ML18089A182
| ML18089A182 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/02/1983 |
| From: | Liden E Public Service Enterprise Group |
| To: | Allan J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML18089A183 | List: |
| References | |
| NUDOCS 8306150267 | |
| Download: ML18089A182 (483) | |
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RTL-ENV-84-01 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1983 RADIOLOGICAL REPORT JANUARY 1 TO DECEMBER 31, 1983 Prepared for PUBLIC SERVICE ELECTRIC AND GAS COMPANY By PSE&G RESEARCH CORPORATION RESEARCH AND TESTING LABORATORY MARCH 1984
TABLE OF CONTENTS PAGE
SUMMARY
1 INTRODUCTION 2 THE PROGRAM 3 Objectives 3 1983 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 16 Terrestrial 16 Aquatic 24 PROGRAM DEVIATIONS 31 CONCLUSIONS 31 REFERENCES 32 APPENDIX A - PROGRAM
SUMMARY
35 APPENDIX B - SAMPLE DESIGNATION AND LOCATIONS 45
- APPENDIX C - 1983 DATA TABLES 53 APPENDIX D - SYNOPSIS OF ANALYTICAL PROCEDURES 107 APPENDIX E -
SUMMARY
OF USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDIES PROGRAM RESULTS 177 APPENDIX F - SYNOPSIS OF DAIRY AND VEGETABLE GARDEN SURVEY 187 i
LIST OF FIGURES NUMBER PAGE
- 1. Comparison of Average Concentrations of Beta Emitters in Precipitation and in Air Particulates, 1973 through 1983 .***********************.*..****** 13
- 2. Average Ambient Radiation Levels from Monthly TLDs in the Vicinity of Artificial Island, 1973 through 1983
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- c 17 2A. Comparison of Ambient Radiation Levels of Off-Site Indicator Stations vs. Control Stations, 1982 through 1 9 8 3 e e o e e O Ci> 0 e 0 Q e o o 0 c O e Co O Ge Cl 0 Q cc Cg COO e o Q O o O 18
- 3. Average Concentrations of Iodine-131 in Milk in the Vicinity of Artificial Island, May 1974 through December 1983e G. 0 ** e 0 Cl ** e 0 0 e () G 0 Cl. 0 Cll c 0 0 c. 0 0. c ** c. e Cl. 20
- 4. Average Concentrations of Beta Emitters and Potassium-40 in the Delaware River in the Vicinity of Artificial Island, 1973 through 1983 *..**.***.*. 25
- 5. Average Concentrations of Tritium in the Delaware River in the Vicinity of Artificial Island, 1973 through 1983. Cle Ce QC Cl 0 GIG 18 Ill C II 0 0 C 0 G ctl e Cl II Cle e e Cl 0 e e O e e O e e e 28 ii
SUMMARY
During the period from January l through December 31, 1983, the Research and Testing Laboratory (RTL), PSE&G Research Corpo-ration, has been responsible for the collection of all samples and maintenance of sampling equipment connected with the Oper-ating Radiological Environmental Monitoring Program at Artificial Island, Salem County, New Jersey. Through June, sample analyses were performed by Radiation Management Corporation (RMC). Beginning July 1, the RTL assumed responsibility for the radio-chemical analysis and has maintained continuity of the program. 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, will fulfill the requirements of the SGS Environmental Technical Specifications, and will provide background data for the Hope Creek Generating Station. -This report presents the results of thermoluminescent dosimetry and radiochemical analyses of environmental samples collected during 1983. A total of 4321 analyses were performed on 1640 environmental samples during the period covered by this report. Samples of air particulates, air iodine, surface, ground and drinking water, benthos, sediment, milk, fish, crabs, vegetables, game, fodder crops, meat, and precipitation were collected. Thermoluminescent dosimeters were used to measure ambient radiation levels. A variety of radionuclides, both naturally-occurring and manmade, were found in the above samples. These nuclides were detected at levels similar to those found during the preoperational phase of this program. It can be concluded that the radiological characteristics of the environment around Artificial Island during 1983 were not affected by the operation of SGS Units One and Two. 1
INTRODUCTION Artificial Island is the site of Salem Generating Station (SGS) which consists of two operating pressurized water nuclear power reactors. Unit One has a net rating of 1090 MWe (3338 MWt), and Unit Two is rated at 1115 MWe (3411 MWt). Artificial Island is a man-made peninsula on the east bank of the Delaware River and was created by the deposition of hydraulic fill from dredging operations. It is located in Lower Alloways creek Township, Salem County, New Jersey. The environment 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 (12]. More specific information on the demography, hydrology, meteorology, and land use of the area may be found in the Environmental Report [12], Environmental Statement (13], and the Final Safety Analysis Report for SNGS [ 14] . Since 1968 an off-site Radiological Environmental Monitoring Program (REMP) has been conducted at the Artificial Island Site. Starting in December 1972, more extensive radiological monitoring programs were initiated. The operational REMP was initiated in December 1976 when Unit 1 achieved criticality. The Research and Testing Laboratory (RTL), PSE&G Research Corporation, a wholly-owned subsidiary of Public Service Electric and Gas Company, has been involved in the REMP since its inception. The RTL is responsible for the collection of all radiological environmental samples, and, since 1973, has conducted a quality assurance program in which duplicates of a portion of those samples analyzed by the primary laboratory were also analyzed by the RTL. Since January 1973, Radiation Management Corporation (RMC) has had primary responsibility for the analysis of all samples under the Artificial Island REMP and the annual reporting of results. RMC reports for the the preoperational phase from 1973 to 1976 and for the operational phase from 1976 through 1982 are referenced in this report (1-11]. On July 1, 1983, the RTL assumed primary responsibility for the analysis of all samples (except TLD's) and the reporting of results. Teledyne Isotopes (TI), Westwood, NJ, at that time was made responsible for third-party QA analyses and TLD's. This report summarizes the results of RMC from January 1 through June 30,1983 and the results of the RTL and TI from July 1 through December 31, 1983 for the Artificial Island Radiological Environmental Monitoring Program. 2
THE PROGRAM The operational phase of the REMP is conducted in accordance with Section 3.2 of the Environmental Technical Specifications for SGS Units 1 and 2 [15,16]. An overview of this program is provided in Table 1. Radioanalytical data from samples collected under this program were compared with results from the preoper-ational phase. Differences between these periods were examined statistically, where applicable, to determine the effects, if any, of station operations. Objectives The objectives of the operational radiological environmental program are:
- 1. To fulfill the obligations of the Radiological surveillance sections of the Environmental Technical Specifications for Salem Nuclear Generating Station (SNGS).
- 2. To determine whether any significant increase occurs in the concentration of radionuclides in critical pathways.
- 3. To determine if SNGS has caused an increase in the radioactive inventory of long lived radionuclides.
- 4. To detect any change in ambient gamma radiation levels.
- 5. To verify that SNGS operations have no detrimental effects on the health and safety of the public or on the environment.
This report, as required by Section 5.6 of the Salem Environ-mental Technical Specifications (ETS), summarizes the findings of the 1983 REMP. Results of the four-year preoperational program have been summarized for purposes of com- parison with subsequent operational reports [4]. 3
TABLE -1 1983 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATION CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS I. ATMOSPHERIC ENVIRONMENT
- a. Air Particulate 2S2 5Dl 16El lFl 3H3 Weekly Gross alpha/weekly 5Sl 1001 2F2 Gross beta/weekly Sr-89 & -90/quarterly Gamma scan/quarterly
- b. Air Iodine 2S2 501 16El lFl 3H3 Weekly Iodine-131/weekly 5Sl lODl 2F2
- c. Precipitation 2F2 Monthly Gross alpha/monthly Gross beta/monthly Tritium/monthly Sr-89 & -90/quarterly Gamma scan/quarterly
- d. Direct Radiation 2S2 5Dl 2El lFl 3Gl 2Hl Monthly & Gamma dose/monthly 5Sl 1001 3El 2F2 3Hl Quarterly Gamma dose/quarterly 6S2 1401 13El 2F6 3H3 7Sl 16El 5Fl lOSl 6Fl llSl 7F2 llFl 13Fl
TABLE -1 (cont'd) 1983 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATION CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS
- d. Direct Radiation 4D2 9El 2F5 lG3 Quarterly Gamma dose/quarterly (cont'd) 11E2 3F2 lOGl 12El 3F3 16Gl 10F2 12Fl 13F2 13F3 14F2 15F3
()'I 16F2 II. TERRESTRIAL ENVIRONMENT
- a. Milk 13E3 2F4 3Gl Semi-monthly Iodine-131/semi-monthly 5F2 Sr-89 & -90/monthly 14Fl Gamma scan/monthly 15Fl
- b. Well Water 4Sl/2S3 5Dl 3El Monthly Gross alpha/monthly Gross beta/monthly Potassium-40/monthly Tritium/monthly Sr-89 & -90/quarterly Gamma scan/quarterly
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TABLE -1 (cont'd) 1983 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATION CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS
- c. Potable Water 2F3 Monthly Gross alpha/monthly (Raw & Treated) (Composited Gross beta/monthly daily) Potassium-40/monthly Tritium/monthly Sr-89 & -90/quarterly Gamma Scan/quarterly
- d. Vegetables 5Dl 2El 1F3 lGl 3H4 Annually Sr-89 & -90/on collection 5Fl (At Harvest) Gamma scan/on collection 14F3
- e. Game 3El llDl Semi- Sr-89 & -90 (bones)/on collection (Muskrat) annually Gamma scan (flesh)/on collection
- f. Beef 3El 14Fl Semi- Gamma scan/on collection annually
- g. Bovine Thyroid 3El 14Fl Semi- Gamma scan/on collection annually
TABLE -1 (cont'd) 1983 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATION CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS
- h. Fodder Crops 3El 2F4 3Gl Annually Gamma scan/on collection 5F2 14Fl 15Fl
- i. Soil 6Sl 5Dl 2El lFl 3Gl 3H3 Collected Sr-90/on collection lODl 16El 2Fl from each Gamma scan/on collection 2F2 location 2F4 once every 5Fl three years.
5F2 14Fl 15Fl III. AQUATIC ENVIRONMENT
- a. Surface Water llAl ?El 1F2 12Cl Monthly Gross alpha/monthly 16Fl Gross beta/monthly Tritium/monthly Sr-89 & -90/quarterly Gamma scan/monthly
TABLE -1 (cont 9 d) 1983 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATION CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS
- 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 llAl 12Cl Semi- Tritium (flesh)/on collection annually Sr-89 & -90 (shell)/on collection Sr-89 & -90 (flesh)/on collection 00 Gamma scan (flesh)/on collection
- d. Benthic Organisms llAl 7El 16Fl 12Cl Semi- Sr-89 & -90/on collection annually Gamma scan/on collection
- e. Sediment llAl 7El 16Fl 12Cl Semi- Sr-90/on collection annually Gamma scan/on collection
- Except for TLDs, the quarterly analysis is performed on a composite of individual samples collected during the quarter.
Sample Collection In order to meet the stated objectives, an appropriate operational 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 radio-nuclides and direct radiation at indicator stations are evaluated with respect to analogous fluctuations at control stations. Indicator and control station data are also evaluated relative to preoperational data. The REMP for the Artificial Island Site includes additional samples and analyses not specifically required by the Salem ETS. The summary tables in this report include these additional samples and analyses. Air particulates were collected on Schleicher-Schuell No. 25 glass fiber filters with low-volume air samplers. Iodine was collected from air by adsorption on TEDA-impregnated charcoal cartridges connected in series after the air particulate filters. Air sample volumes were measured with calibrated dry-gas meters and were corrected to standard temperature and pressure. Precipitation was collected in a Wong Laboratory Automatic Precipitation Collector having a 95 square inch collection area. The collector is automatically covered during periods of no precipitation to exclude fallout resulting from dry deposition. Samples were collected monthly and transferred to new poly-ethylene bottles. The collector was rinsed with distilled water 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 thermoluminescent dosimeters (TLD's). Packets for monthly and quarterly exposure were placed on and around the Artificial Island Site at various distances. TLD's for the months of January through June and for the first and second quarters were CaS04 (Tm) supplied and read by Radiation Management Corporation. TLD's for the months of July through December and for the third and fourth quarters were CaS04 (Dy) supplied and read by Teledyne Isotopes. 9
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. All estuarine samples were collected by Ichthyological Associates 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 a sealed polyethylene container. Benthos and sediment were taken with a bottom grab sampler. Milk samples were taken semi-monthly in new polyethylene containers. Food products, fodder crops, game, beef, and bovine thyroid were sealed in new plastic bags or jars. All perishable samples were transported in ice chests, and no preservatives were added. Appendix A describes and summarizes, in the format of Table 5.6-1 of the Salem ETS, the entire operational program as performed in 1983. Appendix B describes the coding system which identifies sample type and location. Table B-1 lists the sampling stations and the types of samples collected at each station. These sampling stations are indicated on maps B-1 and B-2. Data Interpretation Results of all analyses were grouped according to the analysis performed for each type of sample and are presented in the data tables in Appendix c. All results above the lower limit of detection (LLD) are at a confidence level of +/- 2 sigma. This represents the range of values into which 95% of repeated analyses of the same sample should fall. As defined in Regulatory Guide 4.8, LLD is the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability with only 5% probability of falsely ~oncluding 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 17. Thus, the 2 sigma deviations of the averaged data represent sample and not analytical variability. When a group of data were composed of 50% or more LLD values, averages were not calculated. Grab sampling is a useful and acceptable procedure for taking environmental samples of a medium in which the concentration of radionuclides is expected to vary slowly with time or where intermittent sampling is deemed sufficient to establish the 10
radiological characteristics of the medium. This method, however, is only representative of the sampled medium for that specific location and instant of time. As a result, variation in the radionuclide concentrations of the samples will normally occur. Since these variations will tend to counterbalance one another, the extraction of averages based upon repetitive grab samples is considered valid. Quality Assurance Program PSE&G Research Corporation, Research and Testing Laboratory (RTL), has a quality assurance program designed to maximize confidence in the analytical procedures used. Approximately 20% of the total analytical effort is spent on quality control, including process quality control, instrument quality control, interlaboratory cross-check analyses, and data review. The analytical methods utilized in this program are summarized in Appendix D. The quality of the results obtained by the RTL is insured by the implementation of the Quality Assurance Program as described in the Environmental Division Quality Assurance Manual [18] and the Environmental Division Procedures Manual [19]. The internal quality control activity of the Laboratory includes the quality control of instrumentation, equipment, and reagents, the use of reference standards in calibration, documentation of established procedures and computer programs, and analysis of duplicate and spiked samples. The external quality control activity is implemented through participation in the USEPA Laboratory Inter-comparison Studies Program. These results are listed in Tables E-1 through E-6 in Appendix E. Program Changes As discussed in the Introduction, beginning July 1, 1983, PSE&G Research Corporation, Research and Testing Laboratory assumed responsibility for analysis of all samples under the REMP except TLD's. The TLD's since July have been supplied and analyzed by Teledyne Isotopes. An additional location for monthly and quarterly TLD's was added at 2F6. With the discontinuance of RMC's services, TLD control station SA-IDM-2Hl at its laboratory in Philadelphia, was terminated on June 28, 1983. Well water sampling location 4Sl was replaced by location 2S3 beginning in October, due to the difficulty in obtaining samples at 4Sl. 11
RESULTS AND DISCUSSION The analytical results of the 1983 REMP samples are divided into categories based on exposure pathways: atmospheric, direct, terrestrial, and aquatic. The analytical results for the 1983 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 emitters, sr-89 and -90, and gamma emitters. The weekly air particulate samples were analyzed for gross alpha at eight stations, except for six weeks in June and July when samples at only two stations were analyzed. The weekly samples were analyzed for gross beta at eight stations for the entire year. Quarterly composites of the weekly samples from each station were analyzed for Sr-89, Sr-90 and specific gamma emitters. Concentrations were detected in 320 of the 382 weekly samples analyzed for gross alpha emitters (Table C-l)o Alpha concentra-tions ranged from 0.5 to 14 x io-3 pCi/m3 with the grand average for all stations being 1.6 x lo-3 pCi/m3. Two analyses exhibited high uncertainties due to low sample volumes: the fourth sample in May at location 2S2 (<4% of normal volume) and the first week in October at location !Fl (11% of normal volume). Analysis of weekly air particulate samples for gross beta (Table C-2) indicated concentrations ranging from 5.9 x lo-3 to 70 x lo-3 pCi/m3 with the grand average for all stations being 24 x l0-3 pCi/m3. Figure 1 indicates the relation between gross beta activity in air particulates and precipitation for the preoperational and operational periods, including the effects of atmospheric weapons testing. Of the 32 monthly-composited samples analyzed for strontium-89 and -90, there was no detectable activity. LLD's for Sr-89 ranged from 0.2 x lo-3 to 0.6 x l0-3 pCi/m3 and, for sr-90, from 0.1 x lo-3 to 0.4 x lo-3 pCi/m3. Results of gamma spectrometry indicated detectable levels of Be-7 in all of the 32 monthly composites with a maximum of 69 x lo-3 pCi/m3 in 3 samples. Be-7 is a naturally occurring radionuclide attributed to cosmic ray activity in the atmosphere. Traces of Co-60, Ra-226, and Th-232 were detected in 5 samples; 12
FIGURE 1 CCJ1PARISON OF AVERAGE CONCEHTllATIOtlS OF BETA EllITTERS IU PRECIPITATION AND IN AIR PARTICULATES, 1973 THROUGH 1982 DCi/l - - - - -6 Pree i oita t ion l o- 3 pCi/m 3- - - - . Air Particulates I I I 10 I ~I tI I I II I\ I I I I I
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FIGURE 1 (cont'd) COMPARISON OF AVERAGE CONCENTRATIONS OF BETA EMITTERS IN PRECIPITATION AND IN AIR PARTICULATES, 1983 1000 i
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all of these activities were at or below the maximum LLD's for these radionuclides which were 0.7, 1.6, and 2.1 x lo-3 pCi/m3 respectively. Air Iodine (Table C-4) Cartridges for the adsorption of air iodine were connected in series after each of the air particulate filters. The adsorption media in these cartridges is triethylenediamine (TEDA) impreg-nated charcoal. All results for I-131 were below the LLD and ranged from <3.2 x lo-3 to 60 x lo-3 pCi/m3. In addition, nine did not meet minimum sensitivity of 60 x lo-3 pCi/m3. Precipitation (Tables C-6, C-7) Although not required by the Salem ETS, precipitation samples were collected at 2F2 in the town of Salem. Monthly samples were analyzed for gross alpha, gross beta, and tritium. Alpha activities in 4 samples ranged from 0.5 to 4.6 pCi/L, with LLD's in 8 samples from 0.4 to 1.9 pCi/L. Beta activity in 10 of the monthly samples ranged from 1.4 to 19 pCi/L. Tritium was detected in the January sample at a level of 190 pCi/L; this is below the required sensitivity of 200 pCi/L. Quarterly composites were analyzed for radiostrontium and gamma emitters. Neither Sr-89 nor Sr-90 were detected in the samples for the first two quarters. There was insufficient rainfall during the third quarter for radiostrontium analysis and the fourth quarter sample was lost during analysis. The only gamma emitter detected was Be-7, with activities ranging from 15 to 63 pCi/L. in the four samples. The relatively high levels of alpha and beta activity detected in the July sample (4.6 and 19 pCi/L respectively) was possibly due to the scarcity of rain during this month. Washout of particles from the atmosphere occurs during the initial period of rainfall, with dilution of particle concentration as the rain continues. The total rainfall at this location for the July sampling period was 0.36 inches. It is probable that this small amount of precipitation contained a higher concentration of alpha and beta activity than would have been detected had there been more rain during July. Perhaps a more meaningful assessment of the impact of rainfall on the environment would be obtained if if the activity deposited per unit area were reported. This can be determined by dividing the total activity of the collected sample by the collector area. Thus, for July with a total rainfall of 0.36 inches and alpha and beta activity of 4.6 and 19 pCi/L respectively, the surface deposition was 41 pCi/m2 for alpha and 176 pCi/m2 for beta. For November with a rainfall of 2.80 inches and alpha and beta activity of 0.6 and 3.9 pCi/L, the surface deposition was 46 pCi/m2 alpha and 280 pCi/m2 beta. 15
Direct Radiation (Tables C-8, C-9) A total of 42 locations were monitored for direct radiation during 1983, including 6 on-site locations, 29 off-site locations within the 10 mile zone, and 7 control locations beyond 10 miles. Monthly and quarterly measurements were made at the 6 on-site stations and at 15 off-site indicator stations, with 4 controls through June and 3 for the remainder of the year, as discussed previously. An additional 14 quarterly measurements were taken at schools and population centers with 3 additional controls 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 6.0 millirads per standard month, and the corresponding averaged control dose rate was 6.7 millirads per standard month. The average dose rate for the 29 quarterly off-site indicator TLD's was 5.2 millirads per stanpard month, and the averaged control rate was 6.0. 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 10 year period through 1982. Figure 2A shows the monthly averages of the off-site indicator stations and the control stations for 1982 and 1983. All of the readings, including controls, increased significantly in August. However, the magnitude of this increase was not confirmed by the quarterly data for _these same locations (Table C-8). These results are still being investigated. As was noted in 1982, a general increase in ambient radiation levels was observed at all locations, including control stations, indicating that the increased levels were not due to the operation of SGS. The average of each monthly off-site and control TLD for 1983 was higher than its corresponding average in 1982. For the quarterly TLD's, this increase was noted at twenty of twenty-eight indicator stations and at all of the control stations. Terrestrial Milk (Tables C-10, C-11, C-12, C-13) Milk samples were collected twice each month at six local dairy farms. Each sample was analyzed for I-131 and the first collec-tion each month was also analyzed for sr-89 and -90 and gamma emitters. Figure 3 indicates that I-131 was not detected in any sample during 1983. Table C-10 lists the results and shows that sensitivities ranged from <0.06 to <0.5 pCi/L. Strontium-89 was not detected in any of the samples; LLD values ranged from <l.O to <3.1 pCi/L. Strontium-90 was found in all of the samples analyzed. The Sr-90 annual mean for the indicator locations was 2.7 pCi/L with a range of 0.8 to 5.9 pCi/L; annual mean for the control location was 3.3 pCi/L with a range of 2.2 to 4.2 pCi/L. 16
FIGURE 2 AVERAGE AMBIENT RADIATION LEVELS FROM MONTHLY TLDs IN THE VICINITY OF ARTIFICIAL ISLAND, 1973 THROUGH 1982 ga* All Stations 10 E 9 8
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Gamma spectrometry showed detectable concentrations of K-40 in all samples and Cs-137 in nineteen of the sixty indicator locations and in five of the twelve samples from the control location. The annual mean concentration of K-40 for the indicator locations was 1358 pCi/L with a range of 1100 to 1600 pCi/L; K-40 mean for the control location was 1300 pCi/L with a range of 1000 to 1400 pCi/L. The annual mean of Cs-137 for the indicator locations was 2.1 pCi/L with a range of 1.1 to 4.7 pCi/L; Cs-137 for the control location was 1.4 pCi/L with a range of 1.2 to 1.7 pCi/L. Traces of Co-60 at location 15Fl (5.5 pCi/L), Ce-141 at 13El (2.4 pCi/L), and Th-232 at location 5F2 (8.1 pCi/L), were detected; sensitivities for these radio-nuclides were: Co <1.3 to <6.2 pCi/L; Ce-141 - <1.4 to <13 pCi/L; Th-232 - <3.0 to <15 pCi/L. The results of all radionuclide analyses were within the range of values found in 1982 and throughout the preoperational program. Thus, no contribution from the operation of SGS is indicated. In order to maintain continuity of the program, an alternate location (3G2) supplied the control samples from the second collection in June through the second collection in August while the farmer at location 3Gl replaced his entire dairy herd. 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 composites were analyzed for radiostrontium and gamma emitters. Gross alpha concentrations from 0.4 to 2.1 pCi/L were detected in seven of the indicator sampl~s, with LLD sensitivities for the other analyses ranging from <0.2 to <3.4 pCi/L. Gross beta activity was detected in all of the samples. The mean activity for the indicator locations was 13 pCi/L with a range of 7.9 to 16 pCi/L; mean activity for the control location was 10 pCi/L with a range of 7.6 to 14 pCi/L. K-40 in each monthly sample was determined by atomic absorption spectroscopy. Mean activity for th~ indicator locations was 15 pCi/L with a range of 9 to 27 pCi/L, and mean activity for the control location was 11 pCi/L with a range of 7.2 to 16 pCi/L. A comparison of the gross beta with K-40 results indicates that all the beta activity was due to the K-40 beta emission. All tritium results, except one, were at LLD levels of <120 to <140 pCi/L. In one control sample for October, a lev~l of 430 pCi/L was measured; this is considered an anomaly since sub-sequent samples were below the LLD. 19
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Radiostrontium was not detected in the quarterly composites; Sr-89 LLD's were from <0.5 to <0.7, and Sr~90 LLD's were from <0.4 to <0.6. Potassium-40 at four indicator locations was the only gamma emitter which was detected; activity ranged from 14 to 16 pCi/L, with LLD's from <7.8 to <14. Results for all analyses showed no significant variation from those of 1982 and the preoperational program. Potable Water (Tables C-16, C-17) Both raw and treated water samples were collected from the Salem water treatment plant. Each sample consisted of daily aliquots composited into monthly samples. 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 were analyzed for sr-89, -90, and gamma emitters. Detectable alpha activity was noted in seven raw and five treated water samples with ranges of 0.8 to 3.1 pCi/L (raw), and 0.8 to .2.7 pCi/L (treated), and average for each of 1.4 pCi/L. Beta activity was observed in all 24 of the monthly samples with ranges of 2.4 to 3.9 pCi/L (raw), and 1.5 to 2.6 (treated), and averages of 3.0 pCi/L (raw) and 2.2 pCi/L (treated). K-40 concentrations for raw and treated samples were practically identical except for one treated sample with an activity of 19 pCi/L which is inconsistent with the beta activity of 2.2 pCi/L. K-40 averages were 2.2 pCi/L (raw) and 3.5 pCi/L (treated). Tritium activity was observed in six of the twenty-four ranging from 140 to 220 pCi/L. Sr-90 was observed in one of the quarterly composites at 0.6 pCi/L; no Sr-89 was found. LLD's ranged from 0.5 to 1.7 pCi/L for Sr-89, and from 0.4 to 0.7 pCi/L for sr-90. No gamma emitters were detected in any of the samples. 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, asparagus, cabbage, tomatoes, and cucumbers. Each sample was analyzed for Sr-89, sr-90, and gamma emitters. sr-89 was not found in any of the fifteen samples; Sr-89 LLD's ranged from <20 to <37 pCi/kg-wet. sr-90 was detected in one cabbage (31 pCi/kg-wet), one sweet corn (control location, 17 pCi/kg-wet), and one cucumber (control location, 19 pCi/kg-wet) sample; LLD's ranged from <10 to <15 pCi/kg. All samples contained K-40 at concentrations from 1300 to 3100 pCi/kg-wet, with an average for all samples of 2000 pCi/kg-wet. A trace of Ra-226 was seen in one control station tomato sample and traces of T-232 were noted in an indicator station tomato sample and in a control station sweet corn sample. 22
Game (Table C-19) Two muskrat samples were taken in January. Bones from both samples were analyzed for Sr-89 and -90 while the flesh was analyzed for gamma emitters. Sr-89 for each sample was below an LLD of 36 pCi/kg-dry. Sr-90 at 47 pCi/kg-dry was detected in one sample and the other was <29 pCi/kg-dry. Gamma scans of the flesh indicated the presence of naturally-occurring K-40, only, at levels of 2700 and 3000 pCi/kg-wet. Normally, muskrat samples are also obtained during November or December of the year. However, because of weather conditions and the poor quality of the pelts, muskrat samples were not available from the trappers. Beef and Bovine Thyroid (Table C-19) Two beef samples and the thyroid gland from each were collected. Analysis of the flesh for gamma emitters indicated only the presence of naturally-occurring K-40 at concentrations of 2300 and 2700 pCi/kg-wet. Analysis of the thyroids for gamma emitters indicated only K-40 at concentrations of 1200 and 1900 pCi/kg-wet. No detectable concentrations of I-131 were found. Fodder crops (Table C-20) samples of crops normally used as cattle feed were collected at six locations where these products may be a significant element in the food-chain pathway. Five of the locations are milk and soil sampling stations, one of these also supplied a beef/thyroid sample, and the sixth supplied the second beef/thyroid sample. Samples collected for wet gamma analysis included cured hay, corn silage, green chop, barley, and soybeans. K-40 was detected in all of the eleven samples at concentrations from 400 to 14000 pCi/kg-wet, with an average of 6500 pCi/kg. Be-7, from the atmosphere, was found in eight of the samples at concentrations from 32 to 590 pCi/kg-w~t, with an average of 320 pci/kg. Traces of Ra-226 or Th-232 were detected in barley, hay, silage, and soybeans at three indicator stations. Co-60 at 46 pCi/kg-wet, and zr-95 at 92 pCi/kg-wet were detected in one control station soybean ,sample. Preoperational levels for Zr-95 ranged from 30 to 6300 pCi/kg. Nothing is known of the compo-sition of fertilizers which may have been applied to the soil in which these crops were grown. 23
Soil (Table C-21) Soil is sampled every three years at 15 locations, including two controls, and analyzed for Sr-90 and gamma emitters. Samples are collected at each station in areas that have been relatively undisturbed since the last collection in order to determine any change in the radionuclide inventory of the area. The concentrations of Sr-90 for the indicator stations ranged from 46 to 260 pCi/kg-dry with an average of 125 pCi/kg~ The two control stations were 120 and 250 pCi/kg-dry with an average of 185 pCi/kg. Averages for the indicator stations were 220 pCi/kg in 1977 and 149 pCi/kg in 1980. Averages for the control stations were 430 pCi/kg in 1977 and 195 pCi/kg in 1980. This indicates a continuing decrease in the Sr-90 concentration in the soils. Gamma spectrometry of these samples showed detectable concentra-tions of the naturally occurring radionuclides (K-40,Ra-226, and Th-232) and the fission product Cs-137. The Cs-137 at the indicator stations ranged from 120 to 1600 pCi/kg with an average of 440 pCi/kg. The two control stations were 320 and 910 pCi/kg with an average of 615 pCi/kg. Averages for the indicator stations were 710 pCi/kg in 1977 and 445 pCi/kg in 1980. Averages for the control stations were 620 pCi/kg in 1977 and 650 pCi/kg in 1980. Aquatic Surface Water (Tables C-23, C-24, C-25, C-26) Surface water samples were collected monthly at five locations in the Delaware estuary. One location is at the outfall area, another is downstream from the outfall area, and another is directly west of the outfall area at the mouth of the Appoquinimink River. Two upstream locations are in the Delaware River and at the mouth of the Chesapeake and Delaware Canal, the latter being sampled when the flow is from the Canal into the river. Station 12Cl, at the mouth of the Appoquinimink River, serves as the operational control. All surface water samples were analyzed monthly for gross alpha and gross beta emitters, tritium, and gamma emitters. Quarterly composites were analyzed for sr-89 and Sr-90. Alpha concentrations were detected in six of the 48 indicator samples and in none of the control samples. Levels ranged from 0.2 to 1.7 pCi/L. All the other samples were at or below the LLD, which ranged from <0.2 to <5.0. Beta concentrations for the indicator stations ranged from 4.1 pCi/L to 120 pCi/L with an average of 46 pCi/L, and, for the control station, from 9.9 pCi/L to 86 pCi/L with an average of 37 pCi/L. Nearly all of 24
FIGURE 4 AVERAGE CONCENTRATIONS OF BETA EMITTERS AND POTASSIUM-40 IN THE DELAWARE RIVER IN THE VICINITY OF ARTIFICIAL ISLAND, 1973 THROUGH 1982 1000.------------------------------------------------~~--------~~--~~~~--------~--~----~---------------------.
