due to instrument malfunction.
(1) No sample collected for the period 08-27-85 to 09-03-85 due to vandalism of the sampling assemblies.
TABLE C-6 1985 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, AND TRITIUM IN PRECIPITATION STATION NO. SA-RWA-2F2 Results in Units of pCi/L i 2 sigma COLLECTION PERIOD ALPHA BETA TRITIUM 1-02-85 to 1-28-85 (1) (1) <130 i
1-28-85 to 2-26-85 (1) (1) <140 2-26-85 to 3-26-85 (1) (1) <140 3-26-85 to 4-30-85 (1) (1) <140 4-30-85 to 5-29-85 <2.0 6.2 1.5 <140 5-29-85 to 7-02-85 <2.8 7.313.0 <130 '
7-02-85 to 7-30-85 <1.2 1.6 0.7 <140 7-30-85 to 8-26-85 <1.4 0.8 0.5 <140
~
8-26-85 to 9-30-85 <2.4 1.420.6 <140 9-30-85 to 10-29-85 <1.8 2.2 1.0 <140 10-29-85 to 11-25-85 1.020.9 2.520.6 <150 11-25-85 to 12-31-85 <2.4 2.710.7 <130 AVERAGE -
3.114.7 -
(1) Not analyzed due to insufficient precipitation during sampling period.
i-69
TABLE C-7 1985 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND GAMMA EMITTERS **
4 IN QUARTERLY COMPOSITES OF PRECIPITATION STATION NO. SA-RWA-2F2 Results in Units of.pci/L i 2 sigma 1-02-85 4-30-85(2) 7-02-85 9-30-85 NUCLIDE to to to to AVERAGE 3-26-85 7-02-85 9-30-85 12-31-85 4
Sr-89 (1) (1) <0.5 <0.6 -
Sr-90 (1) (1) <0.5 <0.5 -
Be-7 20 5 5216 17 4 25i7 28132
- 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) Not analyzed due to insufficient precipitation during sampling period.
(2) Second quarter gamma analysis run on May and June samples only due to insufficient precipitation in April.
A TABLE C-8 1985 DIRECT RADIATION MEASUREMENTS - QUARTERLY TLD RESULTS Results in mead / standard month *
(Results by Teledyne Isotopes)
JANUARY APRIL JULY OCTOBER STATION NO. to to to to AVERAGE MARCH JUNE SEPTEMBER DECEMBER SA-IDH-2S2 5.220.5 4.620.4 5.4 0.2 4.920.5 5.020.7 SA-IDM-5S1 4.920.2 4.420.2 5.220.4 4.710.3 4.820.7 SA-IDH-6S2 5.320.3 4.620.3 5.420.4 5.220.6 5.120.7 SA-IDM-7S1 6.620.6 5.910.7 6.720.4 6.420.5 6.420.7 SA-IDH-1051 5.820.4 5.420.8 6.320.5 5.720.4 5.820.7 SA-IDM-llS1 5.720.6 7.621.7 7.2 0.9 5.010.4 6.4t2.4 SA-IDM-4D2 5.920.6 5.1 0.5 6.020.6 5.520.7 5.620.8 SA-IDH-SD1 5.320.5 4.720.4 5.520.3 5.120.4 5.220.7 SA-IDM-10D1 5.7*0.6 4.820.5 5.920.6 5.520.5 5.521.0 SA-IDM-14D1 5.620.4 4.820.3 5.820.4 5.220.6 5.420.9 SA-IDH-2El 5.420.6 4.710.4 5.920.5 5.420.5 5.421.0 SA-IDH-3E1 5.420.4 4.620.2 5.320.5 5.020.4 5.120.7 SA-IDH-9El 6.4t0.8 5.520.7 6.710.8 6.220.9 6.2tl.0 SA-IDM-llE2 6.320.8 5.620.6 6.720.4 6.120.7 6.220.9 SA-IDH-12E1 6.120.6 5.220.4 6.320.5 5.820.8 5.8tl.0 SA-IDM-13El 5.420.4 4.720.3 5.4t0.3 5.120.4 5.220.7 SA-IDM-16El 6.120.6 5.020.5 5.720.3 5.320.6 5.5tl.0 SA-IDH-lF1 5.710.6 4.920.3 5.820.4 5.320.4 5.420.8 SA-IDM-2F2 4.720.2 3.6 0.3 4.720.2 4.li0.2 4.321.1 SA-IDM-2F5 5.920.4 5.020.4 5.820.5 5.320.4 5.St0.8 SA-IDM-2F6 5.720.3 4.8 0.3 5.6t0.2 5.220.3 5.310.7 SA-IDM-3F2 5.320.2 4.320.2 5.320.2 4.720.3 4.910.7 SA-IDH-3F3 5.220.4 4.320.3 5.320.4 4.7 0.4 4.920.8 SA-IDM-5F1 5.420.4 4.620.2 5.220.4 5.020.4 5.0i0.7 SA-IDH-6F1 5.020.2 4.020.1 4.920.1 4.120.3 4.521.0 SA-IDM-7F2 4.520.2 3.620.1 4.620.1 3.820.2 4.121.0 SA-IDH-10F2 5.920.5 5.320.4 6.320.5 5.921.1 5.820.8 SA-IDM-llF1 6.110.5 5.220.4 6.6t0.7 5.920.3 5.921.2 SA-IDM-12F1 5.7t0.4 5.020.4 6.220.5 5.320.4 5.521.0 SA-IDM-13F2 5.7 0.4 4.9 0.4 6.0t0.5 5.7 0.3 5.620.9 SA-IDM-13F3 5.920.3 5.0 0.5 6.320.3 5.520.5 5.721.1 SA-IDM-13F4 5.620.4 4.920.6 5.920.3 5.420.3 5.420.8 SA-IDM-14F2 5.620.5 4.820.4 6.020.3 5.320.5 5.4*l.0 SA-IDM-15F3 6.420.6 5.920.4 6.220.6 6.521.4 6.220.5 SA-IDM-16F2 5.220.3 4.720.3 5.620.4 5.020.5 5.120.8 SA-IDM-lG3 (C) 6.920.9 5.820.6 7.220.4 6.4 0.3 6.621.2 SA-IDM-3G1 (C) 6.320.8 5.320.7 6.820.5 5.821.0 6.021.3 SA-IDM-10G1 (C) 6.220.5 5.720.7 6.4t0.7 5.920.7 6.020.6 SA-IDH-16G1 (C) 6.420.4 5.720.4 7.120.5 6.220.7 6.4tl.2 SA-IDM-3H1 (C) 6.220.5 5.110.3 6.420.3 5.720.2 5.821.2 SA-IDM-3H3 (C) 6.020.3 5.420.3 6.520.6 5.6 0.6 5.921.0 AVERAGE 5.~721.0 5.021.4 6.021.3 5.421.2 Grand Average 5.521.4
- The standard month = 30.4 days.
(C) Control station 71 l
TABLE C-9 1985 DIRECT RADIATION MEASUREMENTS - MONTHLY TLD RESULTS Results in arad/ standard month *
(Results by Teledyne Isotopes)
STATION NO. JANUARY FEBRUARY MARCH AFRIL MAY JUNE SA-IDH-2S2 5.8t0.5 5.810.4 5.820.5 5.620.1 4.810.3 5.920.3 SA-IDM-SSl 4.910.3 5.620.1 5.320.5 5.420.3 4.720.1 5.620.3 SA-IDM-6S2 6.120.5 6.320.3 5.920.3 5.920.3 5.3t0.8 6.120.2 SA-IDM-7S1 6.920.4 7.310.7 7.021.0 7.020.7 6.120.2 7.4t0.5 SA-IDH-10S1 6.510.4 6.520.5 6.610.5 6.7t0.5 5.8t0.6 6.910.4 SA-IDM-11S1 5.810.7 5.620.2 7.6tl.1 8.721.2 8.211.8 9.121.8 SA-IDH-SD1 5.910.5 6.120.7 5.920.5 5.820.4 5.120.2 6.320.5 SA-IDM-10D1 6.320.7 6.220.6 6.110.3 6.320.5 5.610.6 6.720.7 SA-IDM-14D1 6.2t0.7 6.120.4 6.4t0.6 6.220.6 5.5tl.0 6.320.5 SA-IDH-2E1 5.820.3 5.820.5 6.220.6 5.820.1 5.410.7 6.320.2 d SA-IDM-3E1 5.820.3 5.610.4 5.720.2 5.820.2 5.120.2 6.120.4 SA-IDM-13El 5.920.4 5.920.3 5.920.6 6.220.5 4.810.2 6.020.6 SA-IDM-16El 6.010.2 6.320.4 6.110.4 6.320.4 5.4t0.4 6.610.3 SA-IDM-lF1 6.120.8 6.520.3 5.920.4 6.0t0.4 5.520.4 6.520.3 SA-IDM-2F2 5.320.2 5.020.1 4.910.3 5.120.3 4.420.2 5.320.4 SA-IDM-2F6 6.020.7 6.120.2 6.l*0.3 6.2to.2 5.320.2 6.320.4 SA-IDM-5F1 5.920.9 5.720.5 5.810.3 5.810.2 4.920.2 6.020.3 SA-IDM-6F1 5.5 0.6 5.320.4 5.120.2 5.220.3 4.420.2 5.520.5 SA-IDM-7F2 4.9t0.1 5.0t0.1 4.710.3 4.720.2 4.020.1 4.720.4 SA-IDM-llF1 6.610.7 6.6t0.6 6.811.2 6.410.3 5.820.6 6.720.4 SA-IDM-13F4 6.410.7 7.111.5 6.210.5 6.320.4 5.520.4 6.2 0.2 SA-IDM-3G1 (C) 6.410.6 6.410.5 6.3 0.8 6.320.2 5.820.4 6.910.7 SA-IDM-3H1 (C) 6.6 1.0 6.620.4 6.320.4 6.210.4 5.110.2 6.520.2 S A-IDH-3H3 (C) 7.220.7 7.220.6 6.710.3 6.510.3 5.820.1 6.720.5 AVERAGE 6.021.1 6.111.2 6.021.3 6.121.5 5.321.6 6.4tl.6
TABLE C-9 (cont'd) 1985 DIRECT RADIATION MEASUREMENTS - MONTHLY TLD RESULTS Results in arad/ standard month *
(Results by Teledyne Isotopes)
STATION NO. JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECDtBER AVERAGE SA-IDM-2S2 5.220.6 6.520.8 5.6t0.4 5.620.3 4.8t0.3 6.3 0.4 5.621.0 SA-IDM-SS1 5.020.4 6.320.3 4.920.6 5.2*0.4 4.5t0.2 6.0 0.4 5.3tl.1 SA-IDM-6S2 5.320.4 6.4t0.3 5.220.4 5.820.3 5.120.4 6.220.4 5.820.9 SA-IDM-7S1 6.210.4 7.320.4 6.220.5 6.8t0.7 5.920.2 7.720.5 6.821.2 SA-IDM-10S1 6.220.8 6.820.6 5.720.4 6.210.6 5.6t0.7 6.820.6 6.4 0.9 l SA-IDH-llS1 8.121.3 7.720.9 5.3t0.3 5.7t0.4 4.820.4 6.lt0.3 6.9k3.0 j SA-IDh-SD1 5.320.3 6.520.3 5.220.5 5.9 0.9 5.421.0 6.St0.4 5.8tl.0 SA-IDM-10D1 5.620.4 7.320.5 5.7*0.7 6.120.4 5.3t0.6 6.920.9 6.221.2 SA-IDH-14D1 5.720.3 6.820.6 5.420.3 5.920.7 5.120.2 6.420.6 6.0*l.0 ,
SA-IDM-2E1 5.520.5 6.420.5 5.320.5 5.6t0.5 4.9t0.4 6.520.6 5.8tl.0 SA-IDM-3El 5.721.4 6.220.6 5.120.6 5.520.3 4.820.3 6.320.3 5.6t0.9 i [j SA-IDM-13El 5.120.3 6.lto.5 5.120.7 5.620.5 4.920.5 6.420.5 5.621.1 SA~IDH-16El 5.9tl.0 6.510.3 5.6t0.9 6.lt0.6 5.210.4 6.9 0.4 6.121.0 SA-IDH-lF1 5.620.6 6.720.3 5.220.4 5.920.4 5.2t0.6 6.720.4 6.021.1 SA-IDM-2F2 4.620.2 5.220.3 4.420.3 5.020.2 4.020.0 5.420.4 4.920.9 SA-IDM-2F6 5.320.4 6.710.6 4.820.7 5.820.5 4.920.4 6.820.6 5.821.3 SA-IDM-5F1 5.320.7 6.0t0.3 5.220.6 5.620.4 4.6t0.7 6.220.5 5.621.0 SA-IDM-6F1 4.720.3 5.420.3 4.6t0.4 4.820.6 4.2t0.2 5.St0.6 5.020.9 I SA-IDM-7F2 4.120.1 5.020.1 4.010.7 4.620.3 3.720.2 4.920.7 4.520.9 SA-IDM-llF1 6.320.8 6.920.6 5.820.7 6.420.4 5.6t0.5 7.420.6 6.421.0 SA-IDM-13F4 5.520.4 6.820.4 5.720.6 6.120.5 4.822.4 6.820.4 6.121.3 SA-IDM-3G1 (C) 5.920.7 6.8t0.6 6.120.6 6.220.5 5.820.3 6.720.2 6.320.7 SA-IDM-3H1 (C) 5.720.4 6.8t0.8 5.720.5 6.4t0.3 5.720.3 7.120.5 6.221.1 SA-IDM-3H3 (C) 6.120.3 7.520.2 6.li0.4 6.St0.5 6.120.8 6.910.3 6.621.0 AVERAGE 5.621.5 6.521.3 5.321.1 5.821.1 5.021.2 6.5*l.2 Grand Average 5.911.6
- The standard month = 30.4 days.
(C) Control station
.. .,_._s _ ~ . _ - . . . . - _
TABLE C-10 1985 CONCENTRATIONS OF IODINE-131* IN MILK 4
.Results in Units of PC1/L a
j STATION NO.** JANUARY FEBRUARY MARCH APRIL MAY JUNE i SA-MLK-13E3 <0.1 <0.1 <0.2 <0.1 <0.1 <0.1
<0.2 <0.1 <0.1 <0.2 <0.1 <0.1 SA-MLK-2F4 <0.1 <0.1 <0.1 <0.1 -<0.1 <0.1 j
<0.2 <0.1 <0.1 <0.1 <0.1 <0.1 l SA-MLK-5F2 <0.1 <0.1 <0.1 <0.1 <0.1 <0.1
<0.2 <0.1 <0.2 <0.2 <0.1 <0.1
' SA-MLK-14F1 <0.1 <0.1 (0.1 <0.1 <0.2 <0.1 j <0.2 <0.1 <0.1 <0.1 <0.1 <0.1 SA-MLK-15F1 <0.1 <0.1 <0.1 <0.1 <0.1 <0.1 l <0.2 <0.1 <0.1 <0.2 <0.1 <0.1
, SA-MLK-3G1 <0.1 <0.1 <0.1 <0.1 <0.1 <0.1 I (Control) <0.2 <0.1 <0.1 <0.2 <0.1 <0.1
-J l am i STATION NO.** JULY .A9 GUST SEPTEMBER OCTOBER NOVEMBER DECEMBER SA-MLK-13E3 <0.1 <0.1 <0.2 <0.2 <0.2 <0.1
<0.1 <0.2 <0.3 <0.2 <0.1 <0.1 SA-MLK-2F4 <0.1 <0.1 <0.1 <0.1 <0.2 <0.1
<0.2 <0.2 <0.2 <0.2 <0.1 <0.1 4
i SA-MLK-5F2 <0.1 <0.1 <0.1 <0.1 <0.2 <0.1 4
<0.2 <0.2 <0.2 <0.2 <0.1 <0.1 i
i SA-MLK-14F1 <0.1 <0.1 <0.1 <0.2 <0.2 <0.1
<0.2 <0.2 <0.2 <0.2 <0.1 <0.1 SA-MLK-15F1(13 <0.1 <0.1 <0.1 - - -
<0.2 <0.2 <0.2 - - -
SA-MLK-11F3(2) - - -
<0.2 <0.2 <0.1 I
- - - - <0.2 <0.1 <0.1
- l SA-MLK-3G1 <0.1- <0.1 <0.1 <0.1 <0.2 <0.1 (Control) <0.2 <0.1 <0.2 <0.2 <0.1 <0.1
- I-131 results are corrected for decay to midpoint of collection period.
- Sampling dates can be found in Table C-13.
i (1) Station SA-MLK-15F1 terminated milk production on October 7, 1985.
(2) Station SA-MLK-11F3 replaced station SA-MLK-15F1 on October 7, 1985.
f i
y , _ , , _ _ _ .y ,
TABLE C-11 1985 CONCENTRATIONS OF STRONTIUM-898 and -90 IN MILK Results in Units of PC1/L 1 2 signa STATION NO.** NUCLIDE JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-MLK-1353 St-89 <0.9 <0.9 <0.9 <0.9 .<l.0 <l.0 St-90 1.410.4 1.920.4 2.210.4 1.810.4 1.320.4 1.710.4 SA-MLK-2F4 St-89 <0.8 <!.1 <0.0 <0.9 <1.0 <1.0 St-90 1.120.3 1.320.4 1.4t0.3 1.720.3 1.420.4 1.720.4 SA-MLK-5F2 Sr-89 <l.0 <1.0 <1.0 <1.1 <l.2 St-90 <l.3 2.410.4 2.520.4 3.320.4 3.010.4 3.120.4 4.0to.5 SA-MLK-14F1 St-89 <1.0 <1.0 <1.0 <0.9 <1.0 Sr-90
<1.0 1.410.4 2.0t0.4 2.120.4 '1.520.4 1.720.4 2.210.4 SA-MLK-15F1 St-89 <l.0 <1.0 <!.0 <0.9 <1.0 <1.2 St-90 2.0t0.4 1.610.4 3.120.4 1.720.4 1.620.4 2.8t0.5 SA-MLK-3G1 St-89 <l.0 <1.1 <0.9 <1.0 <l.0 <l.2 (Control) Sr-90 2.020.4 2.210.4 2.320.4 3.220.4 1.910.4 3.110.5 4
U1 STATION NO.** NUCLIDE JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE SA-MLK-13E3 St-89 <0.9 <0.9 <0.9 <l.0 <1.0 <1.3 -
Sr-90 <0.8 1.210.3 1.220.4 1.4to.4 1.620.4 2.020.5 1.520.8 SA-MLK-2F4 St-89 1.120.4 <0.9 <0.9 <1.0 <0.9 <1.5 -
St-90 1.210.4 1.320.3 1.420.3 1.020.4 1.220.3 1.310.5 1.320.4 SA-MLK-5F2 St-89 <!.2 <1.1 <1.2 <1.2 + <1.2 <l.1 -
St-90 3.420.5 3.810.4 3.020.5 3.6 0.5 3.120.5 2.520.4 3.111.0 SA-MLK-14F1 Sr-89 <0.9 <1.0 <1.0 <1.0 <1.0 <1.2 -
Sr-90 1.720.4 1.610.4 1.820.4 1.620.4 1.520.4 1.720.4 1.7to.5 SA-MLK-15F1III St-89 <l.1 <l.0 <1.0 - - - -
Sr-90 1.610.4 1.720.4 1.720.4 - - -
2.0t1.1 SA-MLK-11F3I2) St-89 - - -
<l.0 <0.8 <1.1 -
St-90 - - -
1.220.4 1.320.4 1.420.4 1.320.2 SA-MLK-3G1 St-89 <l.2 <1.0 1.5t0.5 <l.1 <1.1 <1.2 -
(Control) Sr-90 2.810.4 2.110.4 1.520.4 2.910.5 2.520.4 2.420.5 2.411.0 Grand Average Sr-89 -
St-90 2.021.5
- 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.
- 11) Station SA-MLK-15F1 terminated milk production on October 7, 1985.
(2) Station SA-MLK-11F3 replaced station SA-MLK-15F1 on October 7, 1985.
> a .a , . . .- .- . .- . . . ~ .
TABLE C-12 1985 CONCENTRATIONS OF GAMMA EMITTERS
- IN MILK Results in Units of PC1/L t 2 signa STATION NO.** NUCLIDE JANUARY FEBRU AR Y MARCH APRIL MAY JUNE SA-MLK-13E3 K-40 1400:54 1400:55 1400260 1300 55 1400155 1400:59 Mn-54 <2.5 <1.7 <1.8 <2.2 <2.2 <1.2 Cs-137 <1.4 <2.1 <1.6 <2.3 <2.4 <2.4 Ra-226 <4.5 <4.3 <4.3 <4.8 <3.9 <4.6 Th-232 <8.1 <7.9 <9.2 1016 <5.8 <9.5 SA-MLK-2F4 K-40 1400267 1400:58 1400168 1300265 1300154 1400268 Mn-54 <2.3 <2.2 <2.3 <2.3 <2.3 <2.3 Cs-137 <2.4 <2.5 <2.6 <2.4 <2.3 <2.4 Ra-226 <4.8 <3.9 <4.8 <4.8 <5.7 <5.1 Th-232 <9.3 <8.3 <9.8 8.024.0 <9.3 <9.3 SA-MLK-5F2 K-40 1300167 1300270 1400270 1400169 1300469 1300267 Mn-54 <2.3 <1.6 <0.5 <2.8 <0.4 <2.4 Cs-137 <2.8 <2.9 <3.0 <2.6 <2.9 3.822.0 Ra-226 <6.0 <5.3 <6.5 <5.4 <5.9 <6.2 Th-232 <8.6 <9.8 <12 <12 <!2 <12
-J SA.MLg-14r1 K-40 1400:55 1400:54 1400:54 1200150 1400153 1400:53 CN Mn-54 <1.7 <1.8 <1.8 <1.6 <1.8 <1.8 Cs-137 <2.0 <2.1 <2.0 <2.1 <2.0 <2.0 Ra-226 <2.5 <3.7 <2.5 7.012.2 <3.7 9.9 2.3 Th-232 (6.6
<7.1 <7.1 <7.1 <7.1 <7.5 SA-MLK-15F1 K-40 1400:57 1300265 1400:59- 1300 55 1300258 1300258 Mn-54 <1.2 <2.5 <0.9 <!.7 <0.3 <2.0 Cs-137 <2.1 <2.6 <2.1 <3.4 <2.2 <2.2 Ra-226 <4.4 <5.1 <4.5 <4.6 <3.5 5.623.0 Th-232 <9.3 <9.3 <8.6 <9.4 <7.0 <8.2 SA-MLK-3G1 K-40 1300tS7 1400267 1300154 1300158 140Ct58 1300154 (Control) Mn-54 <2.1 <2.2 <0.8 <1.0 3.511.6 <2.2 Cs-137 2.311.5 <2.6 <2.5 <1.7 <1.2 <2.5 Ra-226 <4.7 (4.8 <3.8 <4.8 <4.2 <5.5 Th-232 <7.6 <8.0 <8.1 <9.4 <S.6 <6.7 AVERAGE K-40 1400 100 1400 100 1400282 1300 130 14001110 1400:110
-l
t
\ I I
f ?
\ *
' l l
1 TAsLa C-12 (cont'd) 1985 CONCENTRATIONS OF GAMMA BMITTERS* IN MILE 4
Results in Units of pC1/L t 2 sigma STATION NO.** NUCLIDE JULY AUGUST SEPTBMBER OCTOGER NOYBMBER DRCBMSER AVERAGE SA-MLK-13E3 K-40 1400167 1400155 1400268 1400159 1400268 1400:56 1408:58' Mn-54 <2.3 <2.2 <2.5 <1.3 <2.3 <!.7 -
Cs-137 <2.6 <2.4 <2.6 <2.4 <2.4 <2.2 -
Ra-226 4.012.3 <5.5 <5.1 <5.4 <5.1 <5.3 -
Th-232 <9.3 <9.2 <8.9 <8.8 <8.9 <9.1 - '
SA-MLK-2F4 K-40 1400256 1400268 1400:53 1400267 1400155 1400:55 1400178*
Mn-54 <3.0 <2.4 <1.7 <2.2 <1.5 <1.6 - '
Cs-137 <2.4 <2.4 <l.8 <2.4 <2.3 <2.6 -
Ra-226 <5.7 <4.0 <4.0 <4.8 <5.3 <5.3 -
Th-232 <8.0 <9.3 (7.5 <8.9 (6.7 <7.7 -
SA-MLK-5F2 K-40 1300267 1300:52 1300466 1300867 1300:52 1300267 1300270 Mn-54 <1.5 <!.7 <2.3 <3.0 <1.7 <2.1 -
Cs-137 <3.4 2.621.0 3.911.4 <2.7 <2.0 <3.0 -
Ra-226 <5.9 3.321.9 <4.8 <5.2 <4.0 5.213.0 - '
Th-232 <!2 <7.1 <!! <9.0 <7.1 <!! -
%J
-J SA-MLK-14F1 K-40 1400154 1300267 1400 53 1400156 1400254 1300:58 14002130 Mn-54 <!.8 <2.5 <1.8 <2.7 <1.7 <!.9 -
Cs-137 <2.0 <3.1 <2.0 <2.4 <2.0 <2.5 -
Ra-226 <4.0 11 4 1422 <5.3 <4.4 <5.3 -
Th-232 (7.1 (12 (7.1 <8.6 <6.6 1326 -
SA-MLK-15FIIII K-40 1200:52 1300158 1300160 - - -
13008120 Mn-54 <2.3 <3.2 <2.3 - - - -
Cs-137 <2.2 <3.4 <2.5 - - - -
Ra-226 <5.6 <6.5 <5.1 - - - -
Th-232 <10 <!! <9.3 - - - -
SA-MLK-11F3(2) K-40 - - - 1400259 1300258 1400:53 1400:120 Mn-54 - - - <2.5 <2.3 <1.7 -
Cs-137 - - -
<2.6 <2.3 <2.0 -
Ra-226 - - - <5.0 <5.4 <4.0 -
Th-232 - - - <8.5 <9.5 <7.1 -
SA-MLK-3G1 K-40 1300:57 1300:59 1300260 1400453 1400270 1400262 13001100 (controll Mn-54 <2.3 <1.6 <2.4 <1.6 <2.2 <2.3 -
Co-137 <1.7 <2.5 <2.4 <2.0 <2.5 <2.4 -
Ra-226 <5.9 <5.4 <4.8 <4.0 <5.9 <5.1 -
Th-232 <9.1 <9.1 <9.8 <7.5 <!3 <8.4 -
AVERAGE K-40 1300:160 1300 100 1400t!!0 1400282 1400:100 1400 100 Grand Average K-40 14001110 .
- All other gamma emitters searched for were <LLD3 typical LLDs are given in Table C-!!.
- Sampling dates can be found in Table C-13.
Gamma analysis performed only on first milk collection of each month.
(1) Station SA-MLK-15F1 terminated milk product!or, on October 7, 1385.
(2) Station SA-MLK-!!F3 replaced station SA-MLK-15F1 on October 7, 1985.
.w .
.c i i i
i TABLE C-13 1985 SAMPLING DATES FOR MILZ SAMPLES STATION NO.