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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. Tritium analysis for the indicator stations ranged from 150 to 510 pCi/L with one analysis in August at the outfall of 1260 pCi/L. There is no reason to doubt the validity of this result for the sample analyzed. The average of the 18 indicator samples with detectable levels of tritium was 323 pCi/L. Tritium was detected in six of the twelve control samples and ranged from 160 to 450 pCi/L with an average of 227 pCi/L. Levels for the years 1973 through 1983 are plotted in Figure 5. Gamma spectrometric analysis of surface water samples showed detectable concentrations in forty-eight of the sixty samples. The average K-40 concentration at the indicator stations was 60 pCi/L with a range of 14 to 120 pCi/L. Average K-40 concentra-tion at the control station was 44 pCi/L with a range of 10 to 92 pCi/L. Co-58, C~-60, Mo-99, and La-140 was detected at levels near the LLD in six of the sixty samples analyzed. Neither Sr-89 nor Sr-90 was detected in any of the twenty quarterly composited samples. LLD sensitivities for Sr-89 ranged from <0.6 to <1.2 pCi/L and, for Sr-90 from <0.4 to <0.9 pCi/L. Fish (Tables C-37, C-28) Edible species of fish were collected semi-annually at three locations and analyzed for tritium and gamma emitters (flesh) and for strontium-89 and -90 (bones). Samples included spot, channel catfish, Atlantic croaker, white perch, summer flounder, brown bullhead, and weakfish. Gamma spectrometry of these samples indicated K-40 in all six samples at an average concentration of 3000 pCi/kg-wet with a range of 2700 to 3400 pCi/kg-wet. Cs-137 was noted in one sample at 14 pCi/kg-wet, with LLD sensitivities for the other five samples from <14 to <22 pCi/kg-wet. Ra-226 at 37 pCi/kg was detected in the second semi-annual sample from location 7El. All six bone samples analyzed for Sr-89 were below LLD of <64 to <270 pCi/kg-dry. All of the second semi-annual samples analyzed for Sr-90 had detectable concentrations ranging from 110 to 600 pCi/kg-dry with an average of 347 pCi/kg-dry. In 1982 the sr-90 concentration ranged from 50 to 210 pCi/kg-dry with an average of 120 pCi/kg-dry. The maximum level detected during the preoperational period was 940 pCi/kg-dry. Tritium analyses were performed on both aqueous and organic fractions of the flesh portions of these samples. Only one sample had detectable concentration of tritium for the aqueous 27
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fraction with a result of 84 pCi/L. Three -0f the six samples analyzed for the organic fraction of tritium showed detectable activity of 140 pCi/L at the outfall station: llAl, 220 pCi/L at the downstream station: 7El, and 400 pCi/L at the control station. These results probably cannot be attributed to plant operation since the closest indicator station had the lowest level of tritium in the organic fraction. Blue crab (Table C-29) Blue crab samples, collected semi-annually at two locations, were analyzed for gamma emitters, Sr-89 and -90, and tritium in the aqueous fraction. The shells were also analyzed for sr-89 and -90. A trace of Ra-226 in two samples and K-40 in all four samples were the only gamma emitters detected. K-40 levels ranged from 1800 to 3000 pCi/kg-wet with an average of 2400 pCi/kg-wet. Sr-89 was not detected in either the flesh or the shell. Insufficient sample size resulted in high LLD's for two analyses. Sr-90 was detected in two flesh and all four of the shell samples at concentrations of 25 to 35 pCi/kg-wet (flesh) and 250 to 570 pCi/kg-wet (shell). Preoperational average for the shell was 614 pCi/kg. Tritium activity in the aqueous fraction of the flesh was detected at levels of 180, 190, and 200 pCi/kg-wet in the first semi-annual samples with an average of 190 pCi/L This was also the average for the preoperational program. There was insuf-ficient sample for the second semi-annual analysis. Benthic Organisms and Sediment (Tables C-30, C-31) As required by the Technical Specifications, benthic organisms were separated from the bottom sediment and analyzed for sr-89 and -90, and gamma emitters. In one sample, Sr-90 was detected (250 pCi/kg-dry), along with the gamma emitters Mn-54, Ra-226, and Th-232. It should be noted that, due to the very small sample sizes for all samples (0.1 gram to 0.7 gram), satis-factory strontium sensitivities could not be achieved. The small sample size was also responsible for the extremely high 2-sigma uncertainties for the gamma emitters. The benthos samples,which consist of sediment and associated benthic organisms, were collected at the same locations as the benthic organisms and sample sizes are large enough to obtain more reliable results. Sediment was analyzed for sr-89 and -90, and gamma emitters. The sensitivity requirements of the Salem Environmental Technical Specifications were met. 30
Levels of Sr-89 were below LLD (<23 to <46 pCi/kg-dry) in all eight samples analyzed. Results of gamma spectrometry indicated the presence of naturally-occurring Ra-226 and Th232 at expected levels. Co-60 was detected in three of the samples at levels ranging from 48 to 83 pCi/kg-dry with an average of 63 pCi/kg-dry. Co-60 LLD's for the others were from <44 to <88 pCi/kg-dry. Cs-137 was seen at concentrations from 35 to 160 pCi/kg-dry in four samples. PROGRAM DEVIATIONS In June the entire dairy herd at milk control Station 3Gl was replaced. An alternate location, 3G2, in the same sector supplied the control milk samples from the second collection in June through through the second sampling period in August. Sampling was resumed at Station 3Gl with the first milk collection in September. The second semi-annual collection of muskrat samples was not obtained. Muskrats are normally trapped during November and December each year. However, in 1983, because of weather conditions and the poor quality of the pelts, muskrats were not available from the trappers. CONCLUSIONS The Radiological Environmental Monitoring Program for Salem Generating station was conducted during 1983 in accordance with the SGS Environmental Technical Specifications. The objectives of the program were met during this period. The data collected assists in demonstrating that SGS Units One and Two were operated in compliance with Environmental Technical Specifications. From the results obtained, it can be concluded that the levels and fluctuations of radioactivity in environmental samples were as expected for an estuarine environment. Ambient radiation levels were relatively low, averaging about 6.2 mrad/std. month. No other unusual radiological characteiistics were observed in the environs of Artifical Island. The operation of SGS Units #1 and #2 had no discernable effect on the radiological character-istics of the environs of Artifical Island. 31
REFERENCES (1) Radiation Management Corporation. "Salem Nuclear Generating Station - Radiological Environmental Monitoring Program - 1973". RMC-TR-74-09, 1974. (2) Radiation Management Corporation. "Artificial Island Radiological Environmental Monitoring Program - 1974 Annual Report". RMC-TR-75-04, 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) Public Service Electric and Gas Company. "Environmental Report, Operating License Stage - Salem Nuclear Generating Station Units 1 and 2". 1971. (13) United States Atomic Energy Commission. "Final Environmental Statement - Salem Nuclear Generating Station, Units 1 and 2". Docket No. 50-272 and 50-311, 1973. 32
REFERENCES (Cont.) (14) Public Service Electric and Gas Company. "Updated Final Safety Analysis Report - Salem Nuclear Generating Station, Units 1 and 2". 1982. (15) Public Service Electric and Gas Company. "Environmental Technical Specifications - Salem Nuclear Generating Station Units 1 and 2", Appendix B to Operating License DPR-70, 1976. (16) 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. (17) U. S. Environmental Protection Agency. "Prescribed Procedures for Measurement of Radioactivity in Drinking Water." EPA-600/4-80-032, August, 1980. (18) PSE&G Research Corporation, Research and Testing Laboratory. "Environ-mental Division Quality Assurance Manual." September, 1980. (19) PSE&G Research Corporation, Research and Testing Laboratory. "Environ-mental Division Procedures Manual." February, 1981. 33
APPENDIX A PROGRAM
SUMMARY
35
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272/-311 SALEM COUNTY, NEW JERSEY JANUARY 1, 1983 to DECEMBER 31, 1983 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Air Particulates Alpha 382 0.4 1.8 (280/330) 2S2 0.4 mi NNE 2.2 (49/52) 1.8 (40/52) 0 (lo-3 pei/m3) (0.5-14) (0.8-14) (0.9-4.1) Beta 416 3.0*** 24 (363/364) 252 0.4 mi NNE 26 (51/51) 23 (52/52) 0 (7. 7-70) (8.6-70) (5.9-49) Sr-89 32 0.2 <LLD <LLD <LLD 0 Sr-90 32 0.1 <LLD <LLD <LLD 0 Gamma Be-7 32 46 (28/28) 2S2 0.4 mi NNE 58 (4/4) 50 (4/4) 0 (27-69) (48-69) (40-60) w Co-60 32 0.3 0.6 (2/28) 2S2 0.4 mi NNE 0.7 (1/4) <LLD 0 -...J (0.6-0.7) (0. 7) Ra-226 32 0.6 0.6 (3/28) 16El 4.1 mi NNW 0.9 (1/4) <LLD 0 (0.3-0.9) (0.9) Th-232 30 1.0 0.0 (l/26) lFl 5.8 mi N 0.0 (1/4) <LLD 0 (0.8) (0.8) Air Iodine I-131 414 2.0 <LLD <LLD <LLD 0 110-3 pCi/m3) Precipitation Alpha 12 0.4 1.6 (4/12) 2F2 8.7 mi NNE 1.6 (4/12) No Control 0 (pCi/L) (0.5-4.6) (0.5-4.6) Location Beta 12 1.4 5.2 (10/12) 2F2 8.7 mi NNE 5.2 (10/12) No Control 0 (1.4-19) (1.4-19) Location H-3 12 120 190 (1/12) 2F2 8.7 mi NNE 190 (1/12) No Control 0 (190) (190) Location Sr-89 2 0.3 <LLD <LLD No Control 0 Location Sr-90 2 0.2 <LLD <LLD No Control 0 Location Gamma Be-7 4 38 (4/4) 2F2 8.7 mi NNE 38 (4/4) No Control 0 115-63) (15-63) Location
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM NUCLEAR GENERATING STATION DOCKET NO, 50-272/-311 SALEM COUNTY, NEW JERSEY JANUARY 1, 1983 to DECEMBER 31, 1983 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Direct Radiation Gamma 294 (mrad/std. month) Dose (monthly) 6.1 (252/252) 3H3 110 mi NE 6. 9 (12/12) 6. 7 (42/42) 0 (3, 7-12.1) (5. 7-9. 5) (5.1-9.5) Gamma 166 Dose (qtrly.) 5. 3 (140/140) 1G3 19 mi N 6.4 (4/4) 6. 0 (26/26) 0 (3. 5-8.1) (5.9-6.8) (5. 3-7.1) Milk I-131 143 0.06 <LLD <LLD <LLD 0 (pCi/L) Sr-89 72 1.0 <LLD <LLD <~LD 0 w Sr-90 72 2. 7 (60/60) 5F2 7.0 mi E 4.2 (12/12) 3.3 (12/12) 0 CX> (0.8-5.9) (2. 7-5. 9) (2.2-4.2) Gamma K-40 72 1358 (60/60) 2F4 6.3 mi NNE 1392 (12/12) 1300 (12/12) 0 (1100-1600) (1100-1600) (1000-1400) Co-60 72 1.3 5.5 (l/60) 15Fl 5.4 mi NW 5. 5 (1/12) <LLD 0 (5,5) (5.5) Cs-137 72 1.0 2.1 (19/60) 13E3 4.9 mi W 2.4 (5/12) 1. 4 (2/12) 0 (l.1-4. 7) (1.2-4. 7) (1.2-1. 7) Ce-141 72 1.4 2.4 (l/60) 14Fl 5.5 mi WNW 2.4 (1/12) <LLD 0 (2.4) (2.4) Th-232 66 3.0 8.1 (l/55) 5F2 7.0 mi E 8.1 (1/11) <LLD 0 (8.1) (8.1) Well Water Alpha 36 0.2 1. 2 (7/24) 5Dl 3.5 mi E 1.2 (4/12) <LLD 0 (pCi/L) (O. 4-2,l) (0, 4-2.1) Beta 36 1. O*** 13 (24/24) 5Dl 3.5 mi E 13 (12/12) 10 (12/12) 0 (7. 9-16) (7. 9-16) (7.6-14) K-40 36 15 (24/24) 4Sl 1400ft ENE 16 (12/12) 11 (12/12) 0 (9.0-27) (9.0-27) (7. 2-16) H-3 36 120 <LLD 3El 4.1 mi NE 430 (1/12) 430 (l/12) 0 (430) (430) Sr-89 12 0.5 <LLD <LLD <LLD 0 Sr-90 12 0.4 <LLD <LLD <LLD 0 Gamma K-40 12 7.8 23 (4/8) 5Dl 3.5 mi E 31 (2/4) <LLD 0 (14-46) (16-46)
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272/-311 SALEM COUNTY, m.w JERSEY JANUARY 1, 1983 to DECEMBER 31, 1983 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Potable Water Alpha 24 0.5 1.4 (12/24) 2F3 e.o mi NNE 1.4 (12/24) No Control 0 Raw-Treated (0. 8-3 .1) (0.8-3.1) Location (pCi/L) Beta 24 1. O*** 2.6 (24/24) 2F3 8.0 mi NNE 2.6 (24/24) No Control 0 (1. 5-3.9) (1.5-3.9) Location K-40 24 2.8 (24/24) 2F3 8.0 mi NNE 2.8 (24/24) No Control 0 (1. 5-19) (1.5-19) Location H-3 24 120 178 (6/24) 2F3 8.0 mi NNE 178 (6/24) No Control 0 (140-220) (140-220) Location Sr-89 8 0.5 <LLD <LLD No Control 0 Location Sr-90 8 0.4 0.6 (1/8) 2F3 8.0 mi NNE 0.6 (1/8) No Control 0 w (0.6) (0.6) Location l.O Gamma 8 <LLD <LLD No Control 0 Location Fruit & Vegetables Sr-89 15 20 <LLD <LLD <LLD 0 (pCi/kg-wet) Sr-90 15 10 31 (1/8) 1F3 5.9 mi N 31 (1/2) 18 (2/7) 0 (31) (31) (17-19) Gamma K-40 15 1975 (8/8) 2El 4.4 mi NNE 2400 (1/1) 2086 (7/7) 0 (1300-2400) (2400) (1400-3100) 5Fl 6.5 mi E .2400 (l/ll (2400) Ra-226 15 3.7 <LLD 3H4 BB mi NE 37 (1/4) 37 (1/71 0 (37) (37) Th-232 15 6.7 39 (1/8) lGl 10.3 mi N 41 (1/3) 41 (1/7) 0 (39) (41) (41) Game Sr-89 2 36 <LLD <LLD <LLD 0 (pCi/kg-dry) (bones) Sr-90 2 29 47 (1/1) 3El 4.1 mi NE 47 (1/11 <LLD 0 (bones) (47) (47) (pCi/kg-wet) Gamma (flesh) K-40 2 3000 (1/11 3El 4.1 mi NE 3000 (1/1) 2700 (1/1) 0 (3000) (3000) (2700)
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272/-311 SALEM COUNTY, NEW JERSEY JANUARY 1, 1983 to DECEMBER 31, 1983 ANALYSIS AND LOWER NUMBER OF MEDitn~ OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEJ\NAA NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Beef Gamma (pCi/kg-wet) K-40 2 2700 (1/1) 3El 4.1 mi NE 2700 (1/1) 2300 (1/1) 0 (2700) (2700) (2300) Bovine Thyroid Gamma (pCi/kg-wet) K-40 2 1200 (1/1) 14Fl 5.5 mi WNW 1900 (1/1) 1900 (1/1) 0 (1200) (1900) (1900) ""'0 Fodder Crops (pCi/kg-wet) Gamma Be-7 11 140 290 (6/9) 5F2 7.0 mi E 590 (l/l) 415 (2/2) 0 (32-590) (590) (290-540) K-40 11 5924 (9/9) 3El 4.1 mi NE 10233 (3/3) 9100 (2/2) 0 (400-14000) (3700-14000) (4200-14000) Co-60 11 2.3 <LLD 3Gl 17 mi NE 46 (1/2) 46 (1/2) 0 (46) (46) Zr-95 11 4.0 <LLD 3Gl 17 mi NE 92 (1/2) 92 (1/2) 0 (92) (92) Ra-226 11 4.2 50 (2/9) 5F2 7.0 mi E 59 (1/1) <LLD 0 (40-59) (59) Th-232 11 7.0 113 (2/9) lSFl 5.4 mi NW 117 (1/3) <LLD 0 (113) (117) Soil Sr-90 15 125 (13/13) 15Fl 5.4 mi NW 260 (1/1) 185 (2/21 0 (pCi/kg-dry) (46-260) (260) (120-250) Gamma K-40 15 8069 ( 13/13) 14Fl 5.5 mi WNW 13000 (1/1) 8850 (2/2) 0 (3800-13000) (13000) (8600-9100) Cs-137 15 440 (13/13) lFl 5.8 mi N 1600 (1/1) 615 (2/2) 0 (120-1600) (1600) (320-910) Ra-226 15 1055 (13/13) 16El 4.1 mi NNW 2600 (1/1) 2100 (2/2) 0 (390-2600) (2600) (2000-2200) Th-232 15 718 (13/13) 16El 4.1 mi NNW 1200 (1/1) 855 (2/2) 0 (340-1200) (1200) (810-900) 15Fl 5.4 mi NW 1200 (1/1) (1200)
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272/-311 SALEM COUNTY, NEW JERSEY JANUARY 1, 1983 to DECEMBER 31, 1983 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Surf ace Water Alpha 60 0.2 0. 6 (5/48) 1F2 7.1 mi N 1.0 (2/12) <LLD 0 (pCi/L) (0.2-1. 7) (0. 4-1. 7) Beta 60 4.0*** 46 (48/48) 7El 4.5 mi SE 63 (12/12) 37 (12/12) 0 (4.1-120) (9.7-120) (9.9-86) H-3 60 120 323 (18/48) llAl 0.2 mi SW 418 (6/12) 227 (6/12) 0 (160-1260) (160-1260) (160-450) Sr-89 20 0.5 <LLD <LLD <LLD 0 Sr-90 20 0.4 <LLD <LLD <LLD 0 Gamma K-40 60 8.6 60 (37/48) 7El 4.5 mi SE 73 (11/12) 44 (11/12) 0 (14-120) (16-120) (10-92) .i::.. Co-58 60 0.4 1.4 (2/48) llAl 0.2 mi SW 1.4 (2/12) <LLD 0 I-' (0.8-2.1) (0.8-2.1) Co-60 60 0.4 0.9 (2/48) 1F2 7.1 mi N 1.3 (1/12) <LLD 0 (0.5-1.3) (1.3) Mo-99 30 27 120 (1/24) llAl 0.2 mi SW 120 (1/6) <LLD 0 (120) (120) La-140 60 0.7 <LLD 12Cl 2.5 mi WSW 1.3 (1/12) 1.3 (1/12) 0 (1.3) (1.3) Ra-226 60 0.9 0.9 (1/48) 16Fl 6.9 mi NNW 0.9 (1/12) <LLD 0 (0.9) (0.9) Th-232 60 0.8 1. 6 (1/48) 7El 4.5 mi SE 1. 6 (1/12) <LLD 0 (1.6) (1.6) Edible Fish H-3 6 110 84 (1/4) llAl 0.2 mi SW 84 (1/2) <LLD 0 (pCi/L) (aqueous) (84) (84) H-3 6 120 180 (2/4) 12Cl 2.5 mi WSW 400 (1/2) 400 (1/2) 0 (organic) (140-220) (400) (400) (pCi/kg-dry) Sr-89 6 64 <LLD <LLD <LLD 0 (bones) Sr-90 6 26 355 (2/4) llAl 0.2 mi SW 600 (1/2) 330 (1/2) 0 (bones) (110-600) (600) (330)
.(pCi/kg-wet) Gamma Na-22 3 15 25 (1/2) 7El 4.5 mi SE 25 (1/1) <LLD 0 (25) (25)
K-40 6 3075 (4/4) 7El 4.5 mi SE 3100 (2/2) 2700 (2/2) 0 (2800-3400) (2800-3400) (2700-2700) Cs-137 6 13 14 (1/4) llAl 0.2 mi SW 14 (1/2) <LLD 0 (14) (14) Ra-226 6 18 37 (1/4) 7El 4.5 mi SE 37 (1/2) <LLD 0 (37) (37)
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272/-311 SALEM COUNTY, NEW JERSEY JANUARY 1, 1983 to DECEMBER 31, 1983 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEANU NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Blue Crabs H-3 2 200 (1/1) llAl 0.2 mi SW 200 (1/1) 180 (1/1) 0 (pCi/L) (flesh) (200) (200) (180) (pCi/kg-dry) Sr-89 4 110 <LLD <LLD <LLD 0 (shells) Sr-90 4 385 (2/2) 12Cl 2.Sml WSW 555 (2/2) 555 (2/2) 0 (shells) (250-520) (540-570) (540-570) ~ ('\,) Blue Crabs Sr-89 4 46 <LLD <LLD <LLD 0 (pCi/kg-wet) (flesh) Sr--90 4 19 35 (1/2) llAl 0.2 mi SW 35 (1/2) 25 (1/2) 0 (flesh) (35) (35) (25) Gamma K-40 4 2200 (2/2) 12Cl 2.5 mi WSW 2500 (2/2) 2500 (2/2) 0 (1800-2600) (2000-3000) (2000-3000) Ra-226 4 63 47 (1/2) 12Cl 2.5ml WSW 52 (1/2) 52 (1/2) 0 (47) (52) (52) Benthic Organisms Sr-89 8 1300 <LLD <LLD <LLD 0 (pCi/kg-dry) Sr-90 8 300 250 (1/6) llAl 0.2 mi SW 250 (1/2) <LLD 0 (250) (250) Gamma Mn-54 4 3700 34000 (1/3) 16Fl 6.9 mi NNW 34000 (1/1) <LLD 0 (34000) (34000) Ra-226 4 8600 15000 (1/3) llAl 0.2 mi SW 15000 (1/1) <LLD 0 (15000) (15000) Th-232 4 16000 11000 (1/3) 7El 4.5 mi SE 11000 (1/1) <LLD 0 (11000) (11000)
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272/-311 SALEM COUNTY, NEW JERSEY JANUARY 1, 1983 to DECEMBER 31, 1983 ANALYSIS AND LOWER MEDIUM OR PATHWAY TOTAL NUMBER NUMBER OF LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION SAMPLED NONROUTINE OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Sediment Sr-90 8 23 <LLD <LLD <LLD 0 (pCi/kg-dry) Gamma K-40 8 13050 (6/6) 16Fl 6.9 mi NNW 15500 (2/2) 15000 (2/2) 0 (8300-16000) (15000-16000) (14000-16000) Co-58 8 44 44 (1/6) 16Fl 6.9 mi NNW 44 (1/2) <LLD 0 (44) (44) Co-60 8 36 63 (3/6) llAl 0.2 mi SW 70 (2/2) <LLD 0 (48/83) (58-83) Cs-137 8 31 120 (3/6) llAl 0.2 mi SW 130 (2/2) 35 (1/2) 0 ii::. (100-160) (100-160) (35) w Ra-226 8 922 (6/6) 16Fl 6.9 mi NNW 1085 (2/2) 690 (2/2) 0 (570-1600) (570-1600) (690-690) Th-232 8 875 (6/6) 16Fl 6.9 mi NNW 985 (2/2) 970 (2/2) 0 (590-1000) (970-1000) (840-1100)
- LLD listed is the lowest calculated LLD during the reporting period.
** Mean calculated using values above LLD only. Fraction of measurements above LLD are in parentheses.
*** Typical LLD value.
APPENDIX B SAMPLE DESIGNATION AND LOCATIONS 45
APPENDIX B Sample Designation The PSE&G Research Corporation identifies samples by a three part code. The first two letters are the power station identification code, in this case "SA". The next three letters are for the media sampled. AIO = Air Iodine 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 RWA = Rain Water ESS = Sediment SOL = Soil FPB = Beef SWA = Surface Water FPV = Food Products, Various THB = Bovine Thyroid FPG = Grains VGT = Fodder Crops; Vegetation FPL = Green Leafy Vegetables WWA = Well Water GAM = Game The last four symbols are a location code based on direction and distance from the site. Of these, the first two represent each of the sixteen angular sectors of 22.5 degrees centered about the reactor site. Sector one is divided evenly by the north axis and other sectors are numbered in a clock-wise direction; i.e., 2=NNE, 3=NE, 4=ENE, etc. The next digit is a letter which represents the radial distance from the plant: s = On-site location E = 4-5 miles off-site A = 0-1 miles off-site F = 5-10 miles off-site B = 1-2 miles off-site G = 10-20 miles off-site c = 2-3 miles off-site H = >20 miles off-s-ite D -. 3-4 miles off-site The last number is the station numerical designation within each sector and zone; e.g., 1,2,3,o** For example, the designation SA-WWA-5Dl would indicate a sample in the SNGS program (SA) , consisting of well water (WWA) , which had been collected in 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). The number 1 indicates that this is sampling station #1 in that particular sector. 47
Sampling Locations All 1983 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 4Sl 1400 ft. ENE of vent; Production well #5 WWA 5Sl 1.0 mi. E of vent; site access road AIO,APT,IDM 6Sl 0.2 mi. ESE of vent; observation bldg area SOL 6S2 0.2 mi. ESE of vent< observation bldg. IDM 7Sl 0.12 mi. SE of vent; station personnel gate IDM lOSl 0.14 mi. SSW of vent; site shoreline IDM llSl 0.09 mi. SW of vent; site shoreline IDM llAl 0.2 mi. SW of vent; outfall area ECH,ESB,ESF, ESS,SWA 12Cl 2.5 mi. WSW of vent; west bank of Delaware River ECH,ESB,ESF, ESS,SWA 4D2 3.7 mi. ENE of vent; Alloway Creek Neck Road IDM 5Dl 3.5 mi. E of vent; local farm AIO,APT,FPG, FPV, IDM,SOL,WWA lODl 3.9 mi. SSW of vent; Taylor's Bridge Spur AIO,APT,IDM,SOL llDl 3.5 mi. SW of vent GAM 14Dl 3.4 mi. WNW of vent; Bay View, Delaware IDM 2El 4.4 mi. NNE of vent; local farm FPV,IDM,SOL 3El 4.1 mi. NE of vent; local farm FPB,FPG,GAM,IDM, THB,WWA 7El 4.5 mi. SE of vent; 1 mi. W of Mad Horse Creek ESB,ESF,ESS,SWA 48
TABLE B-1 (cont'd) STATION CODE STATION LOCATION SAMPLE TYPES 9El 4.2 mi. S of vent IDM 11E2 5.0 mi. SW of vent IDM 12El 4.4 mi. WSW of vent; Thomas Landing IDM 13El 4.2 mi. w of vent; Diehl House Lab IDM 13E3 4.9 mi. w of vent; local farm MLK 16El 4.1 mi. NNW of vent; Port Penn APT,AIO,IDM,SOL lFl 5.8 mi. N of vent; Fort Elfsborg AIO,APT,IDM,SOL 1F2 7.1 mi. N of vent; midpoint of Delaware River SWA 1F3 5.9 mi. N of vent; local farm FPL,FPV 2Fl 5.0 mi. NNE of vent; local farm SOL 2F2 8.7 mi. NNE of vent; Salem Substation AIO,APT,IDM, RWA,SOL 2F3 8.0 mi. NNE of vent; Salem Water Company PWR,PWT 2F4 6.3 mi. NNE of vent; local farm MLK,SOL,VGT 2F5 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 5Fl 6.5 mi. E of vent FPV, IDM, SOL 5F2 7.0 mi. E of vent; local farm MLK,SOL,VGT 6Fl 6.4 mi. ESE of vent; Stow Neck Road IDM 7F2 9.1 mi. SE of vent; Bayside, New Jersey IDM 10F2 5.8 mi. SSW of vent IDM llFl 6.2 mi. SW of vent; Taylor's Bridge Delaware IDM 49
TABLE B-1 (cont'd) STATION CODE STATION LOCATION SAMPLE TYPES 12Fl 9.4 mi. WSW of vent; Townsend Elementary School IDM 13Fl 9.8 mi. W of vent; Middletown, Delaware IDM 13F2 6.5 mi. W of vent; Odessa, Delaware IDM 13F3 9.3 mi. W of vent; Redding Middle School, IDM Middletown, DE 14Fl 5.5 mi. WNW of vent; local farm FPB,MLK,SOL,THB, VGT 14F2 6.6 mi. WNW of vent; Boyds Corner IDM 14F3 5.4 mi. WNW of vent1 local farm FPG,FPV 15Fl 5.4 mi. NW of vent; local farm FPG,MLK,SOL,VGT 15F3 5.4 mi. NW of vent IDM 16Fl 6.9 mi. NNW of vent; C&D Canal ESB,ESS,SWA 16F2 8.1 mi. NNW of vent; Delaware City Public School IDM lGl 10.3 mi. N of vent; local farm FPV lG3 19 mi. N of vent; Wilmington, Delaware IDM 3Gl 17 mi. NE of vent; local farm FPG,IDM,MLK,SOL, VGT 3G2 14 mi. NE of vent; local farm MLK lOGl 12 mi. SSW of vent; Smyrna, Delaware IDM 16Gl 15 mi. NNW of vent; Greater Wilmington Airport IDM 2Hl 34 mi. NNE of vent; RMC, Phila. IDM 3Hl 32 mi. NE of vent; National Park, N.J. IDM 3H3 110 mi. NE of vent; Research and Testing AIO,APT,IDM,SOL Laboratory 3H4 88 mi. NE of vent; local farm FPG,FPV 50
MAP B-1 ON SITE SAM Pl ING LOCATIONS ARTIFICIAL ISLAND 0 I i E I SCALE OF /AILIS 51
MAP 8-2 OFF-SITE SAMPLING LOCATIONS ARTIFICIAL ISLAND
!OFZ 0
* ..I H- H '1 ,
ICAU Of MILll UIG'I 52
APPENDIX C 1983 DATA TABLES 53
DATA TABLES Appendix C presents the analytical results of the 1983 Artificial Island Radiological Environmental Monitoring Program for the period of January 1 to December 31, 1983. TABLE NO. TABLE OF CONTENTS PAGE ATMOSPHERIC ENVIRONMENT AIR PARTICULATES C-1 1983 Concentrations of Gross Alpha Emitters ******************** 58 C-2 1983 Concentrations of Gross Beta Emitters ********************* 60 C-3 1983 Concentrations of Strontium-89 and -90 and Gamma Emitters in Quarterly Composites...................................... 62 AIR IODINE C-4 1983 Concentrations of Iodine-131 ****************************** 64 DATES C-5 1983 Sampling Dates for Air Samples **************************** 66 PRECIPITATION C-6 1983 Concentrations of Gross Alpha and Gross Beta Emitters and Tritium****************************a************"************* 71 C-7 1983 Concentrations of Strontium-89 and -90 and Gamma Emitters in Quarterly Composites *** 00000*&*******0******************** 72 DIRECT RADIATION C-8 1983 Quarterly TLD Results ************************************* 73 C-9 1983 Monthly TLD Results *************************************** 74 55
DATA TABLES (Cont.) TABLE NO. TABLE OF CONTENTS PAGE TERRESTRIAL ENVIRONMENT MILK C-10 1983 Concentrations of Iodine-131 ***** .' ************************ 76 C-11 1983 Concentrations of Strontium-89 and -90 ******************** 77 C-12 1983 Concentrations of Gamma Emitters ************************** 78 C-13 1983 Sampling Dates for Milk Samples *************************** 80 WELL WATER C-14 1983 Concentrations of Gross Alpha and Gross Beta Emitters; Potassiurn-40 and Tritium. o o Clo., o e . e *
- o *
- o * * * * " ** * * * * * * * * * * * * * *
- 82 C-15 1983 Concentrations of Strontium-89 and -90 and Gamma Emitters POTABLE WATER C-16 1983 Concentrations of Gross Alpha and Gross Beta Emitters; Potassium-40 and Tritium *. o *** o. c:i. o ******* " c ******** * -.-.-~.--;;... 85 C-17 1983 Concentrations of Strontium-89 and -90 and Gamma Emitters in Quarterly Compositese************eeoo****o***ooo**e**o**** 86 FOOD PRODUCTS C-18 1983 Concentrations of Strontium-89 and -90 and Gamma Emitters in Vegetables * .. o * * * * * * * ., * * * * * * * * * * * * * * * * * * * ., * * * * * * * * * * * * * * *
- 87 C-19 1983 Concentrations of Strontium-89 and -90 and Gamma Emitters in Game, Meat and Bovine Thyroid.............................. 88 FODDER CROPS C-20 1983 Concentrations of Gamma Emitters ************************** 89 SOIL C-21 1983 Concentrations of Strontium-90 and Gamma Emitters *** ******* 90 56
DATA TABLES (Cont.) TABLE NO. TABLE OF CONTENTS PAGE AQUATIC ENVIRONMENT SURFACE WATER C-22 1983 Concentrations of Gross Alpha Emitters ******************** 91 C-23 1983 Concentrations of Gross Beta Emitters ...................... 92 C-24 1983 Concentrations of Tritiumc. o * *
- o .. "'e. Cl ... o ****************** 93 C-25 1983 Concentrations of Gamma Emitterso. Cl 0 0. c ** Cl. 0 e ** Cl. 0 II. 0. 0 ** Cl 94 C-26 1983 Concentrations of Strontium-89 and -9Q*****e*****O******** 96 EDIBLE FISH C-27 1983 Concentrations of Strontium-89 and -90 and Tritium ******** 97 C-28 1983 Concentrations of° Gamma Emitters .......................... 98 BLUE CRABS C-29 1983 Concentrations of Strontium-89 and 90; Gamma Emitters and Tritium**************o*************************************** 99 BENTHIC ORGANISMS C-30 1983 Concentrations of Strontium-89 and -90 and Gamma Emitters 100 SEDIMENT C-31 1983 Concentrations.of Strontium-90 and Gamma Emitters ********* 101 SPECIAL TABLES LLDs C-32 Radiation Management Corporation LLDs for Gamma Spectrometry *** 102 C-33 1983 PSE&G Research Corporation LLDs for Gamma Spectrometry **** 104 57
TABLE C-1 1983 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN AIR PARTICULATES Results in Units of io-3 pCi/m3 +/- 2 sigma (Results by PSE&G Research Corporation) STATION NO. MONTH* SA-APT-2S2 SA-APT-5Sl SA-APT-5Dl SA-APT-lODl SA-APT-16El SA-APT-lFl SA-APT-2F2 SA-APT-3H3 AVERAGE ( contrnl) JANUARY 2.2+/-0.8 1.5+/-0.7 <0.8 0.9+/-0.7 2.2+/-1.0 1.7+/-0.8 1.2+/-0.7 1.7+/-0.8 1. 5+/-1.1 1.5+/-0.6 1.0+/-0 .6 1. 6+/-0. 7 1.0+/-0 .5 1.2+/-0.6 0.9+/-0.5 1.6+/-0. 7 <0.7 1.2+/-0. 7 1.5+/-0.6 1.5+/-0.6 1.3+/-0.6 0.9+/-0.6 0.8+/-0.6 1.5+/-0. 7 0.9+/-0.6 1.0+/-0.6 1.2+/-0.6 1.9+/-0. 7 1.2+/-0.7 0.9+/-0.6 <0.6 1.2+/-0.6 0.9+/-0.6' <0.7 <0.8 1.0+/-0.8 3.5+/-1.8 1.2+/-0.6 <0.7 1.0+/-0,6 0.7+/-0.6 1.2+/-0.7 <0.7 <0.8 1.2+/-1.9 FEBRUARY 1.3+/-0.5 0.5+/-0.4 0.6+/-0.4 1.0+/-0.5 0.8+/-0.5 1.0+/-0.5 1.3+/-0.6 1. 2+/-1. 0 1.0+/-0.6 Ul 0.9+/-0.5 0.9+/-0.5 1.1+/-0.6 <0.6 1.0+/-0.6 1.1+/-0.6 0.9+/-0.6 1.1+/-0.6 1.0+/-0.3 00 1.3+/-0.5 2.0+/-0.7 1.3+/-0.6 2.1+/-0.6 1.4+/-0.6 1.4+/-0.6 2.1+/-0.7 1.2+/-0.6 1.6+/-0.8 1.8+/-0.7 <0.7 <0.8 0.7+/-0.5 0.9+/-0.6 0.8+/-0.6 1.3+/-0. 7 <0.9 1.0+/-0.8 MARCH 1.4+/-0. 7 1.6+/-0.7 1.3+/-0.7 <0.8 <0.8 0.8+/-0.6 1.7+/-0.8 <0.7 1.1+/-0.8
<0.6 <0.5 <0.6 0.6+/-0.4 0.8+/-0.5 <0.7 0.7+/-0.5 <0.6
<0.8 <0.7 <0.7 <0.7 <0.8 <0.7 <0.7 <0.7 1.2+/-0.6 0.8+/-0.5 1.4+/-0.6 0.8+/-0.5 0.9+/-0.5 1.4+/-0.6 1.0+/-0.5 1.0+/-0.6 1.1+/-0.5 APRIL 1.5+/-0.6 1.4+/-0.6 1.4+/-0.6 0.8+/-0.5 1.4+/-0.6 1.4+/-0.6 1.3+/-0.6 2.0+/-1.0 1.4+/-0 .6 0.8+/-0.5 <0.4 <0.5 0.7+/-0.4 0.9+/-0.5 0.6+/-0.5 1.0+/-0.5 <0.5 0.7+/-0.4 0.8+/-0.5 <0.6 0.7+/-0.5 1.2+/-0.6 <0.7 <0.6 <0.6 <0.6
<0.8 0.9+/-0.6 1.3+/-0.7 1.0+/-0.6 <0.7 1.3+/-0.7 1.0+/-0.6 0.9+/-0.6 1.0+/-0.4 1.6+/-0.6 1.8+/-0.6 2.2+/-0.7 2.2+/-0.7 2.2+/-0.7 1.3+/-0.5 2.0+/-0.7 1.8+/-0. 7 1.9+/-0.6 MAY 1.0+/-0.6 0.7+/-0.5 <0.7 1.4+/-0.6 1.2+/-0.6 0.8+/-0.6 1.2+/-0.6 <0.7 1.0+/-0.6 1.9+/-0.8 1.3+/-0.7 0.9+/-0.7 <0.9 1.5+/-0.8 <0.8 <0.8 <0.9 1.1+/-0.8 1.6+/-0 .6 <0.4 <0.5 0.7+/-0.4 0.8+/-0.5 <0.5 0.9+/-0.5 1.3+/-0.6 0.8+/-0.8 14+/-1lll) 1.0+/-0.4 1.3+/-0.5 1.2+/-0.4 1.2+/-0.5 1.1+/-0.4 1.1+/-0.5 1.0+/-0.5 2.7+/-9.1 JUNE 1.9+/-0.9 1.1+/-0.6 0.9+/-0.7 <0.8 1.1+/-0.9 1.0+/-0.7 <0.8 1. 2+/-0. 7 1.1+/-0.7 (2) ( 2) ( 2) ( 2) 2.0+/-0.9 ( 2) ( 2) 1.5+/-0.8 (2) ( 2) ( 2) ( 2) 3,9+/-1.4 ( 2) (2) 2.6+/-1.l
( 2) (2) ( 2) ( 2) 2.9+/-0.8 ( 2) ( 2) 2.3+/-0.8
TABLE C-1 (cont'd) 1983 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN AIR PARTICULATES Results in Units of 10-3 pCi/m3 +/- 2 sigma (Results by PSE&G Research Corporation) STATION NO. MONTH* SA-APT-2S2 SA-APT-5Sl SA-APT-5Dl** SA-APT-lODl SA-APT-16El SA-APT-lFl SA-APT-2F2 SA-APT-3H3 AVERAGE (Control) JULY (2) ( 2) ( 3) (2) <0.9 ( 2) ( 2) 1.0+/-0.6 1.9+/-0.8 1.3+/-0. 7 <3.0 3.4+/-1.0 6.0+/-1.3 1.2+/-0.7 0.9+/-0.7 0.9+/-0.7 2.3+/-3.5 2.3+/-0.9 2.2+/-0.9 <2.0 <3.2 1.5+/-1.1 <0.8 1.2+/-0.8 1.1+/-0.7 1. 8+/-1. 6 ( 2) ( 2) 1.4+/-1.2 ( 2) 1.8+/-0. 7 ( 2) ( 2) 2.3+/-0.9 ( 2) ( 2) <2.0 ( 2) 2.6+/-1.0 ( 2) ( 2) 4.1+/-1.1 AUGUST 2.0+/-0.7 1.4+/-0. 7 1. 5+/-1.2 1.4+/-0.7 1.5+/-0.7 1.4+/-0.7 1.2+/-0.6 1.4+/-0, 7 1.5+/-0.5 2.2+/-0.9 2 .5+/-1. 0 1. 6+/-1.3 2.4+/-1.1 3.3+/-1.l 3 .4+/-1.1 3.4+/-1.3 <1.1 2.5+/-1.7 2.6+/-0.8 2.7+/-0.9 1.9+/-1.5 2.4+/-0.7 2.5+/-0.8 2.5+/-0.8 2.6+/-0.9 2.6+/-0.9 2.5+/-0.5 2.6+/-0.9 1.9+/-0.8 3.7+/-1.8 2.7+/-0.9 3.1+/-1.0 1.7+/-0.8 2.6+/-0.9 1.8+/-0.8 2.5+/-1.4 Ul SEPTEMBER 2.1+/-0.1 2.1+/-0.7 1. 4+/-1.2 2.3+/-0.7 2.8+/-0.8 2.2+/-0.6 2.3+/-0.7 3.0+/-0.8 2.4+/-1.0 l.O 3.0+/-1.0 2.7+/-1.2 2.9+/-1.6 1.9+/-0.8 3.5+/-1.0 1.9+/-0.9 4 .1+/-1.3 1.6+/-0.9 2.7+/-1.7 1.8+/-0.7 1.9+/-0.8 1.7+/-1.4 1.1+/-0. 7 2.2+/-0.9 1.0+/-0.6 1.7+/-1.0 1.5+/-0.7 1.6+/-0.8 2.8+/-0.9 1.7+/-0.7 1. 5+/-1. 3 3.3+/-0.9 2.6+/-0.8 2.2+/-0.8 1.3+/-0.7 2.4+/-0.9 2.2+/-1.4 OCTOBER 1.6+/-0.7 2.1+/-0.8 <2.0 2.4+/-0.8 1.8+/-0.8 9.6+/-5,9(1) 2.6+/-0.9 1.8+/-0~7 3.0+/-5.4 3.3+/-0.8 2.6+/-0.8 3.4+/-1.8 2.6+/-0.8 3.0+/-0.8 3.7+/-1.1 2.7+/-0.8 2.4+/-0.9 3.0+/-0.9 1.6+/-0, 7 2.0+/-0.8 <1.0 1.1+/-0.6 1.1+/-0. 7 1.4+/-0.7 2.3+/-0.8 1.7+/-0.7 1.5+/-0.9 1.7+/-0.8 1.7+/-0.7 2.7+/-1.5 0.9+/-0.5 1.6+/-0.7 1.6+/-0.8 2.0+/-0.8 1.8+/-0.9 1. 8+/-1. 0 2.3+/-0.8 1.9+/-0.8 <l. 0 1.2+/-0.7 1.8+/-0.8 1.8+/-0.8 1.7+/-0.7 2.2+/-0.8 1. 7+/-0.9 NOVEMBER 2.3+/-0.9 1.3+/-0.7 1.1+/-0.9 1.8+/-0.8 2.0+/-0.8 1.6+/-1.0 1.4+/-0 .8 1. 7+/-0 .8 1.6+/-0 .8 2.2+/-0.8 1.0+/-0.6 1. 6+/-1.2 1.3+/-0.6 1.2+/-0.7 1.3+/-0.7 2.0+/-0.8 1.6+/-0. 7 1.5+/-0.8 1.2+/-0.8 1.2+/-0.7 2.0+/-1.4 <1.1 1. 8+/-1. 0 1.5+/-1.0 1.6+/-0.9 2.1+/-0.8 1.6+/-0.8 2.3+/-0.8 3.3+/-0.9 1.5+/-1.1 2.9+/-0.8 2.9+/-0.8 2.5+/-0.8 3.9+/-1.0 2.9+/-0.9 2.8+/-1.4 DECEMBER 1.5+/-0.7 2.1+/-0.7 1.2+/-1.0 1.5+/-0. 7 1.5+/-0.7 1.9+/-0.7 2.0+/-0.8 1.1+/-0.6 1.6+/-0.7 2.1+/-0.7 2.1+/-0.6 <4.0 1.6+/-0.6 1.8+/-0.6 1.5+/-0.6 2.1+/-0.8 1.9+/-0.7 2.1+/-1.6 1.9+/-1.0 1.7+/-0.8 1.4+/-1.2 1.6+/-1.0 1.7+/-1.0 1.6+/-0.9 <1.4 2.2+/-0.9 1.7+/-0.5 1.9+/-0.7 2.2+/-0.7 1.0+/-0.9 1.6+/-0.7 2.0+/-0.6 1.4+/-0.6 2.0+/-0.7 2.1+/-0.7 1.8+/-0.8 AVERAGE 2.1+/-3.8 1.5+/-1.4 1.5+/-1. 6 1. 5+/-1. 6 1.8+/-2.0 1.6+/-2.8 1.6+/-1.7 l. 5+/-1. 5 Grand Average 1.6+/-2.2
- Sampling dates can be found in Table C-5.