,_ MONTH 13E3 2F4 5F2 14F1 15F1 ; 3C1 4
JANUARY 1-07-85 1-08-85 1-07-85 1-08-85 1-08-05 1-07-05 to to to to to .to 1-08-85 1-09-85 1-08-85 1-09-05 1-09-85 1-08-85 1-21-85 1-22-85 1-22-85 1-20-85 1-21-85 1-21-85 to to to to to to 1-22-85 1-22-85 1-22-85 1-21-85 1-21-85 1-22-85
. FEBRUARY 2-04-85 2-03-85 2-03-85 2-03-85 2-03-85 2-04-85 to to to to to ' to 2-05-85 2-04-85 2-04-85 2-04-85 2-04-85 2-05-85 2-18-85 2-19-85 2-18-85 2-19-85 2-19-85 2-18-85 to to to to to to a 2-19-85 2-20-85 2-19-85 2-20-85 ?-20-85 2-19-85 MARCH 3-04-85 3-03-85 3-03-85 3-03-85 3 Os-05 3-04-85 4 to to to to to to CD 3-05-85 3-04-85 3-04-85 3-04-85 3-04-85 3-05-85 3-18-85 3-17-35 3-17-85 3-17-85 3-17-85 3-18-05 to to to to to to 3-19-85 3-18-85 3-18-85 3-18-85 3-18-85 3-19-85 APRIL 4-07-85 4-08-85 4-08-85 4-08-85 4-08-85 4-07-85 to to to to to to 4-08-85 4-09-85 4-09-85 4-09-85 4-09-85 4-08-85 4-21-85 4-22-85 4-21-85 4-22-85 4-22-85 4-21-85 to to to to to to i 4-22-85 4-23-85 4-22-85 4-23-85 4-23-85 4-22 MAY 5-06-85 5-06-85 5-05-85 5-06-85 5-06-85 5-05-85 to to to to to to 5-07-85 5-07-85 5-06-85 5-07-85 5-07-05 5-06-05 5-19-85 5-20-85 5-19-85 5-20-85 5-20-85 5-19-85 to to to to to to 5-20-85 5-21-85 5-20-85 5-21-85 5-21-85 5-20-85 JUNE 6-02-85 6-03-85 6-02-e5 6-03-05 6-03-85 6-02-85 to to to to to to 6-03-05 6-04-85 6-03-85 6-04-05 6-04-85 6-03-05 6-16-85 6-17-85 6-16-85 6-17-05 6-17-05 6-16-05 to to to to to to
, 6-17-05 6-18-85 6-17-85 6-18-85 6-18-85 6-18-85
TA8LE C-13 (cont'd) 1985 SANFLING DAT88 FOR MILE SANFLES STATION NO. ,
l MONTH 13E3 2F4 5F2 14F1 15F1/11F3* 301 l
JULY 7-08-85 7-07.a5 7-07-85 7-07-45 7-07-05 7-08-85 to to to to to to 7-09-85 7-08-85 7-08-85 7-08-05 7-08-85 7-09-85 7-22-85 7-21-85 7-21-85 7-21-05 7-21-85 7-22-85 to to to to to to 7-23-85 7-22-65 7-22-85 7-22-85 7-22-85 7-23-85 AUGUST 8-05-85 0-04-85 8-04-05 0-04-05 8-04-05 8-05-85 to to to to to to 8-06-85 8-05-85 4-05-85 8-05-85 8-05-85 8-04-85 8-19-85 8-18-85 8-18-85 8-18-85 8-10-85 8-19-85 to to to to to to 0-20-85 8-19-85 8-19-85 8-19-85 0-19-85 4-20-85 SEPTEMBER 9-08-85 9-09-85 9-08-85 9-09-85 9-09-85 9-08-85
-J to to to to to to 43 9-10-85 9-10-85 9-09-85 9-10-85 9-10-85 9-09-85 9-22-85 9-23-85 9-23-85 9-23-85 9-23-85 9-22-85 to to to to to to 9-23-85 9-24-85 9-24-85 9-24-85 9-24-05 9-23-85 OCTOBER 10-06-85 10-07-05 10-07-05 10-07-05 10-07-85 10-06-05 to to to to to to 10-07-85 10-08-85 10-08-85 10-08-85 10-07-85 10-08-85 10-20-85 10-21-85 10-21-05 10-21-45 10-21-05 10-20-85 to to to to to to 10-21-85 10-22-85 10-21-05 10-22-05 10-21-85 10-21-85 NOVEMBER 11-03-85 11-02-85 11-02-05 11-02-85 11-04-85 11-03-85 to to to to to to 11-04-05 11-04-85 11-03-05 11-04-85 11-04-85 11-04-85 11-17-85 11-18-85 11-17-85 11-18-85 11-18-85 11-17-05 to to to to to to 11-18-85 11-19-85 11-18-85 11-19-85 11-18-85 11-18-85 DECEMBER 12-01-85 12-02-85 12-01-05 12-02-85 12-02-85 12-01-05 to to to to to to .
12-02-85 12-03-85 12-02-85 12-03-05 12-03-85 12-02-85 12-15-85 12-16-85 12-15-85 12-16-85 12-15-85 12-15-85 to to to to to to 12-16-85 12-17-85 12-16-85 12-17-05 12-16-85 12-16-05
- Station S A-MLK-11F3 replaced station SA-MLK-15F1 (terminated milk production) on 10-07-05.
TABLE C-14 1985 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 1-14-85 2-11-85 3-11-85 4-15-85 5-13-85 6-10-85 SA-WWA-2S3
., Alpha 1.611.0 <1.6 <1.6 <1.6 <l.4 <2.0 Beta 4.910.9 1411 7.911.1 7.211.0 8.711.1 6.911.0 K-40 6.510.6 1812 9.711.0 6.810.7 1211 7.610.8 m 11 - 3 <140 <130 <l50 <130 <130 <140 O
SA-WWA-5D1 l Alpha <0.9 <l.5 <l.6 <l.6 <1.6 <2.0 i Beta 1211 1411 1111 1311 1211 1411 K-40 1411 1211 1411 1311 1512 1311 H-3 <140 <150 <160 <130 <130 <130 SA-WWA-3El (Control)
Alpha <0.9 <1.5 <l.6 <1.7 <1.4 <2.2 Beta 8.411.1 9.111.1 7.411.0 9.211.0 7.811.0 9.011.1 K-40 9.210.9 0.810.9 1011 8.910.9 1211 8.810.9 H-3 <130 <140 <l50 <130 <130 <130
i f
TABLE C-14 (cont'd) 1985 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 7-15-85 8-12-85 9-16-85 10-15-85 11-12-85 12-09-85 AVERAGE SA-WWA-2S3 Alpha 1.811.1 <1.4 <1.6 <2.5 <1.6 2.211.4 -
Beta 7.911.1 5.511.0 7.311.0 8.711.1 3.810.8 3.410.8 7.215.6 K-40 8.110.8 5.610.6 7.010.7 7.810.8 3.710.4 4.810.5 8.117.6 q H-3 <140 <130 <130 <140 <140 <130 -
SA-WWA-SD1 Alpha <1.3 <1.6 <1.7 <2.7 <1.8 2.111.3 -
Beta 1111 1211 1311 1311 1211 1411 1312 K-40 1411 1411 1311 1812 1311 1411 1413 H-3 <130 <140 <130 <140 <140 <140 -
SA-WWA-3El (Control)
Alpha <1.3 <1.5 <1.7 <2.7 <1.9 1.411.0 -
Beta 7.711.1 8.211.1 8.711.1 7.911.0 9.711.1 8.411.0 8.411.2 K-40 9.410.9 8.710.9 8.410.8 8.810.9 8.410.8 1011 9.312.0 H-3 <130 <130 <140 <150 <150 <150 -
l
TABLE C-15 1985 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND GAMMA, EMITTERS ** ,
IN QUARTERLY COMPOSITES OF WELL WATER Results in Units of pCi/L i 2 sigma 1-14-85 4-15-85 7-15-85. 10-15-85 STATION NUMBER to to to to RADIOACTIVITY 3-11-85 6-10-85 9-16-85 12-09-85 SA-WWA-2S3 Sr-89 <0.4 <0.6 <0.6 <0.6 Sr-90 <0.4 <0.5 <0.5 <0.4 K-40 <10 <11 <11 <10 m Ra-226 <1.2 <l.2 <l.5 <l.3
" <1.9 <2.7 Th-232 <1.7 2.711.2 SA-WWA-5D1 Sr-89 <0.4 <0.6 <0.6 <0.5 '
Sr-90 <0.4 <0.5 <0.5 <0.4 i K-40 <10 1016 1816 1116 Ra-226 <1.2 <l.1 <1.1 <1.1 Th-232 1.811.2 <1.9 <1.7 <2.4 SA-WWA-3El (Control) l Sr-89 <0.4 <0.6 <0.6 <0.5 St-90 <0.4 <0.5 <0.5 <0.4 K-40 1216 1516 <11 <12 Ra-226 <1.1 <1.1 1.310.7 <l.4 Th-232 <1.8 < 1. 8 <2.4 <2.5
- 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.
_ _ _ _ _ _ _ _ _ _ _ _ - _ _ . _ _ _ - _ m -
TABLE C-16 1985 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, POTASSItM-40 AIO TRITILM IN RAW AND TREATED POTABLE WATER STATION NO. SA-PWR/T-2F3 j Results in Units of pCi/L
- 2 sigma RADIOACTIVITY JANUARY FEBRUARY MARCH APRIL MAY JUNE Alpha (Raw) <l.3 <2.7 <l 9 <2.5 <2.0 <2.3 (Treated) <l.5 <1.8 <1.7 <2.0 <1.8 <1.8
! Beta (Raw) 2.710.7 3.420.7 2.810.6 2.5t0.7 2.820.8 1.5t0.6 (Treated) 2.820.7 2.920.7 2.8t0.6 1.7t0.6 1.7t0.7 1.810.7 K-40 (Raw). 1.4t0.1 2.6t0.3 1.520.2 1.320.1 1.4t0.1 0.8 0.1 m (Treated) 1.520.2 2.6t0.3 1.Sto.2 1.420.1 1.420.1 0.820.1 to H-3 (Raw) <140 <140 <140 <140 160180 <140 (Treated) <130 <140 150t80 <130 <140 <130 RADIOACTIVITY JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE Alpha (Raw) <l.8 <l.7 <3.0 4.2t2.2 1.6t1.0 <3.4 -
(Treated) <l.4 <l.6 <2.4 <l.8 <0.6 <2.4 -
Beta (Raw) 1.120.7 2.410.7 2.lto.6 3.320.7 2.620.6 3.820.8 2.611.5 (Treated) <l.0 2.020.7 1.920.6 3.820.8 2.020.6 3.720.8 2.321.7 K-40 (Raw) 1.lt0.1 0.9t0.1 1.410.1 1.520.2 1.120.1 1.8t0.2 1.420.9 (Treated) 1.110.1 1.010.1 1.320.1 1.610.2 1.220.1 1.920.2 1.420.9 H-3 (Raw) <140 <140 <140 <140 <l50 <140 -
(Treated) <140 180180 <140 <140 <l50 <130 -
a
TABLE C-17 1985 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND GAMMA EMITTERS **
IN QUARTERLY COMPOSITES OF POTABLE WATER Results in Units of PCi/L i 2 sigma 1-01-85 4-01-85 7-01-85 10-01-85 STATION NUMBER to to to to RADIOACTIVITY 3-31-85 6-30-85 9-30-85 12-31-85 SA-PWR-2F3 (Raw)
Sr-89 <0.8 <0.8 <0.8 <0.7 m Sr-90 <0.5 <0.7 <0.7 <0.6 Te-129m <26 36115 <13 <21 Th-232 <1.6 <2.0 <1.9 <1.8 SA-PWT-2P3 (Treated)
Sr-89 <0.7 <0.6 <0.6 <0.8 Sr-90 <0.5 <0.5 <0.6 <0.7 Te-129m <13 <22 <19 <27 Th-232 1.711.1 <1.8 0.810.5 <1.9
- 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-18 <
1985 CONCENTRATIONS OF STRONTILM-89* AND -90 AND GAMMA ENITTERB** IN VEGETAFsLES Results in Units of PCi/kg (wet) 2 2 sigma y COLLECTION STATION NO. DATE SAMPLE TYPE Sr-89 Br-90 K-40 Cs-137 Ra-226 SA-FPV-SDI 8-05-85 Corn < 9.1 < 6.9 2200k280 <18 <36 SA-FPV-2El 4-29-85 Asparagus < 4.6 < 2.9^ ,
2500286 < 2.4 < 4.6 SA-FPL-lF3 7-29-85 Cabbage < 6.0 11t2 '2400198 < 4.3 < 7.9 l
SA-FPV-lF3 8-05-85 Peppers < 3.0 < 2.2 20002230 <17 <38 SA-FPV-4F1 8-05-85 Peppers < 3.2 < 2.4 1900t220 <11 <28 SA-FPL-4F1 8-05-85 Canbage <11 27*4 2900t97 < 3.2 8.4t3.4 ,,
SA-FPV-4F1 8-05-85 Tomatoes < 3.6 < 2.7 2600t55 < l.6 < 1.1 co Ln SA-FPV-5F1 7-29-85 Tomatoes < 3.3 < 2.5 1700t4a < 2.0 4.6 1.9
,< s SA-FPV-14F3 7-29-85' Corn <13 < 9.6 2400t280 (17 '
<39 s A SA-FPV-14F3 7-29-85 Tomatoes < 3.3 < 2.5 1900147 1.520.7 4 < 1.8 S A-FPV-lGl(C) 7-29-85 Peppers < 3.5 < 2.3 1400t'200 <14 ^ <26 S A-FPV-lGl(C) 7-29-85 'Ibma toes < 3.1 2.4tl.0 2000tS7 < 1,6 < 3.6 S A-FPV-lGl(C) 7-29-85 Corn <14 < 9.8 23002270 <14 <30 S A-FPV-2Gl(C) 5-02-85 Asparagus < 3.6 < 2.4 1900tS2 < l.5 < 3.6 S A-PPV-3H5(C) 7-29-85 Tomatoes < 3.1 < 2.3 2000265 < l.7 < 3.5 S A-PPV-3H5(C) 7-29-85 Corn <11 < 7.8 2500 220 <12 <25 S A-FPV-3H5(C) 7-29-85 Peppers < 2.9 < 2.0 13002220 <18 <38 S A-FPL-3H5(C) 7-29-85 Cabbage < 3.2 < 2.2 22002120 < 4.2 6.223.6 I
AVERAGE - -
21001800 - -
- 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 1985 CONCENTRATIONS OF STRONTIUH-85* AND -90 AND GhMMA BMITTERS**
IN GAME, MEAT AND BOVINE THYROID Results in Units of Results in Units of pCi/kg (dry) t 2 sigma pC1/kg (wet)
- 2 signa COLLECTION STATION NO. DATE(S) SAMPLE TYPE Sr-89 Sr-90 K-40 Cs-137 SA-GAM-llD1 1/13-20/85 Muskrat <72 220t27 2800tl50 <6.7 (Control)
SA-GAM-3El 1/13-20/85 Muskrat <140 1300256 28002160 <6.7
$ SA-FPB-3El 2-25-85 Beef (1) (1) 2000tl40 7.8t4.4 SA-THB-3El 2-25-85 Bovine Thyroid (1) (1) <1100 <70 SA-FPB-14F1 6-14-85 Beef (1) (1) 19002160 1126 SA-THB-14F1 6-14-85 Bovine Thyroid (1) (1) 1500t420 <36 j (Control)
AVERAGE Muskrat -
76021500 280020 -
Beef - -
19502140 9.4t4.5 Bovine Thyroid - - - -
- Sr-89 results are corrected for decay to sample stop date.
- All other gasuna emitters Whtched for were <LLD; typical LLDs are given in Table C-31.
(1) Strontium-89 and -90 analysis not required.
TABLE C-20 1985 CONCENTRATIONS OF GANNA EMITTERS
- IN FODDER CROPS Results in Units of PCi/kg (wet) 2 2 sigma COLLECTION STATION NO. DATE SAMPLE TYPE Be-7 K-40 SA-vGT-5D1 06-10-85 Barley 160257 31002260 SA-VGT-2F4 10-15-85 Feed Corn <140 25002260 I SA-VGT-2F4 11-01-85 Soybeans <210 14000 570 SA-vGT-5F2 09-22-85 Corn Silage 5302210 28002440 SA-VGT-5F2 10-26-85 Soybeans <160 160002610 SA-VGT-11F3 11-01-85 Soybeans <130 160002510 SA-VGT-llF3 10-03-85 Feed Corn <220 47002460 SA-VGT-llF3 08-30-85 Corn Silage 430t170 42004440 SA-VGT-14F1 09-16-85 Corn Silage 8402140 54002430 SA-VGT-3Gl(C) 09-16-85 Corn Silage 8002140 45002450 S A-VGT-3G1(c) 11-03-85 Soybeans <160 160002590 AVERAGE -
8100212000
- All other gasma emitters searched for were <LLD; typical LLDs are given in Table C-31.
(C) Control station 87
TABLE C-21 1985 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN SURFACE WATER Results in Units of PC1/L t 2 signa STATION NO. 1-07-85 2-19-85 3-09-85 4-15-85 5-09-85 6-07-85 SA-SWA-11A1 <3.0 -
<3.0 <4.1 <2.5 7.8t4.6 6.6t4.8 SA-SWA-12Cl <2.8 <l.5 <2.0 <2.7 <3.9 <4.8 (Control)
SA-SWA-7El <2.6 2.722.5 < 2. 6 2.0tl.4 2.612.1 <4.5 SA-SWA-lF2 3.222.4 <2.2 <2.0 <2.3 <3.1 <2.7 oo co SA-SWA-16F1 <l.4 2.8t2.0 <2.8 <3.4 <2.2 <3.0 AVERAGE - - - - - -
STATION NO. 7-08-85 8-16-85 9-09-85 10-07-85 11-06-85 12-04-85 SA-SWA-llAl 2.721.6 <2.8 <2.5 <2.3 3.122.1 <3.8 SA-SWA-12Cl 2.921.5 <2.8 <2.5 <3.6 <2.3 <2.8 (Control)
SA-SWA-7El <l.2 <5.0 <2.3 <2.6 <3.2 <2.0 SA-SWA-lF2 1.5 1.1 <2.6 <2.3 <2.8 <2.5 <2.8 SA-SWA-16F1 1.621.2 <2.6 <2.5 <3.1 <2.3 <2.8 AVERAGE 2.011.5 - -
TABLE C-22 1985 CONCENTRATIONS OF GROSS BETA EMITTERS IN SURFACE WATER Results in Units of PCi/L
- 2 sigma STATION NO. 1-07-85 2-19-85 3-09-85 4-15-85 5-09-85 6-07-85 SA-SWA-llAl 9229 8229 5817 7418 6417 6117 SA-SWA-12Cl 6027 46t6 3515 4216 55t6 5016 (Control)
SA-SWA-7El 120211 31 5 8419 8329 94t9 80t9 SA-SWA-lF2 4426 5326 2224 35 5 2614 3425 SA-SWA-16F1 2114 6417 2524 4025 43t5 4826 co AVERAGE 67178 55 38 45252 55t44 56251 55t34 e
STATION NO. 7-08-85 8-16-85 9-09-85 10-07-85 11-06-85 12-04-85 AVERAGE SA-SWA-llAl 8629 3125 7728 55t6 8018 18 4 65244 S A-SWA-12C1 6627 5826 65t7 3625 7628 1123 50235 (Control)
SA-SWA-7El 110210 63t7 110111 4716 120*12 27t4 81266 SA-SWA-lF2 4526 55 6 4826 1713 4726 4.522.2 36:31 SA-SWA-16F1 5426 3525 3715 3325 6217 7.5 2.5 39233 AVERAGE 72152 48*29 67157 38129 77*55 14218 Grand Average 54254 i
O TABLE C-23 1985 CONCENTRATIONS OF TRITIUM IN SURFACE WATER Results in Units of PCi/L
- 2 sigma STATION NO. 1-07-85 2-19-85 3-09-85 4-15-85 5-09-85 6-07-85 SA-SWA-llAl 180290 <140 <140 150280 470t80 140 80 SA-SWA-12C1 <l50 <l50 <l50 160280 <130 140280 (Control)
SA-SWA-7El 160280 <130 180290 150280 160280 150t80 SA-SWA-lF2 <140 <l30 190t100 130280 200180 160280
<140 <140 SA-SWA-16F1 <140 <140 <l50 <140 AVERAGE - - -
150223 2202280 150118 STATION NO. 7-08-85 8-16-85 9-09-85 10-07-85 11-06-85 12-04-85 ANRAGE SA-SWA-llAl 1700*110 <140 170280 <l50 190290 <130 3101900 SA-SWA-12C1 <140 150280 190t80 <140 <l50 <130 -
(Control)
SA-SWA-7El 9402100 <140 <140 160280 170t90 <140 220t460 SA-SWA-lF2 130 80 160280 150280 <150 230180 <140 160264 SA-SWA-16F1 <140 160280 <140 150t90 <l50 <140 -
AVERAGE 610tl400 150220 160243 -
180t67 -
TABLE C-24 1985 CONCENTRATIONS OF STRONTIUH-89* AND -90 IN SURFACE WATER Results in Units of PCi/L
- 2 sigma 1-07-85 4-15-85 7-08-85 10-07-85 STATION NO. to to to to 3-09-85 6-07-85 9-09-85 12-04-85 Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 SA-SWA-llAl <0.4 <0.4 <0.6 <0.4 <0.6 <0.5 <0.6 <0.5 v
SA-SWA-12Cl <0.5 <0.4 <0.7 <0.5 <0.6 <0.5 <0.6 <0.4 (Control)
! SA-SWA-7El <0.5 <0.4 <0.7 <0.5 <0.7 <0.6 <0.6 <0.4 SA-SWA-lF2 <0.4 <0.4 0.9t0.3 <0.5 <0.6 <0.5 '<0.6 <0.4 SA-SWA-16F1 <0.5 <0.5 <0.8 c. 6 <0.6 <0.4 <0.6 < 0.,5
- Sr-89 results are corrected for decay to sample stop date.
TABLE C-25 1985 CONCENTRATIONS OF GAMMA EMITTPJtS* IN SURFACE WATER Results in Units of PCi/L 1 2 sigma STATION NO. NUCLIDE l-07-85 2-19-85 3-09-85 4-15-85 5-09-85 6-07-85 SA-SWA-llAl K-40 93210 100t8 7219 8828 7019 82t7 Ra-226 <1.0 <0.4 <l.1 0.6t0.3 <l.1 <0.7 Th-232 <2.0 <l.6 <l.9 <l.9 <2.1 1.220.7 SA-SWA-12Cl K-40 6629 8129 3718 43t8 5928 6227 e (Control) Ra-226 <l.2 <l.0 <l.1 <l.1 <l.3 <0.6
" Th-232 <2.1 <2.0 <l.9 <1.7 <2.2 <l.6 SA-SWA-7El K-40 110t10 120211 94t10 100210 85210 90t11 Ra-226 <l.1 1.320.7 <l.2 <l.0 <l.2 <l.1 Th-232 <2.0 <2.4 2.921.2 <l.7 <2.6 3.7tl.4 .
SA-SNA-lF2 K-40 5026 5518 2216 2527 2925 36*7 Ra-226 <0.4 <l.1 <l.1 <l.0 0.6t0.4 <l.0 Th-232 <1.6 <2.3 <2.1 <l.9 <l.6 <1.9 SA-SWA-16F1 K-40 2427 7129 3627 3628 4318 5518 Ra-226 <1.3 1.720.7 1.420.8 <l.4 <1.3 <l.0 Th-232 2.911.5 <1.9 <2.1 <2.4 <2.3 <l.9 AVERAGE K-40 69168 85251 52260 58 67 57244 65243
TABLE C-25 (cont'd) 1985 CONCENTRATIONS OF GAMMA EMITTERS
- IN SURFACE WATER Results in Units of PCi/L t 2 sigma STATION NO. NUCLIDE 7-08-85 8-16-85 9-09-85 10-07-85 11-06-85 12-04-85 AVERAGE SA-SWA-llAl K-40 8217 100114 96t8 83210 84t10 2116 81t42 Ra-226 <0.8 <1.9 <0.6 <l.3 <l.3 <l.0 -
Th-232 <1.6 <3.1 <1.6 <2.1 <2.3 <2.0 -
SA-SWA-12Cl K-40 7319 6419 90210 42t8 76t9 1217 59244 ^
(Control) Ra-226 <1.4 <l.0 <1.2 <l.0 <1.4 1.320.6 -
Th-232 <2.4 <l.9 <2.1 1.920.8 3.111.4 <l.9 -
SA-SWA-7El K-40 98t11 120212 140212 5118 130111 3617 98261 Ra-226 <l.2 <0.5 0.6*0.4 <l.1 <l.2 <1.2 -
Th-232 <2.3 <2.3 <1.9 <1.8 <2.1 <2.0 -
SA-SWA-lF2 K-40 4828 5228 5828 21t7 5428 <10 38233 Ra-226 <l.0 <l.0 1.210.6 <1.2 <l.2 <l.1 -
Th-232 <l.9 <l.9 <2.0 2.021.1 <2.2 <2.0 -
l SA-SWA-16F1 K-40 5628 3025 4726 42t6 69210 <10 43136 Ra-226 1.220.6 <0.5 <0.7 <0.6 <l.2 <1.4 -
Th-232 <1.8 <l.6 0.8t0.4 <l.6 <2.3 <2.0 -
AVERAt7 K-40 71240 73273 86173 48245 83257 18 22 Grand Average K-40 64t62
- All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-31.
TABLE C-26 1985 CONCENTRATIONS OF STRONTILBt-89* AND -90 AND TRITIUM IN EDIBLE FISH TRITILBt (FLESH)**
STRONTIUM (BONES) AQUEOUS FRACTION ORGANIC FRACTION pCi/kg (dry)
- 2 sigma PC1/kg (wet) t 2 sigma STATION NO. COLLECTION PERIOD St-89 Sr-90 H-3 H-3 SA-ESF-llAl 06-14-85 to 06-24-85 70t '24 350 22 4001100 <50 09-17-85 to 09-20-85 <e6 31t8 <50 <50 m
b S A-ES F-12Cl 06-22-85 to 06-22-85 <30 95t12 2001100 <50 (Control) 09-19-85 to 09-20-85 <26 3028 <50 <50 l
S A-ES F-7El 06-22-85 to 06-23-85 <36 <29 200t100 <50 09-19-85 to 09-20-85 <26 2427 <50 90160 AVERAGE -
932260 - -
- Sr-89 results are corrected for decay to sample stop date.
- Tritium results by controls for Environmental Pollution, Inc.
l
TABLE C-27 1985 CONCENTRATIONS OF GAMMA EMITTERS
- IN EDIBLE FISH Results in Units of PCi/kg (wet) i 2. sigma i
STATION NO. COLLECTION PERIOD K-40 Cs-137 SA-ESF-llAl 06-14-85 to 06-24-85 30001150 1114 09-17-85 to 09-20-85 30001200 1015 l $ SA-ESF-12C1 06-22-85 to 06-22-85 31001160 1013 (Control) 09-19-85 to 09-20-85 31001250 <11 i
SA-ESP-7El 06-22-85 to 06-23-85 32001120 4.812.0 09-19-85 to 09-20-85 31001250 <13 AVERAGE 31001150 1016 i
- All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-31.
1
TABLE C-28 1985 CONCENTRATIONS OF STRONTIUM-89* AND -90, GAMMA EMITTERS ** AND TRITIUM IN BLUE CRABS Results in Units of PCi/kg (wet) 1 2 sigma COLLECTION AQUEOUS FRACTION STATION NO. PERIOD SAMPLE Sr-89 Sr-90 K-40 H-3***
i SA-ECH-llAl 06/21-22/85 Flesh <27 <22 2500t180 200t100 Shell(l) <120 220t43 (2) (2) 09/17-18/85 Flesh <40 <18 2100t210 <50 ShellII) 50t16 210tli (2) (2) u)
a l
SA-ECH-12Cl 06/21-22/85 Flesh <27 <22 25002220 2002100 ;
(Control) Shell(l) <78 240231 (2) (2) 1 09/17-18/85 Flesh <40 28t8 1700 200 <50 ShellIII 64t19 24 13 (2) (2)
I i
AVERAGE Flesh - -
22002770 -
Shell -
1702200 - -
i j
- Sr-89 results'are corrected for decay to sample stop date.
j ** All other gamma emitters searched for were <LLD; 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) .
j (2) Gamma and tritium analysis not required.