** Results by Teledyne Isotopes.
(1) High uncertainty due to low sample volume. (2) Not analyzed for gross alpha emitters. (3) Not analyzed by Teledyne Isotopes. _J
TABLE C-2 1983 CONCENTRATIONS OF GROSS BETA EMITTERS IN AIR PARTICULATES Results in Units of lo-3 pci/m3 +/- 2 sigma (Results by PSE&G Research Corporation) STATION NOo MONTH" SA-APT-2S2 SA-APT-5Sl SA-APT-5Dl SA-APT-lODl SA-APT-16El SA-APT-lFl SA-APT-2F2 SA-APT-3H3 AVERAGE (Control) JANUARY 32+/-3 27+/-3 27+/-3 28+/-3 25+/-3 30+/-3 28+/-3 28+/-3 28+/-4 25+/-2 22+/-2 22+/-3 16+/-2 17+/-2 20+/-2 22+/-2 22+/-3 21+/-6 18+/-2 14+/-2 14+/-2 16+/-2 14+/-2 13+/-2 12+/-2 13+/-2 14+/-4 18+/-2 14+/-2 17+/-2 14+/-2 15+/-2 15+/-2 15+/-2 20+/-3 16+/-4 70+/-7 22+/-2 24+/-2 24+/-2 21+/-2 23+/-2 24+/-2 23+/-3 29+/-33 FEBRUARY 21+/-2 19+/-2 21+/-2 19+/-2 19+/-2 20+/-2 23+/-2 25+/-5 21+/-4 0\ 26+/-2 23+/-2 25+/-3 25+/-2 26+/-2 23+/-2 25+/-2 23+/-2 24+/-3 0 25+/-2 22+/-2 23+/-2 20+/-2 21+/-2 22+/-2 25+/-2 25+/-2 23+/-4 22+/-2 21+/-2 23+/-2 19+/-2 20+/-2 21+/-2 22+/-2 25+/-3 22+/-4 MARCH 20+/-3 18+/-2 18+/-3 18+/-3 17+/-3 16+/-2 18+/-3 20+/-3 18+/-3 8.6+/-1.9 9.1+/-1.9 8.8+/-2.0 9.6+/-1.8 12+/-2 9.3+/-2.2 900+/-2,0 5.9+/-1.9 9.0+/-3.3 14+/-2 9.2+/-1.9 10+/-2 7.7+/-2.0 9.0+/-2.1 11+/-2 9.1+/-2.1 11+/-2 10+/-4 24+/-2 19+/-2 18+/-2 16+/-2. 17+/-2 21+/-2 20+/-2 22+/-2 20+/-5 APRIL 25+/-2 22+/-2 26+/-3 25+/-2 25+/-3 23+/-2 25+/-3 43+/-5 27+/-13 11+/-2 11+/-2 11+/-2 8.9+/-1. 7 9.1+/-2.0 11+/-2 10+/-2 10+/-2 10+/-2 12+/-2 12+/-2 13+/-2 12+/-2 14+/-2 11+/-2 13+/-2 9.9+/-2.1 12+/-2 21+/-2 19+/-2 19+/-2 19+/-2 21+/-2 20+/-2 20+/-2 19+/-2 20+/-2 37+/-3 31+/-3 33+/-3 38+/-3 35+/-3 36+/-3 34+/-3 32+/-3 34+/-5 MAY 25+/-3 20+/-2 20+/-3 20+/-2 21+/-2 19+/-3 22+/-3 20+/-3 21+/-4 21+/-2 19+/-2 21+/-2 17+/-2 18+/-2 20+/-2 18+/-2 14+/-2 18+/-5 17+/-2 12+/-2 13+/-2 13+/-2 15+/-2 12+/-2 14+/-2 18+/-2 14+/-4
<75(1) 11+/-2 12+/-2 11+/-2 12+/-2 12+/-2 14+/-2 11+/-2 12+/-2 JUNE 20+/-3 19+/-3 20 3 17+/-3 21+/-4 17+/-3 21+/-3 17+/-3 19+/-4 28+/-3 26+/-2 23 3 30+/-2 38+/-3 29+/-3 33+/-3 28+/-3 29+/-8 54+/-8 42+/-7 40 7 39+/-7 48+/-9 48+/-7 36+/-7 49+/-8 44+/-12 29+/-6 33+/-5 30 5 33+/-5 27+/-5 26+/-5 35+/-6 31+/-6 30+/-6
TABLE C-2 (cont'd) 1983 CONCENTRATIONS OF GROSS BETA EMITTERS IN AIR PARTICULATES Results in Units of lo-3 pci/m3 +/- 2 sigma (Results by PSE&G Research Corporation) STATION NO. MONTH* SA-APT-2S2 SA-APT-5Sl SA-APT-5Dl** SA-APT-lODl SA-APT-16El SA-APT-lFl SA-APT-2F2 SA-APT-3H3 AVERAGE (Control) JULY 25+/-3 20+/-2 19+/-3 21+/-3 22+/-3 21+/-3 24+/-3 27+/-3 22+/-5 26+/-3 22+/-3 20+/-4 30+/-3 31+/-3 21+/-3 22+/-3 20+/-3 24+/-9 39+/-3 38+/-3 19+/-6 24+/-8 39+/-4 34+/-3 39+/-4 29+/-3 33+/-16 28+/-3 30+/-4 22+/-3 27+/-2 22+/-3 28+/-3 28+/-3 25+/-3 26+/-6 33+/-3 34+/-3 32+/-5 27+/-3 32+/-3 30+/-3 32+/-3 26+/-3 31+/-6 AUGUST 26+/-3 23+/-3 21+/-3 21+/-2 24+/-3 22+/-2 25+/-3 22+/-3 23+/-4 28+/-3 26+/-3 23+/-3 20+/-3 26+/-3 25+/-3 24+/-3 20+/-3 24+/-6 34+/-3 38+/-3 49+/-3 30+/-2 32+/-3 32+/-3 40+/-3 36+/-3 36+/-12 26+/-3 24+/-3 29+/-3 22+/-3 29+/-3 25+/-3 29+/-3 25+/-3 26+/-5 SEPTEMBER 27+/-2 26+/-3 28+/-3 25+/-2 28+/-3 26+/-2 30+/-3 34+/-3 28+/-6 37+/-3 37+/-4 32+/-4 30+/-3 35+/-3 37+/-4 41+/-4 31+/-4 35+/-7 29+/-3 29+/-3 28+/-4 26+/-3 28+/-3 24+/-2 24+/-4 21+/-3 26+/-6 34+/-3 28+/-3 33+/-4 31+/-3 35+/-3 32+/-3 31+/-3 33+/-3 32+/-4 OCTOBER 25+/-3 26+/-3 31+/-4 14+/-2 28+/-3 34+/-17(2) 27+/-3 22+/-3 26+/-12 33+/-3 33+/-3 37+/-4 30+/-3 31+/-2 33+/-4 31+/-3 35+/-3 33+/-4 14+/-3 13+/-3 16+/-3 10+/-3 11+/-3 15+/-3 14+/-3 12+/-3 13+/-4 20+/-3 21+/-2 23+/-3 16+/-2 21+/-2 22+/-3 22+/-3 23+/-3 21+/-4 16+/-2 18+/-2 16+/-3 17+/-2 19+/-3 18+/-3 14+/-2 14+/-2 16+/-4 NOVEMBER 15+/-2 15+/-2 16+/-3 13+/-3 13+/-2 13+/-3 15+/-3 11+/-2 14+/-3 21+/-2 20+/-2 24+/-3 22+/-2 20+/-2 22+/-2 22+/-2 24+/-2 22+/-3 21+/-3 19+/-3 27+/-4 20+/-3 24+/-3 21+/-3 22+/-3 25+/-3 22+/-5 36:!;3 36+/-3 35+/-4 34+/-3 35+/-3 33+/-3 41+/-3 34+/-3 36+/-5 DECEMBER 26+/-3 24+/-2 27+/-4 22+/-3 28+/-3 24+/-3 28+/-3 25+/-2 26+/-4 29+/-3 28+/-2 23+/-3 23+/-3 25+/-2 25+/-3 30+/-3 29+/-3 26+/-6 25+/-3 25+/-2 24+/-3 26+/-3 25+/-3 24+/-3 27+/-3 24+/-3 25+/-2 30+/-2 32+/-2 33+/-3 28+/-2 32+/-2 27+/-2 29+/-3 30+/-2 30+/-4 AVERAGE 26+/-20 23+/-16 23+/-16 22+/-15 24+/-17 23+/-16 24+/-16 23+/-17 Grand Average 24+/-17
- Sampling dates can be found in Table C-5.
** Results by Teledyne Isotopes.
(1) Result not included in any averages. High LLD due to low sample volume. (2) High uncertainty due to low sample volume.
TABLE C-3 1983 COijCENTRATIONS OF STRONTIUM-89* AND -90 AND GAMMA EMITTERS** IN QUARTERLY COMPOSITES OF AIR PARTICULATES Results in Units of 10-3 pCi/m3 +/- 2 sigma (Results by PSE&G Research Corporation) STATION NO. AND DATES Sr-89 Sr-90 Be-7 Co-60 Ra-226 Th-232 SA-APT-2S2 12-27-82 to 3-28-83 <0.2 <0.2 48+/-4 <0.4 <0.6 <l. 6 3-28-83 to 6-28-83 <0.5 <0.3 69+/-5 <0.5 <1.1 <1.3 6-28-83 to 9-26-83 <0.4 <0.3 69+/-5 0.7+/-0.3 <1.1 <l. 9 9-26-83 to 12-27-83 <0.3 <0.2 48+/-4 <0.4 <0.6 <1.2 SA-APT-5Sl O'I 12-27-82 to 3-28-83 <0.2 <0.2 35+/-4 <0.5 <0.9 <1.8 (\.) 3-28-83 to 6-28-83 <0.4 <0.2 46+/-4 <0.4 <0.9 <2.2 6-28-83 to 9-26-83 <0.4 <0.3 53+/-5 <0.7 <1.5 <3.0 9-26-83 to 12-27-83 <0.3 <0.2 40+/-4 <0.4 <0.9 <l. 5 SA-APT-5Dl 12-27-82 to 3-28-83 <0.3 <0.2 32+/-3 <0.5 <1.0 <1.2 3-28-83 to 6-28-83 <0.5 <0.3 48+/-4 <0.4 <1.2 <l. 6 7-05-83 to 9-26-83(1) <0.6 <0.3 69+/-16 <1.0 <10 ( 2) 9-26-83 to 12-27-83(1) <0.3 <0.1 57+/-7 <0.5 <8 ( 2) SA-APT-10Dl 12-28-82 to 3-29-83 <0.3 <0.2 28+/-4 <0.6 <1.2 <1.5 3-29-83 to 6-29-83 <0.4 <0.2 36+/-3 <0.4 <0.6 <1.1 6-29-83 to 9-27-83 <0.4 <0.3 32+/-3 <0.4 <0.7 <l. 3 9-27-83 to 12-27-83 <0.3 <0.2 38+/-4 <0.5 <0.9 <l. 9
TABLE C-3 (cont'd) 1983 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND GAMMA EMITTERS*~ IN QUARTERLY COMPOSITES OF AIR PARTICULATES Results in Units of l0-3 pCi/m3 +/- 2 sigma (Results by PSE&G Research Corporation) STATION NO. AND DATES sr-89 Sr-90 Be-7 Co-60 Ra-226 Th-232 SA-APT-16El 12-28-82 to 3-29-83 <0.3 <0.2 27+/-3 <0.3 <1.0 <1.6 3-29-83 to 6-29-83 <0.5 <0.3 42+/-5 <0.6 <1.0 <2.1 6-29-83 to 9-27-83 <0;4 <0.3 54+/-5 <0.6 0.9+/-0.5 <1.0 9-27-83 to 12-27-83 <0.3 <0.2 43+/-4 <0.4 <l. 0 <l. 7 SA-APT-lFl 12-27-82 to 3-28-83 <0.3 <0.2 33+/-3 <0.4 0.3+/-0.2 0.8+/-0.4 3-28-83 to 6-28-83 <0.6 <0.3 47+/-5 <0.6 <1.6 <2.2 6-28-83 to 9-26-83 <0.4 <0.3 43+/-4 <0.5 <1.0 °' w 9-26-83 to 12-27-83 <0.4 <0.2
<1.6 51+/-5 0.6+/-0.3 <1.1 <2.2 SA-APT-2F2 12-27-82 to 3-28-83 <0.2 <0.2 36+/-4 <0.6 0.6+/-0.4 <2.0 3-28-83 to 6-28-83 <0.5 <0.3 58+/-5 <0.5 <l. 3 <2.2 6-28-83 to 9-26-83 <0.4 <0.3 60+/-6 <0.7 <1.5 <LO 9-26-83 to 12-27-83 <0.3 <0.2 48+/-5 <0.6 <1.5 <2.2 SA-APT-3H3 (Control) 12-27-82 to 3-28-83 <0.3 <0.2 40+/-5 <0.6 <1.4 <2.2 3-28-83 to 6-28-83 <0.5 <0.3 60+/-5 <0.5 <1.5 <2.2 6-28-83 to 9-26-83 <0.4 <0.4 57+/-5 <0.4 <0.9 <2.0 9-26-83 to 12-27-83 <0.3 <0.2 43+/-4 <0.4 <0.9 <1.5 AVERAGE 46+/-23
- Strontium-89 results are corrected for decay to sample stop date.
** All other gamma emitters searched for were LLD; typical LLDs are given
( 1) Results by Teledyne Isotopes in Table C-33. ( 2) Not analyzed for Th-232
TABLE C-4 19a3 CONCENTRATIONS OF IODINE-131 IN FILTERED AIR Results in Units of lo-3 pCi/m3 Results* by Radiation Management Corporation STATION NO. MONTH**** SA-AI0-2S2 SA-AI0-5Sl SA-AI0-5Dl SA-AIO-lODl SA-AIO-l6El SA-AIO-lFl** SA-AI0-2F2 SA-AI0-3H3 (Control) JANUARY <13 <30 <36 < a.2 <41 <13 <la
<a6(1) <90(1) <95(1) <20
<7a(l) <42 < 9.3 <72(1) <77(1)
<46 <44 <4a <52 <4a <10 <43 <23
<3a <39 <3a <29 <16 < 9.4 <50 <57
<9a(l) <34 <42 <3a <39 <13 <40 <27 FEBRUARY <23 <24 <26 <27 <42 <10 <3a
<21 <15 <39
<33 <29 <2a <10 <31 <31
<13 <14 <10 <12 <12 < a.a <12 <12 O'I < 9.a < 8.6
,j:>.
<10 < 8.6 < 9.0 <10 <10 <14 MARCH <10 < 9.1 <11 <13 <12 <12 <12
< 8.8 <12
< 9.8 <11 < 8.4 < 8.3 <11 < 9.8 <12
<13 <10 <11 <12 <12 <14 <13
<12 <12
<13 <11 <11 <12 <11 <12 <14
*APRIL <12 <13 <12 <13 <12 <14 <13
<11 <27
<11 <11 <10 <13 <16 <13 <14
< 9.8 <11 <11 <11 <13 <12 <14 <15
<12 <10 <12 <10 <10 <13 <13 <10
<17 <18 <21 <20 <25 < 8.2 <22 <19 MAY <16 <15 <20 <15 <16 < 8.5 <la
<12 <18
<13 <14 <14 <15 < 8.0 <14 <11
<13 <12 <16 <12 <14 < 8.8 <16
<302(2) <10 <15
<11 < 9.5 <12 < 6.7 <12 <14 JUNE <18 <15 <17 <18 <24 <11 <19
<12 <12 <16
<14 <11 <15 < 8.6 <14 ( 3)
<14 <14 <16 <15 <18 < 8.8 <18 <17
<14 <11 <13 <10 <16 <14 <16 <18
TABLE C-4 (cont'd) 1983 CONCENTRATIONS OF IODINE-131 IN FILTERED AIR Results in Units of lo-3 pCi/m3 Results* by PSE&G Research Corporation STATION NO. MONTH**** SA-AI0-2S2 SA-AI0-5Sl SA-AI0-5Dl*** SA-AIO-lODl SA-AI0-16El SA-AIO-lFl SA-AI0-2F2 SA-AI0-3H3 (Control) JULY < 8.7 < 9.9 < 2.0 <12 <17 <14 <18 <12
< 7.4 < 9.4 <10 < 9.3 <14 <13 <16 <20
< 7.0 < 9.4 < 3.0 <28(4) <15 <11 <16 <14
< 6.1 <13 < 2.0 < 6.4 < 3.1 < 7.7 < 6.3 < 6.9
< 3.2 < 9.5 <10 < 7.7 < 5.7 < 3.7 < 7.1 < 4.3 AUGUS'J; < 7.8 < 6.2 < 3.0 <12 < 6.7 < 6.4 < 5.9 < 7.3
< 5.1 < 6.1 <30 < 6.2 < 5.5 < 6.4 < 8.5 < 9.0
< 3.9 < 4.8 <20 < 6.7 < 5.9 < 7.4 < 7.8 < 6.4
< 7.2 < 9.4 <30 < 6.8 < 9.3 < 5.8 < 5.9 < 6.7 SEPTEMBER < 5.3 < 8.2 <10 < 5.4 < 7.5 < 4.8 < 5.0 < 6.9
< 8.1 <10 <20 < 6.7 < 5.3 < 9.5 < 8.9 <12
°'Ul < 6.0 5.9
< 9.0
< 8.2
<60
<20 6.8 5.8 7.1 5.5
< 5.1
( 4) 8.7 9.0
< 5.1
< 5.6 OCTOBER < 8.6 < 9.4 <30 < 5.5 < 7.1 <99(2) < 8.4 < 7.4
< 6.9 < 4:7 <10 < 5.5 < 6.7 < 6.0 < 7.5 < 6.6
< 5.5 < 6.0 <30 < 8.1 <11 < 9.2 < 7.2 < 4.4
< 6.9 < 8.0 <20 < 6.7 < 5.6 < 5.9 < 8.0 < 9.4
< 7.5 < 4.6 <20 < 6.5 < 8.0 < 6.2 < 6.3 < 6.3 NOVEMBER < 6.9 < 6.1 <20 < 7.0 < 7.4 <11 < 6.8 < 6.0
< 7.1 < 7.7 <20 < 4.8 < 4.1 < 4.7 < 6.4 < 7.0
< 9.0 < 6.5 <20 <10 < 8.5 < 8.3 < 5.9 < 7.6
< 5.6 < 7.5 <20 < 3.7 < 5.2 < 5.5 < 7.2 < 5.9 DECEMBER < 6.5 < 6.2 <20 < 7.2 <10 < 6.2 <12 < 5.3
< 5.9 < 4.9 <40 < 6.5 < 3.8 < 6.1 < 9.3 < 4.2
< 5.8 < 4.9 <40 < 7.5 <10 < 5.9 <10 < 5.5
< 5.2 < 6.0 <20 < 5.6 < 6.5 < 4.1 < 6.6 < 3.9
- I-131 results are corrected for decay to sample stop date.
** Results by PSE&G Research Corporation.
*** Results by Teledyne Isotopes.
**** Sampling dates can be found in Table c-5.
(1) Does not meet sensitivity requirements. ( 2) High LLD due to low sample volume. ( 3) Data lost due to computer malfunction. ( 4) Sample lost.
TABLE C-5 1983 SAMPLING DATES FOR AIR SAMPLES STATION NO. MONTH 2S2 5Sl 501 1001 16El lFl 2F2 3H3 JANUARY 12-27-82 12-27-82 12-27-82 12-28-82 12-28-82 12-27-82 12-27-82 12-27-82 to to to to to to to to 1-03-83 1-03-83 1-03-83 1-03-83 1-03-83 1-03-83 1-03-83 1-03-83 1-03-83 1-03-83 1-03-83 1-03-83 1-03-83 1-03-83 1-03-83 1-03-83 to to to to to to to to 1-10-83 1-10-83 1-10-83 1-11-83 1-11-83 1-10-83 1-10-83 1-10-83 1-10-83 1-10-83 1-10-83 1-11-83 1-11-83 1-10-83 1-10-83 1-10-83 to to to to to to to to 1-17-83 1-17-83 1-17-83 1-17-83 1-17-83 1-17-83 1-17-83 1-17-83 1-17-83 1-17-83 1-17-83 1-17-83 1-17-83 1-17-83 1-17-83 1-17-83 to to to to to to to to 1-24--83 1-24-83 1-24-83 1-25-83 1-25-83 1-24-83 1-24-83 1-24-83 O'\ O'\ 1-24-83 1-24-83 1-24-83 1-25-83 1-25-83 1-24-83 1-24-83 1-24-83 to to to to to to to to 1-31-83 1-31-83 1-31-83 2-01-83 2-01-83 1-31-83 1-31-83 1-31-83 FEBRUARY 1-31-83 1-31-83 1-31-83 2-01-83 2-01-83 1-31-83 1-31-83 1-31-83 to to to to to to to to 2-07-83 2-07-83 2-07-83 2-07-83 2-07-83 2-07-83 2-07-83 2-07-83 2-07-83 2-07-83 2-07-83 2-07-83 2-07-83 2-07-83 2-07-83 2-07-83 to to to to to to to to 2-14-83 2-14-83 2-14-83 . 2-15-83 2-15-83 2-14-83 2-14-83 2-14-83 2-14-83 2-14-83 2-14-83 2-15-83 2-15-83 2-14-83 2-14-83 2-14-83 to to to to to to to to 2-22-83 2-22-83 2-22-83 2-22-83 2-22-83 2-22-83 2-22-83 2-22-83 2-22-83 2-22-83 2-22-83 2-22-83 2-22-83 2-22-83 2-22-83 2-22-83 to to to to to to to 3-01-83 3-01-83 to 3-01-83 3-02-83 3-02-83 3-01-83 3-01-83 2-28-83 MARCH 3-01-83 3-01-83 3-01-83 3-02-83 3-02-83 3-01-83 3-01-83 2-28-83 to to to to to* to to to 3-07-83 3-07-83 3-07-83 3-07-83 3-07-83 3-07-83 3-07-83 3-07-83 3-07-83 3-07-83 3-07-83 3-07-83 3-07-83 3-07-83 3-07-83 3-07-83 to to to to to to to to 3-14-83 3-14-83 3-14-83 3-15-83 3-15-83 3-14-83 3-14-83 3-14-83
TABLE C-5 (cont'd) 1983 SAMPLING DATES FOR AIR SAMPLES STATION NO. MONTH 2S2 5Sl 5Dl lODl 16El lFl 2F2 3H3 MARCH 3-14-83 3-14-83 3-14-.83 3-15-83 3-15-83 3-14-83 3-14-83 3-14-83 to to to to to to to to 3-21-83 3-21-83 3-21-83 3-21-83 3-21-83 3-21-83 3-21-83 3-21-83 3-21-83 3-21-83 3-21-83 3-21-83 3-21-83 3-21-83 3-21-83 3-21-83 to to to to to to to to 3-28-83 3-28-83 3-28-83 3-29-83 3-29-83 3-28-83 3-28-83 3-28-83 APRIL 3-28-83 3-28-83 3-28-83 3-29-83 3-29-83 3-28-83 3-28-83 3-28-83 to to to to to to to to 4-04-83 4-04-83 4-04-83 4-04-83 4-05-83 4-04-83 4-04-83 4-04-83 4-04-83 4-04-83 4-04-83 4-04-83 4-05-83 4-04-83 4-04-83 4-04-83 to to to to to to to to 4-11-83 4-11-83 4-11-83 4-12-83 4-12-83 4-11-83 4-11-83 4-11-83 4-11-83 4-11-83 4-11-83 4-12-83 4-12-83 4-11-83 4-11-83 4-11-83 O'\ to to to to to to to to -....J 4-18-83 4-18-83 4-18-83 4-18-83 4-18-83 4-18-83 4-18-83 4-18-83 4-18-83 4-18-83 4-18-83 4-18-83 4-18-83 4-18-83 4-18-83 4-18-83 to to to to to to to to 4-25-83 4-25-83 4-25-83 4-26-83 4-26-83 4-25-83 4-25-83 4-25-83 4-25-83 4-25-83 4-25-83 4-26-83 4-26-83 4-25-83 4-25-83 4-25-83 to to to to to to to to 5-02-83 5-02-83 5-02-83 5-02-83 5-02-83 5-02-83 5-02-83 5-02-83 MAY 5-02-83 5-02-83 5-02-83 5-02-83 5-02-83 5-02-83 5-02-83 5-02-83 to to to to to to to to 5-09-83 5-09-83 5-09-83 5-10-83 5-10-83 5-09-83 5-09-83 5-09-83 5-09-83 5-09-83 5-09-83 5-10-83 5-10-83 5-09-83 5-09-83 5-09-83 to to to to to to to to 5-16-83 5-16-.83 5-16-83 5-16-83 5-16-83 5-16-83 5-16-83 5-16-83 5-16-83 5-16-83 5-16-83 5-16-83 5-16-83 5-16-83 5-16-83 5-16-83 to to to to to to to to 5-23-83 5-23-83 5-23-83 5-24-83 5-24-83 5-23-83 5-23-83 5-23-83 5-23-83 5-23-83 5-23-83 5-24-83 5-24-83 5-23-83 5-23-83 5-23-83 to to to to to to to to 5-23-83 5-31-83 5-31-83 6-01-83 6-01-83 5-31-83 5-31-83 5-31-83
TABLE C-5 (cont'd) 1983 SAMPLING DATES FOR AIR SAMPLES STATION NO. MONTH 252 5Sl 501 1001 16El lFl 2F2 3H3 JUNE 6-01-83 5-31-83 5-31-83 6-01-83 6-01-83 5-31-83 5-31-83 5-31-83 to to to to to to to to 6-06-83 6-06-83 6-06-83 6-06-83 6-06-83 6-06-83 6-06-83 6-06-83 6-06-83 6-06-83 6-06-83 6-06-83 6-06-83 6-06-83 6-06-83 6-06-83 to to to to to to to to 6-13-83 6-13-83 6-13-83 6-14-83 6-14-83 6-13-83 6-13-83 6-13-83 6-13-83 6-13-83 6-13-83 6-14-83 6-14-83 6-13-83 6-13-83 6-13-83 to to to to to to to to 6-20-83 6-20-83 6-20-83 6-20-83 6-20-83 6-20-83 6-20-83 6-20-83 6-20-83 6-20-83 6-20-83 6-20-83 6-20-83 6-20-83 6-20-83 6-20-83 to to to to to to to to 6-28-83 6-28-83 6-28-83 6-29-83 6-29-83 6-28-83 6-28-83 6-28-83 O'\ CX> JULY 6-28-83 6-28-83 6-28-83 6-29-83 6-29-83 6-28-83 6-28-83 6-28-83 to to to to to to to to 7-05-83 7-05-83 7-05-83 7-05-83 7-05-83 7-05-83 7-05-83 7-05-83 7-05-83 7-05-83 7-05-83 7-05-83 7-05-83 7-05-83 7-05-83 7-05-83 to to to to to to to to 7-11-83 7-11-83 7-11-83 7-12-83 7-12-83 7-11-83 7-11-83 7-11-83 7-11-83 7-11-83 7-11-83 7-12-83 7-12-83 7-11-83 7-11-83 7-11-83 to to to to to to to to 7-18-83 7-18-83 7-18-83 7-18-83 7-18-83 7-18-83 7-18-83 7-18-83 7-18-83 7-18-83 7-18-83 7-18-83 7-18-83 7-18-83 7-18-83 7-18-83 to to to to to to to to 7-25-83 7-25-83 7-25-83 7-26-83 7-26-83 7-25-83 7-25-83 7-25-83 7-25-83 7-25-83 7-25-83 7-26-83 7-26-83 7-25-83 7-25-83 7-25-83 to to to to to to to to 8-01-83 8-01-83 8-01-83 8-02-83 8-02-83 8-01-83 8-01-83 8-01-83 AUGUST 8-01-83 8-01-83 8-01-83 8-02-83 8-02-83 8-01-83 8-01-83 8-01-83 to to to to to to to to 8-08-83 8-08-83 8-08-83 8-09-83 8-09-83 8-08-83 8-09-83 8-08-83 8-08-83 8-08-83 8-08-83 8-09-83 8-09-83 8-08-83 8:..09-03 8-08-83 to to to to to to to to 8-15-83 8-15-83 8-15-83 8-15-83 8-15-83 8-15-83 8-15-83 8-15-83
TABLE C-5 (cont'd) 1983 SAMPLING DATES FOR AIR SAMPLES STATION NO. MONTH 2S2 5Sl 501 lODl 16El lFl 2F2 3H3 AUGUST 8-15-83 8-15-83 8-15-83 8-15-83 8-15-83 8-15-83 8-15-83 8-15-83 to to to to to to to to 8-23-83 8-22-83 8-22-83 8-23-83 8-23-83 8-22-83 8-22-83 8-22-83 8-23-83 8-22-83 8-22-83 8-23-83 8-23-83 8-22-83 8-22-83 8-22-83 to to to to to to to to 8-29-83 8-29-83 8-29-83 8-30-83 8-30-83 8-29-83 8-29-83 8-29-83 SEPTEMBER 8-29-83 8-29-83 8-29-83 8-30-83 8-30-83 8-29-83 8-29-83 8-29-83 to to to to to to to to 9-06-83 9-06-83 9-06-83 9-06-83 9-06-83 9'-06-83 9-06-83 9-06-83 9-06-83 9-06-83 9-06-83 9-06-83 9-06-83 9-06-83 9-06-83 9-06-83 to
- to to to to to to to 9-12-83 9-12-83 9-13-83 9-13-83 9-13-83 9-12-83 9-12-83 9-12-83 9-12-83 9-12-83 9-13-83 9-13-83 9-13-83 9-12-83 9-12-83 9-12-83
°' \D to 9-19-83 to 9-19-83 to 9-19-83 to 9-19-83 to 9-19-83 to 9-19-83 to 9-19-83 to 9-19-83 9-19-83 9-19-83 9-19-83 9-19-83 9-19-83 9-19-83 9-19-83 9-19-83 to to to to to to to to 9-26-83 9-26-83 9-26-83 9-27-83 9-27-83 9-26-83 9-26-83 9-26-83 OCTOBER 9-26-83 9-26-83 9-26-83 9-27-83 9-27-83 9-26-83 9-26-83 9-26-83 to to to to to to to to 10-03-83 10-03-83 10-03-83 10-03-83 10-03-83 10-03-83 10-03-83 10-03-83 10-03-83 10-03-83 10-03-83 10-03-83 10-03-83 10-04-83 10-03-83 10-03-83 to to to to to to to to 10-11-83 10-11-83 10-11-83 10-12-83 10-12-83 10-11-83 10-11-83 10-11-83 10-11-83 10-11-83 10-11-83 10-12-83 10-12-83 10-11-83 10-11-83 10-11-83 to to to to to to to to 10-17-83 10-17-83 10-17-83 10-17-83 10-17-83 10-17-83 10-17-83 10-17-83 10-17-83 10-17-83 10-17-83 10-17-83 10-17-83 10-17-83 10-17-83 10-17-83 to to to to to to to to 10-24-83 10-24-83 10-24-83 10-25-83 10-25-83 10-24-83 10-24-83 10-24-83 10-24-83 10-24-83 10-24-83 10-25-83 10-25-83 10-24-83 10-24-83 10-24-83 to to to to to to to to 10-31-83 10-31-83 10-31-83 10-31-83 10-31-83 10-31-83 10-31-83 10-31-83
TABLE C-5 (cont'd) 1983 SAMPLING DATES FOR AIR SAMPLES STATION NO" MONTH 2S2 SSl SDI lODl 16El lFl 2F2 3H3 NOVEMBER 10-31-83 10-31-83 10-31-83 10-31-83 10-31-83 10-31-83 10-31-83 io-31:..93 to to to to to to to to ll-07-83 11-07-83 ll-07-83 ll-07-83 ll-07-83 ll-07-83 ll-07-83 ll-07-83 ll-07-83 ll-07-83 ll-07-83 ll-07-83 ll-07-83 ll-07-83 ll-07-83 ll-07-83 to to to to to to to to ll-14-83 ll-14-83 ll-14-83 ll-15-83 ll-15-83 ll-14-83 ll-14-83 ll-14-83 ll-14-83 ll-14-83 ll-14-83 ll-15-83 ll-15-83 11-14-83 ll-14-83 ll-14-83 to to to to to to to to ll-21-83 ;J..l-21-83 ll-21-83 ll-21-83 ll-21-83 ll-21-83 ll-21-83 ll-21-83 -...) 0 ll-21-83 ll-21-83 11-21-83 ll-21-83 ll-21-83 ll-21-83 ll-21-83 11-21-83 to to to to to to to to n-2a:..a3 11-28-83 11-28-83 ll-29-83 ll-29-83 ll-28-83 ll-28-83 11-28-83 DECEMBER ll-28-83 ll-28-83 11-28-83 ll-29-83 ll-29-83 ll-28-83 ll-28-83 11-28-83 to to to to to to to to 12-05-83 12-05-83 12-05-83 12-05-83 12-05-83 12-05-83 12-05-83 12-05-83 12-05-83 12-05-83 12-05-83 12-05-83 12-05-83 12-05-83 12-05-83 12-05-83 to to to to to to to to 12-12-83 12-12-83 12-12-83 12-13-83 12-13-83 12-12-83 12-12-83 12-12-83 12-12-83 12-12-83 12-12-83 12-13-83 12-13-83 12-12-83 12-12-83 12-12-83 to to to to to to to to 12-19-83 12-19-83 12-19-83 12-19-83 12-19-83 12-19-83 12-19-83 12-19-83 12-19-83 12-19-83 12-19-83 12-19-83 12-19-83 12-19-83 12-19-83 12-19-83 to to to to to to to to 12-27-83 12-27-83 12-27-83 12-27-83 12-27-83 12-27-83 12-27-83 12-27-83
TABLE C-6 1983 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, AND TRITIUM IN PRECIPITATION STATION NO. SA-RWA-2F2 Results in Units of pCi/L +/- 2 sigma Results by Radiation Management Corporation COLLECTION PERIOD ALPHA BETA TRITIUM* 12-28-82 to 2-01-83 <1.1 4.5+/-2.2 190+/-80 2-01-83 to 3-02-83 <0.7 <3.0 <140 3-02-83 to 3-28-83 0.8+/-0.7 4.0+/-1.2 <130 3-28-83 to 4-25-83 <l. 3 3.6+/-2.l <130 4-25-83 to 6-01-83 <l. 0 3.8+/-2.3 <120 6-01-83 to 6-29-83 <0.7 3.3+/-2.l <130 Results by PSE&G Research Corporation COLLECTION PERIOD ALPHA BETA TRITIUM 6-29-83 to 8-01-83 4.6+/-1.6 19+/-2 <130 8-01-83 to 8-30-83 <1.2 6.1+/-0.9 <130 8-30-83 to 9-27-83 <l. 9 2.4+/-0.7 <130 9-27-83 to 11....:01-83 0.5+/-0.4 1.4+/-1.0 <130 11-01-83 to 11-29-83 0.6+/-0.5 3.9+/-1.2 <120 11-29-83 to 12-27-83 <0.4 <1.4 <140 AVERAGE 4.7+/-9.4
- January through June tritium results by PSE&G Research Corporation.