TABLE C-29 1985 CONCENTRATIONS OF SR-89* AND -90 AND GAMMA EMITTERS **
IN BENTHIC ORGANISMS Results in Units of PCi/kg (dry) i 2 sigma COLLECTION STATION NO. DATE Sr-89 Sr-90 Gamma SA-ESB-llAl 05-20-85 <2500 <1400 <LLD 09-23-85 <530 <280 <LLD SA-ESB-12C1 05-20-85 <21000 <13000 <LLD (Control) 09-23-85 <7500 <4000 <LLD SA-ESB-7El 05-20-85 <11000 <6200 <LLD 09-23-85 <2300 <1200 <LLD SA-ESB-16F1 05-20-85 <40000 <25000 <LLD 09-23-85 <l5000 <8500 <LLD NOTE: Analyses performed on benthic organisms have extremely high uncertainties and sensitivities due to the unavailability of an adequate sample. Sample sizes ranged from 0.02 grams to 1.72 grams dry.
- Sr-89 results are corrected for decay to sample stop date.
- All gamma emitters searched for were <LLD; typical LLDs are given in Table C-31.
i I
l i
97
TABLE C-30 1985 CONCENTRATIONS OF STRONTIUM-90 AND GAMMA EMITTERS
- IN SEDIMENT **
Results in Units of PC1/kg (dry)
- 2 sigma STATION NO.
DATE Sr-90 Be-7 E-40 Mn-54 Co-60 Cs-134 Cs-137 ma-226 Th-232 SA-ESS-IIAI 5-20-85 <22 <220 130002480 <28 <29 <16 <22 6302280 780171 9-23-85 <19 <230 140002560 <25 <37 <23 <14 9801330 830186 SA-ESS-ISAl***
9-23-85 <20 <100 72002390 <22 66217 <29 32210 640136 640163 SA-ESS-16Al***
9-23-85 <20 <190 45002260 38 11 160218 <35 <20 1400245 1600276 m
OD SA-ESS-12Cl (control)
! 5-20-85 <19 <200 140001510 <21 <36 <21 28216 7402290 770279 9-23-85 <20 <190 160002630 <24 <36 53217 <28 530238 760178 SA-ESS-7El 5-20-85 <23 <220 13000:520 <22 50217 <31 35112 730 40 770272 9-23-85 <20 <l50 8400 340 <20 45212 <30 1628 950238 1100264 SA-ESS-16F1 5-20-85 <23 4302150 12000:470 <28 110216 <22 42217 6502270 670274 9-23-85 <21 <210 14000 570 <29 75224 41214 88217 620140 730174 AVERAGE - -
12,00027300 - 64183 -
32243 7902520 8601570
- All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-31.
- Sediment samples which include benthic organisms constitute the benthos sample.
- New location added on 9-23-85.
TABLE C-31 1985 PSE6C RESEARCN CORPORATION LLDs FOR GANNA SPECTRONETRY AIR WELL/ POTABLE POOD NEAT AND POODER '
PARTICULATES PRECIPITATION MILE NATER PRODUCTS GAME CROPS
- NUCL1 DES (10*3pC1/m3) (PC1/L) (PC1/L) (PCl/L) (PC1/kg-wet) (PCi/kg-wet) (PC1/kg-wet)
CEOMETRY: 13 Filters 100ml 3.5 Liter 100ml 100ml 400a1 100ml 100e1 s
I t
se-7 3.0 4.3 14 4.0 8.0 120 43 78 Na-22 0.54 0.62 1.8 0.50 1.2 15 6.0 10 K-40 - - - - - - - -
Cr-51 2.8 5.2 12 4.6 9.5 140 54 100 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 Pe-59 0.83 1.2 3.2 1.1 2.4 32 12 23 Co-60 0.46 0.57 2.0 0.52 1.1 16 5.5 9.4 an-65 0.86 1.0 3.3 0.93 2.0 31 10 17 Nb-95 0.43 0.59 1.7 0.53 1.1 16 6.0 11 U$ ar-95 0.71 1.0 3.0 0.93 2.0 28 10 19 Mo-99 12 55 20 48 51 1300 990 6800 Ru-103 0.39 0.57 1.4 0.50 1.0 16 5.7 11 Nu-106 4.0 4.9 14 4.4 10 130 47 81 Ag-110m 0.67 0.82 1.5 0.72 1.6 14 8.0 14 sb-125 0.90 1.4 4.1 1.2 2.6 39 13 22 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 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 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 32 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 Ra-226 0.86 1.2 4.0 1.0 2.2 32 11 19 Th-232 1.7 2.0 6.8 1.0 3.8 54 19 33
TABLE C-31 (cont'd) 1985 PSE6G NESEARCH CORFOMATION LLDs FOR GANNA SFBCTROMETRY SURFACE FISH SMELLFISM SEDINENT AIR WATER IODINs NUCLIDES (PC1/L) (PCi/kg-wet) (PC1/kg-wet) (pci/kg-d ry ) NUCLIDES (10-3pC1/m3)
GEOnETRY: 100ml 100ml 400a1 100e1 400ml 100e1 100ml se-7 4.1 37 92 142 85 120 I-131 15 Na-22 0.59 5.3 11 21 10 14 I-132 26 K-40 - - - - - - I-133 39 Cr-51 5.1 45 107 170 91 150 I-135 1.2 Mn-54 0.48 4.4 10 17 10 13 Co-58 0.50 4.5 11 18 10 14 Fe-59 1.2 10 24 41 22 36 Co-60 0.54 5.0 11 19 11 15 2n-65 0.99 9.0 22 35 22 25 12 19 10 15
({ Nb-95 0.58 5.0 j C3 tr-95 1.0 8.8 21 35 20 26
, Mo-99 68 370 2400 1200 530 13000 Ru-103 0.55 4.9 12 19 11 14 Ru-106 4.6 42 98 160 97 120 Ag-110m 0.79 7.2 11 28 10 19 Sb-125 1.3 12 27 46 27 20 Te-129m 21 103 480 720 430 600 I-131 1.2 9.0 30 33 18 52 Te-132 18 26 170 85 49 650 Cs-134 0.62 5.7 9.3 22 9 12 Cs-136 0.78 6.4 20 24 14 31 Cs-137 0.47 4.4 12 17 12 12 Ba-140 3.0 25 71 94 51 105 La-140 1.3 11 28 41 20 52 Ce-141 0.64 5.6 15 22 13 17 Ce-144 2.0 18 57 73 56 55 Ra-226 1.1 10 23 40 23 230 Th-232 1.8 17 40 69 40 48
- Indicates a positive concentration was measured in all samples analysed.
APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES 101
SYNOPSIS OF ANALYTICAL PROCEDURES Appendix D presents a synopsis of the analytical procedures utilized by various laboratories for analyzing the 1985 Artificial Island Radiological Environmental Monitoring Program samples.
TABLE OF CONTENTS .
LAB
- PROCEDURE DESCRIPTION PAGE GROSS ALPHA l
PSEEG Analysis of Air Particulates.................... 105 TI Analysis of Air Particulates.................... 107 PSEEG Analysis of Water............................... 108 GROSS BETA PSE&G Analysis of Air Particulates.................... 109 TI Analysis of Air Particulates.................... 111 PSEEG Analysis of Water............................... 112 POTASSIUM-40 PSEEG Analysis of Water............................... 113 TRITIUM PSEEG Analysis of Water............................... 114 CEP Analysis of Aqueous Fraction of Fish and Crab... 115 CEP Analysis of Organic Fraction of Fish and crab... 116 IODINE-131 PSEEG Analysis of Filtered Air........................ 117 TI Analysis of Filtered Air........................ 118 PSEEG Analysis of Raw Milk............................ 119 PSEEG Analysis of Bovine Thyroid...................... 121 l
103
SYNOPSIS OF ANALYTICAL PROCEDURES (cont'd)
TABLE OF CONTENTS LAB
- PROCEDURE DESCRIPTION PAGE STRONTIUM-89 AND -90 PSEEG ?.nalysis of Air Particulates.................... 122 TI Analysis of Air Particulates.................... 125 PSE&G Analysis of Raw Milk............................ 127 PSEEG Analysis of Water............................... 130 PSE&G Analysis of Vegetation, Meat and Aquatic Samples 133 PSEEG Analysis of Bone and Shel1...................... 136 PSEEG Analysis of Soil and Sediment................... 139 PSEEG 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 PSEEG Analysis of Water............................... 147 PSEEG Analysis of Solids (combined procedures)........ 148 ENVIRONMENTAL DOSIMETRY TI Analysis of Thermoluminescent Dosimeters........ 150 i
- PSEEG - PSEEG Research Corporation TI - Teledyne Isotopes CEP - Controls for Environmental Pollution, Inc.
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SYNDPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE GROSS ALPHA 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, air particulate samples are counted 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 241Am air filter geometry ,
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 I correction factor of the temperature-corrected gas meter as well as ';,he gas !
meter efficiency itself. j Calculation of Gscos Alpha Activity:
Air flow is corrected first by using the following equations:
f P = (B-V)/29.92 P = Pressure correction factor l B = Time-averaged barometric pressure during sampling period, "Eg i V = Time-averaged vacuum during sampling period, "Hg 29.92 = Standard atmospheric pressure at 32*F, "Hg l V= F*P*0.946*0.0283 3
E F = Uncorrected air flow, ft3 1 0.946 = Temperature correction factor ,
fros 60*F to 32*F 0.0283 = Cubic meters per cubic foot E = Gas meter efficiency (= 4 efficiency /100)
, V = Corrected air flow, m3 P = Pressure correction factor Using these corrected air flows, the gross alpha activity is computed as follows:
i' Result (pCi/m 3) = (G-B)/T (2.22) * (E) * (V) G = Sample gross counts B = Background counts (from blank i
filter)
T = Count time of sample and blank, mins.
E = Fractional 241Am counting l efficiency V = Corrected air flow of sample, m3
! 2.22 = No. of dpm per pCi i 105
2-signa error (pci/m ) = 3 (1. 96 * (G+B) 1/2) . A (G-8)
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 not count is less than 4.66 times the standard deviation of the count on the blank.
LLD(pCi/m3) = 4.66 * (B)1/2 (2. 22) * (E) * (V) * (T)
B = Background counts (from blank
~ filter) 4 E = Fractional 241Am counting efficiency V = Cberected air flow of sample, m3 T = Count time of blank, ains.
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106
SYNDPSIS OF TELEDY2 ISOTOPES PROCEDURE ANALYSIS OF AIR PARTICULATE FILTERS FOR GROSS ALPHA AND BETA The air filter is first stored for 2 to 5 days from date of receipt to allow
~
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 l alpha activity (at a different voltage setting) in a Beckman-Sharp Wide Beta II automatic alpha-beta counter.
Gross alpha and beta activity (pCi/m3) are computed as follows:
A= (G/T -B)
- Om*((G/T +B)/T)1/2 (2.22*V*Y*D*E) ( 2. 2 2*V* Y* D* E)
Where G = Total sample counts B = Background counts per minute T = Sample count time, ains.
2.22 = dpe/pci y = 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 efficiency a, = Multiples of counting error If the not 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.
where MDL = 3 * (2 *B/T) 1/2
( 2. 22
- V* Y* D* E)
Variables are as previously defined i
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1 i
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 cilute 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 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 238U 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. 22) * (E) * (V) * (S)
G = Sample gross counts B = Background counts (from blank sample)
T = Count time of sample and blank E = Fractional counting efficiency from 238U 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) 108
SYNDPSIS OF PSE&G RESEARCH CORPORATION 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, 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 90Sr air filter geometry beta counting standard.
The gross beta activity is computed on the basis of total corrected air flow 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 Gross Beta Activity:
Air flow is corrected first by using the following equations:
P = (B-V)/29.92 P = Pressure correction factor B = Time-averaged barometric pressure during sampling period, "Hg
_V = Time-averaged vacuum during sampling period, "Hg 29.92 = Standard atmospheric pressure at 32*F, "Hg V= F*P*0.946*0.0283 E F = Uncorrected air flow, ft3 0.946 = Temperature correction factor from 60*F to 32*F -
- 0.0283 = Cubic meters per cubic foot E = Gas meter efficiency (= 4 efficiency /100)
V = Corrected air flow, m3 P = Pressure correction factor Using these corrected air flows, the gross beta activity is computed as follows:
Result (pCi/m 3) . (c.B)/T (2.22) * (E) * (V) G = Sample gross counts B = Background counts (from blank filter) l T = Count time of sample and blank, l mins.
( E = Fractional 90Sr counting i
efficiency V = Corrected air flow of sample, m3 2.22 = No. of dpm per PCi 109
2-signa error (pci/m3) = (1. 96 * (G+B) 1/2)
- A (G-8)
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 not count is less than 4.66 times the standard deviation of the count on the blank.
LLD(pCi/m3) = 4.66 * (B)l/2 (2. 22) * (E) * (V) * (T)
B = Background counts (from blank filter)
E = Fractional 90S r counting efficiency V = Corrected air flow of sample, m3 T = Count time of blank, ains.
110 j
SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE ANALYSIS OF AIR PARTICULATE FILTERS FOR GROSS ALPHA AND EETA The air filter is first stored for 2 to 5 days from date of receil t to allow 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 follows4 I A= (G/T -B) i Un*((G/T +B)/T)1/2
( 2. 22
- V* Y*D* E) ( 2. 2 2*V* Y*D*E)
! Where G = Total sample counts B = Background counts per minute T = Sample count time, ains.
2.22 = dps/pci V = Sample volume, m 3 Y = Chemical yield (Y = 1 in this case)
D = Decay factor from collection to count date (D = 1 in this case)
E = Counter efficiency a, = Multiples of counting error If the not activity (G/T -B) is equal to or less than the countin;r error, then the activity is considered to be the minimum detectable les.1, or MDL.
where MDL = 3*(2*B/T)1/2 (2.22*V'Y*D*E)
Variables are as previously defined l
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SYNOPSIS OF PSEEG RESEARCH CORPORATION PROCEDURE GROSS BETA ANALYSIS OF WATER SAMPLES t The sample is mixed tboroughly. Then, a 1.0 liter portion is removed from T 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 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 transferred to tared stainless steel ribbed planche.tg and evaporated to dry-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 90Sr source of the same (Jeometry.
Calculation of Gross Beta Activity
\
Result (pCi/L) = (G-B) /T (2.22) * (E) *V) * (S)
G = Sample gross counts
' B = Background counts (from blank sample)
T = Count time of sample and blank
! E = Fractional counting efficiency from 90Sr source V = Sample volume, liters S = Normalized efficiency regression equation as a function of thick-ness 2.22 = No. of dpa per pCi 2-sigma error (pci/L) = (1 36*(G+B)l/2).3 (G-B)
- ' A = Gross beta activity, pCi/L G = Sample gross counts B = Background counts (from blank
' sample) f 112
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 analysed 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.