71
TABLE C-7 1983 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND GAMMA EMITTERS** IN QUARTERLY COMPOSITES OF PRECIPITATION STATION NO. SA-RWA-2F2 Results in Units of pCi/L +/- 2 sigma RESULTS BY RESULTS BY RADIATION MANAGEMENT CORPORATION PSE&G RESEARCH CORPORATION 12-28-82 3-28-83 6-29-83 9-27-83 NUCLIDE to to
- to to AVERAGE 3-28-83 6-29-83 9-27-83 12-27-83
-..J IV Sr-89 <0.3 <3.oO> (2 ) (4) Sr-90 <0.3 <0.2(1) (2) (4 ) Be-7 28+/-6 15+/-5 63+/-28(3) 47+/-25(5) 38+/-42
- Sr-89 results are corrected for decay to sample stop date.
** All other gamma emitters searched for were <LLD; typical LLDs are given in Tables C-32 (RMC) and C-33 (PSE&G).
(1) Second quarter Sr-89 and -90 analysis performed by Teledyne Isotopes. (2) Insufficient rainfall collected to perform this analysis. (3) Results for gamma taken from one sample collected 8/1-30/83 due to insufficient rainfall over the entire 3rd quarter of 1983. (4) Sample lost during analysis. (5) This is a mathematical composite of 3 monthly rainfall gamma results for the months of October, November and December, 1983.
TABLE C-8 1983 DIRECT RADIATION MEASUREMENTS - QUARTERLY TLD RESULTS Results in mrad/standard month* RESULTS BY RADIATION RESULTS BY MANAGEMENT CORPORATION TELEDYNE ISOTOPES JANUARY APRIL JULY OCTOBER STATION NO. to to to to AVERAGE MARCH JUNE SEPTEMBER DECEMBER SA-IDM-2S2 4.9+/-0.4 5.4+/-0.1 6.0+/-0.5 5.5+/-0.2 5.4+/-0.9 SA-IDM-5Sl 4.4+/-0.5 3.9+/-0.5 4.2+/-0.9 4.1+/-0.1 4.2+/-0.4 SA-IDM-652 5.3+/-0.4 4.5+/-0.2 5.4+/-0.6 4.9+/-0.3 5.0+/-0.8 SA-IDM-7Sl 6.0+/-0.4 5.7+/-0.7 6.5+/-0~5 5.7+/-0.1 6.0+/-0.8 SA-IDM-lOSl 6.7+/-0.5 5.5+/-0.8 6. 1+/-0. 7 5.3+/-0.1 5.9+/-1.3 SA-IDM-llSl 8.1+/-2. 0 4.9+/-0.6 5.4+/-0.5 4.1+/-0.1 5.6+/-3.5 SA-IDM-4D2 5.2+/-0.6 4.8+/-0.3 5.2+/-0.7 5.6+/-0.2 5.2+/-0.6 SA-IDM-5Dl 4.8+/-0.6 4.2+/-0.1 5.1+/-0.5 4.7+/-0.2 4.7+/-0.7 SA-IDM-lODl 5.5+/-0.4 4.8+/-0.4 5.6+/-0.2 5.2+/-0.4 5.3+/-0.7 SA-IDM-14Dl 5.4+/-0.9 5.2+/-0.9 5.9+/-0.7 5.3+/-0.2 5.4+/-0.6 SA-IDM-2El 5.2+/-0.5 5.2+/-0.1 5.4+/-0.7 5.0+/-0.1 5.2+/-0.3 SA-IDM-3El 4.8+/-0.3 4.8+/-0.5 5.6+/-0.3 4.7+/-0.0 5.0+/-0.8 SA-IDM-9El 6.2+/-0.9 6.2+/-0.4 6.6+/-0.8 6.5+/-0.3 6.4+/-0.4 SA-IDM-11E2 6.3+/-0.4 6.0+/-1.0 6.3+/-0.5 6.0+/-0.2 6.2+/-0.3 SA-IDM-12El 5.9+/-0.3 5.6+/-0.6 5.9+/-0.8 6.0+/-0.2 5.8+/-0.3 SA-IDM-13El 5.1+/-0. 6 5.0+/-0.4 5. 2+/- 0. 7 5. 2+/- 0. 3 5.1+/-0.2 SA-IDM-16El 5.5+/-0.3 5.6+/-0.7 6.1+/-0.3 5.1+/-0.3 5.6+/-0.8 SA-IDM-lFl 5.4+/-0.5 5.2+/-0.7 5.5+/-0.7 5.0+/-0.4 5.3+/-0.4 SA-IDM-2F2 4.3+/-0.3 4.0+/-0.4 4.3+/-0.5 3.9+/-0.2 4.1+/-0.4 SA-IDM-2F5 5.6+/-0.4 5.5+/-0.7 5.7+/-0.7 5.6+/-0.2 5.6+/-0.2 SA-IDM-2F6 5.2+/-0.8 5.0+/-0.2 5.6+/-0.3 4.8+/-0.7 5.2+/-0.7 SA-IDM-3F2 4.7+/-0.8 4.8+/-0.6 4.7+/-0.6 4. 9+/- 0. 2 4.8+/-0.2 SA-IDM-3F3 4.5+/-0.6 4.5+/-0.1 5.1+/-0.5 4.9+/-0.4 4.8+/-0.4 SA-IDM-5Fl 4.4+/-0.2 4.7+/-0.5 5.0+/-0.9 4.7+/-0.2 4.7+/-0.5 SA-IDM-6Fl 4.4+/-0.2 4.3+/-0.4 4.4+/-0.5 3.9+/-0.2 4.2+/-0.5 SA-IDM-7F2 4.9+/-0.9 3.9+/-0.1 4.1+/-0.5 3.5+/-0.0 4.1+/-1.2 SA-IDM-10F2 5.5+/-0.5 5.2+/-0.5 6.0+/-0.9 5.6+/-0.2 5.6+/-0.7 SA-IDM-llFl 6.0+/-0.8 5.6+/-0.5 5.9+/-0.5 5. 5+/- 0 .1 5.8+/-0.5 SA-IDM-12Fl 5.3+/-0.5 4.7+/-0.4 5.9+/-0.7 5.6+/-0.2 5.4+/-1.0 SA-IDM-13Fl 5.2+/-0.4 5.1+/-0.9 5.4+/-0.3 4.9+/-0.1 5.2+/-0.4 SA-IDM-13F2 5.5+/-0.4 5.0+/-0.6 5.4+/-0.9 5.4+/-0.2 5.3+/-0.4 SA-IDM-13F3 5.5+/-0.6 5.6+/-0.9 6.1+/-0. 5 5.5+/-0.3 5.7+/-0.6 SA-IDM-14F2 5.2+/-0.8 5.0+/-0.2 5.9+/-0.9 5.4+/-0.2 5.4+/-0.8 SA-IDM-15F3 6.0+/-0.5 5.5+/-0.8 6.9+/-0. 7 6.2+/-0.2 6.2+/-1.2 SA-IDM-16F2 5.5+/-0.4 4.7+/-0.4 5.9+/-0.5 5.2+/-0.0 5.3+/-1.0 SA-IDM-1G3 (C) 6.8+/-0.7 5.9+/-0.5 6.6+/-0. 9 6. 3+/- 0 .1 6.4+/-0.8 SA-IDM-3Gl (C) 5.6+/-0.2 5.7+/-0.7 6.0+/-0.9 5.7+/-0.2 5.7+/-0.3 SA-IDM-lOGl (C) 5.7+/-0.9 5.7+/-0.8 6.4+/-0.3 6.1+/-0.5 6.0+/-0.7 SA-IDM-16Gl (C) 6.0+/-0.4 5.6+/-1.0 7.1+/-0.8 6.3+/-0.2 6.2+/-1.3 SA-IDM-2Hl (C) 6.0+/-0.6 6.2+/-0.3 (1) ( 1) 6.1+/-0.3 SA-IDM-3Hl (C) 6.0+/-0.4 5.8+/-0.7 5.8+/-0.6 5. 5+/- 0 .1 5.8+/-0.4 SA-IDM-3H3 (C) 5.8+/-0.4 5.6+/-0.4 5.9+/-0. 7 5.3+/-0.2 5.6+/-0.5 AVERAGE 5.5+/-1.5 5.l+/-L 2 5. 7+/-1. 4 5.2+/-1.4 5.4+/-1.4
- The standard month = 30.4 days.
(C) Control station (1) Station SA-IDM-2Hl was terminated on 6-28-83. 73
TABLE C-9 1983 DIRECT RADIATION MEASUREMENTS - MONTHLY TLD RESULTS Results in mrad/standard month* Results by Radiation Management Corporation STATION NO. JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-IDM-2S2 4. 5+/- o. 3 5.1+/-0.4 6.2+/-0.3 6.4+/-0.2 6.2+/-0~3 4. 8+/-0. 2 SA-IDM-5Sl 4.4+/-0.4 4.7+/-0.4 4.7+/-0.7 5.0+/-0.2 5.0+/-0.2 4.9+/-2.0 SA-IDM-6S2 5.3+/-0.2 5.6+/-0.2 5.9+/-0.7 6.3+/-0.5 4.8+/-0.3 5.3+/-0.9 SA-IDM-7Sl 6.6+/-0.6 6.8+/-0.2 7.0+/-0.2 6.3+/-0.5 6.6+/-0.7 5.5+/-0.8 SA-IDM-lOSl 8.0+/-0.7 6.3+/-1.3 7.0+/-0.7 5.9+/-0.9 6.6+/-0.6 5.6+/-1.0 SA-IDM-llSl 12.1+/-0.8 8. 6+/-1. 2 5.6+/-0.4 5.3+/-0.4 5.6+/-0.9 5.4+/-0.5 SA-IDM-501 4.9+/-0.3 5.1+/-0.2 5.6+/-2.0 5.6+/-0.9 5. 2+/-0. 4 4.1+/-0.5 SA-IDM-1001 5.7+/-0.4 5.9+/-1.l 6.3+/-1.3 6.2+/-0.2 6.3+/-0.5 5.8+/-0.6 -...] SA-IDM-1401 5.4+/-0.4 6.2+/-0.5 6.1+/-0.7 6.1+/-0.6 6.2+/-0.3 5.3+/-l.O """ SA-IDM-2El 5.4+/-0.7 5.6+/-0.4 5. 6+/-1. 0 5.8+/-0.3 5.7+/-0.9 5.0+/-0.7 SA-IDM-3El 5.6+/-0.5 5.2+/-0.4 5.5+/-1.0 5.7+/-0.4 5.4+/-0.5 5.2+/-0.4 SA-IDM-13El 5.1+/-0.7 6.0+/-0.6 6.2+/-0.4 5.8+/-0.3 5.4+/-0.7 5.2+/-0.2 SA-IDM-16El 5.8+/-0.4 6.0+/-0.3 6.0+/-0.7 6.0+/-0.5 5. 9+/- o. 6 5.0+/-0.7 SA-IDM-lFl 5.8+/-0.3 5.6+/-0.2 6.2+/-0.5 6.0+/-0.8 6.0+/-1.0 4.8+/-0.4 SA-IDM-2F2 4.2+/-0.4 4.4+/-0.4 4.9+/-0.4 5.0+/-0.2 4. 9+/- o. 8 4.4+/-0.9 SA-IDM-2F6 5.7+/-0.5 5.4+/-0.6 6.8+/-0.1 6.2+/-0.8 6.2+/-0.4 4.6+/-0.3 SA-IDM-5Fl 4.9+/-0.6 5.1+/-0.2 5.6+/-0.6 5. 3+/- o. 4 5.2+/-0.4 4.6+/-0.6 SA-IDM-6Fl 4.6+/-0.4 4.8+/-0.2 5.0+/-0.3 4.6+/-0.6 5.1+/-0.4 4.1+/-0.9 SA-IDM-7F2 3.9+/-0.5 4.3+/-0.6 4.6+/-0.4 4.3+/-0.6 4. 2+/-0. 2 3.7+/-0.6 SA-IDM-llFl 6.2+/-1.1 6.2+/-0.6 6.5+/-0.7 6.3+/-1.0 6.4+/-0.6 5.1+/-0. 8 SA-IDM-13Fl 5.5+/-1:2 5.5+/-0.6 6.2+/-0.2 5.4+/-0.6 5.8+/-0.5 5.5+/-0.4 SA-IDM-3Gl (C) 6.0+/-0.9 5.6+/-0.3 7.0+/-0.8 6.6+/-1.3 6.1+/-0. 6 5.7+/-0.6 SA-IDM-2Hl (C)** 5.9+/-1.0 5.8+/-0.4 7.0+/-0.3 6.4+/-0.3 5.7+/-0.8 5. 6+/-1. 0 SA-IDM-3Hl (C) 7.0+/-1.0 6.1+/-0. 6 6.7+/-0.2 6.0+/-0.9 5.9+/-0.5 5.1+/-1.3 SA-IDM-3H3 (C) 6.5+/-0.4 6.4+/-0.2 6.9+/-0.7 6.5+/-1.4 6.5+/-1.1 5. 7+/-1. 0 AVERAGE 5.8+/-3.2 5. 7+/-1. 7 6.0+/-1.5 5.8+/-1.2 5. 7+/-1.2 5.0+/-1.1
TABLE C-9 (cont'd) 1983 DIRECT RADIATION MEASUREMENTS - MONTHLY TLD RESULTS Results in mrad/standard month* Results by Teledyne Isotopes STATION NO. JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE SA-IDM-2S2 7.2+/-0.2 8.8+/-0.9 7.1+/-0.9 7.4+/-0.2 6.1+/-0. 2 7.3+/-0.2 6.4+/-2.5 SA-IDM-5Sl 5.6+/-0.2 7. 6+/-1. 7 5.3+/-0.7 6.3+/-2.0 8.3;t5.5 5.9+/-0.1 5.6+/-2.4 SA-IDM-6S2 6. 6+/- o. 4 8.0+/-0.9 5.9+/-0.9 6.5+/-0.2 6.2+/-0.4 6.3+/-0.1 6. 0+/-1. 6 SA-IDM-7Sl 7.2+/-0.2 8.9+/-0.9 6.2+/-0.4 7.0+/-0.3 6.4+/-0.2 7.4+/-0.4 6.8+/-1.6 SA-IDM-lOSl 7.3+/-0.4 8.7+/-0.7 6.6+/-0.2 6.9+/-0.0 6. 3+/- 0. 2 7 .1+/- o. 3 6. 8+/-1. 7 SA-IDM-llSl 7.2+/-0.4 8.5+/-0.4 5.6+/-0.4 5.5+/-0.3 5.5+/-0.2 5.9+/-0.1 6.7+/-4.1 SA-IDM-5Dl 6.0+/-0.2 8.1+/-0. 7 5.6+/-0.4 6. 2+/- o. 2 5. 8+/-0. 2 6.2+/-0.2 5. 7+/-1. 9 ~ U1 SA-IDM-1001 7.3+/-0.2 8.6+/-1.1 6.4+/-0.4 7.0+/-0.3 6.4+/-0.4 6.9+/-0.2 6. 6+/-1. 6 SA-IDM-1401 7.3+/-0.4 8.8+/-1.3 5. 9+/- o. 4 7.1+/-0.2 5.8+/-0.2 6.9+/-0.2 6.4+/-1.9 SA-IDM-2El 6.8+/-0.2 9.1+/-2.0 6.1+/-0.2 6.7+/-0.0 5.9+/-0.2 6.8+/-0.3 6.2+/-2.1 SA-IDM-3El 6.4+/-0.4 8.1+/-0. 9 5.8+/-0.4 7.1+/-2.0 6.0+/-0.4 6.3+/-0.1 6.0+/-1.7 SA-IOM-13El 6.7+/-0.4 8.0+/-0.9 5.5+/-0.4 6.3+/-0.2 6.0+/-0.4 6.4+/-0.1 6. 0+/-1. 6 SA-IDM-16El 6.9+/-0. 2 8. 8+/-1. 3 5.5+/-0.4 7.8+/-1.9 6. 6+/- o. 4 6.9+/-0.2 6.4+/-2.1 SA-IDM-lFl 6.7+/-0.2 8. 7+/-1.1 6.3+/-0.4 6.8+/-0.2 6.2+/-0.2 6.8+/-0.3 6. 3+/-1. 9 SA-IDM-2F2 5.6+/-0.2 7. 0+/- 0. 9 5.2+/-0.2 7.0+/-0.2 4.0+/-0.2 5.7+/-0.3 5.2+/-2.0 SA-IDM-2F6 6.6+/-1.4 8.3+/-0.7 6.2+/-0.4 5.5+/-0.2 6.1+/-0.2 6.8+/-0.2 6.2+/-1.8 SA-IDM-5Fl 6.4+/-0.4 8.4+/-0.4 5. 8+/-0. 4 6.3+/-0.2 6. 7+/-1. 5 6.4+/-0.3 5.9+/-2.1 SA-IDM-6Fl 5.8+/-0.2 7.9+/-0.9 4.9+/-0.4 5.7+/-0.2 5. 7+/-1. 3 5.6+/-0.2 5. 3+/-1. 9 SA-IDM-7F2 5.4+/-0.4 7.1+/-0. 4* 3.9+/-0.7 4.9+/-0.2 4. 9+/- 0. 2 5. 2+/-0.1 4. 7+/-1. 8 SA-IDM-llFl 7.7+/-0.7 9.6+/-0.9 6.6+/-0.2 7.0+/-0.2 6.6+/-0.2 7.4+/-0.8 6.8+/-2.2 SA-IDM-13Fl 6.9+/-0.2 8.6+/-1.3 5. 5+/-0. 4 7.3+/-1.9 6.6+/-0.6 6.9+/-0.2 6.3+/-1.9 SA-IDM-3Gl (C) 7.2+/-0.5 8.6+/-1.1 6.7+/-0.4 7.1+/-0.3 6.7+/-0.4 7.3+/-0.3 6.7+/-1.6 SA-IDM-3Hl (C) 7.3+/-0.7 8.8+/-0.4 6.7+/-0.2 7.1+/-0.2 6.8+/-0.2 6. 9+/- 0.1 6. 7+/-1. 8 SA-IDM-3H3 (C) 6.8+/-1.3 9.5+/-0.7 6.6+/-0.4 7.1+/-0.2 6. 7+/-0. 4. 7.6+/-0.2 6. 9+/-1. 9 AVERAGE 6. 7+/-1. 3 8.4+/-1.3 5.9+/-1.4 6.6+/-1.4 6.2+/-1.6 6.6+/-1.3 6.2+/-2.3
- The standard month = 30.4 days.
** Station SA-IDM-2Hl was terminated on 6-28-83.
(C) Control station
TABLE C-10 1983 CONCENTRATIONS OF IODINE-131 IN MILK Results in Units of pCi/L Results" by Radiation Management Corporation STATION NO,*** JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-MLK-13E3 <0.2 <0.1 <0.08 <0.09 <0.l <0.07
<0.08 <0.l <0.07 <O.l <0.09 <0.l SA-MLK-2F4 <0.5 <0.2 <0.08 <0.08 <0.l <0.09
<0.09 <0.08 <0.07 <0.09 <0.09 <0.l SA-MLK-5F2 <0.2 <0.2 <0.1 <0.07 <0.2 <0.09
( 2) <0.l <O.l <0.08 <0.09 <0.l SA-MLK-l4Fl <0.2 <0.2 <0.1 <0.09 <0.l <0.l
<0.1 <0.l <0.09 <0.09 <0.09 <0.l SA-MLK-15Fl <0.2 <0.2 <O.l <0.l <0.l <0.09
<0.l <0.l <0.1 <O.l <0.1 <0.l SA-MLK-3Gl <0.3 <0.2 <O.l <O.l <0.l <O.l (Control) <0.1 <0.2 <0.09 <0.2 <0.l <o.1Cll
-...] O'I Results"* by PSE&G Research Corporation STATION NO.*** JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER SA-MLK-13E3 <0.l <0.1 <0.06 <O.l <0. 06 . <0.09
<0.l <0.07 <0.09 <0.l <0.09 <0.l SA-MLK-2F4 <0.l <0.2 <0.06 <0.1 <0.06 <0.09
<0.l <0.06 <0.09 <O.l <0.09 <0.l SA-MLK-5F2 <0.2 <0.l <0.06 <O.l <0.07 <0.09
<0.2 <0.06 <0.1 <0.1 <0.10 <0.l SA-MLK-14Fl <0.2 <0.l <0.06 <0.1 <0.07 <0.09
<0.l <0.06 <0.l <0.1 <0.09 <0.l SA-MLK-l5Fl <0.2 <0.1 <0.07 <0.1 <0.09 <0.09
<0.l <0.07 <0.l <0.1 <0.09 <0.l SA-MLK-3Gl <0.2(1) <o.2Cll <0.07 <0.1 <0.06 <0.l (Control) <0.1(1) <0.06Cll <0.08 <O.l <O.l <0.l
- I-131 results are corrected for decay to sample stop date.
** I-131 results are corrected for decay to midpoint of collection period.
*** Sampling dates can be found in Table C-13.
(1) Station SA-MLK-3G2 supplied the milk sample while station SA-MLK-3Gl replaced its entire herd. (2) Analysis spectrum and results lost due to computer malfunction.
TABLE C-11 1983 CONCENTRATIONS OF STRONTIUM-89" and -90 IN MILK Results in Units of pCi/L +/- 2 sigma (All Results by PSE&G Research Corporation) STATION NO.** NUCLIDE JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-MLK-13E3 Sr-89 <l.6 <2.0 <l.9 <l.8 <l.6 <l.5 Sr-90 2.6+/-0.6 3.0+/-0.7 3.2+/-0.8 2.4+/-0.7 2.3+/-0,6 2.3+/-0.5 SA-MLK-2F4 Sr-89 <l.4 <l. 8 <2.0 <l. 4 <l.6 <l.2 Sr-90 2.0+/-0.5 1.8+/-0.6 2.2+/-0,8 1.9+/-0.5 2.0+/-0.6 1.3+/-0.4 SA-MLK-5F2 Sr-89 <l. 7 <2.1 <2.2 <l.9 <l.9 <l.9 Sr-90 3.3+/-0,6 2.9+/-0.7 2.7+/-0.8 3.7+/-0.8 4.9+/-0,8 5.8+/-0.7 SA-MLK-14Fl Sr-89 <l.6 <l.8 <l. 9 <l.5 <l. 7 <l.5 Sr-90 2.6+/-0.6 2.7+/-0.7 2.1+/-0.7 2.4+/-0.6 2.6+/-0.7 3.1+/-0.6 SA-MLK-15Fl Sr-89 <l.6 <2.3 <2.1 <l.6 <l.9 <l.5 Sr-90 2.8+/-0.6 2.4+/-0.8 3.0+/-0,8 2.0+/-0.6 2.4+/-0.7 2.7+/-0.6 SA-MLK-3Gl Sr-89 <l. 8 <2.4 <2.2 <l. 8 <l. 7 <l. 7 (Control) Sr-90 3.3+/-0.7 3.2+/-0.8 2.2+/-0.8 2.8+/-0.7 3.2+/-0.7 3.8+/-0.6 ..;._J -.J STATION NO. ** NUCLIDE JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE SA-MLK-13E3 Sr-89 <l. 7 <2.1 <2.0 <l.3 <l.3 <l.l Sr-90 3.1+/-0.7 3.0+/-0.8 3.0+/-0,8 2.5+/-0.5 2.3+/-0.5 2.1+/-0.4 2.6+/-0.8 SA-MLK-2F4 Sr-89 <3.1 <l.6 <l.0 <1.2 <1.1 <1.0 Sr-90 1.9+/-0,8 1.5+/-0.6 0.8+/-0.3 1.7+/-0.5 1.8+/-0.4 1.6+/-0.4 1. 7+/-0. 8 SA-MLK-5F2 Sr-89 <2.2 <2.0 <2.1 <1.5 <l.5 <1.3 Sr-90 5.9+/-0.8 4.3+/-0.8 5.0+/-0.8 4.6+/-0.6 4.0+/-0,5 4.0+/-0.5 4.2+/-2.l SA-MLK-14Fl Sr-89 <l.6 <l.8 <1.6 <1.5 <1.4 <1.1 Sr-90 2.0+/-0.6 2.2+/-0.7 1.7+/-0.7 .2.4+/-0.6 2.7+/-0.5 2.8+/-0.4 2.4+/-0.8 SA-MLK-15Fl Sr-89 <l.8 <1.8 <1.8 <1.3 <l.4 <1.4 Sr-90 1.8+/-0,6 2.2+/-0.7 2.3+/-0.7 1.6+/-0.5 2.8+/-0.5 2.1+/-0.6 2.3+/-0.8 SA-MLK-3Gl Sr-89 <1.9(1) <2.0<1> <1.9 <1.4 <1.3 <1.2 (Control) Sr-90 3.4+/-0.7 4.2+/-0.8 3.0+/-0.8 3.6+/-0.6 3.3+/-0.5 3.7+/-0.5 3.3+/-1.0 Grand Average sr-89 Sr-90 2.8+/-2.0
- 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. ( 1) Station SA-MLK-3G2 supplied the milk sample while station SA-MLK-3Gl replaced its entire herd.
TABLE C-12 1983 CONCENTRATIONS OF GAMMA EMITTERS" IN MILK Results in Units of pCi/L :t 2 sigma Results by Radiation Management Corporation STATION NO."" NUCLIDE JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-MLK-13E3 K-40 1200+/-120 1400+/-140 1300+/-130 1400+/-140 1200+/-120 1500+/-150 Co-60 <5.3 <L6 <1.3 <2.0 <1.4 <l. 7 Cs-137 <5,5 2.8+/-1.0 1.2+/-0. 7 1.8+/-0,9 4.7+/-0.9 1.4+/-0.B Ce-141 <9.B <7.7 <3.B <3.7 <2.9 <1.4 Th-232 (1) <4.4 <3.1 <5.0 <3.l <3.6 SA-MLK-2F4 K-40 1100+/-110 1200+/-120 1500+/-150 1500+/-150 1600+/-160 1500+/-150 Co-60 <6 .2 <2.0 <1.9 <1.5 <l.B <l. 7 Cs-137 <7.2 <1.6 <1.4 <1.0 <1.5 <1.3 Ce-141 <13 <8.0 <3.7 <3.6 <1.9 <1.5 Th-232 ( 1) <5.l <3.9 <3.1 <3,6 <3.6 SA-MLK-5F2 K-40 1300+/-130 1300+/-130 1300+/-130 1300+/-130 1500+/-150 1500+/-150 .....J Co-60 <6.2 <l.5 <l. 7 <l.B <l.6 <l.5 co Cs-137 <6.7 1.1+/-0, 7 1.3+/-0,7 1.2:!:0.B 1. 6+/-1. 0 4.0+/-1.0 Ce-141 <12 <6.1 <2.6 <2.3 <3.7 <2.9 Th-232 (1) <3.0 <3.6 <3.6 <4.2 <4.3 SA-MLK-14Fl K-40 1200+/-120 1200+/-120 1200+/-120 1400+/-140 1500+/-150 1500:!:150 Co-60 <5.4 <l.6 <l.5 <1.B <1.9 <1.5 Cs-137 <6.0 <1.1 <1.3 L3+/-0.B <l. 7 1.3+/-0.B Ce-141 <12 <5.4 <4.7 <2.2 <3.B <2.5 Th-232 (1) <3.6 <4.1 <3,7 <5.l <3.2 SA-MLK-15Fl K-40 1200+/-120 1400+/-140 1200+/-120 1600+/-160 1300+/-130 1400:!:140 Co-60 <4.B <l. 7 <2.l <l. 7 <1.4 <2.0 Cs-137 <6.1 <1.2 <1.6 1.7+/-0.9 1.3+/-0.7 <l. 6 Ce-141 <6.6 <3.9 <5.3 <4.6 <3.1 <2.3 Th-232 (1) <3.6 <5.0 <4 .4 <3.1 <3.9 SA-MLK-3Gl K-40 1000+/-100 1400+/-140 1400+/-140 1400+/-140 1200+/-120 1300+/-130 (Control) Co-60 <6.3 <l. 7 <1.4 <1.5 <1.6 <l. 7 Cs-137 <7.0 <1.4 1. 7+/-0.B <1.4 <1.0 1.2+/-0, 7 Ce-141 <13 <7.7 <3.9 <4.3 <LB <1.5 Th-232 (1) <4.3 <3.0 <4.0 <3.5 <3.5
TABLE C-12 (cont'd) 1983 CONCENTRATIONS OF GAMMA EMITTERS* IN MILK Results in Units of pCi/L +/- 2 sigma Results by PSE&G Research Corporation STATION NO.** NUCLIDE JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE SA-MLK-13E3 K-40 1300+/-57 1300+/-68 1300+/-68 1400+/-69 1500+/-71 1400+/-69 1400:1:200 Co-60 <3.7 <2.6 <3.0 <4.0 <3.4 <2.7 cs-137 <3.6 <2.7 <2.3 <3.5 <2.2 <3.4 Ce-141 <8.1 <.2. 7 <2.8 <2.3 <2.0 <3.1 Th-232 <11 <9.3 <7.4 <6.9 <11 <7.4 SA-MLK-2F4 K-40 1400+/-55 1300+/-59 1400+/-55 1400+/-59 1400+/-60 1400+/-60 1400:1:280 Co-60 <3.8 <3.4 <2.9 <3.2 <3.0 <3.5 Cs-137 <2.6 <2.3 <1.8 <2.2 <2.2 <2.6 Ce-141 <4.8 <3.1 <2.3 <3.2 <3.1 <2.4 Th-232 <10 <8.0 <7.2 <10 <8.2 <9.0 SA-MLK-5F2 K-40 1400+/-55 1300+/-67 1300+/-56 1300+/-54 1400+/-60 1300+/-53 1400+/-160 Co-60 <4.1 <3.4 <2.5 <2.5 <3.2 <3.4 Cs-137 4.4+/-1.8 2.6+/-1.4 <3.1 <2.2 2.2+/-1.1 <3.0 2.8+/-3.3 Ce-141 <5.4 <2.8 <2.5 <2.2 <3.5 <3.0 Th-232 <13 <9.8 <8.7 8.1+/-4. 7 <8.0 <9.6 -....) l.O SA-MLK-14Fl K-40 1400+/-59 1300+/-60 1300+/-57 1400+/-67 1400+/-60 1400+/-61 1400:1:220 Co-60 <3.0 <3.0 <5.2 <3.6 <3.2 <3.2 Cs-137 <2.3 <1.9 <3.4 <2.4 1.9+/-1.1 <2.4 Ce-141 <3.5 <3.4 <4.5 <2.9 2.4+/-1.5 <3.1 Th-232 <8.4 <7.8 <15 <8.9 <8.4 <8.9 SA-MLK-15Fl K-40 1300+/-54 1400+/-60 1400+/-54 1400+/-54 1200+/-52 1400+/-67 1400+/-230 Co-60 <4.9 <3.1 <3.2 5.5+/-2.3 <4.2 <3.6
. cs-137 2.6+/-1. 7 <2.4 <2.6 <3.7 <2.6 <2.6 Ce-141 <7.3 <3.2 <2.9 <3.0 <4.0 <2.8 Th-232 <8.6 <8.0 <9.5 <11 <8.5 <9.3 SA-MLK-3Gl K-40 1200+/-65(2) 1200+/-53(2) 1300+/-68 1400+/-61 1400+/-68 1400+/-66 1300:1:260 (Control) Co-60 <5.1 <3.1 <5.1 <3.0 <3.5 <3.7 Cs-137 <4.3 <2.0 <3.2 <2.4 <2.6 <2.4 Ce-141 <5.1 <3.3 <2.7 <3.1 <2.9 <2.8 Th-232 <15 <8.1 <11 <8.4 <9.3 <9.3 Grand Average K-40 1300+/-220 Co-60 Cs-137 Ce-141 Th-232
*All other gamma emitters searched for were <LLD; typical LLDs are given in Tables C-32 (RMC) and c-33 (PSE&G).
** sampling dates can be found in Table C-13.
Gamma analysis performed only on first milk collection of each month. (1) Not analyzed for Th-232. (2) Station SA-MLK-3G2 supplied the milk sample while station SA-MLK-3Gl replaced its entire herd.
. I TABLE C-13 1983 SAMPLING DATES FOR MILK SAMPLES STATION NO.
MONTH 13E3 2F4 5F2 14Fl 15Fl 3Gl JANUARY 1-02-83 1-03-83 1-03-83 1-02-83 1-03-83 1-02-83 to to to to to to 1-03-83 1-04-83 1-03-83 1-03-83 1-04-83 1-03-83 1-16-83 1-17-83 1-17-83 1-16-83 1-17-83 1-16-83 to to to to to to 1-17-83 1-18-83 1-17-83 1-17-83 1-18-83 1-17-83 FEBRUARY 2-07-83 2-06-83 2-06-83 2-06-83 2-06-83 2-07-83 to to to to to to 2-08-83 2-07-83 2-07-83 2-07-83 2-07-83 2-08-83 2-21-83 2-22-83 2-22-83 2-22-83 2-22-83 2-21-83 to to to to to to 2-22-83 2-23-83 2-22-83 2-23-83 2-23-83 2-22-83 MARCH 3-07-83 3-06-83 3-06-83 3-06-83 3-06-83 3-07-83 to to to to to to 00 3-08-83 3-07-83 3-07-83 3-07-83 3-07-83 3-08-83 0 3-21-83 3-20-83 3-20-83 3-20-83 3-20-83 3-21-83 to to to to to to 3-22-83 3-21-83 3-21-83 3-21-83 3-21-83 3-22-83 APRIL 4-04-83 4-03-83 4-03-83 4-03-83 4-03-83 4-04-83 to to to to to to 4-05-83 4-04-83 4-04-83 4-04-83 4-04-83 4-05-83 4-18-83 4-17-83 4-17-83 4-17-83 4-17-83 4-18-83 to to to to to to 4-19-83 4-18-83 4-18-83 4-18-83 4-18-83 4-19-83 MAY 5-02-83 5-01-83 5-01-83 5-01-83 5-01-83 5-02-83 to to to to to to 5-03-83 5-02-83 5-02-83 5-02-83 5-02-83 5-03-83 5-16-83 5-15-83 5-15-83 5-15-83 5-15-83 5-16-83 to to to to to to 5-17-83 5-16-83 5-16-83 5-16-83 5-16-83 5-17-83 JUNE 6-05-83 6-06-83 6-06-83 6-06-83 6-06-83 6-05-83 to to to to to to 6-07-83 6-07-83 6-07-83 6-06-83 6-06-83 6-06-83 6-19-83 6-20-83 6-20-83 6-20-83 6-20-83 6-20-83(1) to to to to to to 6-20-83 6-21-83 6-21-83 6-21-83 6-20-83 6-21-83
TABLE C-13 (cont'd) 1983 SAMPLING DATES FOR MILK SAMPLES STATION NO. MONTH 13E3 2F4 5F2 14Fl 15Fl 3Gl JULY 7-05-83 7-04-83 7-04-83 7-06-83 7-04-83 7-04-83 (1) to to to to to to 7-06-83 7-05-83 7-05-83 7-06-83 7-05-83 7-05-83 7-17-83 7-18-83 7-18-83 7-18-83 7-18-83 7-18-83 (1) to to to to to to 7-18-83 7-19-83 7-19-83 7-19-83 7-19-83 7-19-83 AUGUST 7-31-83 8-01-83 8-01-83 8-01-83 8-01-83 8-01-83 (1) to to to to to to 8-01-83 8-02-83 8-02-83 8-01-83 8-02-83 8-02-83 8-14-83 8-15-83 8-15-83 8-15-83 8-15-83 8-15-83 (1) to to to to to to 8-15-83 8-16-83 8-16-83 8-15-83 8-16-83 8-16-83 SEPTEMBER 9-05-83 9-06-83 9-06-83 9-06-83 9-06-83 9-05-83 to to to to to to 9-;-07-83 9-07-83 9-07-83 9-06-83 9-06-83 9-06-83 O'.l 9-19-83 9-18-83 9-18-83 9-18-83 9-18-83 9-19-83 I-' to to to to to to 9-20-83 9-19-83 9-19-83 9-19-83 9'-19-83 9-20-83 OCTOBER 10-03-83 10-02-83 10-02-83 10-02-83 10-02-83 10-03-83 to to to to to to 10-04-83 10-03-83 10-03-83 10-03-83 10-03-83 10-04-83 10-17-83 10-16-83 10-16-83 10-16-83 10-16-83 10-17-83 to to to to to to 10-18-83 10-17-83 10-17-83 10-17-83 10-17-83 10-18-83 NOVEMBER ll-06-83 ll-05-83 ll-05-83 ll-05-83 ll-05-83 ll-06-83 to to to to to to ll-07-83 ll-07-83 ll-06-83 ll-06-83 ll-06-83 ll-07-83 ll-20-83 ll-21-83 ll-21-83 ll-21-83 ll-21-83 ll-20-83 to to to to to to ll-22-83 ll-22-83 ll-21-83 11-22-83 11-22-83 ll-21-83 DECEMBER 12-05-83 12-05-83 12-05-83 12-05-83 12-05-83 12-04-83 to to to to to to 12-06-83 12-06-83 12-06-83 12-06-83 12-06-83 12-05-83 12-18-83 12-18-83 12-17-83 12-17-83 12-17-83 12-18-83 to to to to to to 12-19-83 12-19-83 12-18-83 12-18-83 12-18-83 12-19-83 (1) Station SA-MLK-3G2 supplied the milk sample while station SA-MLK-3Gl replaced its entire herd.