Calculation of 4% Activity:
4 Activity (pci/L) = 0.85*C 0.85 = Proportionality constant for converting ppm to PCi/L C = Potassium concentration, ppm l
l 113 1
c r
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE ANALYSIS OF NATER FOR TRITIUM Approximately 50ml of raw sample is mixed with sodium hydroxide and potassium permanganate and is distilled under vacuum. Eight al of distilled sample is mixed with 10ml of Instagel@ liquid scintillation solution, and placed in the liquid scintillation spectrometer for countiag. An internal standard is prepared by mixing Sal of sample,10ml of Instagel, and 0.lal of a standard with known activity. The efficiency is determined from this. Also prepared is a blank consisting of Sal 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. i Activity is computed as follows:
- A (pCi/L) = (G-8)*(1000)
- 2. 22* (E) * (V) * (T)
A = Activity B = Background count of sample G = Gross count of sample E = Counting Efficiency V = Aliquot volume (al)
T = Count time (min) 2.22 = DPN/pCi 1000 = Number of al per L Efficiency (E) is computed as follows:
E= (N) * (D)
A' N = Net CPM of spiked sample D = Decay factor of spike A' = DPM 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)
The associated error is expressed at 954 confidence limit, as follows:
1.96*(G/T2+B/T2)1/2*(1000)
- 2. 22* (V) * (E)
Samplee are designated LLD if the activity is less than the following value: ,
LLD (pCi/L) = (4. 66) * (B) 1/2 * (1000 )
2.22" (V) * (E) " (T) 114
SYNOPSIS OF CONTROLS FOR ENVIRoletENTAL POLLUTION, INC., PROCEDURE TRITItSt ANALYSIS OF AQUEOUS FRACTION OF BkOLOGICAL MATERIALS An aliquot of fish or crab flesh is placed in a round bottom flask, along with 200ml of benzene, and the water removed via azootropic distillation.
Three milliliters of the extracted water is then mixed with aquasol cocktail
~ (NEF-934 Aquaso10 cocktail, manufactured by New England Nuclear Corpora-tion).
He resultant mixture is comprised of 19 percent sample in a clear gel-type aguasol and provides a tritium counting efficiency of approximately 30 percent, when counted on a Beckman LS-100 Liquid Scintillation Spectrometer.
He efficiency of the counting system is determined by placing 6 tritium standards (certified by NBS) before each set of water samples to be counted.
The counting efficiency is determined from these standards which 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 POR ENVIRODGENTAL POLLUTION, INC., PROCEDURE
- TRITIIM ANALYSIS OF ORGANIC FRACTION OF BIOIDGICAL MATERIALS 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. He resulting converted water is then mixed with aquasol cocktail (NEF-934 Aquaso1@ cock-tail, manufactured by New England Nuclear Corporation).
The resultant mixture is comprised of 19 percent sample in a clear gel-type aquasol and provides a tritium counting efficiency of approximately 30 percent when counted on a Beckman LS-100 Liquid Scintillation Spectrometer.
The efficiency of the counting system is determined by placing 6 tritium standards (certified by NBS) before each set of water samples to be counted.
The counting efficiency is detegnined from these standards which are equal in activity but vary in tne amount 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 PSEEG RESEARCH CORPORATION PROCEDURE GAletA ANALYSIS OF AIR IODINE Approximately 300m3 of air is drawn through a 50ml bed of triethylenediamine (TEDA)-impregnated charcoal granules at a rate which closely corresponds to the breathing rate of an adult male. He contents of the exposed air iodine cartridge are emptied into an aluminum sample can containing 50ml of fresh TEDA-impregnated charcoal. He can is hermetically sealed and then counted on a gamma detector.
Calculation of (:amma Activity:
1 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 D = Decay correction factor Atl*EXP(At2) 1-EXP (- Atl) l t1 = Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition A = 0.693/nuclide half life E = Deteccor efficiency A = Gamma abundance factor (no. of photons per disintegration)
T = Acquisition live time, ains.
V = Sample volume, m3 2.22 = No. of dpa per PCi 2-sigma error (pCi/m )3 = 1.96*(GC+BC)1/2*R N
GC = Gross counts BC = Background counts All other variables are as defined earlier. )
l l The LLD (PCi/m3) = 4. 66 * (BC) 1/2*D l (2.22) * (E) * ( A) * (T) * (V) l l
117
SYNDPSIS 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. Telodyne 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.
118
SYNDPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE
. ANALYSIS OF RAW MIIK 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 free
- iodine is then extracted into carbon tetrachloride and reduced to iodide with sodium bisulfite when back-extracted into water. Then cupcous 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.
On the same day the above analysis is performed, a stable iodide analysis is also run, using a digital voltmeter, iodide 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. Per 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 131I Activity:
131I Results (PCi/L) = (G-B) /T* (1.0 5) * (H)
(2.22) * (E) * (V) * (Y)
G = Sample gross counts B = Background counts (from blank sample)
T = Count time of sample and blank
., E = E 0*EXP(-l*M) = efficiency equation where EO = counting efficiency at zero sample thickness 1 = Self-absorption coefficient M = sample thickness, ag/cm2 V = Sample volume, liters Y = Chemical recovery =
R Rl+R2 where R = ag of I recovered R1 = ag of I carrier added R2 = ag of intrinsic stable I measured in sample l.05 = Correction f actor for protein-i bound iodine l
119
L = correction H = J/(1-K) *EXP(3{I factor for 1 decay during counting period J = (0.693/8.05)*(R/1440)
R = Count time, minutes 1440 = No. of minutes per day 8.05 = Half-life of 131I , days K = EXP(-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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SYNOPSIS OF PSEEG 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 At1*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 = ca - abundance factor (no of photons per disintegration)
T = Acquisition live time, ains.
V = Sample quantity, kg wet 2.22 = No. of dpa per pCi 2-signa error (pci/kg wet) = 1. 96 * (GC+BC)1/2*R GC = Gross counts BC = Background counts All other variables are as defined earlier.
The LLD (pCi/kg wet) = 4.66*(BC)1/2*D (2.22) * (E) * ( A) * (T) * (V) i 121 l
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE ;
RADIOSTRONTIUM ANALYSIS OF AIR FILTERS l
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 introduced into each sample and several fuming nitric acid leachings are l 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 a barium chromate strip. The strontium is precipitated as a carbonate, which is dried ;
and weighed. The samples and blank are then counted 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 89S r are both unknown quantities requiring two simultaneous equations to solve for them.
Calculation of 90S r Activity
- 90S r Results (pCi/m3) = N4/R (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 C are regression coefficients.)
M = Thickness density of strontium carbonate precipitate, ag/cm 2 E(15)/E' = Ratio of 90Sr efficiency at thickness value of 15mg/cm2 to 90Sr counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)
E = 90S r counting standard efficiency V = Sample quantity (m3}
U = Chemical yield N4 = (N2 - Fl*N1)/W1 = not counts due to 90Sr only W1 = ( (1 + R1*I 2) - '(1 + Rl*Il) *F1)
Il = 1 - EXP ((-0.693/2.667)*tl) i I2 = 1 - EXP ((-0.693/2.667)*t2) tl = Elapsed time from 90Y strip to first count t2 = Elapsed time from 90Y strip to second count 122
2.667 = Balf-life of 90Y , days R1 = D + E*M + F*M2 (This is the general form of the regression equation for 90y eggeyf90Sr 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 dpa per pCi F1 = EXP ((-0.693/2.667)*t2)
R = Count time of sample and blank Ustng the same variable definitions as above, tae 2-signa error for 90Sr (pci/m3) .
~
2* X+Y + (11+Yl)*F12- 1/2* (Wl*W2)
W1 W12 ,
(N2-Fl*N1) the same variable definitions, Again,keepingSr(pCi/m3) the I1D for 9 =
4.66* (X+Y) + (X1+Yl)*F12- 1/2 W12 W12 .
Calculation of 89Sr Activity:
89S r Results (pCi/m3) = N6/R (2.22) * (E) * (E (15)/E') * (S7) * (V) * (U) * (F9)
= N3 S7 = G + H*M + I*M2 (This is the general form of the normalized 89S r 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 (This represents counts due to 90S r)
E(15)/E' = Ratio of 89se efficiency at thickness value of 15mg/cm2 to 90Sr counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)
F9 = EXP ( (-0. 693/50. 5)
- t) 123
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 89S r, days All other quantities are as previously defined.
The 2-sigma error for 89S r (pci/m3) = 2* (S8 2+392 )l/2 *W3 (N1 - N7* (1+Rl*II)
S8 m X+Y + (X1+Yl)*F12"1/2 W1 W12 S9 = (X1+Yl)l/2 All other variables are as previously defined.
Keeping the same variable definitions, the LLD for 89S r (pci/m3) .
4.66*(S8 2
+392 )1/2 4
124
SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE ANALYSIS OF COMPOSITED AIR PARTICULATE FILTERS FOR RADIOSTRONTIUM The composited air filters are leached with concentrated nitric acid, with heating, in the presence of strontium carrier. After adding deionized water, the sample a gravity filtered through a paper filter and the filtrate 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 evaporated on a hotplate to a small volume. The sample is transferred to a centrifuge tube and fuming nitric acid added to form the strontium nitrate precipitate. After centrifuging and pouring off the supernate, the precipi-tate is dissolved in deionized water and an iron scavenge performed. This marks the beginning of the 90Y ingrowth period. Centrifuging and discarding i 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 alkalinized with asmonium hydroxide and heated in a hot water bath to form yttrium hydroxide. After cooling, the sample is centrifuged and the supernate saved for 89 8 r 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 i
counter. The sample is then recounted the following day to confirm the decay .'
of 90y, l
The supernate, saved for 89Sr determination, is treated with saturated 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 80mg/cm2 aluminum absorber to stop the 90 S r beta emissions, thus allowing the 89Sr betas to be counted alone.
The 89 Sr activity (pCi/m 3 ) is computed as follows:
A= (G/T-Be-Ba )
- Ca*((G/T+Be+Ba)/T)1/2
( 2 . ZZ "V = I "U"E) (2. 2 2 "V"I"D"E)
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) 1/2
- ( 2. 2 2 *V *Y *D
- E) where G = Total sample counts T = Sample count time, ains.
Be = Background rate of counter, cpm i
Ba = Background addition from 90S r and ingrowth of 90y 2.22 = dps/pci V = Sample volume, m 3 Y = Chemical yield of strontium D = 89Sr decay factor from midpoint of collection period to counting date.
E = 89S r counting efficiency with 80 mg/cm2 aluminum absorber om = Multiples of countins error 125
The 90Sr activity (pci/m 3) is computed as follows:
A= (G/T-B) 2 cm*((G/T+B)/T)l/2 ,
(2.22*V*Y*D*E) (2.22*V8Y*D*E)
Y = Otomical yield of the mount or sample counted D = Decay factor from the collection to the counting date E = Counter efficiency All other variables are as previously defined.
If the not activity (G/T-B) is less than or equal to the 20 counting error, the activity is considered ML where MDL = 2* (2*B/T) l/2 (2.22*V*Yl*Y2 *I*D*E) e i
l 126
l SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE RADIO 6TRONTIUM ANALYSIS OF RAW MIIJC 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, j 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. The carbonates are converted to nitrates with 6N nitric acid
- and, by acidifying further to an overall concentration of 704 nitric acid, i strontium is forced out of solution somewhat ahead of calcium. Barium chromate precipitation is then performed to remove any traces of radium and radiobarium. Strontium recrystallisation is carried out to resove l
residual calcium which may have been coprecipitated with the initial strontium precipitation. Another recrystallisation removes ingrown 90 Y, marking the time 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 background gas proportional counter and, g9ain, at least 14 days later. The basis for this two-count method is that Sr and 898 r are both unknown quantities requiring two simultaneous equations to solve for them.
Calculation of 90S r Activity:
90 Sr Results (pCi/L) = N4/R (2.22) * (E) * (E (15)/E') S (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 C ar6 ragression
! coefficients.)
M = Thickness density of strontium carbonate precipitate, ag/cm2 E(15)/E' = Ratio of 90Sr efficiency at thickness value of 15mg/cm2 to 90Sr counting standard efficiency run at tha time of instrument calibration (This standard is run with each group of environmental strontium samples)
E = 90Sr counting standard efficiency V = Sample quantity (liters)
U = Oienical yield N4 = (N2 - Fl*N1)/W1 = net counts due to 90Sr only W1 = ((1 + Rl*I2) -
(1 + Rl*II) *F1)
Il = 1 - EXP ( (-0. 69 3/2. 667) *tl)
I2 = 1 - EXP ( (-0. 693/2. 667)
- t2) 127
t1 = Blapsed 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 (This is the general form of the regression equation for 90y eggsyf90S r 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 dpa 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-signa error for 90Sr (PCi/L) =
~
2* (X+Y) + (11+Yl)*F12'1/2* (Wl*W2)
W13 W13 ,
(N2-Fl*N1)
Again, keepi the same variable definitions, the LLD for 9 Sr (pCi/L) =
4.66* + (X1+Yl)*F12- 1/2 W1 W12 _
calculation of 89Sr Activity:
89Sr Results (pCi/L) = N6/R (2.22) * (E) * (E (15) /E ') * (S7) * (V) * (U) * (F9 )
t
= W3 S7 = G + H*M + I*M2 (This is the general form of the normalized 895 r 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 (This represents counts due to 90Sr) 4 128
e E(15)/E' = Ratio of 895r efficiency at thickness value of 15mg/cm2 to 90Sr counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)
F9 = EIP ((-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 = Balf-life of 89 Sr, days All other quantities are as previously defined.
j The 2-signa error for 89S r (pCi/L) = 2* (S82+392 }l/2 *w3 (N1 - N7* (1+R1*II) 88 = + fx1+Yll*F12 1/2 W1 W12 89 = (X1+Yl)1/2 All other variables are as previously defined.
Keeping the same variable definitions, the LLD for 89S r (pCi/L) =
4.66*(S82+gg23 1/2 1
e.
t 129
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE RADIOSTRONTIUM ANALYSIS OF MATER 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. The sample (s) and blank are then made alkaline and heated to near boiling before precipitating the carbonates. He carbonates are converted to nitrates by fuming nitric acid recrystallization which acts to purify the sample of most ,
of the calcium. Radioactive interferences are stripped out by coprecipita-tion on ferric hydroxide (yttrium strip) followed by a barium chromate strip.
The 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. The basis for this two count method is that 90Sr and 89S r 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 from each sample is analyzed for stable strontium. These results are used in correcting the chemical recovery of strontium to its true value.
Calculation of 90Sr Activity:
90Sr Results (pCi/L) = N4/R (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 C are regression coefficients.)
M = Thickness density of strontium carbonate precipitate, ag/cm 2 E(15)/E' = Ratio of 90S r efficiency at thickness value of 15mg/cm2 to 90S r 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 (liters)
U = Chemical yield 90 Sr only N4 = (N2 - Fl*N1)/W1 = net counts due to W1 = ((1 + Rl*I2) - (1 + Rl*II) *F1) 130
Il = 1 - EXP ( (-0. 693/2. 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 = Balf-life of 90Y , days R1 = D + E*M + F*M2 (This is the general form of the regression equation for 90y ,ggsyj90Sr 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 XI and Y1 are initial gross counts and background counts, respectively 2.22 = No. of dpa 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/L) =
~
2* (X+Y) + (Kl+Yl)*Fl I 1/2* (Wl*W2)
Wid W12 , (N2-Fl*N1)
Again,. keeping the same variable definitions, the LLD for 90Sr (pCi/L) =
4.66* (X+Y) + (Kl+Yl)*Fl f 1/2 W12 W12 -
Calculation of 89Sr Activity:
89Sr Results (pCi/L) = N6/R (2.22) * (E) * (E(15)/E') * (S7) * (V) * (U) * (F9)
= W3 S7 = G + H*M + I*M2 (This is the general form of the normalized 4
89 Sr efficiency regression equation for one particular ges proportional counter where G, H and I are regression coefficients.)
N6 = N1 - N7* (1 + Rl*Il)
N7 = (N2 - Fl*N1)/W1 (This represents counts due to 90Sr) 131
2 to E(15)/E' = Ratio of 89Sr efficiency at thickness value of 15mg/cm 90Sr counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental 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 = Ealf-life of 89S r, days All other quantities are as previously defined.
The 2-sigma error for 89S r (pCi/L) = 2* (S8 2+39 2)1/2 *W3 (N1 - N7* (1+Rl*II)
S8 = (X+Y) + (X1+Yl)*F1 2 1/2 Wld W12 -
S9 = (Kl+Yl)1/2 All other variables are as previously defined.
Keeping the same variable definitions, the LLD for 89Sr (pci/L)
=
4.66* (S82 +392 )1/2 132
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE i
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 tensitivity) of the pulverized sample is first charred cver a Bunsen burner and then ashed in a muffle furnace. The ash is fused with 40g sodium carbonate, along with 20mg strontium carrier, 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 (ENO3 ) . The resultant nitrates are heated to dryness and are dissolved in 20ml distilled water before adding 60ml fuming ENO3 . After 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 dried and weighed. The samples are then counted 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 89Sr are both unknown quantities requiring two simultaneous equations to solve for them.
Calculation of 90Sr Activity:
4 90 Sr Results (pCi/kg wet) = N4/R (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 C are regression coefficients. )
M = Thickness density of strontium carbonate precipitate, ag/cm2 E(15)/E' = Ratio of 90Sr efficiency at thickness value of 15mg/cm 2 to 90 Sr counting standard efficiency run at the time of instrament calibration (This standard is run with each group of environmental strontium samples)
E = 90Sr counting standard efficiency m
V = Sample quantity (kg wet)
U = Chemical yield N4 = (N2 - Fl*N1)/W1 = net counts due to 90 Sr only W1 = ((1 + Rl*I2) - (1 + Rl*Il) *F1)
/
133
Il = 1 - EXP ((-0.693/2.667) *tl)
I2 = 1 - EXP ( (-0. 693/2. 667)
- t2) tl = Elapsed time from 90Y 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 (This is the general form of the regression equation for 90y eggsyf90S r 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/kg wet) =
2* (X+Y) + (X1+Yl)*F1 2' 1/2* (Wi*W2)
Wld Wld ,
(N2-Fl*N1)
Again, keeping the same variable definitions, the LLD for 90Sr (pCi/kg wet) =
4.66* '(X+Y) + (X1+Yl)*F12~ 1/2 WlZ Wld -
Calculation of 89S r Activity:
895r Results (pCi/kg wet) = N6/R (2.22) * (E) * (E (15)/E') * (S7) * (V) * (U) * (F9)
= W3 S7 = G + H*M + I*M 2 (This is the general form of the normalized 89Sr 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 (This represents counts due to 90S r) 134
E(15)/E' = Ratio of 89S r efficiency at thickness value of 15mg/cm2 to 90Sr counting standard efficiency run at the time of instrument calibration (This standard is run with each group ot environmental 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 89S r, days All other quantities are as previously defined.
The 2-sigma error for 89 Sr (pci/kg wet) = 2* (S82 +sg2)l/2 *W3 (N1 - N7* (1+Rl*II)
S8 = (X+Y) + (X1+Yl)*F12 1/2 W2
,1 y12 _
S9 = (X1+Y1)l/2 All other variables are as previously defined.
Keeping the same variable definitions, the LLD for 89S r (pci/kg wet) =
4.66*(S82 +s92 }l/2
)
135:
SYNOPSIS OF PSE&G RESEABCH 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 boiling 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. The 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 followed by coprecipitation with barium chromate. The strontium is precipi-tated as strontium carbonate, which is dried, weighed, then beta-counted on a low background gas proportional counter. A second count is performed at least 14 days later. The basis fo. this two-count method is that 90S r and 89S r are both unknown quantities requiring two simultaneous equations to solve for them.
Calculation of 90 S r Activity:
90Sr Results (pCi/kg dry) = N4/R (2.22) * (E) * (E (IS)/E') * (S6) * (V) * (U)
= W2 where S6 = A + B*M + C*M2 (This is the general form of the normalized 90S r efficiency regression equation for one particular gas proportional counter, where A, B and C are regression coefficients.)
M = Thickness density of strontium carbonate precipitate, mg/cm 2 E(IS)/E' = Ratio of 90S r efficiency at thickness value of 15mg/cm 2 to 90Sr counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samphs)
E = SOSr counting rtandard efficiency V = Sample quantity (kg dry)
U = Chemical yield N4 = (!T2 - Fl*N1)/W1 = net counts due to 90Sr only W1 = ((1 + Rl*I2) - (1 + Rl*II) *F1) 136
Il = 1 - EXP ((-0.693/2.667) *tl) 12 = 1 - EXP ((-0.693/2.667)*t2) tl = Elapsed time from 90Y 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 (This is the general form of the regression equation for 90y eggsyf90Sr 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 X1 and Y1 are initial gross counts and background counts, respectively 2.22 = No. of dpa per pCi g F1 = EXP ((-0.693/2.667)*t2)
R = Count time of sample and blank Using the same variable definitions as above, the 2-signa error for 90Sr (pCi/kg dry) =
2* + (X1+Yl)*F12 1/2* (W1*W2)
_1 W W12 _
(N2-Fl*N1)
Again, keepin the same variable definitions, the LLD for 9 Sr (pCi/kg dry) =
4.66* (X+Y) + (XI+Yl)*F12 1/2 y12
_1 W2 _
Calculation of 89 Sr Activity:
89 Sr Results (pCi/kg dry) = N6/R (2.22) * (E) * (E (15) /E ' ) * (S7) * (V) * (U) * (F9 )
= W3 S7 = G + H*M + I*M2 (This is the general form of the normalized 89st efficiency regression equation for one particular gas proportional counter where G, H and I are regression coefficient.3.)
N6 = N1 - N7* (1 + Rl*II)
N7 = (N2 - Fl*N1)/W1 (This represents counts due to 90Sr) 137
2 E(15)/E' = Ratio of 89Sr efficiency at thickness value of 15mg/cm to 90S r counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)
FD = 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 89S r, days All other quantities are as previously defined.
The 2-signa error for 89S r (pCi/kg dry) = 2* (S82 +s92 )l/2 ew3 (N1 - N7* (1+Rl'II)
S8 = + (xl+Yl) *Flf 1/2 W1 W12 ,
S9 = (X1+Yl)l/2 All other variables are as previously defined.
Keeping the same variable definitions, the LLD for 89S r (pci/kg dry) =
4.66*(S82 +s92 )1/2 138
f SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE RADIOSTRONTIUM ANALYSIS OF SOIL AND SEDIMENT A?ter the soil or sediment sample has been dried and pulverized, a 50gm aliquot is added to approximately 1/3 - liter concentrated hydrochloric acid (hcl),
containing Sal of strontium carrier (10mg Sr++/ml) . A blank containing only 1/3 - liter concentrated hcl and Sal strontium carrier is run in parallel with the sample. The samples are stirred vigorously for at least 30 minutes and then filtered. The filtrate is then diluted to a known volume and aliquots removed for stable strontium. The remaining sample is alkalinized with ammonium hydroxide to precipitate all the transitional elements. After filter-ing out these interferences, the filtrate is heated and sodium ca.:bonate added to precipitate strontium and calcium carbonate. These carbonates are first filtered and then digested with 6N HNO .3 Two fuming (90%) BNO3 recrystal-lizations are then performed to remove calcium. Subsequently, radioactive impurities are removed by two precipitation steps, using ferric hydroxide and barium chromate as carriers. The strontium is precipitated as strontium carbonate before being dried and weighed. The samples are counted for beta activity in a low background gas proportional counter (Count time will vary, depending on the desired sensitivity.). There is a second count at least 14 days later. The basis for this tw>-count method is that 90Sr and 89S r are both unknown quantities requiring two simultaneous equations to solve for them.
Calculation of 90Sr Activity:
90Sr Results (pCi/kg dry) = N4/R (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 C are regression coefficients.)
M = Thickness density of strontium carbonate precipitate, ag/cm2 E(15)/E' = Ratio of 90S r efficiency at thickness value of 15mg/cm2 to 90Sr 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 N4 = (N2 - Fl*N1)/W1 = net counts due to 90Sr only W1 = ((1 + Rl*I2) - (1 + Rl*Il) *F1) 139
l l
Il = 1 - EXP ( (-0. 693/2. 667)
- tl)
I2 = 1 - EXP ( (-0. 693/2. 667)
- t2) tl = Elapsed time from 30Y 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 (This is the general form of the regression equation for 90y eggeyf90Sr 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 dpa 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-signa error for 90S r (pCi/kg dry) =
~
2* (X+Y) + (X1+Yl)*Fl E 1/2* (Wl*W2)
_1W2 w12 ,
(N2-Fl*N1)
Again, keeping the same variable definitions, the LLD for 90Sr (pCi/kg dry) =
4.66* (Xill + fYl+Yli*F1 2 1/2 W2
_1 w12 _
Calculation of 89S r Activity:
89Sr Results (pCi/kg dry) = N6/R (2.22) * (E) * (E (15)/E') * (S7) * (V) * (U) * (F9)
= W3 S7 = G + H*M + I*M2 (This is the general form of the normalized 89S r 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)/W1 (This represents counts due to 90S r) 140
E(15)/E' = Ratio of 898 r efficiency at thickness value of 15mg/cm2 to 90Sr counting standard efficiency run at the time of instrument '
l calibration (This standard is run alth each group of environmental 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 89S r,-days All other quantities are as previously defined.
The 2-sigma error for 89S r (pci/kg dry) = 2* (S8 +gg2)1/2 2 *W3 (N1 - N7* (1+Rl*II)
~
88 = X11) + fX1+Yl)*F12 1/2 W
_12 y12 ,
S9 = (X1+Yl)l/2 All other variables are as previously defined.
Keeping the same variable definitions, the I1D for 89S r (PCi/kg dry) =
4.66* (S82 +gg23 1/2 i
G 141
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE ANALYSIS OF ENVIRONMENTAL SAMPLES FOR STABLE STRONTIUM It has been the practice of the Environmental Divisio_n 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.
For water samples, this involves removal of a 60-al aliquot of sample. How-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.
The 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 Sediment:
Reported concentration of stable strontium (ag/L):119 volume of specimen (al):25 (removed from 1000ml of diluted leachate)
Proportion of sample used for aliquot: 0.025 Milligrams strontium in 25ml 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
2.98mq Se = 119 mg 0.025 Net weight of SrCO3 precipitate (ag): 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 The calculations follow the same sequence for bone and shell samples.
142
Sample Calculation of Corrected Chemi::al Recovery of Strontium in Water:
Reported concentrations of stable strontium (ag/L): 1.65 volume of radiochemical water sample (liters) : 2.0 Stable strontium in 2 liter sample = (1.65mg/L) x (2.0L)
= 3.30mg
- Quantity of strontium carrier added to sample (aq)
- 20.0 Total amount of strontium in sample (ag): 20.0 + 3.30 = 23.3mg Net weight of SrCO3 precipitate (ag): 28.9 l Percent of Sr in precipitate: 59.35 l Quantity of strontium recovered = (28.9mg) x (.5935) = 17.2mg Corrected chemical recovery of strontium = 17.2nq = .738 23.3mg l
l 143
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 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 D = Decay correction factor Atl*EXP(At2) 1-EXP(-Atl) tl = Acquisition live time t2 = Elapsed time from sample collection 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, ains.
V = Sample volume, m3 2.22 = No. of dpa per pCi 2-signa error (pci/m3) = 1.96* (GC+BC)l/2*R N
GC = Gross counts BC = Background counts All other variables are as defined earlier.