TABLE C-14 1983 CONCENTRATIONS OF GROSS ALPHA & GROSS BETA EMITTERS, POTASSIUM-40 AND TRITIUM IN WELL WATER Results in Units of pCi/L +/- 2 sigma Results* by Radiation Management Corporation STATION NO. RADIOACTIVITY 1-10-83 2-14-83 3-14-83 4-11-83 5-09-83 6-13-83 SA-WWA-4Sl Alpha <2.4 <1.5 <3.4 <l. 9 1.5+/-1.4 <2.6 Beta 13+/-3 12+/-2 14+/-3 13+/-4(1) 13+/-3 . 14+/-2 K-40 13+/-1 14+/-1 14+/-1 13+/-1 10+/-1 13+/-1 H-3 <140 <140 <140 <120 <130 <130 ()) N SA-WWA-5Dl Alpha <1.9 1.2+/-1.2 <2.5 <1.6 1.3+/-1.l 2.1+/-1.7 Beta 16+/-3 12+/-2 14+/-3 16+/-3 13+/-3 13+/-2 K-40 14+/-1 13+/-1 14+/-1 13+/-1 9.9+/-1.0 13+/-1 H-3 <140 <140 <130 <130 <120 <130 SA-WWA-3El (Control) Alpha <2.1 <1.2 <2.6 <1.4 <0.9 <2.6 Beta 14+/-3 9.5+/-1.6 10+/-3 9.8+/-2.2 7.6+/-2.3 12+/-2 K-40 9.4+/-0.9 8.8+/-0.9 9.5+/-1.0 7.2+/-0.7 7.2+/-0.7 9.4+/-0.9 H-3 <140 <140 <130 <120 <120 <130
TABLE C-14 (cont'd) 1983 CONCENTRATIONS OF GROSS ALPHA & GROSS BETA EMITTERS, POTASSIUM-40 AND TRITIUM IN WELL WATER Results in Units of pCi/L +/- 2 sigma Results by PSE&G Research Corporation STATION NO. RADIOACTIVITY 7-11-83 8-08-83 9-12-83 10-11-83 11-14-83 12-05-83 AVERAGE SA-WWA-4Sl (July-Sept.) SA-WWA-2S3** (Oct.-Dec.) Alpha 0.4+/-0.2 <1.1 <1.6 <2.6(2) 1.6+/-1.2 <l. 6 Beta 14+/-1 13+/-1 11+/-1 15+/-2 15+/-2 8.6+/-1.1 13+/-4 OJ K-40 20+/-2 20+/-2 17+/-2 27+/-3 18+/-2 9.0+/-0.9 16+/-10 w H-3 <130 <130 <130 <130 <130 <130 SA-WWA-5Dl Alpha 0.4+/-0.3 <1.3 <1.4 <2.4 <l. 8 <1.4 Beta 15+/-1 14+/-1 13+/-1 10+/-1 12+/-1 7.9+/-1.1 13+/-5 K-40 19+/-2 18+/-2 19+/-2 20+/-2 14+/-1 11+/-1 15+/-7 H-3 <120 <130 <140 <130 <130 <130 SA-WWA-3El (Control) Alpha <0.2 <l. 5 <l. 7 <2.4 <1.5 <1.4 Beta 9.8+/-1.1 8.8+/-1.1 9.9+/-1.1 8.4+/-1.1 9.3+/-1.1 12+/-1 10+/-4 K-40 14+/-2 14+/-1 14+/-1 16+/-2 9.2+/-0.9 8.9+/-0.9 11+/-6 H-3 <120 <130 <130 430+/-80 <140 <130
- Tritium results by PSE&G Research Corporation.
** Location 2S3 replaced 4Sl.
( 1) Results by Teledyne Isotopes. ( 2) Station SA-WWA-2S3 was collected on 10-24-83.
TABLE C-15 1983 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND GAMMA EMITTERS** IN QUARTERLY COMPOSITES OF WELL WATER Results in Units of pCi/L +/- 2 sigma (Results*** by PSE&G Research Corporation) 1-10-83 4-11-83 7-11-83 10-11-83 STATION NUMBER to to to to RADIOACTIVITY 3-14-83 6-13-83 9-12-83 12-05-83 SA-WWA-4Sl Sr-89 <0.6 <0.6 <0.5 <0.5(1) Sr-90 <0.5 <0.5 <0.4 <0.4(1) K-40 <7.8 15+/-10 <9.4 14+/-60) CD ""' SA-WWA-5Dl Sr-89 <0.6 <0.7 <0.5 <0.5 Sr-90 <0.4 <0.6 <0.4 <0.4 K-40 16+/-7 <11 <8.9 46+/-25 SA-WWA-3El (Control) Sr-89 <0.6 <0.7 <0.5 <0.5 Sr-90 <0.5 <0.6 <0.4 <0.4 K-40 <8.9 <9.3 <14 <9.8
- Sr-89 results are corrected for decay to sample stop date.
** All other gamma emitters searched for were <LLD; typical LLDs are given in Tables C-32 (RMC) and C-33 (PSE&G). *** First and second quarter gamma results by Radiation Management Corporation.
(1) Sample collected from station SA-WWA-2S3 on 10-24-83.
TABLE C-16 1983 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, POTASSIUM-40 AND TRITIUM IN RAW AND TREATED POTABLE WATER STATION NO. SA-PWR/T-2F3 Results in Units of pCi/L +/- 2 sigma Results by Radiation Management Corporation RADIOACTIVITY JANUARY FEBRUARY MARCH APRIL MAY JUNE Alpha (Raw) 0.9+/-0.5 0.8+/-0.6 0.8+/-0.6 1. 8+/-0. 7 <0. 8 1.2+/-0.8 (Treated) 1.2+/-0.7 <0.8 1.4+/-0.6 0.8+/-0.5 <0.9 <1.0 Beta (Raw) 3.0+/-0.5 3.2+/-0.5 2.6+/-0.4 3.2+/-0.4 3.0+/-0.4 3.8+/-0.5 (Treated) 2.6+/-0.5 2.3+/-0.5 2.4+/-0.4 2.1+/-0.4 2.3+/-0.4 2.1+/-0. 4 K-40 (Raw) 1. 9+/-0. 2 1. 5+/-0. 2 1.8+/-0.2 1.7+/-0.2 1.5+/-0.2 1.7+/-0.2(1) (Treated) 2.0+/-0.2 1. 5+/-0. 2 2.0+/-0.2 1.5+/-0.2 1.5+/-0.2 1. 7+/-0. 2 (1) 00 U1 H-3* (Raw) <140 <140 <130 <130 <130 140+/-80 (Treated) <140 <140 <130 <130 <130 <120 Results by PSE&G Research Corporation RADIOACTIVITY JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE Alpha (Raw) 3.1+/-1.6 <l. 7 <2.6 <l. 7 1.4+/-0.8 <0.5 1. 4+/-1. 6 (Treated) <1.4 <l. 6 <2.4 <l. 5 2.7+/-1.2 0.9+/-0.8
-Beta (Raw) 2.6+/-0.6 2.7+/-0.7 3.0+/-0.7 2.4+/-0.7 2.9+/-0.7 3.9+/-0.8 3.0+/-0.9 (Treated) 1. 8+/-0. 6 2.4+/-0.6 2.2+/-0.7 1.5+/-0.6 2.3+/-0.7 2.3+/-0.6 2.2+/-0.6 K-40 (Raw) 3.7+/-0.4 3.2+/-0.3 2.9+/-0.3 2.4+/-0.2 1. 7+/-0. 2 2.0+/-0.2 2.2+/-1.4 (Treated) 3.5+/-0.4 3.0+/-0.3 19+/-1. 9 2.5+/-0.3 1. 6+/-0. 2 2.0+/-0.2 3.5+/-9.8 H-3 (Raw) <130 160+/-80 200+/-80 <130 190+/-80 <130 (Treated) <130 <130 160+/-80 220+/-80 <130 <130
- Tritium results by PSE&G Research Corporation.
(1) K-40 results by Teledyne Isotopes.
TABLE C-17 1983 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND GAMMA EMITTERS** IN QUARTERLY COMPOSITES OF POTABLE WATER Results in Units of pCi/L +/- 2 sigma (Results*** by PSE&G Research Corporation) 1-01-83 4-01-83 7-01-83 10-01-83 STATION NUMBER to to to to RADIOACTIVITY 3-31-83 6-30-83 9-30-83 12-31-83 SA-PWR-2F3 (Raw) Sr-89 <0.8 <0.9 <1.7 <0.5 CXl Sr-90 <0.6 <0.7 <0.6 <0.4 O'I Gamma LLD LLD LLD LLD SA-PWT-2F3 (Treated) Sr-89 <0.8 <0.8 <0.8 <0.5 Sr-90 0.6+/-0.2 <0.7 <0.6 <0.4 Gamma LLD LLD LLD LLD
- Sr-89 results are corrected for decay to sample stop date.
** All gamma emitters searched for were <LLD; typical LLDs are given in Tables C-32 (RMC) and C-33 (PSE&G). *** First and second quarter gamma results by Radiation Management Corporation.
TABLE C-18 1983* CONCENTRATIONS OF STRONTIUM-89* AND -90 AND GAMMA EMITTERS** IN VEGETABLES Results in Units of pCi/kg (wet) +/- 2 sigma (Results by PSE&G Research Corporation) COLLECTION STATION NO. DATE(S) SAMPLE TYPE Sr-89 Sr-90 K-40 Ra-226 Th-232 SA-FPG-5Dl 8-01-83 Corn <26 <14 1300+/-700 <41 . <64 SA-FPV-5Dl 8-01-83 Peppers <24 <15 2300+/-230 <31 <50 SA-FPV-2El*** 5-15-83 Asparagus <20 <10 2400+/-240 <14 <23 SA-FPL-1F3 7-25-83 Cabbage <37 31+/-9 2200+/-210 <30 <56 SA-FPV-1F3 7-25-83 Peppers <29 <15 1800+/-62 < 3.7 < 6.7 CX> SA-FPV-5Fl 8-01-83 Tomatoes <20 <11 2400+/-240 <19 <52 -...J SA-FPG-14F3 8-01-83 Corn <20 <12 2000+/-240 <32 <46 SA-FPV-14F3 7/29-30/83 Tomatoes <25 <15 1400+/-170 <36 39+/-22 SA-FPG-lGl(C) 7-25-83 Corn <24 17+/-6 2400+/-230 <29 41+/-27 SA-FPV-lGl(C) 7-25-83 Peppers <23 <12 1500+/-53 <25 < 7.4 SA-FPV-lGl(C) 7-25-83 Tomatoes <21 <11 2100+/-55 <23 < 7.2 SA-FPG-3H4(C) 8-02-83 Corn <22 <12 3100+/-310 <23 <58 SA-FPV-3H4(C) 8-02-83 Cucumbers <22 19+/-6 1400+/-190 <17 <43 SA-FPV-3H4(C) .8-02-83 Peppers <22 <15 2100+/-220 <29 <49 SA-FPV-3H4(C) 8-02-83 Tomatoes <28 <15 2000+/-210 37+/-18* <42 Average 2000+/-980
- Sr-89 results are corrected for decay to sample stop date.
** All other gamma emitters searched for were <LLD; typical LLDs are given in Tables C-32 (RMC) and C-33 (PSE&G).
*** Results by Radiation Management Corporation.
(C) Control station
TABLE C-19 1983 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND GAMMA EMITTERS** IN GAME, MEAT AND BOVINE THYROID (Results by Radiation Management Corporation) Results in Units of Results in Units of pCi/kg (dry) +/- 2 sigma pCi/kg (wet) +/- 2 sigma COLLECTION STATION NO. DATE(S) SAMPLE TYPE Sr-89 Sr-90 K-40 SA-GAM-llDl 1/01-31/83 Muskrat <36 <29 2700+/-270 (Control) SA-GAM-3El 1/22-31/83 Muskrat <36 47+/-28 3000+/-300 00 00 SA-FPB-3El 2-07-83 Beef (1) ( 1) 2700+/-290 SA-THB-3El 2-07-83 Bovine Thyroid (1) (1) 1200+/-250 SA-FPB-14Fl*** 12-20-83 Beef (1) (1) 2300+/-160 SA-THB-14Fl 12-20-83 Bovine Thyroid (1) (1) 1900+/-500 (Control) AVERAGE Muskrat 2800+/-210 Beef 2500+/-280 Bovine Thyroid 1600+/-500
- Sr-89 results are corrected for decay to sample stop date.
** All other gamma emitters searched for were <LLD7 typical LLDs are given in Tables C-32 (RMC) and C-33 (PSE&G) ** *** Station No. 14Fl results by PSE&G Research Corporation.
(1) Strontium-89 and -90 analysis not required.
TABLE C-20 1983 CONCENTRATIONS OF GAMMA EMITTERS* IN FODDER CROPS Results in Units of pCi/kg (wet) +/- 2 sigma (All Results by PSE&G Research Corporation) COLLECTION STATION NO. DATE(S) SAMPLE TYPE Be-7 K-40 Co-60 Zr-95 Th-232 SA-FPG-3El 7-10-83 Barley 430+/-130 3700+/-340 <28 <38 40+/-26 <75 SA-FPG-3El 11-14-83 Soybeans <230 14000+/-720 <44 <52 <41 <108 SA-VGT-3El 7-12-83 Hay 520+/-110 13000+/-550 <28 <15 <36 109+/-52 00 \0 SA-VGT-2F4 9-02-83 Corn Silage 32+/-20 2200+/-73 < 4.4 < 6.8 <35 < 9.3 SA-VGT-5F2 10-23-83 Corn Silage 590+/-170 3800+/-440 <32 <48 59+/-35 <99 SA-VGT-14Fl 8/22-26/83 Corn Silage <580 3400+/-340 <33 <95 <48 <llO SA-FPG-15Fl 12/17-18/83 Soybeans <140 12000+/-550 <30 <34 <32 ll7+/-49 SA-VGT-15Fl 9-30-83 Corn Silage 68+/-13 400+/-36 < 3.1 < 4.0 < 4.2 < 9.5 SA-VGT-15Fl 10-02-83 Green Chop 100+/-17 820+/-44 < 2.3 < 4.2 <32 < 7.0 SA-FPG-3Gl(C) 11-14-83 Soybeans 290+/-140 14000+/-640 46+/-22 92+/-32 <52 <95 SA-VGT-3Gl(C) 9-06-83 Corn Silage 540+/-130 4200+/-440 <29 <41 <37 <78 Average 320+/-440 6500+/-11000
- All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-33.
(C) Control station
TABLE C-21 1983 CONCENTRATIONS OF STRONTIUM-90 AND GAMMA EMITTERS* IN SOIL Results in Units of pCi/kg (dry) +/- 2 sigma (All Results by PSE&G Research Corporation) COLLECTION STATION NO. DATE Sr-90 K-40 Cs-137 Ra-226 Th-232 SA-SOL-6Sl 5-23-83 49+/-15 9300+/-460 120+/-19 500+/-37 550+/-71 SA-SOL-SD! 5-23-83 140+/-20 6500+/-420 280+/-26 780+/-47 660+/-75 SA-SOL-lODl 5-24-83 220+/-22 8600+/-460 510+/-30 880+/-50 870+/-82 SA-SOL-2El 5-23-83 64+/-25 6600+/-350 420+/-25 1500+/-290 640+/-69 SA-SOL-16El 5-24-83 110+/-18 12000+/-530 180+/-26 2600+/-390 1200+/-94 l.O SA-SOL-lFl 5-23-83 99+/-21 4300+/-300 1600+/-43 390+/-31 340+/-47 0 SA-SOL-2Fl 5-23-83 160+/-32 9500+/-440 370+/-27 1900+/-280 890+/-81 SA-SOL-2F2 5-23-83 46+/-13 7600+/-440 190+/-20 480+/-39 430+/-60 SA-SOL-2F4 5-24-83 100+/-20 7800+/-450 400+/-27 950+/-50 700+/-79 SA-SOL-SF! 5-23-83 200+/-19 3900+/-300 560+/-28 560+/-36 410+/-53 SA-SOL-5F2 5-23-83 120+/-18 3800+/-320 370+/-25 570+/-39 450+/-59 SA-SOL-14Fl 5-24-83 62+/-17 13000+/-550 170+/-20 1200+/-52 1000+/-85 SA-SOL-15Fl 5-24-83 260+/-25 12000+/-620 550+/-35 1400+/-67 1200+/-100 SA-SOL-3Gl 5-24-83 120+/-16 8600+/-430 320+/-28 2200+/-380 810+/-80 (Control) SA-SOL-3H3 5-26-83 250+/-24 9100+/-450 910+/-38 2000+/-400 900+/-88 (Control) Average 130+/-140 8200+/-5700 460+/-750 1200+/-1400 740+/-550
- All other gamma emitters searched for were <LLD1 typical LLDs are given in Table C-33.
TABLE C-22 1983 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma Results by Radiation Management Corporation STATION NO. 1-03-83 2-09-83 3-09-83 4-05-83 5-05-83 6-08-83 SA-SWA-11Al <0.4 <0.2 <0.5 0.5+/-0.3 <0.8 0.4+/-0.2 SA-SWA-12Cl <0.3 <0.2 <0.5 <O. 5 <0.8 <0.2 (Control) SA-SWA-7El <0.4 <0.2 <O. 4 <0.3 <0.6 0.2+/-0.2 SA-SWA-1F2 <0.4 0.4+/-0.3 <0.5 <0.4 <0.6 <0.2 l.O I-' SA-SWA-16Fl <0.3 <0.2 <O. 4 <0.4 <O. 7 <0.2 Results by PSE&G Research Corporation STATION NO. 7-07-83 8-03-83 9-07-83 10-04-83 11-07-83 12-08-83 SA-SWA-llAl <2.0 <3.5 <5.0 <3.8 <4.3 <4.9 SA-SWA-12Cl <l. 5 <2.2 <1.8 <3.0 <3. 8 <3.8 (Control) SA-SWA-7El <l. 3 <1. 8 <2.5 <3.5 <3.5 <3.8 SA-SWA-1F2 <l. 5 1. 7+/-1. 4 <2.0 <2.8 <1.9 <3.6 SA-SWA-16Fl <2.0 <1.8 <3.6 <4.3 <4.9 <3.8
TABLE C-23 1983 CONCENTRATIONS OF GROSS BETA EMITTERS IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma Results by Radiation Management Corporation STATION NO. 1-03-83 2-09-83 3-09-83 4-05-83 5-05-83 6-08-83 SA-SWA-llAl 48+/-6 69+/-7 47+/-6 11+/-3 7.8+/-2.6 24+/-2 SA-SWA-12Cl 40+/-5 27+/-3 31+/-4 9.9+/-2.7 11+/-3 (Control) 20+/-2 SA-SWA-7El 78+/-8 58+/-6 63+/-7 24+/-4 9.7+/-2.8 37+/-4 SA-SWA-1F2 25+/-4 33+/-3 36+/-5 4.1+/-2.2 8.3+/-2.6 6. 8+/-1.4 SA-SWA-16Fl 38+/-5 43+/-4 39+/-5 8.3+/-2.5 5.0+/-2.4 11+/-2 l.D N Average 46+/-40 46+/-35 43+/-25 ll+/-15 8.4+/-4.5 20+/-24 Results by PSE&G Research Corporation STATION NO. 7-07-83 8-03-83 9-07-83 10-04-83 11-07-83 12-08-83 AVERAGE SA-SWA-llAl 53+/-6 59+/-6 110+/-10 120+/-11 84+/-9 12+/-3 54+/-75 SA-SWA-12Cl 31+/-4 45+/-6 71+/-8 86+/-9 66+/-8 (Control) 10+/-3 37+/-51 SA-SWA-7El 65+/-7 91+/-9 120+/-11 120+/-11 77+/-9 17+/-3 63+/-74 SA-SWA-1F2 21+/-4 31+/-4 63+/-7 73+/-8 52+/-6 8.6+/-2.4 30+/-46 SA-SWA-16Fl 34+/-5 40+/-5 65+/-7 85+/-9 74+/-8 7.6+/-2.3 37+/-54 Average 41+/-36 53+/-47 86+/-54 97+/-44 71+/-24 11+/-7 44+/-64
TABLE C-24 1983 CONCENTRATIONS OF TRITIUM IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma (All Results by PSE&G Research Corporation) STATION NO. 1-03-83 2-09-83 3-09-83 4-05-83 5-05-83 6-08-83 SA-SWA-llAl <130 <140 <140 <130 <130 160+/-80 SA-SWA-12Cl <130 <140 <140 <130 <130 160+/-80 \.D (Control) w SA-SWA-7El 180+/-100 <130 <140 <130 <130 <140 SA-SWA-1F2 <140 <140 <140 <130 <130 <130 SA-SWA-16Fl <140 <140 <140 <130 <130 <130 Average STATION NO. 7-07-83 8-03-83 9-07-83 10-04-83 11-07-83 12-08-83 SA-SWA-llAl 180+/-80 1260+/-100 230+/-80 330+/-80 350+/-80 <130 SA-SWA-12Cl 170+/-80 450+/-80 ?1 180+/-80 200+/-80 200+/-80 <130 (Control) SA-SWA-7El 160+/-80 150+/-80 <130 600+/-90 180+/-80 <130 SA-SWA-1F2 <120 170+/-80 <140 520+/-80 <130 <120 SA-SWA-16Fl 190+/-80 510+/-80 190+/-90 210+/-80 250+/-80 <130 Average 160+/-54 500+/-900 170+/-81 370+/-360 220+/-170
TABLE C-25 1983 CONCENTRATIONS OF GAMMA EMITTERS~ IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma Results by Radiation Management Corporation STATION NO. NUCLIDE 1-03-83 2-09-83 3-09-83 4-05-83 5-05-83 6-08-83 SA-SWA-llAl K-40 67+/-7 87+/-10 29+/-12 <16 Co-58 <16 16+/-7
<1.8 <1.0 <1.3 <1.3 <1.3 <0.6 Co-60 <0.8 <0.7 <0.8 <1.0 <Ll Mo-99 (1) (1)
<0.7 (1) (1) (1) (1)
La-140 <66 <22 <9.8 <7.6 <6.2 Ra-226 <l. 7 <2.3
<1.0 <1.6 <1.9 <1.8 <1.1 Th-232 <2.7 <1.8 <2.6 <3.3 <3.1 <2.0 SA-SWA-12Cl K-40 45+/-6 20+/-8 46+/-13 19+/-5 (Control) Co-58 <10 14+/-7
<1.3 <1.2 <1.5 <0.7 <0.9 <0.7 Co-60 <0.8 <1.1 <1.1 <0.6 <1.1 Mo-99 (1)
<0.7 (1) ( l) (1) (1) (1)
La-140 <48 <26 <14 <5.2 <5.l Ra-226 <1.3 <2.9
<1.3 <1.8 <1.1 <1.3 <1.2
~ Th-232 <1.9 <2.2 <3.4 <l. 7 <2.4 <2.0 ~ SA-SWA-7El K-40 88+/-9 66+/-9 94+/-11 18+/-8 Co-58 <11 30+/-8
<1.8 <1.0 <0.8 <0.8 <0.8 <0.6 Co-60 <0.9 <0.7 <0.6 <0.8 <0.7 Mo-99 (1)
<0.7 (1) ( 1) (1) (1) (1)
La-140 <50 <21 <9.0 <5.7 <4.9 Ra-226 <2.0
<l. 7 <1.1 <1.1 <1.4 <1.3 <1.2 Th-232 <2.8 <l.8 <l. 7 <2.1 <2.l <l.9 SA-SWA-1F2 K-40 21+/-4 23+/-9 53+/-10 <15 Co-58 <1.3 <14 <9.7
<1.2 <1.1 <1.0 <1.0 <0.8 Co-60 <0.8 <l.l <l.l <0.7 <0.8 Mo-99 (1) (1) <l.l (1) (1) (1) (1)
La-140 <56 <30 <10 <6.0 <5.4 Ra-226 <1.4 <2.1
<l.4 <l.3 <1.6 <1.6 <l.4 Th-232 <2.;t. <2.4 <2.3 <2.6 <2.6 <2.5 SA-SWA-16Fl K-40 38+/-4 22+/-9 3 2 :tlO <16 Co-58 <16 <8.6
<2.0 <1.1 <l.O <l.4 <l.3 <0.6 Co-60 <l.l <0.8 <0.8 <1.0 <l.0 Mo-99 (1) <0.8 (1) ( 1) (1) (1)
La-140 <60 (1)
<27 <8.7 <7.9 <6.4 <2.1 Ra-226 <l.9 <1.4 <l.4 <l.8 <1.8 Th-232 <2.9 <1.2
<2.0 <2.1 <3.3 <3.3 <l.9 Average K-40 52+/-52 44+/-62 51+/-52 16:tl 7
TABLE C-25 (Cont'd) 1983 CONCENTRATIONS OF GAMMA EMITTERS* IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma Results by PSE&G Research Corporation STATION NO. NUCLIDE 7-07-83 8-03-83 9-07-83 10-04-83 11-07-83 12-08-83 Average SA-SWA-llAl K-40 60+/-9 68+/-8 100+/-10 120+/-11 110+/-10 14+/-6 58+/-80 co-58 2.1+/-0.5 <0.5 0.8+/-0.4 <0.7 <0.4 <0.5 Co-60 <0.7 <0.7 <1.0 <0.9 <0.7 <0.7 Mo-99 <63 <36 <180 <190 120+/-45 <120 La-140 <1.3 <1.0 <1.9 <1.5 <l. 3 <1.3 Ra-226 <1.2 <1.0 <11 <13 <11 <1.0 Th-232 <2.4 <1.9 <2.4 <2.6 <2.1 <1.9 SA-SWA-12Cl K-40 23+/-7 53+/-9 75+/-9 92+/-9 89+/-9 10+/-6 41+/-61 (Control) Co-58 <0.6 <0.5 <0.7 <0.6 <0.5 <0.5 Co-60 <0.5 <0.5 <0.8 <0.7 <0.5 <0.6 Mo-99 <130 <29 <180 <210 <130 <78 La-140 <1.1 <1.0 <1.8 <1.4 <1.2 1.3+/-0.6 Ra-226 <9.1 <1.3 <9.5 <10 <8.5 <11 Th-232 <2.1 <2.3 <2.2 <2.3 <2.3 <2.2 l.D SA-SWA-7El K-40 74+/-9 75+/-10 110+/-11 110+/-11 120+/-11 16+/-7 68+/-79 Ul Co-58 <0.6 <0.7 <0.7 <0.8 <0.5 <0.8 Co-60 <0.7 <0.8 <0.7 <0.8 <0.8 <0.7 Mo-99 <130 <44 <170 <200 <59 <120 La-140 <1.6 <1.0 <2.0 <1.6 <l. 2 <1.2 Ra-226 <11 <1.3 <1.4 <1.3 <1.1 <0.9 Th-232 <2. 4 1.6+/-0.9 <3.1 <2.7 <2.5 <2.3 SA-SWA-1F2 K-40 26+/-6 24+/-6 68+/-8 77+/-10 70+/-9 <8.8 34+/-51 Co-58 <0.5 <0.5 <0.4 <0.7 <0.7 <0.8 Co-60 <0.6 <0.4 1.3+/-0.5 <0.7 <0.6 <0.6 Mo-99 <120 <27 <120 <180 <64 <150 La-140 <1.5 <0.7 <1.1 <1.6 <1.3 <1.3 Ra-226 <1.0 <7.5 <9.3 <1.1 <10 <0.9 Th-232 <1.9 <2.1 <2.2 <2.3 <2.1 <2.0 SA-SWA-16Fl K-40 28+/-8 38+/-8 66+/-9 72+/-10 85+/-10 <8.6 36+/-51 Co-58 <0.8 <0.6 <0.5 <0.5 <0.6 <0.4 Co-60 <0.8 <0.7 0.5+/-0.3 <0.6 <0.7 <0.7 Mo-99 <150 <95 <200 <150 <130 <71 La-140 <1.3 <1.1 <1.3 <1.1 <1.1 <1.9 Ra-226 <1.3 <1.3 0.9+/-0.4 <1.1 <1.2 <9.8 Th-232 <2.3 <2.3 <0.8 <2.7 <2.1 <2.0 Average K-40 42+/-46 52+/-42 84+/-40 94+/-41 95+/-40 11+/-7 Grand Average K-40 48+/-69
- All other gamma emitters searched for were <LLD; typical LLDs are given in Tables C-32 (RMC) and C-33 (PSE&G).
(1) Not analyzed for Mo-99 by Radiation Management Corporation.
TABLE C-26 1983 CONCENTRATIONS OF STRONTIUM-89* AND -90 IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma (All Results by PSE&G Research Corporation) 1-03-83 4-05-83 7-07-83 10-04-83 STATION NO. to to to to 3-09-83 6-08-83 9-07-83 12-08-83 Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 SA-SWA-llAl <0.6 <0.5 <1.1 <0.8 <0.7 <0.5 <0.8 <0.6 l.O O'I SA-SWA-12Cl <0.7 <0.5 <l. 0 <0.7 <0.6 <0.5 <0.7 <0.6 (Control) SA-SWA-7El <1.0 <0.5 <1.2 <0.9 <O. 7 <0. 6 <0.8 <0.7 SA-SWA-1F2 <0.7 <0.5 <1.0 <0.7 <0.7 <0.6 <0.7 <0.6 SA-SWA-16Fl <0.7 <0.5 <1.2 <O. 9 <O. 5 <0.4 <O. 8 <0.7
- Strontium-89 results are corrected for decay to sample stop date.
TABLE C-27 1983 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND TRITIUM IN EDIBLE FISH TRITIUM (FLESH) STRONTIUM (BONES) AQUEOUS FRACTION ORGANIC FRACTION pCi/kg (dry) +/- 2 sigma pCi/L +/- 2 sigma pCi/L +/- 2 sigma STATION NO. COLLECTION PERIOD Sr-89 Sr-90 H-3 H-3 SA-ESF-llAl 2-15-83 to 4-27-83** <82 <35 84+/-71 140+/-71 8-25-83 to 10-17-83*** <140 600+/-41 <140 <120 l.O .....] SA-ESF-12Cl 2-15-83 to 4-27-83** <79 <34 <110 400+/-75 (Control) 8-25-83 to 10-17-83*** <170 330+/-45 <140 <120 SA-ESF-7El 2-15-83 to 4-27-83** <64 <26 <110 220+/-72 8-25-83 to 10-17-83*** <270 110+/-38 <140 <120
- Sr-89 results are corrected for decay to sample stop date.
** All results by Radiation Management Corporation.
*** Strontium results by PSE&G Research Corporation.
Tritium results by NUS Corporation.
TABLE C-28 1983 CONCENTRATIONS OF GAMMA EMITTERS* IN EDIBLE FISH Results** in Units of pCi/kg (wet) +/- 2 sigma STATION NO. COLLECTION PERIOD Na-22 K-40 Cs-137 Ra-226 SA-ESF-llAl 2-15-83 to 4-27-83 (1) 3200+/-320 <14 <32 8-25-83 to 10-17-83 <18 2900+/-260 14+/-8 <32 SA-ESF-12Cl 2-15-83 to 4-27~83 ( 1) 2700+/-330 <22 <43 (Control) 8-25-83 to 10-17-83 <15 2700+/-240 <13 <18 SA-ESF-7El 2-15-83 to 4-27-83 (1 ) 2800+/-280 <14 <26 8-25~83 to 10-17-83 25+/-10 3400+/-280 <16 37+/-21 AVERAGE 3000+/-580
- All other gamma emitters searched for were <LLD; typical LLDs are given in Tables C-32 (RMC) and C-33 (PSE&G).
** Results for 2-15-83 to 4-27-83 samples by Radiation Management Corporation.
Results for 8-25-83 to 10-17-83 samples by PSE&G Research Corporation. (1) Not analyzed for Na-22.
TABLE C-29 1983 CONCENTRATIONS OF STRONTIUM-89* AND -90; GAMMA EMITTERS** AND TRITIUM IN BLUE CRABS Results in Units of COLLECTION Results in Units of pCi/kg (wet) +/- 2 sigma pCi/L +/- 2 sigma STATION NO. DATE SAMPLE Sr-89 Sr-90 K-40 Ra-226 H-3 J SA-ECH-llAl 6-24-83(1) Flesh <500 35+/-12 2600+/-450 <63 200+/-72 Shell (3) <1000 520+/-~0 (4) (4) (4) 9-19-83(2) Flesh <52 <20 1800+/-280 47+/-17 (5) Shell (3) <llO 250+/-21 (4) (4) (4) SA-ECH-12Cl 6-24-83(1) Flesh <300 25+/-17 3000+/-840 <130 180+/-72 ~ (Control) She11(3) <1000 540+/-30 (4) (4) (4) ~ 9-19-83(2) Flesh <46 <19 2000+/-250 52+/-25 (5) Shell (3) <130 570+/-27 (4) (4) (4) AVERAGE Flesh 2400+/-1100 190+/-28 Shell 470+/-300 (4) (4) (4)
- Sr-89 results are corrected for decay to sample stop date.
** All other gamma emitters searched for were <LLD; typical LLDs are given in Tables C-32 (RMC) and C-33 (PSE&G).
(1) Strontium results by Teledyne Isotopes. Gamma and tritium results by Radiation Management Corporation. (2) Strontium and .gamma results by PSE&G Research Corporation. Tritium results by NUS Corporation. (3) Strontium results in units of pCi/kg (dry). High Sr-89 LLD due to insufficient sample. (4) Gamma and tritium analysis not required. (5) Not analyzed due to insufficient sample.
TABLE C-30 1983 CONCENTRATIONS OF SR-89* AND -90 AND GAMMA EMITTERS** IN BENTHIC ORGANISMS Results*** in Units of pCi/kg (dry) +/- 2 sigma COLLECTION STATION NO. DATE Sr-89 Sr-90 Mn-54 Ra-226 Th-232 SA-ESB-llAl 5-10-83 <10000 250+/-130 (1) (1) (1) 9-19-83 <5800 <27.00 <9900 15000+/-9500 <25000 SA-ESB-12Cl 5-10-83 <100000 <2000 (1) (1) (1) (Control) 9-19-83 <1400 <690 <5000 <8600 <16000 I-' SA-ESB-7El 5-10-83 <20000 <300 (1) (1) (1) 0 9-19-83 <1300 <600 <3700 <67000 11000+/-5600 0 SA-ESB-16Fl 5-10-83 <700000 <10000 (1) (1) (1) 9-19-83 <18000 <8600 34000+/-16000 <490000 <120000 NOTE: Analyses performed on benthic organisms have extremely high uncertainties and sensitivities due to the unavailability of an adequate sample. Sample sizes ranged from 0.1 grams to 0.7 grams.
- 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-33. *** Results for May samples by Teledyne Isotopes.
Results for September samples by PSE&G Research Corporation. (1) Not analyzed for gamma emitters by Teledyne Isotopes.
TABLE C-31 1983 CONCENTRATIONS OF STRONTIUM-90 AND GAMMA EMITTERS* IN SEDIMENT** Results*** in Units of pCi/kg (dry) +/- 2 sigma STATION NO. DATE Sr-90 K-40 Co-58 Co-60 Cs-137 Ra-226 Th-232 SA-ESS-llAl 5-11-83 <31 15000+/-1500 <57 83+/-35 160+/-38 640+/-74 910+/-110 9-19-83 <23 12000+/-630 <44 58+/-23 100+/-20 720+/-50 830+/-99 SA-ESS-12Cl (Control) I-' 5-11-83 <33 14000+/-1400 <54 <36 35+/-21 690+/-69 840+/-100 0 I-' 9-19-83 <25 16000+/-810 <50 <54 <37 690+/-60 1100+/-110 SA-ESS-7El 5-11-83 <30 12000+/-1200 <56 <45 100+/-27 800+/-80 950+/-95 9-19-83 <34 8300+/-520 <45 <43 <42 1200+/-380 590+/-84 SA-ESS-16Fl 5-11-83 <46 15000+/-1500 <88 <81 <61 570+/-110 1000+/-160 9-19-83 <27 16000+/-690 44+/-27 48+/-29 <31 1600+/-410 970+/-110 AVERAGE 14000+/-5300 860+/-710 900+/-300
- All other gamma emitters searched for were <LLD; typical LLDs are given in Tables C-32 (RMC) and C-33 (PSE&G).
** Sediment samples which include benthic organisms constitute the benthos sample. *** Results for May samples by Radiation Management Corporation.
Results for September samples by PSE&G Research Corporation.
TABLE C-32 RADIATION MANAGEMENT CORPORATION .LLDs FOR GAMMA SPECTROMETRY AIR WELL/POTABLE FOOD MEAT AND PARTICULATES PRECIPITATION MILK WATER PRODUCTS GAME NUCLIDES (lo-3pci/m3) (pCi/L) (pCi/L) (pCi/L) (pCi/g-wet) (pCi/g-wet) Be-7 8.1 7.6 6.3 0.02 0.04 Na-22 0.3 0.8 1.0 0.8 0.003 0.006 K-40 5.5 7.8 7.0 0.6 Cr-51 3.2 7.8 7.9 5.9 0.02 0.06 Mn-54 0.3 0.7 1. 0 0.6 0.003 0.006 Co-57 Co-58 0.4 2.0 0.8 1.1 0.7 0.002 0.007 Fe-59 0.7 1. 7 2.0 1.4 0.007 0.008 Co-60 0.3 0.8 0.9 0.6 0.002 0.003 Zn-65 0.7 1.5 1. 7 1.4 0.005 0.006 I-' Zr-95 0.7 * * * *
- 0 Nb-95 0.4 * * * *
- N ZrNb-95
- 0.6 0.9 0.6 0.002 0.002 Mo-99 17 160 87 52 0.4 0.4 Ru-103 0.4 * * * *
- Ru-106 3.4 6.5 8.0 6.3 0.2 0.06 Ag-llOm 0.3 0.7 1. 0 0.6 0.002 0.006 Sb-125 0.7 Te-129m 3.4 17
- 19
- 13 *
- 0.05
- 0.08 I-131 0.6 3.5 1.9 1.4 0.01 0.009 Te-132 1. 3 11 4.9 3.7 0.03 0.03 I-133 * * *
- 0.06 0.8 Cs-134 0.3 0.6 1.0 0.6 0.002 0.002 Cs-136 0.5 2.3 2.6 1. 6 0.1 0.01 Cs-137 0.4 0.8 1.1 0.6 0.002 0.006 Ba-140 1.5 * * * *
- La-140 0.7 * * * *
- BaLa-140
- 2.4 1. 7 1.3 0.006 0.01 Ce-141 0.5 * * *
- Ce-144 1.6 3.3 3.2 1.6 0.007
- 0.02 Ra-226 1. 0 1.2 1.6 1. 2 0.003 0.003 Th-232 1.5 3.1 3.1 3.1 0.008 0.03
TABLE C-32 (Cont'd) RADIATION MANAGEMENT CORPORATION LLDs FOR GAMMA SPECTROMETRY FODDER SURFACE FISH SHELLFISH SEDIMENT CROPS WATER NUCLIDES (pCi/g-wet) (pCi/L) (pCi/g-wet) (pCi/g-wet) (pCi/g-dry) Be-7 0.2 5.2 0.1 0.1 0.3 Na-22 0.02 0.6 0.01 0.02
- K-40 7.8 Cr-51 0.2 5.6 0.1 0.1 0.5 Mn-54 0.02 0.6 0.01 0.01 0.02 Co-57 * * *
- 0.02 Co-58 0.02 0.7 0.01 0.02 0.03 Fe-59 0.07 1.4 0.02 0.04 0.08 Co-60 0.03 0.6 0.01 0.02 0.03 I-'
Zn-65 0.06 1.4 0.02 0.03 0.05 0 Zr-95 * * *
- 0.05 w Nb-95 ZrNb-95
- 0.03
- 0.6
- 0.009
- 0.02 0.05 Mo-99 0.4 27 36 3.6 Ru-103
- Ru-106 0.3 6.3 0.08 0.1 0.04 0.2 Ag-llOm 0.03 0.6 0.01 0.02 0.02 Sb-125 * * *
- 0.06 Te-129m 0.5 11 0.2 0.2 1. 5 I-131 0.04 1.1 0.07 0.04 0.6 Te-132 0.04 2.1 1.4 0.2
- I-133 0.6 * * *
- Cs-134 0.03 0.6 0.01 0.01 0.02 Cs-136 0.06 1.4 0.05 0.03 0.2 Cs-137 0.03 0.6 0.009 0.02 0.03 Ba-140 * * *
- 0.8 La-140 * * *
- 0.2 BaLa-140 0.04 1.0 0.04 0.03
- Ce-141 * * *
- 0.06 Ce-144 0.09 1.6 0.03 0.05 0.1 Ra-226 0.05 1.1 0.02 0.03 Th-232 0.1 3.1 0.03 0.06
- Indicates a positive concentration was measured in all samples analyzed.
- Indicates that no LLD was calculated for that nuclide in that media.
TABLE C-33 1983 PSE&G RESEARCH CORPORATION LLDs FOR GAMMA SPECTROMETRY AIR WELL/POTABLE FOOD MEAT AND FODDER PARTICULATES PRECIPITATION MILK WATER PRODUCTS GAME CROPS NUCLIDES 110-3pci/rn3) (pCi/L) (pCi/L) (pCi/L) (pCi/kg-wet) (pCi/kg-wet) (pCi/kg-wet) Be-7 20 6.7 180 110 260 Na-22 0.8 1.1 6.0 2.0 21 13 80 K-40 14 15 16 Cr-51 6.1 14 18 10 190 130 240 Mn-54 0.8 0.7 2.8 0.81 22 11 30 Co-58 0.7 0.9 2.6 0.92 22 7.6 37 Fe-59 1.6 2.3 6.6 2.9 50 42 100 Co-60 0.7 1. 0 4.2 0.85 52 12 42 zn-65 1. 7 1.9 7.0 1.6 51 24 93 I-' Nb-95 0.8 1. 7 2.7 0.96 23 0 19 52 ~ zr-95 1.5" 1. 8 4.8 1.5 35 23 63 Mo-99 44 .. 28 1300 3500 580
- Ru-103 7.4 1.4 2.3 0.96 21 12 40 Ru-106 6.2 6.8 23 8.4 200 80 240 Ag-llOm 10 o.80 2.6 0.78 19 13 60 Sb-125 1.9 2.0 6.6 1.8 53 28 67 Te-129rn 32 27 90 40 790 100 1800 I-131 1.4 18 2.8 13 46 19 230 Te-132 4.9 2400 3.0 1400 210 41 Cs-134 7.9 1.0 3.0 0.90 20 13 33 Cs-136 1.2 5.0 3.0 3.8 30 17 95 Cs-137 1.0 0.80 3.0 0.76 22 14 38 Ba-140 3.7 2.2 9.7 15 110 r 71 280 La-140 1.6 6.5 3.0 6.6 34 20 91 Ce-141 0.9 1. 8 3.4 1. 3 29 19 40
- Ce-144 2.7 3.8 14 3.6 100 47 150 Ra-226 1. 8 18 5.7 15 44 170 41 Th-232 2.5 3.4 11 3.2 70 39 110
TABLE C-33 (cont'd) 1983 PSE&G RESEARCH CORPORATION LLDs FOR GAMMA SPECTROMETRY SURFACE FISH SHELLFISH SEDIMENT SOIL AIR WATER IODINE NUCLIDES (pCi/L) (pCi/kg-wet) (pCi/kg-wet) (pCi/kg-dry) (pCi/kg-dry) NUCLIDES c10-3pci/m3) Be-7 6.7 160 330 570 1100 I-131 7.3 Na-22 0.97 27 27 68 48 I-132 12 K-40 I-133 24 Cr-51 6.9 210 570 880 2300 I-135 2.7 Mn-54 0.76 18 31 62 45 Co-58 0.90, 18 33 72 63 Fe-59 1.8 46 110 180 26 Co-60 0.94 20 30 78 57 Zn-65 1.8 40 51 130 100 Nb-95 0.9 24 82 99 220 Zr-95 1.6 33 51 140 210 I-' Mo-99 * * * *
- 0 78 120 lTI Ru-103 0.82 19 43 Ru-106 6.5 150 260 490 500 Ag-llOm 0.87 15 22 64 130 Sb-125 1.7 45 65 130 140 Te-129m 37 740 370 2700 5500 I-131 1. 7 1300 1000 600 4300 Te-132 9.8 * * *
- Cs-134 0.66 17 21 48 62 Cs-136 1.2 190 210 300 960 Cs-137 0.91 18 22 52 38 Ba-140 4.3 690 720 940 3600 La-140 2.2 220 300 350 1100 Ce-141 1.0 29 64 130 240 Ce-144 3.5 82 100 320 250 Ra-226 12 340 52 Th-232 3.4 59 120
- Indicates a positive concentration was measured in all samples analyzed.
- Indicates that no LLD was calculated for that nuclide in that media.
APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES 107
SYNOPSIS OF ANALYTICAL PROCEDURES Appendix D presents a synopsis of the analytical procedures utilized by various laboratories for analyzing the 1983 Artificial Island Radiological Environmental Monitoring Program samples. LAB* TABLE OF CONTENTS PAGE GROSS ALPHA PSE&G Analysis of Air Particulates ******************** 111 TI Analysis of Air Particulates .******************* 113 PSE&G Analysis of Water **********.**********.********* 114 RMC Analysis of Water ******************************* 115 GROSS BETA PSE&G Analysis of Air Particulates ******************** 116 TI Analysis of Air Particulates **.***************** 118 PSE&G Analysis of Water .....*. o c o *
- Q D * *
- e * * * * * * * * * * * *
- 119 RMC Analysis of Water *****************.************* 120 POTASSIUM-40 PSE&G Analysis of Water ******************************. 121 RMC Analysis of Water ************************.****** 122 TRITIUM PSE&G Analysis of Water ******************************* 123 RMC Analysis of Samples (combined procedures) ******* 124 NUS Analysis of Aqueous Fraction of Biological Materials. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 7 NUS Analysis of Organic Fraction of Biological Materials . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . e e c ca Q D 128 IODINE-=131 PSE&G Analysis of Filtered Air ****** ~ ***************** 129 TI Analysis of Filtered Air ************************ 131 PSE&G Analysis of Raw Milk **************************** 132 PSE&G Analysis of Bovine Thyroid ********************** 134 RMC Analysis of Samples (combined procedures) ******* 136 109
SYNOPSIS OF ANALYTICAL PROCEDURES (cont'd) LAB* TABLE OF CONTENTS PAGE STRONTIUM-89 AND -90 PSE&G Analysis of Air ParticulateSccooeciceoooceoeeooo* 138 TI Analysis of Air Particulates ******************** 141 PSE&G Analysis of Raw Milk ... o . c o . a o c . o o Clo * * * * * * * * * *
- Q 143 PSE&G Analysis of Water ** Cl ** D
- Cl
- Ill Cl c o G c .... Cl ************ 146 PSE&G Analysis of Vegetation, Meat and Aquatic Samples 149 PSE&G Analysis of Bone and Shellc ... Cl ***************** 152 PSE&G Analysis of Soil and Sediment ******.*****.****** 155 PSE&G Analysis of Samples for Stable Strontium ******** 158 RMC Analysis of Samples (combined procedures} ******* 160 GAMMA SPECTROMETRY PSE&G Analysis of Air Particulates ******************** 163 TI Analysis of Air Particulates *******************. 165 PSE&G Analysis of Raw l\1ilk e Cle e 0 D 0 Ce e Cl 0 e Cle e e e e e ~ e e e e e e Cl 166 PSE&G Analysis of Water ******** o Cl., Cl. e ** e . . . . . . . . . . . . . . . 168 PSE&G Analysis of Solids (combined procedures} ******** 170 RMC Analysis of Samples (combined procedures) ******* 172 ENVIRONMENTAL DOSIMETRY TI Analysis of Thermoluminescent Dosimeters **.****. 174 RMC Analysis of Thermoluminescent Dosimeters ******** 175
- PSE&G - PSE&G Research Corporation TI - Teledyne Isotopes RMC - Radiation Management Corporation NUS - NUS Corporation 110
SYNOPSIS 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 into account the air pressure correction due to the vacuum being drawn, the correction factor of the temperature-corrected gas meter as well as the gas meter efficiency itself. Calculation of Gross Alpha Activity: 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, nHg v Time-averaged vacuum during sampling period, wHg 29.92 Standard atmospheric pressure at 32°F, nHg 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 (= % efficiency/100) v Corrected air flow, m3 p Pressure correction factor Using these corrected air flows, the gross alpha activity is computed as follows: Result (pCi/m3) (G-B)/T (2.22)*(E)*(V) G Sample gross counts B Background counts (from blank filter) T Count time of sample and blank, mins. E Fractional 241Am counting efficiency v Corrected air flow of sample, m3 2.22 No. of dpm per pCi 111
2-sigma error (pCi/m3) (l.9G*(G+B)l/2)*A (G-B) A Gross alpha activity, pCi/m3 G Sample gross counts B Background counts (from blank filter) Calculation of lower limit of detection: A sample activity is assumed to be LLD if the sample net count is less than 4.66 times the standard deviation of the count on the blank. LLD(pCi/m3) = 4.66 * (B)l/2 (2.22)*(E)*(V)*(T) B Background counts (from blank filter) E Fractional 241Am counting efficiency V Corrected air flow of sample, m3 T = Count time of blank, mins. 112
SYNOPSIS OF TELEDYNE 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 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) +/- crm*((G/T +B)/T)l/2 (2.22*V*Y*D*E) (2.22*V*Y*D*E) Where G Total sample counts B Background counts per minute T Sample count time, mins. 2.22 dpm/pCi v Sample volume, m3 y Chemical yield (Y = 1 in this case) D Decay factor from collection to count date (D 1 in this case) E Counter efficiency am Multiples of counting error If the net activity (G/T -B) is equal to or less* than the counting error, then the activity is considered to be the minimum detectable level, or MDL. where MDL 3* ( 2*B/T) 1/2 (2.22*V*Y*D*E) Variables are as previously defined 113
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE GROSS ALPHA ANALYSIS OF WATER SAMPLES The sample is thoroughly mixed. Then, a 250ml portion of sample and an equal volume of deionized water blank are acidified with dilute sulfuric acid. Barium carrier is added and the sample heated to 50°C in order to help precipitate barium sulfate. Maintaining the same temperature for the remainder of the procedure, iron carrier is then introduced. After a 30 minute equilibration period, the sample is neutralized with dilute ammonium hydroxide to precipitate ferric hydroxide. The mixed precipitates are then 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) (l.96*(G+B)l/2)*A (G-B) A Gross alpha activity, pCi/L G Sample gross counts B Background counts (from blank sample) 114
SYNOPSIS OF RADIATION MANAGEMENT CORPORATION PROCEDURE GROSS ALPHA ANALYSIS OF SAMPLES Total Water (A0, Al) A 250 ml (A0) or one 1 (Al) aliquot of the sample is evaporated to dryness on a hot plate in a preweighed, 2 X 1/4 ringed planchet, allowed to cool, and re-11 11 weighed. The planchet is counted in a low-background, gas flow proportional counter. Self-absorption corrections are made based on the measured sample weight and calculated thickness. The calibration standard used is Pu-239. A 250 ml or one 1 sample of distilled water is evaporated in the same manner and used as a blank. Total Salt Water (AA) Alpha emitters are concentrated initially from a liter aliquot of water sample by coprecipitation with magnesium hydroxide. The precipitate is then dissolved in hydrochloric acid and titanium trichloride is added to the solution. The alpha emitters are coprecipitated by adding barium chloride and sulfuric acid to pre-cipitate barium sulfate. The precipitate is transferred to a tared stainless steel planchet and dried. The planchet is reweighed and counted in a low back-ground gas-flow proportional counter. Self-absorption corrections are made on the basis of the weight of the precipitate. Calculations are made utilizing the following equations: Result (pCi/l) = ((S/T) - (B/t)) I (2.22 VE TF) 2 sigma error (pCi/l) = 2 ((S/T 2) + (B/t 2)) 1/ 2 / (2.22 VE TF) where: S = Gross counts of sample B = Counts of blank . E = Fractional Pu-239 counting efficiency T = Number of minutes sample was counted t = Number of minutes blank was counted V = Sample aliquot size {liters) TF = Transmission factor {based on net weight of sample in counting planchet) Calculation of lower limit of detection (LLD) The detection limit is assumed to be exceeded when the counting result is different from the blank reading by at least 4.66 times the standard deviation of that back-ground. LLD {pCi/l) = 4.66 (sl/Z) I (2.22 VE- TF t) where: B = Counts of blank E = Fractional Pu-239 counting efficiency t = Number of minutes blank was counted v = *Sample aliquot size (liters) TF = Transmission factor (based on net weight of sample in counting planchet) 115
SYNOPSIS 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 specific 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)/29092 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*Oo946*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 (= % 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/m3) (G-B)/T (2.22)*(E)*(V) G Sample gross counts B Background counts (from blank filter) T Count time 9f sample and blank, minso E Fractional 90sr counting efficiency v Corrected air flow of sample, m3 2.22 No. of"dpm per pCi 116
2-sigma error (pCi/m3) = (l.96*(G+B)l/2)*A (G-B) A Gross beta activity, pCi/m3 G Sample gross counts B Background counts (from blank filter) Calculation of lower limit of detection: A sample activity is assumed to be LLD if the sample net count is less than 4.66 times the standard deviation of the count on the blank. LLD(pCi/m3) = 4
- 66 * ( B ) 1/ 2 (2.22)*(E)*(V)*(T)
B Background counts (from blank filter) E = Fractional 90sr counting efficiency v Corrected air flow of sample, m3 T Count time of blank, mins. 117
SYNOPSIS OF TELEDYNE 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 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) Clffi* ( (G/T +B) /T) 1/2 (2.22*V*Y*D*E) (2. 22*V*Y*D*E) Where G = Total sample counts B = Background counts per minute T = Sample count time, mins. 2.22 = dpm/pCi v = Sample volume, m3 y = Chemical yield (Y
= 1 in this case)
D Decay factor from collection to count date (D =1 in this case) E Counter efficiency crm = Multiples of counting error If the net activity (G/T -B) is equal to or less than the counting error, then the activity is considered to be the minimum detectable level, or MDL. where MDL= 3*(2*B/T)l/2 ( 2. 22*V*Y*D*E) Variables are as previously defined 118
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE GROSS BETA ANALYSIS OF WATER SAMPLES The sample is mixed thoroughly. Then, a 1.0 liter portion is removed from 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 planchets 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 geometry. 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 dpm per pCi 2-sigma error (pCi/L) (l.96*(G+B)l/2)*A (G-B) A Gross beta activity, pCi/L G Sample gross counts B Background counts (from blank sample) 119
SYNOPSIS OF RADIATION MANAGEMENT CORPORATION PROCEDURE GROSS BETA ANALYSIS OF SAMPLES Total Water (80, Bl) A 250 ml (B~) or one 1 (Bl) aliquot is evaoorated to dryness on a hot plate in a preweighed, 2" X 1/4", ringed planchet and reweighed. The planchet is then counted in a low background gas-flow proportional counter. Self-absorotion corrections are made based on the measured residue weight and calculated thickness. The calibration standard used is Sr Y-90. A 250 ml or one 1 sample of distilled water is evapo-rated in the same manner and used as a blank. Calculations are made. utilizing the following equations: Result (pCi/l) =((SIT) - (B/t)) I (2.22 VE TP) 2 sigma error (pCi/l) = 2 ((S/T 2) + (B/t 2)) 112 / (2.22 V E TF) where: s = Gross counts of sample B = Counts of blank E = Fractional Sr-90-Y-90 counting efficiency T = Number of minutes samole was counted t = Number of minutes blank was counted v = Volume of aliquot (liters) TF = Transmission factor (based on net weight of sample in counting planchet) Calculation of lower limit of detection (LLD) The detection limit is assumed to be exceeded when the counting result for the sample is different from the blank reading by at least 4.66 times the standard deviation of that background. LLD (oCi/l) = 4.66 (B 1/ 2) I (2.22 VE TF t) where: B = Counts of blank E = Fractional Sr-90-Y-90 counting ~fficiency t = Number of minutes blank wai counted* v = Volume of aliquot (liters) TF = Transmission factor (based on net weight of sample in counting planchet) 120
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE ANALYSIS OF WATER FOR POTASSIUM 40 Water samples (with the exception of rain water) received by the Research and Testing Laboratory are routinely analyzed for potassium by the Chemical Division. The results, reported in parts per million (ppm), are converted to pCi/L by means of a computer program. Calculation of 40K Activity: 40K Activity (pCi/L) = 0.85*C 0.85 Proportionality constant for converting ppm to pCi/L C Potassium concentration, ppm 121
SYNOPSIS OF RADIATION MANAGEMENT CORPORATION PROCEDURE ANALYSIS OF WATER SAMPLES FOR POTASSIUM-40 BY AA (E0) Sample Preparation An aliquot sample size of 100 ml is filtered. The concentration of ootassium is determined soectroohotometrically on a Perkin Elmer Model 373 atomic absorotion unit. The result obtained, in micrograms per milliliter is multiplied by the 9 specific activity of 0.12% for natural potassium to determine the amount of potassium-40 oresent in the samole. The error reported is 10% of the result. A sample of distilled water is processed as a blank. Calculations are made using the following equations: K-40 ( pCi /l ) = Cs D ( C/S) K LLD (pCi/l) = Cs D (. l/S) K where: Cs = Concentration of Standard (µg K/ml) c = Sample reading s = Standard reading D = Dilution factor K = Specific activity of K-40 per unit weight of potassium (.852 pCi/mg) 122
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE ANALYSIS OF WATER FOR TRITIUM Approximately 50ml of raw sample is mixed with sodium hydroxide and potassium permanganate and is distilled under vacuum. Eight ml of distilled sample is mixed with lOml of InstagelR liquid scintillation solution, and placed in the liquid scintillation spectrometer for counting. An internal standard is prepared by mixing eight ml of sample, 10 ml of Instagel, and O.lrnl of a standard with known activity. The efficiency is determined from this. Also prepared is a blank consisting of eight ml of distilled low-tritiated water and lOml of Instagel, to be used for a background determination. This is done for each pair of samples to be counted. Activity is computed as follows: 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 (ml) T Count time (min) 2.22 DPM/pCi 1000 Number of ml 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 95% confidence limit, as follows: l.96*(G/T2+B/T2)1/2*(1000) 2.22*(V)*(E) Samples are designated LLD if the activity is less than the following value: LLD (pCi/L) (4.66)*(B)l/2*(1000) 2.22*(V)*(E)*(T) 123
SYNOPSIS OF RADIATION MANAGEMENT CORPORATION PROCEDURE ANALYSIS OF SAMPLES FOR TRITIUM Water (H2) A 15 ml aliquot of the samole is vacuum distilled to eliminate dissolved gases and non-volatile matter. The distillate is frozen in a trao cooled with a dry ice-isopropanol mixture. Eight (8) ml of the distillate are mixed with ten (10) ml of Insta-Gel liquid scintillation solution. The samole is then counted for tritium in a liquid scintillation counter. A sample of low tritium (<50 pCi/1) water is vacuum distilled as a blank and is counted with each batch of samoles. In the calculation of the result it is assumed that the condensated and original sample are of equivalent volumes. The volume change associated with the removal of dissolved gases and non-volatile matter is not significant compared to the other errors in the analysis. Calculations are made utilizing the following equations: Result (pCi/1) = ((S/T) - (B/t)) I (2.22 VE) 2 sigma error (pCi/l) = 2 ((S/T 2) + (B/t 2)) 112 I (2.22 VE) where: s = Total gross counts of sample B = Counts of blank E = Fractional H-3 counting efficiency T = Number of minutes sample was counted t = Number of minutes blank was counted v = Aliquot volume (liters) Gross counts of sample may be corrected for the blank activity. If the collection container is rinsed with distilled water and the rinse is added to the samole, the rinse plus sample and a separate aliquot of the distilled water are counted. The corrected gross counts for the sample only are calculated using the following equa-tions: s = ((s-b)v) I G s = (c(G+H)) IV b = (d(H)) IV v* = G V/(G+H) where: s = Gross counts of sample G = Volume of sample H = Volume of rinse s = Volume corrected gross counts of sample plus rinse b = Volume corrected gross counts of rinse v = Corrected aliquot volume c = Uncorrected gross counts of samole plus rinse d = Uncorrected gros~ counts of rinse 124
Calculation of lower limit of detection (LLD) The detection limit is assumed to be exceeded when the counting result is different from the blank reading by at least 4.66 times the standard deviation of that background. LLD (pCi/l) = 4.66 (B 112 ) I (2.22 VE t) where: B = Counts of blank E = Fractional H-3 counting efficiency t = Number of minutes blank was counted V = Aliquot volume (liters) Aqueous and Organic Fraction of Milk or Organic Solids (H3, H4, H9) A carefully measured aliquot of a food product, such as milk or fish, is dried in a rotating vacuum flash evaporator. During the evaporation process, the evaporated water fraction is trapped out by a dry ice isopropanol mixture for counting as in (a) below. The dried residue is reserved for (b). The wet sample is analyzed as in (c).
- a. Aqueous H-3 in Food Products An eight (8) ml aliquot of the cold-trapped water is counted in a liquid scintillation counter in the same manner as surface water samoles are counted.
- b. Organic Bound H-3 in Food Products The dried residue is combusted in an RMC designed oxidizer. The collected water - organic fraction is measured and vacuum distilled to remove any impurities. Permanganate in KOH solution is added to remove impurities which may cause quenching. An eight (8) ml aliquot is counted in a liquid scintillation counter. If less than eight (8) ml a*re collected, the entire portion collected is carefully measured with a 10 ml pipette and then counted.
A sample of deep well water is counted as a blank. *
- c. Aqu*eous and Organic Bound H-3 in Food Products A wet weight aliquot is combusted in an RMC designed oxidizer. The collected water fraction is measured and vacuum distilled to remove any impurities. Per-manganate in KOH solution is added to remove impurities which may cause quenching.
An eight (8) ml aliquot is counted in a liquid scintillation counter. If less than eight (8) ml are collected, the entire portion collected is carefully measured with a 10 ml pipette and then counted. A sample of deep well water is counted as a blank. Calculations are made utilizing the following equations: Result (pCi/l) = ((S/T) (B/t)) I (2.22 V E) of di sti 11 ate 2 sigma error (pCi/l) = 2 ((S/T 2) + (B/t 2)) 112 / *(2.22 VE) of di sti 11 ate 125
-Result (oCi/g
. of freeze
. dried sample) = A (YI) 2 sigma error (pCi/g of freeze dried sample) = C (YI)
Result (pCi/g or 1 of original sample) = A (VF) 2 sigma error (pCi/g or 1 of original sample) = C (VF) where: s = Gross counts of sample B = Counts of blank E = Fractional H-3 counting efficiency T = Number of minutes sample was counted t = Number of minutes blank was counted v = Volume of distillate counted YI = Liters of water-organic recovered/ g of freeze dried sample VF = Li~ers of water recovered/ (1 or g) of sample aliquot counted A = Result in pCi/l of distillate c = 2 sigma error in pCi/l of distillate Calculation of lower limit of detection (LLD) The detection limit is assumed to be exceeded when the counting result is different from the blank reading by at least 4.66 times the standard deviation of that back-ground. LLD (pCi/l) = 4.66 (Bl/Z) I (2.22 VE t) LLD (pCi/g of freeze dried sample) = F (YI) LLD (pCi/l or g) = F (YF) of original sample where: B = Counts of blank E = Fractional H-3 counting efficiency t = Number of minutes blank was counted v = Volume of di sti 11 ate counted YI = Liters of water-organic recovered/g of freeze dried sample VF = Liters of water recovered/{l or g) of sample aliquot counted F = LLD in pCi/l of distillate 126
SYNOPSIS OF NUS CORPORATION PROCEDURE TRITIUM ANALYSIS OF AQUEOUS FRACTION OF BIOLOGICAL t'1ATERIALS Approximately 150g of food product is weighed and placed into a 300ml round bottomed flask for freeze drying. The freeze drying appartus is set up and run until the sample is dry to touch. The collector is then allowed to warm to room temperature, and a graduated cylinder is used to measure the collected water volume. An 8ml aliquot of distillate is mixed with lOml of scintillation counting solution in an ultralow-potassium counting vial, and the specimen is counted for an appropriate time in a liquid scintillation counter. A low tritium-background water sample is treated identically to the samples and used as a blank. Calculations: Result (J.1Ci/ml distillate) = (c (s+b) - C (b)~x --=1--....- .J:.xj,_= A
~ (s+b) T(b)j 2.22x106 E V Error (2 sigma) (J.JCi/ml distillate) = 2 (s+b) + C(b) x 1 x
-E1 x 1
-V =B T (s+b) T (b) 2 2.22x106 Result (J.1Ci/g original sample) =A x YF Error (2 sigma) (µCi/g orignal sample) =B x YF C (s+b) = Gross counts of sample T(s+b) = Sample counting time c (b) = Blank counts T (b) = Blank counting time E = Tritium counting efficiency v = volume of distillate YF = ml water recovered/g of sample counted aliquot taken, typically 0.75 for fish 127
SYNOPSIS OF NUS CORPORATION PROCEDURE TRITIUM ANALYSIS OF ORGANIC FRACTION OF BIOLOGICAL MATERIALS Approximately 150g of food product in weighed and freeze-dried to remove all water. The residue is reweighed to determine the dry weight, then 15-20g of dried sample is combusted in a closed system and the product water collected. The volume of water is measured and the entire volume is then vacuum distilled from alkaline potassium permanganate solution. The entire final distillate or 8ml thereof, whichever is less, is mixed with lOml of scintillation count-ing solution, and the specimen is counted for an appropriate time in a liquid scintillation counter. A low tritium-background water sample is treated identically to the samples and used as a blank. Calculations: Result (µCi/ml distillate) =( T(s+b) C(s+b) - C(b)) x T(b) 1 2.22106 x 1 x 1
-E -V =A Error (2 sigma) (µCi/ml distillate) 2/.C(s+b) +*C(b) x 1 x 1 x 1 =B T(s+b)2 T ( b) 2 .-2-2_x_l_0..,...6 -E -V Result (µCi/g freeze-dried sample) =A x YI Error ( 2 sigma) (µ Ci/g freeze-dried sample) = B x YI Result (µCi/g original sample.) = A x YF Error (2 sigma) (µCi/g original sample) =B + YF C (s+b) = Gross counts of sample v Volume of distillate counted c (b) = Blank counts YI = ml water recovered/g of E = Tritium counting efficiency freeze-dried sample T (s+b) = Sample counting time YF = ml water recovered/g of T (b) = Blank counting time original sample aliquot 128
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE GAMMA 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. The contents of the exposed air iodine cartridge are emptied into an aluminum sample can containing 50ml of fresh TEDA-impregnated charcoal. The can is hermetically sealed and then counted on a gamma detector. Calculation of Gamma Activity: The following are the calculations performed for the gamma activity, 2-sigma error and LLD: Result (pCi/m3) = N*D R (2.22)*(E)*(A)*(T)*(V) N Net counts under photopeak D Decay correction factor Atl*EXP(f-t2) 1-EXP(-Atl) tl Acquisition live time t2 Elapsed time from sample collec-tion to start of acquisition
;\ 0.693/nuclide half life E Detector efficiency A Gamma abundance factor (no. of photons per disintegration)
T Acquisition live time, mins. v Sample volume, m3 2.22 No. of dpm per pCi 2*sigma error (pCi/m3) = 2* (crk 2+crs 2) 1/2 1
~.lz ak = statistical error of the activity measurement. It is determined
_J_ (f.2 I
*ACY); J from the accuracy of the least squares evaluation performed on the peaks of a particular nuclide.
n = number of peaks in the nuclide of question cri = (GC+Bc)l/2, where GC and BC are gross counts and background counts, respectively A(y)i = N*D gamma abundance factor for the (E)*(R)*(2.22)*(T)*(V) ith peak under consideration, for a given nuclide 129
as represents systematic errors (such as errors in detector efficiency) over and above the statistical er~or of the activity measurement. It is assigned a fixed value representing 5% of the computed activity and should be regarded as a minimum estimate of the activity error. All other variables are as defined earlier. The LLD (pCi/m3) = 4.66*(GC)l/2*o (2.22)*(E)*(A)*(T)*(V) Again, all other variables are as defined earlier. 130
SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE ANALYSIS OF CHARCOAL FILTERS FOR IODINE-131 Charcoal cartridges are analyzed for I-131 using a lithium-drifted germanium detector interfaced with a 2048 channel pulse height analyzer calibrated at 1.0 Kev per channel. Teledyne Isotopes employs one of three possible data acquisition and computation systems. The first, a Data General NOVA mini-computer, in series with the pulse height analyzer, calculates the number of counts (and a one standard deviation) in the peak region by performing a linearly-interpolated background subtraction. If no peak is observed, then only the background is used (along with sample volume, 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-11 and a Nuclear Data 6620 which perform all the above computations automatically. All resultant spectra are stored on magnetic tape. 131
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE ANALYSIS OF RAW MILK FOR IODINE-131 Stable iodine carrier is equilibrated in a 4-liter volume of raw milk before two separate batches of anion exchange resin are introduced to extract iodine. The iodine is removed from the resin and converted to free iodine. The free iodine is then extracted into carbon tetrachloride and reduced to iodide with sodium bisulfite when back-extracted into water. Then cuprous chloride is added to precipitate cuprous iodide, which is mounted on a membrane filter, sealed in a cut-down x-ray cell, vacuum dried and counted for 120 minutes on a beta-gamma coincidence system. 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 lOOml of raw milk. For ~ach 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 (2.22)*(E)*(V)*(Y)*(l.OS)*(H) G Sample gross counts B Background counts (from blank sample) T = Count time of sample and blank E = Eo*EXP(-A*M) = efficiency equation where Eo = counting efficiency at zero sample thickness A = Self-absorption coefficient M = sample thickness, mg/cm2 V = Sample volume, liters Y Chemical recovery = R Rl+R2 where R mg of I- recovered Rl mg of I- carrier added R2 mg of intrinsic stable I- measured in sample 1.05 Correction factor for protein-bound iodine 132
H = J/(1-K)*EXP(L) =correction factor for 13lr decay during counting period J (0.693/8.0S)*(R/1440) R Count time, minutes 1440 No. of minutes per day 8.05 Half-life of 13lr, days K EXP(-J) L (0.693/8.0S)*N N Elapsed time (days) from mid-point of collection period to beginning of count time. 133
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE ANALYSIS OF BOVINE THYROID FOR IODINE-131 The thyroid sample is first weighed and then, in combination with ethyl alcohol and 3.0ml iodine carrier, pureed in a blender in order to achieve a reasonably homogeneous sample. The contents are transferred to a sample can and additional alcohol added until the total sample volume reaches lOOml. The can is then hermetically sealed and counted on a gamma detector. Calculation of 131I 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 coµnts under photopeak D Decay correction factor A.tl*EXP( At2) 1-EXP(-A.tl) tl Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition
>.. 0.693/nuclide half life E Detector efficiency A Gamma abundance factor (no. of photons per disintegration)
T Acquisition live time, mins. v Sample quantity, kg wet 2.22 No. of dpm per pCi 2-sigma error (pCi/kg wet) = 2* (CTk 2+crs 2) 1/2
~ crk = statistical error of the activity measurement. It is determined n I 2
,;, o:. 2 *A(Y).