The LLD (pCi/m3) = 4. 66 * (BC) l/2*D (2.22) * (E) * ( A) * (T) * (V) 1 1
144
SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE ANALYSIS OF AIR PARTICULATE FILTERS FOR GAMMA Air particulate filters are analysed for gamma using a lithium-drifted germanium detector interfaced with a 2048 channel pulse height analyser calibrated at 1.0 Kev per channel. Telodyne Isotopes employs one of three possible data acquisition ~and computation systems. The first,'a'D'ata General
~
NOVA minicomputer, in series with the pulse height analyzer, calculates the number of counts (and a one standard deviation) in the peak region by performing a linearly-interpolated background subtraction. If no peak is l
, 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, nanely, a Tracor Northern TN-11 and Nuclear Data 6620 which perform all the above computations automatically. All resultant spectra are stored on magnetic tape.
4 t
a 145
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE GAMMA ANALYSIS OF RAW MIIJC 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 Gasma Activity:
The following are the calculations performed for the gaEna 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 Itl*EXP (It2) 1-EXP(~ltl) t1 = Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition 1 = 0.693/nuclide half life E = Detector efficiency A = cm=== abundance factor (no. of photons per disintegration)
T = Acquisition live time, ains.
V = Sample volume, liters 2.22 = No. of dpa per PCi 2-signa error (pci/L) = 1.96*(GC+BC)l/2*R N
GC = Gross counts BC = Background counts All other variables are as defined earlier.
! The LLD (pCi/L) = 4.66*(BC)l/2*D (2. 2 2) * (E) " ( A) " (T) " (V)
E 146
- ~
SYMOPSIS 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 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 aluminum can is positioned on a hotplate underneath the end of the glass tube. The cork is removed with the aid of a forceps and the water flows into 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 100c1 mark scribed on the inside of the can. After all the 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 jeg and glass tube are rinsed with distilled water and the rinsing added to the can. The water level is then adjusted back to the 100ml level by additional evaporation. The sample is finally left to cool to room t temperature before sealing the can and then counting on a gamma detector for 1000 minutes.
Calculation of C==== Activity:
The following are the calculations performed for the gamma activity, 2-signa error and LLD:
Result (pCi/L) = N*D =R (2. 22) * (E) * ( A) * (T) * (V)
N = Net counts under photopeak D = Decay correction factor A tl*EXP ( At2) 1-EXP (-ltl) tl = Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition 1 = 0.693/nuclide half life E = Detector efficiency A = c==== abundance factor (no. of photons per disintegration) ,
T = Acquisition live time, ains. )
V = Sample volume, liters 2.22 = No. of dpa per pCi i 2-sigma error (pCi/L) = 1.96*(GC+BC)l/2*R N
GC = Gross counts BC = Background counts All other variables are as defined earlier.
The LLD (pCi/L) = 4.66*(BC)l/2*D l (2.22) * (E) * (A) * (T) * (V) l 147
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE GAleth 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 unit density (1g/cm3), whenever possible, in a tared-aluminum can. The can is weighed and then hermetically sealed and counted on a gamma detector.
i 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. Ttie sample volume is brought up to the standard geometry with distilled water and the can hermetically sealed before gasma counting.
Calculation of ca=== Activity The following are the calculations performed for the gamma activity, 2-signa error and lim:
Result (pCi/kg) = N*D =R (2.22) * (E) * ( A) * (T) * (V)
N = Net counts ur. der photopeak D = Decay correction factor Atl*EXP(It2) 1-EXP (-A 1) tl = Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition A = 0.693/nuclide half life
- E = Detector efficiency l A = Gas 1ma abundance factor (no. of photons per disintegration)
T = Acquisition live time, mins.
V = Sample volume, kilograms 2.22 = No. of dpm per pCi 148
- - - ,, - - - - - - - - . - - , . , ~ .r- n-- - ,
2-signa error (pci/kg) = 1.96*(GC+BC)l/2*R '
H -
BC = Background counts
_ All other variables are as defined earlier.
The LLD (pCi/kg) = 4.66*(BC)l/2*D (2.22) * (E) " (A) " (T) " (V) t J
l 149
SYNOPSIS OF TRLEDYNE ISOTOPES PROCELURE ANALYSIS OF TELEDYNE TSOTOPES THERMOLUMINESCENT DOSIMETERS These devices are rectangular Teflon wafers impregnated with 25% CaSO4: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 separate areas _of the dosimeter are read in a Telodyne Isotopes aodel 8300 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 b&ck-ground.
The results are computed as follows:
f 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 (after re-irradiation)
REDOSE = Re-irradiation dose, mR AVC = Average of control values, mR 4N where AVC = ICDOSE/4N i=1 N = Total number of control dosi-meters CDOSE = CR* (CREDOSE/CRR) i CDOSE = Control area dose, mR CR = Initial reading of control area CRR = Second reading of the control area (after re-irradiation)
CREDOSE = Re-irradiation dose of the control dosimeter, mR 150
e APPENDIX E
SUMMARY
OF USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDIES PROGRAM RESULTS 151
i SUHMARY OF USEPA INTERCOMPARISON STUDIES PROGRAM Appendix E presents a summary of the analytical results for the
~' -'
1985-USEPA-Environmental Radioactivity Laboratory Intercomparison Studies Program.
TABLE OF CONTENTS TABLE NO. TABLE DESCRIPTION PAGE E-1 Gross Alpha 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 I
l 153
i TABLE E-1 USEPA ENVIROBBlFNTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM
~ ~
- Gross Alpha and Gross Beta Analysis of Water (pCi/L) and Air Particulate (pCi/ filter)
PSEEG PSEEG EPA GRAND AVG .
DATE ENV ID BRBIBER MEDIIBt ANALYSIS Mean
- s.d. Mean t s.d. Mean t s.d.
1/85 EPA-WAT-AB128 Water Alpha 521 525 522 85-90 Beta 1621 15 5 17t3 a
3/85 EPA-WAT-AB134 Water Alpha 621 6t5 622 85-344 Beta 1221 15 5 1523 3/85 EPA-APT-GABS 135 APT Alpha 1121 1025 11t2 85-433 Beta 3322 36 5 38 6 4/85 EPA-WAT-P138 Water Alpha 3124 32t5 31 10 85-502 Beta 6223 7225 70210 i'
5/85 EPA-WAT-AB144 Water Alpha 10t2 12 5 1023 85-681 Beta lotl 1125 1223 7/85 EPA-WAT-AB149 Water Alpha 9t1 1125 923 85-948 Beta 721 825 9t3
]
8/85 EPA-APT-GABS 153 APT Alpha 1521 13t5 13t3 85-1134 Beta 4622 4425 4826
! 9/85 EPA-WAT-AB156 Water Alpha 7tl 825 822 85-1235 Beta 8tl 825 822 1
10/85 EPA-WAT-P159 Water Alpha (1) 85-1464 Beta 11/85 EPA-WAT-AB165 Water Alpha 13t2 (2) (2) 85-1640 Beta 12t1 (1) Not analyzed by PSE&G.
(2) Results not received from EPA.
154
l l
TABLE E-2 USEPA ENVIROletENTAL RADIOACTIVITY IABORATORY INTERCOMPARSION STUDY PROGRAM i
n==== Analysis of Milk, Water (pCi/L), Air Particulate '
(pci/ filter) and Food Products (Pci/kg) l PSEEG PSE&G EPA GRAND AVG DATE ENV ID NUMBER MEDItm NUCLIDE Mean t s.d. Mean s.d. Mean i s.d.
1/85 EPA-ORG-GS129 Food I-131 3422 3526 3625 ,85-110 Cs-137 2921 2925 3124 K(*) 1348236 13822120 1379 145 2/85 EPA-WAT-G130 Water Cr-51 5024 48t5 47t9 85-163 Co-60 2022 2022 1923 In-65 5522 5525 5626 Ru-106 2221 2525 25t7 Cs-134 3422 35t5 3324 Cs-137 2421 2525 2523 3/85 EPA-APT-GABS 135 APT Cs-137 621 625 722 85-433 4/85 EPA-WAT-P138 Water Co-60 1512 15t5 1623 85-502 Cs-134 1422 1525 1523 Cs-137 12 1 1225 1323 6/85 EPA-MLK-GS148 Milk I-131 1221 lit 6 1223 85-854 Cs-137 1121 1125 1222 K(*) 1580250 1525276 15242117 i
6/85 EPA-WAT-G145 Water Cr-51 4422 4425 48t11 85-713 Co-60 1422 1425 1523
- In-65 5225 4725 49 6 l Ru-106 5124 6225 58212 I Cs-134 3321 3515 33 4 Cs-137 2120 2025 2123 7/85 EPA-ORG-GS150 Food I-131 3522 3526 3725 85-984 Cs-137 31t2 2925 3123 K (*) 1530 27 1514276 15002120 8/85 EPA-APT-GABS 153 APT CS-137 821 825 922 85-1134 155
TABLE E-2 (cont'd)
USEPA ENVIRO MENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM cannna Analysis of Milk, Water (pCi/L), Air Particulate (pCi/ filter) and Food Products (Pci/kg)
PSE&G PSE&G EPA GRAND AVG ENV ID NUMBER MEDIUM NUCLIDE Mean t s.d. Mean i s.d. Mean t s.d.
DATE EPA-WAT-G157 Water Cr-51 2125 2125 24211 10/8 20t2 85-1377 Co-60 1921 2025 Zn-65 20t3 19 5 20t3 Ru-106 2123 2025 2327 Cs-134 1722 2025 1922 Cs-137 19t2 20 5 20 2 10/85 EPA-MLK-GS160 Milk I-131 3825 (1) (1) 85-1506 Cs-137 5622 K (*) 1550250 11/85 EPA-WAT-P159 Water Co-60 1721 (1) (1) 85-1464 Cs-134 17 1 Cs-137 1721
(*) Reported as mg/L of Potassium.
(1) Results not received from EPA.
156
TABLE E-3 USEPA ENVI]t089tENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Tritium Analysis of Water (pCi/L)
PSEEG PSE&G EPA GRAND AVG DATE ENV ID NtBIBER MEDIUM NUCLIDE Mean 2 s.d. Mean i s.d. Mean i s.d.
2/85 EPA-WAT-H131 Water H-3 3900tl80 3796t366 39162372
'I 4/85 EPA-WAT-H137 Water H-3 3650270 35592364 3534 268 85-472 6/85 EPA-WAT-H146 Water H-3 2400250 24162351 23992311 85-785 8/85 EPA-WAT-H152 Water H-3 45302130 4480 448 44222341 85-1133 10/85 EPA-WAT-H158 Water H-3 1960260 19742345 19842200 85-1425 157
TABLE E-4 USEPA ENVIROletENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Iodine Analysis of Water and Milk (pCi/L)
PSE&G PSE&G EPA GRAND AVG DATE ENV ID NtBEBER MEDIUM NUCLIDE Mean t s.d. Mean i s.d. Mean t s.d.
3/85 EPA-MLK-Il32(*) Milk I-131 921 920.9 822 85-261-4/85 EPA-WAT-Il36 Water I-131 711 821 71 85-434 8/85 EPA-WAT-Il51 Water I-131 30tl 3326 3224 85-1056 12/85 EPA-WAT-Il66 Water I-131 46tl (1) (1) 85-1715
(*) Special EPA /NRC low level study.
(1) Results not received from EPA.
t I
158
d TABLE E-5 USEPA ENVIROIStENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Strontium-89 and -90 Analysis of Air Particulates (pC1/ filter),
Milk, Water (pci/L) and Food Products (pCi/kg) j PSE&G PSE&G EPA GRAND AVG DATE ENV ID NtMBER MEDIIM NUCLIDE Mean 2 s.d. Mean t s.d. Mean t s.d.
1/85 EPA-NAT-8127 Water Sr-89 4.120.5 3.0 5 2*6 85-47 Sr-90 23.720.6 3021.5 2823 1/85 EPA-ORG-GS129 Food Sr-89 1721(1) 34t5 25210 85-110 Sr-90 20t3(1) 26*l.5 3029 2
3/85 EPA-APT-GABS 135 APT Sr-90 1221 15tl.5 1522 85-433 4/85 EPA-NAT-P138 Nater Sr-89 822 1025 10 4 85-502 Sr-90 12tl 15 1.5 1422 5/85 EPA-NAT-S143 Water Sr-89 3122 39 5 3628 85-643 Sr-90 1222 1521.5 1423 6/85 EPA-MLK-GS148 Milk Sr-89 10t1 1125 10t2 85-854 Sr-90 921 1121.5 1022 7/85 EPA-ORG-GS150 Food Sr-89 2321 33t5 2526 85-984 Sr-90 2321 2621.5 2726 8/85 EPA-WAT-GABS 153 APT Sr-90 15.829 1821.5 1812 85-1134 9/85 EPA-MAT-S154 Water Sr-89 1621 2025 1925 85-1178 Sr-90 621 721.5 721 10/85 EPA-MLK-GS160 Milk St-89 4521 (2) (2) 85-1506 Sr-90 2221 11/85 EPA-WAT-P159 Water Sr-89 (3) 85-1464 Sr-90 j (1) Two analyses reported to EPA.
(2) Resulta not received from EPA.
(3) Not analyzed by PSE&G.
159
i APPENDIX F SYNOPSIS OF DAIRY AND VEGETABLE GARDEN SURVEY 161
APPENDIX F SYNOPSIS OF 1985 LAND USE CENSUS A land use census was conducted to identify, within a distance of 8 km (5 miles), the location of the nearest milk animal, the 2
nearesg)residenceandthenearestgardenofgreaterthan50m (500ft producing broad leaf vegetation in each of the 16 meteorological sectors. I Tabulated below are the results of these su reys:
Milk
- Nearest ** Vegetable Anima? Residence Garden Meteorological May, af4d5 Aug., 1985 Sept., 1985 Sector km (miles) km (miles) km (miles)
N None None None NNE None 6.9 (4.3) None NE None 6.4 (4.0) None ENE None 5.4 (3.4) None E None None None ESE None None None SE None None None SSE None None None S None 6.1 (4.1) None SSW None 5.5 (3.4) None SW None 6.9 (4.3) None WSW None 7.1 (4.4) None W 7.8 (4.9) 6.5 (4.0) None WNW None 5.5 (3.4) None NW None 5.9 (3.7) None NNW None 6.8 (4.2) None
- A second milk animal survey was performed in September 1985.
No change from the May survey was found.
- Nearest residence survey conducted by LLesdner Associates.
163
. - _ _