I from the accuracy of the least squares evaluation performed on I the peaks of a particular nuclide. n = number of peaks in the nuclide of question cri = (GC+BC)l/2, where GC and BC are gross counts and background counts, respectively A(y)i = N*D gamma abundance factor for the (E)*(R)*(2.22)*(T)*(V) ith peak under consideration, for a given nuclide 134
cr represents systematic errors (such as errors in detector efficiency) s over and above the statistical error of the activity measurement. It is assigned a fixed value representing 5% of the computed activity and should be regarded as a minimum estimate of the activity error. All other variables are as defined earlier. The LLD (pCi/kg wet) 4.66*(Gc)l/2*o (2.22)*(E)*(A)*(T)*(V) All quantities are as defined earlier. 135
SYNOPSIS OF RADIATION MANAGEMENT CORPORATION PROCEDURE ANALYSIS OF SAMPLES FOR IOOINE-131 Milk or Water (I0) The initial stable iodide concentration in milk is determined with an iodide ion specific electrode. Thirty milligrams of stable iodide carrier is then added to four (4) liters of milk. The iodide is removed from the milk by passage through ion-exchange resin. The iodide is eluted from the resin with sodium hypochlorite~ and purified by a series of solvent extractions with the final extraction into a toluene phase. The toluene phase is mixed with a toluene-based liquid scintilla-tion solution. The sample is then counted in a beta-gated gamma coincidence de-tector, shielded by six inches of steel. Distilled water is used as a blank. The yield is calculated from stable iodine recovery based on the recovered volume. Calculations.are made utilizing the following equations: Result = (S-B) I (2.22 V E F Y T) (pCi/1) 2 sigma error = 2 (S+B) 112 I (2.22 V E FY) ( pCi /l) LLD. = 4.66 (8 112) I (2.22 VE FY T) (pCi/1) where: s = Gross counts of sample in channels containing I-131 peak B = Background counts in channels containing I-131 peak T = Number of minutes sample was counted E = Iodine-131 counting efficiency v = Sample aliquot size F = Fractional garmna abundance y = Chemical yield of iodine Air Cartridges (Il) An iodine adsorber composed of charcoal is emptied into an aluminum can (6 ems high by 8 ems in diameter) and counted with a NaI(Tl) scintillation detector, coupled to a multi-channel pulse-height analyzer. Calculation of results and tWo sigma error Peaks are identified by changes in the slope of the spectrum. If peaks are identified the spectrum obtained is smoothed to minimize the effects of random statistical fluctu ations. The presence of iodine-131 is identified by the presence of a 364 Kev peak. The net area above the baseline is calculated. This area is converted to activity in curie units, making allowance for counting efficiency and gamma ray abundance. A PDP-11 computer program is used for spectrum analysis. Results are corrected for de-cay from the sampling time to the middle of the counting period, using a half-life value for I-131 of 8.06 days. C~lculations are made utilizing the following equations: Result 3 = ((S/T) - (B/t)) I (2.22 V E FY) (pCi/m ) 136
2 sigm~ error = 2 ((S/T 2) + (B/t 2)) 112 / (2.22 V E FY) (pCi/m ) LLD 3 = 4.66 (.63(Q 112 )b) 112- I (2.22 VE FY t) (pCi/m ) where: s = Net area, in counts, of sample in I-131 peak B = Net area, in counts, of background in I-131 peak b = Counts in I-131 peak channel T = Number of minutes sample was counted t = Number of minutes background was counted E = Iodine-131 counting efficiency v = Sample aliquot size y F = Fractional gamma abundance
= Chemical yield of iodine 137
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE RADIOSTRONTIUM ANALYSIS OF AIR FILTERS The air filters are placed in a small beaker and just enough concentrated 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 nitric acid leachings are carried out to remove the radiostrontium from the filter media. Once this is done, the resultant nitrates are dissolved in distilled water and the filter residue is filtered out. Radioactive interferences are stripped out by coprecipitation on ferric hydroxide (yttrium strip) followed by a barium chromate strip. The strontium is precipitated as its 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 89sr are both unknown quantities requiring two simultaneous equations to solve for them. Calculation of 90sr Activity: 90sr Results (pCi/m3) = N4/R (2.22)*(E)*(E(l5)/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, mg/cm2 E(l5)/E' =Ratio of 90sr efficiency at thickness value of 15mg/cm2 to 90sr counting standard efficiency run at the time of instrument calibrition (This standard is run with each group of environmental strontium samples) E = 90sr counting standard efficiency V = Sample quantity (m3) U = Chemical yield N4 (N2 Fl*Nl)/Wl net counts due to 90sr only Wl ((1 + Rl*I2) - (1 + Rl*Il)*Fl) Il 1 - EXP ((-0.693/2.667)*tl) I2 = l - EXP ((-0.693/2.667)*t2) tl Elapsed time from 90y strip to first count t2 Elapsed time from 90y strip to second count 138
2.667 Half-life of 90y, days Rl D + E*M + F*M2 (This is the general form of the regression equation for 90y eff'y/90sr 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 Nl Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2o22 No. of dpm per pCi Fl 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/m3)
'2* LlX+Y) + ( Xl+Yl) *Fl2]1/2* (Wl*W2)
Lw12 w12 (N2-Fl*Nl) Again, keeping the same variable definitions, the LLD for 90sr (pCi/m3) = 4.66* Dx+Y) + (Xl+Yl)*Fl~ 1/2 L w12 w12 J Calculation of 89sr Activity: 89sr Results (pCi/m3) = N6/R (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U)*(F9)
= W3 S7 G + H*M + I*M2 (This is the general form of the normalized 89sr efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.)
N6 Nl - N7*(1 + Rl*Il) N7 (N2 - Fl*Nl)/Wl (This represents counts due to 90sr) E(l5)/E' Ratio of 89sr 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.S)*t) 139
t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount. 50.5 = Half-life of 89sr, days All other quantities are as previously defined. The 2-sigma error for 89sr (pCi/m3) = 2* (sa2+s92)1/2 *W3 (Nl - N7*(l+Rl*Il)) S8 = r X+Y) LWIT
+ ( X1+ Y1)
- F 1 !} l/ 2 w12 J s 9 = (x l+ y 1 ) 1/ 2 All other variables are as previously defined.
Keeping the same variable definitions, the LLD for 89sr (pCi/m3) 4.66*Csa2+s92)1/2 140
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 is 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 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 ammonium hydroxide and heated in a hot water bath to form yttrium hydroxide. After cooling, the sample is centrifuged and the supernate saved for 89sr determination. The precipitate is dissolved with dilute nitric and hydrochloric acids, and the yttrium precipitated as oxalate using saturated ammonium oxalate solution. The yttrium oxalate is mounted on a tared paper filter, oven dried, weighed and counted on a gas proportional counter. The sample is then recounted the following day to confirm the decay of 90y. 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 90sr beta emissions, thus allowing the 89sr betas to be counteC. alone. The 89sr activity (pCi/m3) is computed as follows: A= (G/T-Bc-Ba) +/- crm*((G/T+Bc+Ba)/T)l/2 (2.22*V*Y*D*E) (2.22*V*Y*D*E) If the net activity (G/T -B) is less than or equal to the 2cr counting error, the activity is considered MDL where MDL= 2*(2*B/T)l/2 (2.22*V*Y*D*E) where G Total sample counts T Sample count time, mins. Be Background rate of counter, cpm Ba Background addition from 90sr and ingrowth of 90y 2.22 dpm/pCi v Sample volume, m3 y Chemical yield of strontium D 89sr decay factor from midpoint of collection period to counting date. 89sr counting efficiency with 80 mg/cm2 aluminum absorber Multiples of counting error 141
The 90sr activity (pCi/m3) is computed as follows: A= (G/T-B) +/- crm*((G/T+B)/T)l/2 (2.22*V*Y*D*E) (2.22*V*Y*D*E) Y Chemical 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 net activity (G/T-B) is less than or equal to the 2cr counting error, the activity is considered MDL where MDL = 2*(2*B/T)l/2 (2.22*V*Y1*Y2*I*D*E) 142
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE RADIOSTRONTIUM ANALYSIS *OF RAW MILK Stable strontium carrier is first introduced into a milk sample and into a distilled water sample of equal volume to be used as a blank. The sample(s) and blank are passed through cation resin columns which adsorb strontium, 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 70% nitric acid, strontium is forced out of solution somewhat ahead of calcium. Barium chromate precipitation is then performed to remove any traces of radium and radiobarium. Strontium recrystallization is carried out to remove residual calcium which may have been coprecipitated with the initial strontiu'm precipitation. Another recrystallization removes ingrown 9Dy, 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, again, at least 14 days later. The basis for this two-count method is that 9Dsr and 89sr are both unknown quantities requiring two simultaneous equations to solve for them. Calculation of 9Dsr Activity: 9Dsr Results (pCi/L) = N4/R (2.22)*(E)*(E(l5)/E')*(S6)*(V)*(U)
= W2 where S6 A + B*M + C*M2 (This is the general form of the normalized 9Dsr 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/cm2 E(l5)/E' Ratio of 9Dsr efficiency at thickness value of 15mg/cm2 to 9Dsr counting standard efficiency run at the time of instrument calibration (This standard is run wit~ each group of environmental strontium samples) E 9Dsr counting standard efficiency V Sample quantity (liters) U Chemical yield N4 (N2 - Fl*Nl)/Wl net counts due to 9Dsr only Wl ((1 + Rl*I2) - (1 + Rl*Il)*Fl) Il 1 - EXP ((-0.693/2.667)*tl) I2 1 - EXP ((-0.693/2.667)*t2) 143
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 Rl = D + E*M + F*M2 (This is the general form of the regression equation for 90y eff'y/9Dsr 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 Nl Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 No. of dpm per pCi Fl= 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*f<X+Y) + (Xl+Yl)*Fl2]1/2* (Wl*W2) L w12 w12 CN2-Fl*Nl) Again, keeping the same variable definitions, the LLD for 9Dsr (pCi/L) = 4
- 6 6 * [( X+Y) + ( X1+ Y1 )
- F 1211/ 2 w12 wi2 J Calculation of B9sr Activity:
B9sr Results (pCi/L) = N6/R (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U)*(F9)
= W3 S7 G + H*M + I*M2 (This is the general form of the normalized B9sr efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.)
N6 Nl - N7*(1 + Rl*Il) N7 (N2 - Fl*Nl)/Wl (This represents counts due to 90sr) 144
E(l5)/E' Ratio of 89sr 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) t Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount. 50.5 = Half-life of 89sr, days All other quantities are as previously defined. The 2-sigma error for 89sr (pCi/L) = 2* (ss2+s92)1/2 *W3 (Nl - N7*(l+Rl*Il)) SS = r(WIT X+Y) + ( Xl+Yl) *Fli] 1/2 w12 j S9 = (Xl+Yl) 1/2 All other variables are as previously defined. Keeping the same variable definitions, the LLD for 89sr (pCi/L) = 4.66*(ss2+s92)1/2 145
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE RADIOSTRONTIUM ANALYSIS OF WATER Stable strontium carrier is introduced into a water sample and into a distilled water sample of the same volume which is used as a blank. The sample(s) and blank aie then made alkaline and heated to near boiling before precipitating the carbonateso The 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 coprecipitation on ferric hydroxide (yttrium strip) followed by a barium chromate strip. The strontium is precipitatd as its 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 9Dsr and 89sr 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 strontiumo These results are used in correcting the chemical recovery of strontium to its true value. Calculation of 9Dsr Activity: 9Dsr Results (pCi/L) = N4/R (2.22)*(E)*(E(l5)/E' )*(S6)*(V)*(U)
= W2 where S6 A + B*M + C*M2 (This is the general form of the normalized 9Dsr 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/cm2 E(l5)/E' =Ratio of 9Dsr efficiency at thickness value of 15mg/cm2 to 9Dsr counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples) E 9Dsr counting standard efficiency V Sample quantity (liters) U = Chemical yield N4 (N2 - Fl*Nl)/Wl net counts due to 9Dsr only Wl ((1 + Rl*I2) - (1 + Rl*Il)*Fl) 146
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 Rl D + E*M + F*M2 (This is the general form of the regression equation for 90y eff'y/90sr 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 Nl Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 No. of dpm per pCi Fl 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) + (Xl+Yl) *Fl2l l/2* (Wl*W2) w12 w12 J (N2-Fl*Nl) Again, keeping the same variable definitions, the LLD for 90sr (pCi/L) =
- 4. 66* [< X+Y) + ( Xl+Yl) *Fl2]1/2 w12 w12 Calculation of 89sr Activity:
89sr Results (pCi/L) = N6/R (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U)*(F9)
= W3 S7 G + H*M + I*M2 (This is the general form of the normalized 89sr efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.)
N6 = Nl - N7*(1 + Rl*Il) N7 = (N2 - Fl*Nl)/Wl (This represents counts due to 90sr) 147
E(l5)/E' Ratio of 8 9sr 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) t Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samplesp this represents the elapsed time from sample stop date to time of recount. 50.5 = Half-life of 89sr, days All other quantities are as previously defined. The 2-sigma error for 89sr (pCi/L) = 2~ (S82+s92)1/2 *W3 (Nl - N7*(l+Rl*Illl S8 =[(X+Y) + (Xl+Yl)*FI!} 1/2 WIT w12 J S9 = ( Xl+Yl) 1/2 All other variables are as previously defined. Keeping the same variable definitions, the LLD for 89sr (pCi/L) = 4.66*Csa2+s92)1/2 148
l SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE RADIOSTRONTIUM ANALYSIS OF VEGETATION, MEAT AND AQUATIC SAMPLES The samples are weighed (recorded as nwetn 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 nary" weight) and then pulverized. A measured amount (quantity dependent on desired sensitivity) of the pulverized sample is first charred over a Bunsen burner and then ashed in a muffle furnace. 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 (HN03). The resultant nitrates are heated to dryness and are dissolved in 20ml distilled water before adding 60ml f~ming HN03. 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 9Dsr and 89sr are both unknown quantities requiring two simultaneous equations to solve for them. Calculation of 9Dsr Activity: 9Dsr Results (pCi/kg wet) = N4/R (2.22)*(E)*(E(l5)/E' )*(S6)*(V)*(U)
= W2 where S6 A + B*M + C*M2 (This is the general form of the normalized 9Dsr efficiency regression equation for one particular gas proportional counter, where A, B and c are regression coefficients.)
M Thickness density of strontium carbonate precipi~ate, mg/cm2 E(l5)/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 9Dsr counting standard efficiency V = sample quantity (kg wet) U Chemical yield N4 (N2 - Fl*Nl)/Wl net counts due to 90sr only Wl ((1 + Rl*I2) - (1 + Rl*Il)*Fl) 149
Il = l - EXP ((-0.693/2.667)*tl)
!2 l - EXP ((-0.693/2.667)*t2) tl Elapsed time from 90y strip to first count t2 Elapsed time from 90y strip to second count 20667 = Half-life of 90y, days Rl D + E*M + F*M2 (This is the general form of the regression equation for 90y eff'y/9Dsr 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 Nl Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2o22 = No. of dpm per pCi Fl EXP ((-Oo693/2o667)*t2) R Count time of sample and blank Using the same variable definitions as ~bove, the 2-sigma error for 9Dsr (pCi/kg wet) = 2*[CX+Y) + (Xl+Yl)*Fl2Jl/2* (Wl*W2} L w12 w12 (N2-Fl*Nl) Again, keeping the same variable definitions, the LLD for 9Dsr (pCi/kg wet) =
- 4. 66* [cx+Y) + ( Xl+Y 1) *Fl2]1/2 Lw12 w12 Calculation of 89sr Activity:
89sr Results (pCi/kg w~t) = N6/R (2o22)*{E)*(E(l5)/E')*(S7)*(V)*{U)*(F9)
= W3 S7 G + H*M + I*M2 (This is the general form of the normalized 89sr efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.}
N6 Nl - N7*(1 + Rl*Il} N7 = (N2 - Fl*Nl)/Wl (This represents counts due to 9Dsr) 150
E(l5)/E' Ratio of 89sr 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) 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 = Ralf-life of 89sr, days All other quantities are as previously defined. The 2-sigma error for 89sr (pCi/kg wet) = 2* (sa2+s92)1/2 *W3 (Nl - N7*(l+Rl*Il)) sa = fj_x+Y) + (Xl+Yll *F12l 112 Lw12 w12 J S9 = ( Xl+Yl) 1/2 All other variables are as previously defined. Keeping the same variable definitions, the LLD for 89sr (pCi/kg wet) 4.66*Csa2+s92)1/2 151
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE RADIOSTRONTIUM ANALYSIS OF BONE AND SHELL The bone or shell is first physically separated from the rest of the sample before being broken up and boiled in 6N sodium hydroxide (NaOH) solution for a brief time to digest remaining flesh/collagen material adhering to the sample. After multiple rinses with distilled water, the bone/shell is then oven dried and pulverized. An aliquot of the sample is removed, weighed and ashed in a muffle furnace. Then in the presence of strontium carrier and cesium holdback carrier, the radiostrontium is leached out of the ash with nitric acid and the sample filtered. A portion of the filtrate is removed for stable strontium determination and the remaining sample treated with fuming nitric acid to ~recipitate strontium nitrate. The strontium nitrate is freed of calcium by treatment with anhydrous acetone. From this point on, any radiological impurities are removed by coprecipitation with ferric hydroxide followed by coprecipitation with barium chromate. The strontium is precipitated as strontium carbonate, which is dried, weighed, then beta-counted on a low background gas propor-tional counter. A second count is performed 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 9Dsr Activity: 9Dsr Results (pCi/kg dry) = N4/R (2.22)*{E)*(E(l5)/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, mg/cm2 E(lS)/E' Ratio of 9Dsr 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 9Dsr counting standard efficiency V Sample quantity (kg dry) U Chemical yield N4 (N2 Fl*Nl)/Wl net counts due to 90sr only Wl ((1 + Rl*I2) - (1 + Rl*Il)*Fl) 152
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 Rl D + E*M + F*M2 {This is the general form of the regression equation for 90y eff'y/9Dsr 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 Nl Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 No. of dpm per pCi Fl 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 9Dsr {pCi/kg dry) = 2* llx+Y) + { Xl+Yl) *Fl2, l/2* (Wl*W2) Lw12 w12 J {N2-Fl*Nll Again, keeping the same variable definitions, the LLD for 9Dsr {pCi/kg dry) =
- 4. 66* e X+~) + {Xl+Yl) *Fl!} l/ 2 Wl w12 j Calculation of 89sr Activity:
89sr Results {pCi/kg dry) = N6/R (2.22)*{E)*{E{l5)/E')*(S7)*{V)*(U)*(F9)
= W3 s7 G + H*M + I*M2 (This is the general form of the normalized 89sr efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.)
N6 Nl - N7*{1 + Rl*Il) N7 (N2 - Fl*Nl)/Wl (This represents counts due to 9Dsr) 153
E(l5)/E' =Ratio of 89sr 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) t Elapsed time from midp~int of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount. 50.5 = Half-life of 89sr, days All other quantities are as previously defined. The 2-sigma error for 89sr {pCi/kg dry) = 2* {S82+s92)1/2 *W3 {Nl - N7*(l+Rl*Il)) sa =fu+/-.x.L+ (Xl+Yl)*Fl2]1/2 Lw12 w12 S9 = {Xl+Yl)l/2 All other variables are as previously defined. Keeping the same variable definitions, the LLD for 89sr {pCi/kg dry) = 4.66*Csa2+s92Jl/2 154
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE RADIOSTRONTIUM ANALYSIS OF SOIL AND SEDIMENT After the soil or sediment sample has been dried and pulverized, a SOgm aliquot is added to approximately 1/3 - liter concentrated hydrochloric acid (HCl), containing Sml of strontium carrier (lOmg sr++;ml). A blank con-taining only 1/3 - liter concentrated HCl and Sml strontium carrier is run in parallel with the sample. The samples are stirred vigorously for at least 30 minutes and then filtered. A portion of the filtrate is removed for stable strontium determination and the remainder is evaporated to near dryness and the residue dissolved in concentrated HCl before being passed through an anion exchange column to remove impurities. The resultant eluate is evapo-rated to dryness, then dissolved in 6N nitric acid (HN03). Fuming (90%) HN03 is added to bring the HN03 concentration to approximately 70%. 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 two-count method is that 90sr and 89sr are both unknown quantities requiring two simultaneous equations to solve for them. Calculation of 9Dsr Activity: 9Dsr Results (pCi/kg dry) = N4/R (2.22)*(E)*(E(l5)/E' )*(S6)*(V)*(U)
= W2 where S6 A + B*M + C*M2 (This is the general form of the normalized 9Dsr 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/cm2 E(lS)/E' Ratio of 9Dsr efficiency at thickness value of 15mg/cm2 to 9Dsr counting standard efficien~y run ~t the time of instrument calibration (This standard is run with each group of environmental strontium samples) E 9Dsr counting standard efficiency V Sample quantity (kg dry) U Chemical yield N4 (N2 Fl*Nl)/Wl net counts due to 9Dsr only Wl ((1 + Rl*I2) - (1 + Rl*Il)*Fl) 155
Il l - EXP ((-0.693/2~667)*tl) I2 l - 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 Rl D + E*M + F*M2 (This is the general form of the regression equation for 90y .eff'y/9Dsr 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 Nl Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 No. of dpm per pCi Fl= 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 dry) = 2* ttX+Y) + (Xl+Yl)*Flt) 1/2* (Wl*W2) LWIT w12 -J (N2-Fl*Nl) Again, keeping the same variable definitions, the LLD for 9Dsr (pCi/kg dry) = 4.66*[(x+Y) + (Xl+Yl)*Fl2]1/2 WIT w12 Calculation of 89sr Activity: 89sr Results (pCi/kg dry) = N6/R (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U)*(F9)
= W3 s7 G + H*M + I*M2 (This is the general form of the normalized 89sr efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.)
N6 Nl - N7*(1 + Rl*Il) N7 (N2 - Fl*Nl)/Wl (This represents counts due to 90sr) 156
E(l5)/E' Ratio of 89sr 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 samples) F9 EXP ((-0.693/50.5)*t) t Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount. 50.5 = Half-life of 89sr, days All other quantities are as previously defined. The 2-sigma error for 89sr (pCi/kg dry) = 2* (ss2+s92)1/2 *W3 (Nl - N7*(l+Rl*Il)) S 8 = [( X+Y) + ( X1+ Y1)
- F1111/ 2
---wi"T Wl 2 .j S9 = ( Xl+Yl) 1/2 All other variables are as previously defined.
Keeping the same variable definitions, the LLD for 89sr (pCi/kg dry) 4.66*(ss2+s92)1/2 157
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE ANALYSIS OF ENVIRONMENTAL SAMPLES FOR STABLE STRONTIUM It has been the practice of the Environmental Division to perform a stable strontium determination on any samples to be analyzed for strontium 90 and 89, if they are likely to contain significant amounts of the stable isotopes. For water samples, this involves removal of a 60-ml 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 10 percent of a known volume of sample filtrate or leachate after the strontium carrier has been added to the sample. This aliquot is transferred to a 25ml volumetric flask and brought up to volume with distilled water. These aliquots are always in a hydrochloric acid (HCl) medium. Those which are not must first be evaporated to dryness, reconstituted with concentrated HCl and evaporated to dryness once more before being brought back to their original volume with concentrated HCl. These latter aliquots can then be transferred to volumetric flasks and brought to volume with distilled water. They are then 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 and the quantity of strontium intrinsic to the sample. Sample Calculation of Corrected Chemical Recovery of Strontium in Biological and Mineral Media: Reported concentration of stable strontium (mg/L):ll9 Volume of specimen (ml):25 Proportion of sample used for aliquot: 0.10 Milligrams Strontium in 25ml flask (119mg/L) x (.025L/25ml)
= 2.98mg Sr Since 2.98mg Sr represents the quantity of stable strontium in 10 percent of the sample, total strontium (stable + carrier) in the full sample 2.98mg Sr = 29.8 mg 0.1 Net weight of SrC03 precipitate (mg): 35.2 Percent of Sr in precipitate: 59.35 Quantity of strontium recovered= (35.2mg) x (.5935) = 20.9 Corrected Chemical Recovery of strontium= 20.9 = 0.701 29.8 158
Sample Calculation of Corrected Chemical Recovery of Strontium in Water: Reported concentrations of stable strontium (ppm): 1.65 Volume of radiochemical water sample (liters): 2.0 l.65ppm is equivalent .to l.65mg/L Stable strontium in 2 liter sample (l.65mg/L) x (2.0L) 3.30mg Quantity of strontium carrier added to sample (mg): 20a0 Total amount of strontium in sample (mg): 20.0 + 3.30 = 23.3mg Net weight of SrC03 precipitate (mg): 28.9 Percent of Sr in precipitate: 59.35 Quantity of strontium recovered= (28.9mg) x (.5935) = 17.2mg Corrected Chemical Recovery of Strontium= 17.2mg = .738 23.3mg 159
SYNOPSIS OF RADIATION MANAGEMENT CORPORATION PROCEDURE ANALYSIS OF SAMPLES FOR STRONTIUM-89 AND -90 Total Water (S0, T0) A two liter aliquot of sample is used. Stahle strontium carrier is added to the liquid to facilitate chemical separation of Sr-89 and -90, and to determine the strontium recovery. Strontium concentration and purification is ultimately real-ized by at least two precipitations of strontium nitrate in concentrated nitric acid. Additional iron/rare earth hydroxide precipitations and barium chromate separations are perfonned to remove suspected interfering nuclides. After puri-fication, the Y-90 is allowed to ingrow for a known period of time. Sr-90 is then determined by counting yttrium oxalate after initially precipitating Y-90 as yttrium hydroxide. Sr-89 is determined by counting strontium carbonate and correcting the observed activity for the amount 'of Sr-90 and Y-90 on the plan-chet. A sample of distilled water is used as a blank. Milk (S4, T4) A one and half liter aliquot of milk is ashed to destroy organic material and then dissolved in concentrated mineral acid. Stable strontium is added to the eluted liquid or dissolved ash to facilitate chemical separation of Sr-89 and -90, and to detennine the strontium recovery. Strontium concentrations and purification is ultimately realized by at least two precipitations of strontium nitrate in concen~ trated nitric acid. Additional iron/rare earth hydroxide precipitations and barium chromate separations are performed to remove suspected interfering nuclides. After purification, the Y-90 is allowed to ingrow for a known period of time. Sr-90 is then determined by counting yttrium oxalate after initially precipitating Y-90 as yttrium hydroxide. Sr-89 is determined by counting strontium carbonate and correcting the observed activity for the amount of.Sr-90 and Y-90 on the planchet. A sample of distilled water is used as a blank. Bones and Shells (S5, TS) A large quantity of the sample is dried, ashed and a 25 g portion is then dissolved in concentrated acid. Stable strontium carrier is added to the dissolved sample to facilitate chemical separations of Sr-89 and -90, and to determine the strontium recovery. Strontium concentration and purification is ultimately realized by at least two precipitations of strontium nitrate in concentrated nitric acid. Addi-tional iron/rare earth hydroxide precipitations and barium chromate separations are performed to remove suspected interfering nuclides. After purification, the Y-90 is allowed to ingrow for a known period of time. Sr-90 is then determined by counting yttrium oxalate after initially p~ecipitating Y-90 as yttrium hydroxide. Sr-89 is determined by counting strontium carbonate and correcting the observed activity for the amount of Sr-90 and Y-90 on the planchet. A sample of distilled water is used as a blank. Soil and Sediment (S6, T6) A large quantity of sample is dried, and a 25 g portion is then leached with concen-trated HCl before drying. Stable strontium carrier is added to the sample to facili-tate isolation of the strontium and to determine the strontium recovery. Strontium concentration and purification is ultimately realized by at least two precipitations of strontium nitrate in concentrated nitric acid. Additional iron/rare earth hydroxid precipitations and barium chromate separations are performed.to remove suspected 160
interfering nuclides. After purification, the Y-90 is allowed to ingrow for a known period of time. Sr-90 is then determined by counting yttrium oxalate after initially precipitating Y-90 as yttrium hydroxide. Sr-89 is determined by counting strontium carbonate and correcting the observed activity for the amount of Sr-90 and Y-90 on the planchet. A sample of distilled water is used as a blank. Organic Solids (S8, TB) A 250 g portion of the sample is ashed and then dissolved in concentrated acid. Stable strontium carrier is added to the dissolved sample to facilitate chemical separation of Sr-89 and -90, and to determine the strontium recovery. Strontium concentration and purification is ultimately realized by at least two precipitations of strontium nitrate in concentrated nitric acid. Additional iron/rare earth hy-droxide precipitations and barium chromate separations are performed to remove suspected interfering nuclides. After purification, the Y-90 is allowed to ingrow for a known period of time. Sr-90 is then determined by counting yttrium oxalate after initially precipitating Y-90 as yttrium hydroxide. Sr-89 is determined by counting strontium carbonate and correcting the observed activity for the amount of Sr-90 and Y-90 on the planchet. A sample of distilled water is used as a blank. Calculations of the results, the two sigma errors and minimum detectable levels (MDL) for Sr-89,.-90 are expressed in activity (pCi) per unit volume (liter) or mass (gram). Result Sr-90 = (A/Tl-B/T2) / (2.22 VEY X exp(-0.693 tl/64.l)(l-exp(-0.693t2/64.1))) (pCi/l or g) 2 sigma error Sr-90 = 2(A/Tl 2+B/T2 2) 112 / (2.22 VEY X exp(-0.693tl/64.1)(1-exp(-0.693 (pCi/l or g) t2/64.1))) MDL Sr-90 = 3 s112 I (2.22 T2 V E Y X exp(-0.693tl/64.1)(1-exp(-0.693t2/64.l))) (pCi /1 or g) where: A = Gross Y-90 counts B = Gross blank counts of yttrium Tl = Y-90 counting time T2 = Blank counting time v = Sample aliquot size E = Y-90 counting efficiency y = Yttrium chemical yield x = Strontium chemical Yield tl = Time in hours from second separation of Y-90 until counting time of yttrium planchet plus one-half the counting time t2 = Time in hours between first and second separati ans of Y-90 (ingrowth ti me) Result Sr-89 = (C/T3 - D/T4 - G - H)/(2.22 V F X exp(-0.693t4/50.5)) ( pCi /1 or g) 2 sigma error Sr-89 = 2 (C/T3 2 + D/T4 2 + G/T3 + H/T3) 112 I (2.22 VF X exp(-0.693t4/50.5)) (pCi/l or g} 161
1 MDL Sr-89 = 3{n+GT3+HT3) 12 I (2.22 T4 V F X exp{-0.693t4/50.5)) (pCi/l or g) where: c = Gross strontium counts D = Gross blank counts of strontium G = Additional background from Sr=90 activity
= {Sr=90 activity of sample) {2.22 VXJ)
H. = Additional background from Y-90 activity
= (Sr-90 activity of sample) (2.22 VXE) (1-exp(-0.693t5/64.l))
v = Sample aliquot size J = Sr-90 counting efficiency F = Sr-89 counting efficiency x = Strontium chemical yield t4 = Time in days from sampling date to strontium count T3 = Strontium counting time T4 = Blank counting time ts = Time in hours from second separation of Y-90 to counting of strontium planchet plus one~half the counting time 162
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE GAMMA ANALYSIS OF AIR PARTICULATE COMPOSITES At the end of each cal~ndar quarter, 13 weekly air filters from a given loca-tion are stacked in a two inch diameter Petri dish in chronological order, active area facing down, 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/m3) N*D R (2.22)*(E)*(A)*(T)*(V) N = Net counts under photopeak D Decay correction factor
;>..tl*EXP( At2) 1-EXP(-;i,,tl) tl Acquisition live time t2 Elapsed time from sample col lee-tion to start of acquisition A. 0.693/nuclide half life E Detector efficiency A Gamma abundance factor (no. of photons per disintegration)
T Acquisition live time, mins. v Sample volume, m3 2.22 = No. of dpm per pCi 2-sigma error (pCi/m3) 2* ( crk 2+cr s 2)1/2 1--~~~~~~l:...._~~~~~--1
~~ statistical error of the activity measurement. It is determined
>1 ~ from the accuracy of the least l: *A(Y), squares evaluation performed on i=I I the peaks of a particular nuclide.
n = number of peaks in the nuclide of question 163
°i_ = (GC+BC)l/2, where GC and BC are gross counts and background counts, respectively A(y)i = N*D (E)*(R)*(2.22)*(T)*(V)
= gamma abundance factor for the ith peak under consideration, for a given nuclide crs represents systematic errors (such as errors in detector efficiency) over and above the statistical error of the activity measurement. It is assigned a fixed value representing 5% of the computed activity and should be regarded as a minimum estimate of the activity error.
All other variables are as defined earlier. The LLD(pCi/m3) = 4.66*(GC)l/2*D (2.22)*(E)*(A)*(T)*(V) Again, all quantities are as defined earlier. 164
SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE ANALYSIS OF AIR PARTICULATE FILTERS FOR GAMMA Air particulate filters are analyzed for gamma using a lithium-drifted germanium detector interfaced with a 2048 channel pulse height analyzer calibrated at 1.0 Kev per channel. Teledyne Isotopes employs one of three possible data acquisition and computation systems. The first, a Data General 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 observed, then only the background is used (along with sample volume, collec-tion date and length of count) to determine the detection limit. The activity or MDL of each nuclide is computed on an IBM 360. This semi-automatic system is in contrast with the other two data acquisition and computation systems, namely, a Tracor Northern TN-11 and Nuclear Data 6620 which perform all the above computations automatically. All resultant spectra are stored on magnetic tape. 165
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE GAMMA ANALYSIS OF RAW MILK A well mixed 3.5-liter sample of raw milk is poured into a calibrated Marinelli beaker along with 20ml of 37% formaldehyde solution (used as a preservative). After stirring, the sample is allowed to reach ambient temperature and then counted on a gamma detector for 1000 minutes. Calculation of Gamma Activity: The following are the calculations performed for the gamma activity, 2-sigma error a~d 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(-Atl) tl Acquisition live time t2 Elapsed time from sample collec-t ion to start of acquisition A. 0.693/nuclide half life E = Detector efficiency A Gamma abundance factor (no. of photons per disintegration) T Acquisition live time, mins. v Sample volume, liters 2.22 No. of dpm per pCi 2-sigma error (pCi/L) = 2* (crk 2+crs 2) 1/2 crk = l t-~~~~~~~~~~~-l
-i crk = statistical error of the activity measurement. It is determined
- 2. from the accuracy of the least
*A (Y).
I squares evaluation performed on the peaks of a particular nuclide. n = number of peaks in the nuclide of question cri = (GC+Bc)l/2, where GC and BC are gross counts and background counts, respectively A(Y)i = N*D = gamma abundance factor for the (E)*(R)*(2.22)*(T)*(V) ith peak under consideration, for a given nuclide 166
cr represents systematic errors (such as errors in detector efficiency) s over and above the statistical error of the activity ~easurement. It is assigned a fixed value representing 5% of the computed activity and should be regarded as a minimum estimate of the activity error. All other variables are as defined earlier. The LLD (pCi/L) = 4.66*(Gc)l/2*o (2.22)*(E)*(A)*(T)*(V) All quantities are as defined earlier. 167
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE GAMMA ANALYSIS OF WATER A 4-liter sample of water is added to a brown glass jug. Then, a bent glass tube is connected to the open end of the jug by means of a rubber stopper 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 lOOml 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 jug and glass tube are rinsed with distilled water and the rinsing added to the can. The water level is then adjusted back to the lOOml level by additional evaporation. The sample is finally left to cool to room temperature before sealing the can and then counting on a gamma detector for 1000 minutes. Calculation of Gamma Activity: The following are the calculations performed for the gamma activity, 2-sigma error and LLD: Result (pCi/L) N*D = R (2.22)*(E)*(A)*(T)*(V) N = Net counts under photopeak D Decay correction factor
),. tl*EXP(A. t2) 1-EXP(-A.tl) tl Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition A 0.693/nuclide half life E Detector efficiency A = Gamma abundance factor (no. of photons per disintegration)
T Acquisition live time, mins. v = Sample volume, liters 2.22 No. of dpm per pCi 2-sigma error (pCi/L) 2*(ak 2+as 2)1/2
}2 ak Statistical error of the activity I 2.
measurement. It is determined.
*A(Y). from the accuracy of the least Cf:z I squares evaluation performed on I
the peaks of a particular nuclide. n = number of peaks in the nuclide of question 168
0i = (GC+Bc)l/2, where GC and BC are gross counts and background counts, respectively A(y)i = N*D (E)*(R)*(2.22)*(T)*(V) gamma abundance factor for the ith peak under consideration, for a given nuclide ~ represents systematic errors (such as errors in detector efficiency) over and above the statistical error of the activity measurement. It is assigned a fixed value representing 5% of the computer activity and should be regarded as a minimum estimate of the activity error. All other variables are as defined earlier. The LLD (pCi/L) = 4.66*(Gc)l/2.*n (2.22)*(E)*(A)*(T)*(V) Again, all other variables are as defined earlier. 169
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE GAMMA ANALYSIS OF SOLIDS Several methods are employed in preparing solids for gamma analysis, depending on the type of sample or sensitivity required. For high sensitivity analysis of vegetation, meat and seafood, the sample is first weighed, then oven-dried to a constant weight. A ratio of wet-to-dry weight is computed before the sample is ground and compressed to unit density (lg/cm3), whenever possible, in a tared aluminum can. The can is weighed and then hermetically sealed and counted on a gamma detector. When sample size or time is limited, a wet sample can be prepared (assuming sensitivity can be met) by using a food processor to puree it. The sample is then poured into a calibrated and tared clear plastic container until a standard volume is reached. The sample is weighed and then sealed with a screw cap before gamma counting. Soil and sediment samples are first oven dried until a constant weight is achieved and then pulverized. The sample is added to a tared aluminum can, compacted to a standard volume and weighed. It is hermetically sealed and gamma counted. Benthic organisms are ~ven 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 di~tilled water. The sample is filtered and the filtrate added to an aluminum can. The sample volume is brought up to the standard geometry with distilled water and the can hermetically sealed before gamma counting. Calculation of Gamma Activity: The following are the calculations performed for the gamma activity, 2-sigma error and LLD: Result (pCi/kg) = N*D =R (2.22)*(E)*(A)*(T)*(V) N = Net counts under photopeak D = Decay correction factor Atl*EXP(At2) 1-EXP(-Atl) tl = Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition A 0.693/nuclide half life E = Detector efficiency A = Gamma abundance factor (no. of photons per disintegration) T = Acquisition live time, mins. v = Sample volume, liters 2.22 = No. of dpm per pCi 170
2-sigma error (pCi/kg) 2*(crk 2+crs 2)1/2 (jk = 1
%z (jk Statistical error of the activity measurement. It is determined l1 i. from the accuracy of the least I
L: i=I d.2
*A (Y)
I
. squares evaluation performed on the peaks of a particular I
nuclide. n = number of peaks in the nuclide of question i = (GC+BC)l/2, where GC and BC are gross counts and background counts, respectively cri = (GC+BC)l/2, where GC and BC are gross counts and background counts, respectively. A(Y)i = N*D (E)*(R)*(2.22)*(T)*(V) = gamma abundance factor for the ith peak under consideration, for a given nuclide crs represents systematic errors (such as errors in detector efficiency) over and above the statistical error of the activity measurement. It is assigned a fixed value representing 5% of the computer activity and should be regarded as a minimum estimate of the activity error. All other variables are as defined earlier. The LLD (pCi/kg) = 4.66*(GC)l/2*o (2.22)*(E)*(A)*(T)*(V) Again, all other variables are as defined earlier. 171
SYNOPSIS OF RADIATION .MANAGEMENT CORPORATION PROCEDURE GAMMA SPECTROMETRY OF SAMPLES Water (Nl) Four liters of sample is reduced. to 100 ml and sealed in a standard container and counted with a NaI(Tl) detector coupled to a multi-channel pulse-height analyzer. The counting time is 50,000 seconds. Milk (N7) A 4 liter aliquot is dried at 175°C, ashed at 500°C until no carbon residue is present, compressed and sealed in a standard container, and then counted with a NaI(Tl) detector, coupled to a multi-channel pulse-height analyzer. The counting time is 50,000 seconds. Dried Solids (N8, GB) A large quantity of the sample is dried at a low temperature, less than 100°C. A 100 gram aliquot (or the total sample if less than 100 grams) is taken, com-pressed to a known geometry, sealed in a standard container, and counted with a NaI(Tl) or Ge(Li) detector, coupled to a multi-channel pulse-height analyzer. The counting time is 50,000 seconds. Air Dried Solids (NA) A large quantity of sample is air dried. A 100 gram aliquot (or the total sample if less than 100 grams) is taken, compressed to unit density, sealed in a stan-dard container and counted with a NaI(Tl) detector, coupled to a multi-channel pulse=height analyzer. The counting time is 50,000 seconds. Calculation of results and two sigma error The spectrum obtained is smoothed to minimize the effects of random statistical fluc-tuations. Peaks are identified by changes in the slope of the gross spectrum. The net area, in counts, above the baseline is calculated. This area is converted to activity in curie units, making allowance for counting efficiency and gamma ray abundance. A co~uter program is used for spectrum analysis. Calculations are made utilizing the following equations: Result {pCi/l or g) = ({S/T) - (B/t)) I (2.22 V E F) 2 sigma error (pCi/l or g) = 2 ((S/T 2 ) + (B/t 2 )) 112 / (2.22 V E F) where: s = Net area, in counts, of sample (Region of spectrum of interest) B = Net area, in counts, of background (Region of spectrum of interest) T = Number of minutes sample was counted t = Number of minutes background was counted E = Detector efficiency for energy of interest v = Sample aliquot size . F = Fractional garrana abundance (specific for each emitted nuclide) 172
Calculation of lower limit of detection (LLD) for G8 LLD (pCi/l or g) = 4.66 (6 s) 112 I (2.22 V E FT) where: S = Net area, in counts, of sample (Region of spectrum of interest) T = Number of minutes samole was counted E = Detector efficiency for energy of interest V = Sample aliquot size F = Fractional gamma abundance Calculation of lower limit of detection (LLD) for Nl, N7, N8 and NA LLD (pCi/l or g) = 4.66 (.63 (Q) 112 S) 112 I (2.22 VE FT) where: S = Net area, in counts, of sample (Region of spectrum of~ interest) T = Number of minutes sample was counted E = Detector efficiency for energy of interest V = Samp_le aliquot size F = Fractional ganma abundance Q = Channel number 173
SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE ANALYSIS OF TELEDYNE ISOTOPES THERMOLUMINESCENT DOSIMETERS These devices are rectangular Teflon wafers impregnated with 25% CaS04: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 Teledyne Isotopes model 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 back-ground. The results are computed as follows: For any given area of the dosimeter, the dose in rnR is calculated by the formula DOSE R * (REDOSE/RR)-AVC R Initial reading of the area RR = Second reading of the area (after re-irradiation) REDO SE Re-irradiation dose, mR AVC Average of control values, rnR
~N where AVC ECDOSE/4N i:1 N = Total number of control dosi-meters CDOSE = CR*(CREDOSE/CRR)
CDOSE Control area dose, rnR CR Initial reading of control area CRR = Second reading of the control area (after re-irradiation) CREDO SE Re-irradiation dose of the control dosimeter, mR 174
SYNOPSIS OF RADIATION MANAGEMENT CORPORATION PROCEDURE ENVIRONMENTAL DOSIMETRY (D0, Dl, D2) Measurement Techniques Each dosimeter utilized is a capillary tube containing calcium sulfate (Tm) powder as the thermoluminescent dosimeter (TLD) material. This was chosen primarily for its high light output, minimal thermally induced signal loss (fading), and lack of self-dosing. The energy response curve has been flattened by a complex multi-ple element energy compensation shield supplied by Panasonic Corporation, manu-facturer of the TLD reader. The four dosimeters per station are sealed in a polyethy*lene bag to demonstrate integrity at time of measurement. Visible through the bag are the sample placement instructions. One set of TLDs is placed in a lead shield at RMC and represents a zero dose. The TLDs are then taken and placed in the field stations; one field TLD set is placed in a field lead shield
- at station 18 and is used in calculating the in-transit dose.
*Following the pre-designated exposure period the TLD is heated with hot gas and the luminescence measured with a TLD reader. Data are normalized to standard machine conditions by correcting machine settings to zero before readout. Data are corrected for in-transit dose using a set of TLDs which is kept in a lead shield in the field and only exposed during transit. Average dose per exposure period, and its error, are calculated.
The basic calibration is in mR exposure to a standard Cs-137 source. This is converted to absorbed dose in tissue by the factor : 0.955 rad/Roentgen and to dose equivalent by using a quality factor of 1. Calculations are made utilizing the following equations: T = (G-Z) R C 0.955 mrad/ Roentgen I = SZ - (RZ DL I DR) N = T-I n Average = ((sum N) I n) (30.4 I DL) i=l Error = t (n-1) (SD I n112) (30.4 I DL) where: T = Individual TLD reading corrected to standard instrument conditions G = Gross reading of dosimeter i z = Zero for dosimeter, i R = Correction factor of reader (see .Procedure T-6)
~ = Calibration factor dosimeter i I = In-transit dose sz = Mean of n dosimeters in site lead shield.
RZ = Mean of n dosimeters in RMC lead shield DL = Exposure period of location (days) DR = Exposure period of RMC0 (days) 175
ENVIRONMENTAL DOSIMETRY (cont.) Average = Mean exposure per standard exposure period at a given station N = Net dose obtained during exposure period in the field n = Number of readings 30.4 = Days in standard exposure period Error = The 95% confidence limit error of the average t(n-1) = t-distribution (student) factor for 95% CL so = Standard deviation of n readings of sum N 176
APPENDIX E
SUMMARY
OF USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDIES PROGRAM RESULTS 177
SUMMARY
OF USEPA INTERCOMPARISON STUDIES PROGRAM Appendix E presents a summary of the analytical results for the 1983 USEPA Environmental Radioactivity Laboratory Intercomparison Studies Program. TABLE NO. TABLE OF CONTENTS PAGE E-1 Gross Alpha and Gross Beta Emitters in Water and Air Particulates **.***.*.*..**.*************.* 180 E-2 Gamma Emitters in Milk, Water, Air Particulates and Food Products ** ~ ***********************... 181 E-3 Tritium in Water ***************.****.*********** 183 E-4 Iodine in Water . . . . . . . . . . . . . . . e ***** D *********** 184 E-5 Strontium-89 and -90 in Air Particulates, Milk, Water and Food Products .***.***..**..******.** 185 E-6 Radium-226 and -228 in Water .*****.***.********* 186 179
TABLE E-1 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Gross Alpha and Gross Beta Analysis of Water (pCi/L) and Air Particulate (pCi/filter) PSE&G PSE&G EPA GRAND AVG DATE ENV ID NUMBER MEDIUM ANALYSIS Mean +/- s.d. Mean +/- s.a. Mean +/- s.d. 1/83 EPA-WAT-AB49 Water Alpha 21+/-6 29+/-7 26+/-6 83-104 Beta 28+/-1 31+/-5 32+/-5 3/83 EPA-WAT-AB55 Water Alpha 32+/-2 31+/-8 27+/-8 83-349 Beta 23+/-3 28+/-5 28+/-4 3/83 EPA-APT-GABS57 APT Alpha 29+/-1 26+/-6 28+/-4 83-471 Beta 76+/-1 68+/-5 69+/-6 5/83 EPA-BLD-Z59 Water Alpha 54+/-2 64+/-16 58+/-16 83-569 Beta 111+/-7 149+/-8 136+/-17 5/83 EPA-WAT-AB61 Water Alpha 12+/-1 11+/-5 11+/-3 83-594 Beta 55+/-2 57+/-5 54+/-8 7/83 EPA-WAT-AB66 Water Alpha 7+/-2 7+/-5 8+/-2 83-944 Beta 18+/-2 22+/-5 22+/-4 8/83 EPA-APT-GABS69 APT Alpha 15+/-1 13+/-5 14+/-3 83-1014 Beta 47+/-1 36+/-5 39+/-6 9/83 EPA-WAT-AB72 Water Alpha 4+/-1 5+/-5 5+/-2 83-1127 Beta 8+/-1 9+/-5 10+/-3 11/83 EPA-WAT-AB79 Water Alpha 11+/-1 14+/-5 13+/-3 83-1573 Beta 15+/-1 16+/-5 17+/-4 11/83 EPA-BLD-Z77 Water Alpha 19+/-2 ( 1) (1) 83-1511 Beta 53+/-1 (1) (1) 11/83 EPA-APT-GABS82 APT Alpha 24+/-1 (1) (1) 83-1618 Beta 68+/-2 ( 1) (1) (1) Results not received. 180
TABLE E-2 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Gamma Analysis of Milk, Water (pCi/L) , Air Particulate (pCi/filter) and Food Products (Pei/kg) PSE&G PSE&G EPA GRAND AVG DATE ENV ID NUMBER MEDIUM NUCLIDE Mean +/- s.d. Mean +/- s.d. Mean +/- s.d. 2/83 EPA-WAT-G51 Water Cr-51 55+/-6 45+/-5 48+/-10 83-180 Co-60 24+/-2 22+/-5 23+/-3 Zn-65 23+/-4 21+/-5 22+/-5 Ru-106 56+/-2 48+/-5 47+/-10 Cs-134 21+/-1 20+/-5 20+/-3 Cs-137 21+/-1 19+/-5 19+/-3 2/83 EPA-MLK-GS52 Milk I-131 56+/-1 54+/-6 54+/-5 83-213 Cs-137 27+/-3 26+/-5 26+/-4 K (*) 1570+/-10 1512+/-76 1517+/-172 Ba-140 <14 0 0 3/83 EPA-ORG-GS53 Food I-131 38+/-1 37+/-6 37+/-4 83-238 Cs-137 34+/-1 31+/-5 33+/-3 Ba-140 <18 0 0 K (*) 2690+/-120 2590+/-130 2650+/-280 3/83 EPA-APT-GABS57 APT Cs-137 35+/-1 27+/-5 31+/-5 83-471 5/83 EPA-BLD-Z59 Water Co-60 30+/-2 30+/-5 31+/-4 83-569 Cs-134 31+/-2 33+/-5 31+/-4 Cs-137 26+/-1 27+/-5 27+/-4 6/83 EPA-MLK-GS62 Milk I-131 30+/-2 30+/-6 30+/-4 83-738 Cs-137 48+/-1 47+/-5 47+/-3 Ba-140 <14 0 0 K (*) 1520+/-50 1486+/-74 1494+/-148 6/83 EPA-WAT-G64 Water Cr-51 71+/-13 60+/-5 62+/-11 83-782 Co-60 13+/-1 13+/-5 14+/-2 Zn-65 39+/-3 36+/-5 37+/-6 Ru-106 42+/-11 40+/-5 40+/-7 Cs-134 45+/ 47+/-5 44+/-4 Cs-137 27+/-1 26+/-5 28+/-5 8/83 EPA-APT-GABS69 APT CS-137 16+/-1 15+/-5 19+/-4 83-1014 181
TABLE E-2 (cont'd) USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Gamma Analysis of Milk, Water (pCi/L), Air Particulate (pCi/filter) and Food Products (Pei/kg) PSE&G PSE&G EPA GRAND AVG DATE ENV ID NUMBER MEDIUM NUCLIDE Mean +/- s.d. Mean +/- s.d. Mean +/- s.d. 10/83 EPA-WAT-G75 Water Cr-51 68+/-13 51+/-5 48+/-9 83-1305 Co-60 19+/-2 19+/-5 19+/-2 Zn-65 39+/-3 40+/-5 40+/-6 Ru-106 57+/-2 52+/-5 48+/-8 Cs-134 14+/-2 15+/-5 15+/-3 Cs-137 23+/-1 22+/-5 22+/-3 10/83 EPA-MLK-GS76 Milk I-131 37+/-6 40+/-6 (1) 83-1423 Cs-137 34+/-1 33+/-5 (1) Ba-140 K (*) 1540+/-35 1550+/-75 (1) 11/83 EPA-BLD-Z77 Water Co-60 12+/-2 ( 1) (1) 83-1511 Cs-134 15+/-1 ( 1) (1) Cs-137 15+/-1 ( 1) ( 1) 11/83 EPA-APT-GABS82 APT Cs-137 22+/-2 (1) (1) (*) Reported as mg/L of Potassium (1) Results not received. 182
TABLE E-3 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Tritium Analysis of Water (pCi/L) PSE&G PSE&G EPA GRAND AVG DATE ENV ID NUMBER MEDIUM NUCLIDE Mean +/- s.d. Mean +/- s.d. Mean +/- s.d. 2/83 EPA-WAT-H50 Water H-3 2760+/-50 2560+/-350 2530+/-270 83-181 6/83 EPA-WAT-H63 Water H-3 1500+/-50 1530+/-340 1550+/-200 83-739 8/83 EPA-WAT-H68 Water H-3 1850+/-60 1836+/-342 1864+/-207 83-1013 10/83 EPA-WAT-H74 Water H-3 2920+/-40 1210+/-329 1226+/-185 83-1304 12/83 EPA-WAT-H81 Water H-3 2350+/-60 2389+/-351 2341+/-262 83-1607 183
TABLE E-4 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Iodine Analysis of Water (pCi/L) PSE&G PSE&G EPA GRAND AVG DATE ENV ID NUMBER MEDIUM NUCLIDE Mean +/- s.d. Mean +/- s.d. Mean +/- s.d. 4/83 EPA-WAT-156 Water I-131 26+/-1 27+/-6 26+/-5 83-367 8/83 EPA-WAT-I67 Water I-131 13+/-2 14+/-6 14+/-3 83-969 12/83 EPA-WAT-178 Water I-131 20+/-1 20+/-6 20+/-4 83-1572 184
TABLE E-5 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Strontium-89 and -90 Analysis of Air Particulates (pCi/filter) , Milk, Water (pCi/L) and Food Products (pCi/kg) PSE&G PSE&G EPA GRAND AVG DATE ENV ID NUMBER MEDIUM NUCLIDE Mean +/- s.d. Mean +/- s.d. Mean +/- s.d. 1/83 EPA-WAT-S48 Water Sr-89 28+/-2 29+/-5 27+/-7 83-87 Sr-90 14+/-1 17+/-2 17+/-2 2/83 EPA-MLK-GS52 Milk Sr-89 33+/-2 37+/-5 32+/-7 83-213 Sr-90 17+/-1 18+/-2 17+/-4 3/83 EPA-ORG-GS53 Food Sr-89 35+/-1 35+/-5 33+/-6 83-238 Sr-90 30+/-1 28+/-2 29+/-2 3/83 EPA-APT-GABS57 APT Sr-90 19+/-2 20+/-2 19+/-2 83-471 5/83 EPA-BLD-Z59 Water Sr-89 26+/-1 24+/-5 25+/-5 83-569 Sr-90 12+/-1 13+/-2 13+/-2 5/83 EPA-WAT-S60 Water Sr-89 56+/-2 57+/-5 57+/-10 83-593 Sr-90 39+/-1 38+/-2 37+/-5 6/83 EPA-MLK-GS62 Milk Sr-89 23+/-1 25+/-5 23+/-4 83-738 Sr-90 15+/-1 16+/-2 15+/-2 8/83 EPA-WAT-GABS69 APT Sr-90 10+/-1 10+/-2 10+/-1 83-1014 9/83 EPA-WAT-S71 Water Sr-89 15+/-2 15+/-5 15+/-3 83-1126 Sr-90 10+/-1 10+/-2 10+/-2 10/83 EPA-MLK-GS76 Milk Sr-89 17+/-1 15+/-5 (1) 83-1423 Sr-90 13+/-1 14+/-2 (1) 11/83 EPA-BLD-Z77 Water Sr-89 15+/-2 ( 1) (1) 83-1511 Sr-90 6+/-1 ( 1) ( 1) (1) Results not received. 185
TABLE E-6 US EPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Radium-226 and -228 Analysis of Water (pCi/L) PSE&G PSE&G EPA GRAND AVG DATE ENV ID NUMBER MEDIUM NUCLIDE Mean +/- s.d. Mean +/- s.d. Mean +/- s.d~ 3/83 EPA-WAT-R54 Water Ra-226 11+/-1 13+/-2 12+/-2 83-348 Ra-228 <6 0 1+/-2 5/83 EPA-BLD-Z59 Water Ra-226 22+/-1 8+/-1 8+/-1 83-569 Ra-228 5.0+/-1 5+/-1 6+/-3 6/83 EPA-WAT-R65 Water Ra-226 4.1+/-1 4.8+/-1 5+/-1 83-836 Ra-228 <l 0 1+/-3 9/83 EPA-WAT-R73 Water Ra-226 3.4+/-1 3.1+/-0.5 3.1+/-0. 6 83-1227 Ra-228 <2 2.0+/-0.3 2.3+/-1.l 12/83 EPA-WAT-R83 Water Ra-226 9.4+/-1 (1) (1) 83-1617 Ra-228 4.0+/-1 ( 1) (1) (1) Results not received. 186
APPENDIX F SYNOPSIS OF DAIRY AND VEGETABLE GARDEN SURVEY 187
APPENDIX F SYNOPSIS OF 1983 MILK ANIMAL AND VEGETABLE GARDEN SURVEYS MILK ANIMAL SURVEY A survey of dairy farms conducted out to a distance of five miles from the Salem Nuclear Generating Station (SNGS) was per-formed in April and July, 1983. The result of the April survey were as follows: One dairy farm, situated 4.9 miles West of SNGS was located. One dairy farm, situated 5.0 miles NNE of SNGS was located. The result of the July survey were as follows: No change from the April survey. VEGETABLE GARDEN SURVEY A survey of vegetable gardens conducted out to a distance of one mile of the SNGS was performed in September 1983. No vegetable gardens were found within this area. 189
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RTL-ENV-85-01 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1984 RADIOLOGICAL REPORT JANUARY l TO DECEMBER 31, 1984 Prepared for PUBLIC SERVICE ELECTRIC AND GAS COMPANY By PSE&G RESEARCH CORPORATION RESEARCH AND TESTING LABORATORY MARCH 1985
TABLE OF CONTENTS PAGE
SUMMARY
1 INTRODUCTION 2 THE PROGRAM 3 Objectives 3 1984 Program Overview (Table-1) 4 Sample Collection 8 Data Interpretation 9 Quality Assurance Program 10 Program Changes 10 RESULTS AND DISCUSSION 10 Atmospheric 11 Direct Radiation 14 Terrestrial 17 Aquatic 22 PROGRAM DEVIATIONS 29 CONCLUSIONS 29 REFERENCES 30 APPENDIX A - PROGRAM
SUMMARY
33 APPENDIX B - SAMPLE DESIGNATION AND LOCATIONS 43 APPENDIX C - 1984 DATA TABLES 51 APPENDIX D - SYNOPSIS OF ANALYTICAL PROCEDURES 101 APPENDIX E -
SUMMARY
OF USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDIES PROGRAM RESULTS 151 APPENDIX F - SYNOPSIS OF DAIRY AND VEGETABLE GARDEN SURVEY 161 i
LIST OF FIGURES NUMBER PAGE
- 1. Comparison of Average Concentrations of Beta Emitters in Precipitation and in Air Particulates, 1973 through 1984.................................. 12 lA. Comparison of Average Concentrations of Beta Emitters in Precipitation and in Air Particulates, 1983 through 1984 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13
- 2. Average Ambient Radiation Levels from Quarterly TLDs in the Vicinity of Artificial Isl~nd, 1973 through 1984 . . . . . . . . . . . . . . e *********************** Cl 15 Comparison of Ambient Radiation Levels of Off-Site Indicator Stations vs. Control Stations, 1982 through 19 8 4 . . . . . . . . . . . . " .. o o * * * * " * * * * * * * * * * * * *
- o o o 16
- 3. Average Concentrations of Iodine-131 in Milk in the Vicinity of Artificial Island, May 1974 through December 1984 ** a. Cl ***** c. o * ., o . o o Cl **** o a ** *** Cl **** o o 18 3A. Average Concentrations of Iodine-131 in Milk in the Vicinity of Artificial Island, 1983 through 1984 .** 19
- 4. Average Concentrations of Beta Emitters and Potassium-40 in the Delaware River in the Vicinity of Artificial Island, 1973 through 1984 ************ 23 Average Concentrations of Beta Emitters and Potassium-40 in the Delaware River in the Vicinity of Artificial Island, 1983 through 1984 ************ 24
- 5. Average Concentrations of Tritium in the Delaware River in the Vicinity of Artificial Island, 1973 through 1984 o o o o o a o o . c o o o o o o *
- o o o *
- o. o o . o" o o o *
- 0 Q Cl f) 25 SA. Average Concentrations of Tritium in the Delaware River in the Vicinity of Artificial Island, 1983 through 1984 .... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 26 ii
SUMMARY
During the period from January l through December 31, 1984, the Research and Testing Laboratory (RTL), PSE&G Research Corpo-ration, has been responsible for the collection and analysis of all samples and the maintenance of sampling equipment for SGS connected with the Operating Radiological Environmental Monitoring Program at Artificial Island, Salem County, New Jersey. 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, will fulfill the requirements of the SGS Environmental Technical Specifications, and will provide background data for the Hope Creek Generating Station. This report presents the results of thermoluminescent dosimetry and radiochemical analyses of environmental samples collected during 1984. A total of 4305 analyses were performed on 1626 environmental samples during the period covered by this report. Samples of air particulates, air iodine, surface, ground and drinking water, benthos, sediment, milk, fish, crabs, vegetables, game, fodder crops, meat, and precipitation were collected. Thermoluminescent dosimeters were used to measure ambient radiation levels. A variety of radionuclides, both naturally-occurring and manmade, were found in the above samples. An elevated level of two radionuclides was found in one sediment/benthic organism sample. subsequent sampling of the indicators in the estuarine food-chain were at levels similar to those found* during the peroperational phase of this program. It can be concluded that the radiological characteristics of the environment around Artificial Island during 1984 were not adversely affected by the operation of SGS Units One and Two. l
INTRODUCTION Artificial Island is the site of Salem Generating Station (SGS) which consists of two operating pressurized water nuclear power reactors. Unit One. has a net rating of 1090 MWe (3338 MWt), and Unit Two is rated at 1115 MWe (3411 MWt). Artificial Island is a man-made peninsula on the east bank of the Delaware River and was created by the deposition of hydraulic fill from dredging operations. It is located in Lower Alloways Creek Township, Salem County, New Jersey. The environment surrounding Artificial Island is characterized mainly by the Delaware River and Bay, extensive tidal marshlands, and low-lying meadowlands. These land types make up approximately 85% of the land area within five miles of the site. Most of the remaining land is used for agriculture [13]. More specific information on the demography, hydrology, meteorology, and land use of the area may be found in the Environmental Report [13], .Environmental Statement [14], and the Final Safety Analysis Report for SGS [ 15] . Since 1968 an off-site Radiological Environmental Monitoring Program (REMP) has been conducted at the Artificial Island Site. Starting in December 1972, more extensive radiological monitoring programs were initiated. The operational REMP was initiated in December 1976 when Unit l achieved criticality. The Research and Testing Laboratory (RTL), PSE&G Research Corporation, a wholly-owned subsidiary of Public Service Electric and Gas Company, h~s been involved in the REMP since its inception. The RTL is responsible for the collection of all radiological environmental samples, and, from 1973, through June, 1983, conducted a quality assurance program in which duplicates of a portion of those samples analyzed by the primary laboratory were also analyzed by the RTL. From January 1973, through June 1983, Radiation Management Corporation (RMC) had primary responsibility for the analysis of all samples under the Artificial Island REMP and the annual reporting of results. RMC reports for the the preoperational phase from 1973 to 1976 and for the operational phase from 1976 through 1982 are referenced in this report [1-11]. On July 1, 1983, the RTL assumed primary responsibility for the analysis *of all samples (except TLD's) and the reporting of results. Teledyne Isotopes (TI), Westwood, NJ, at that time was made responsible for third-party QA analyses and TLD's. This report summarizes the results from January l through December 31, 1984 for the Artificial Island Radiological Environmental Monitoring Program. 2
THE PROGRAM The operational phase of the REMP is conducted in accordance with Section 3.2 of the Environmental Technical Specifications for SGS Units 1 and 2 [16,17]. An overview of this program is provided in Table 1. Radioanalytical data from samples collected under this program were compared with results from the preoper-ational phase. Differences between these periods were examined statistically, where applicable, to determine the effects, if any, of station operations. Objectives The objectives of the operational radiological environmental program are:
- 1. To fulfill the obligations of the Radiological Surveillance sections of the Environmental Technical Specifications for Salem Generating Station (SGS).
- 2. To determine whether any significant increase occurs in the concentration of radionuclides in critical pathways.
- 3. To determine if SGS has caused an increase in the radioactive inventory of long lived radionuclides.
- 4. To detect any change in ambient gamma radiation levels.
- 5. To verify that SGS operations have no detrimental eff~cts on the health and safety of the public or on the environment.
This report, as required by section 5.6 of the Salem Environ-mental Technical Specifications (ETS), summarizes the findings of the 1984 REMP. Results of the four-year preoperational program have been summarized for purposes of comparison with subsequent operational reports [4]. 3
TABLE -1 1984 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATION CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS I. ATMOSPHERIC ENVIRONMENT ao Air Particulate 282 5Dl 16El lFl 3H3 Weekly Gross alpha/weekly 5Sl lODl 2F2 Gross beta/weekly Sr-89 & -90/quarterly Gamma scan/quarterly
- b. Air Iodine 282 5Dl 16El lFl 3H3 Weekly Iodine-131/weekly 5Sl lODl 2F2 Co Precipitation 2F2 Monthly Gross alpha/monthly Gross beta/monthly Tritium/monthly Sr-89 & -90/quarterly Gamma scan/quarterly II. DIRECT RADIATION
- a. Thermoluminescent 2S2 5Dl 2El lFl 3Gl 3Hl Monthly & Gamma dose/monthly Dosimeters 5Sl lODl 3El 2F2 3H3 Quarterly Gamma dose/quarterly 6S2 1401 13El ~F6 781 16El 5Fl lOSl* 6Fl llSl 7F2 llFl 13Fl/4
TABLE -1 (cont'd) 1984 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATION CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS
- a. Thermoluminescent 402 9El 2F5 1G3 Quarterly Gamma dose/quarterly Dosimeters (cont'd) 11E2 3F2 lOGl 12El 3F3 16Gl 10F2 12Fl 13F2 13F3 14F2 15F3 U1 16F2 III. TERRESTRIAL ENVIRONMENT
- a. Milk 13E3 2F4 3Gl Semi-monthly Iodine-131/semi-monthly SF2 Sr-89 & -90/monthly 14Fl Gamma scan/monthly 15Fl
- b. Well Water 2S3 SDl 3El Monthly Gross alpha/monthly Gross beta/monthly Potassium-40/monthly Tritium/monthly Sr-89 & -90/quarterly Gamma scan/quarterly
TABLE -1 (cont'd) 1984 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATION CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS
- c. Potable Water 2F3 Monthly Gross alpha/monthly (Raw & Treated) (Composited Gross beta/monthly daily) Potassium-40/monthly Tritium/monthly Sr-89 & -90/quarterly Gamma Scan/quarterly
- d. Vegetables 5Dl 2El 1F3 lGl 3H5 Annually Sr-89 & -90/on collection 4Fl (At Harvest) Gamma scan/on collection 5Fl l4F3
- e. Game 3El llDl Semi- Sr-89 & -90 (bones)/on collection (Muskrat) annually Gamma scan (flesh)/on collection
- f. Beef 3El Semi- Gamma scan/on collection annually
- g. Bovine Thyroid 3El Semi- Gamma scan/on collection annually
- h. Fodder Crops 3El 2F4 3Gl Annually Gamma scan/on collection 5F2 14Fl 15Fl
TABLE -1 (cont'd) 1984 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATION CODE COLLECTION MEDIUM INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS IV. AQUATIC ENVIRONMENT
- a. Surface Water llAl 7El 1F2 12Cl Monthly Gross alpha/monthly 16Fl Gross beta/monthly Tritium/monthly Sr-89 & -90/quarterly Gamma scan/monthly
- 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 llAl 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 16Fl 12Cl Semi- Sr-89 & -90/on collection annually Gamma scan/on collection
- e. Sediment llAl 7El 16Fl 12Cl Semi- Sr-90/on collection annually Gamma scan/on collection
- Except for TLDs, the quarterly analysis is performed on a composite of individual samples collected during the quarter.
J
Sample Collection In order to meet the stated objectives, an ap~ropriate oper-ational 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 typea 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. Indicator and control station data are also evaluated relative to preoper-ational data. The REMP for the Artificial Island Site includes additional samples and analyses not specifically required by the Salem ETS. The summary tables in this report include these additional samples and analyses. Air particulates were collected on Schleicher-Schuell No. 25 glass fiber filters with lo~-volume air samplers. Iodine was collected from air by adsorption on TEDA-impregnated charcoal cartridges connected in series after the air particulate filters. Air sample volumes were measured with calibrated dry-gas meters and were corrected to standard temperature and pressure. Precipitation was collected in a Wong Laboratory Automatic Precipitation Collector having a 95 square inch collection area. The collector is automatically covered during periods of no precipitation to exclude fallout resulting from dry deposition. Samples were collected monthly and transferred to new poly-ethylene bottles. The collector was rinsed with distilled water 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 CaS04 (Dy) thermoluminescent dosimeters (TLD's) supplied and read by Teledyne Isotopes. Packets for monthly and quarterly exposure were placed *on and around the Artificial Island Site at various distances. Well water samples were collected monthly by PSE&G personnel and separate raw and treated potable water samples were composited daily by personnel of the City of Salem water treatment plant. New two-gallon polyethylene containers were used for all water samples.
- 8
All estuarine samples were collected by v. J. Schuler Associates, Inc. (formerly Ichthyological Associates) and delivered by PSE&G personnel. Surface water samples were collected in new con-tainers which were rinsed twice with the sample medium prior to collection. Edible fish and crabs were taken by net, and frozen in sealed polyethylene containers. Benthos and sediment were taken with a bottom grab sampler. Milk samples were taken semi-monthly in new polyethylene con-tainers. Food products, fodder crops, game, beef, and bovine thyroid were sealed in new plastic bags or jars. All perishable samples were transported in ice chests, and no preservatives were added. Appendix A describes and summarizes, in the format of Table 5.6-1 of the Salem gTS, the entire operational program as performed in 1984. Appendix B describes the coding system which identifies sample type and location. Table B-1 lists the sampling stations and the types of samples collected at each station. These sampling stations are indicated on maps B-1 and B-2. Data Interpretation Results of all analyses were grouped according to the analysis performed for each type of sample and are presented in the data tables in Appendix C. All results above the lower limit of detection (LLD) are at a confidence level of +/- 2 sigma. This represents the range of values into which 95% of repeated analyses of the same sample should fall. As defined in Regulatory Guide 4.8, LLD is the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real signal". LLD is normally calculated as 4.66 times one standard deviation of the background count or of the blank sample count as appropriate. The grouped data were averaged and standard deviations calcu-lated in accordance with Appendix B of Reference 18. Thus, the 2 sigma deviations of the averaged data represent sample and not analytical variability. When a group of data were composed of 50% or more LLD values, averages were not calculated, Grab sampling is a useful and acceptable procedure for taking environmental samples of a medium in which the concentration of radionuclides is expected to vary slowly with time or where intermittent sampling is deemed sufficient to establish the radiological characteristics of the medium. This method, however, is only representative of the sampled medium for that specific location and instant of time. As a result, variation 9
in the radionuclide concentrations of the samples will normally occur. Since these variations will tend to counterbalance one another, the extraction of averages based upon repetitive grab samples *is considered valid. Quality Assurance Program PSE&G Research Corporation, Research and Testing Laboratory (RTL), has a quality assurance program designed to maximize confidence in the analytical procedures used. Approximately 20% of the total analytical effort is spent on quality control, including process quality control, instrument quality control, interlaboratory cross-check analyses, and data review. The analytical methods utilized in this program are summarized in Appendix D. The quality of the results obtained by the RTL is insured by the implementation of the Quality Assurance Program as described in 1 the Environmental Division Quality Assurance Manual [19] and the Environmental Division Procedures Manual [20].
- The internal quality control activity of the Laboratory includes the quality control of instrumentation, equipment, and reagents, the use of reference standards in calibration, documentation of established procedures and computer programs, and analysis of duplicate and spiked samples. The external quality control activity is implemented through participation in the USEPA Laboratory Inter-comparison Studies Program. These results are listed in Tables E-1 through E-6 in Appendix E.
Program Changes TLD location 13Fl was relocated to an adjacent site and designated 13F4 on March 27, 1984. This move became necessary when the new owners of the building upon which the TLD was mounted began renovation work. An additional leafy vegetable location (14Fl) became available in 1984 and was added to the program. Vegetable control location 3H4 which is no longer growing crops was replaced by location 3H5. RESULTS AND DISCUSSION The analytical results of the 1984 REMP samples are divided into categories based on exposure pathways: atmospheric, direct, terrestrial, and aquatic. The analytical results for the 1984 REMP are summarized in Appendix A. The data for individual samples are presented in Appendix c. 10
This section discusses the data for samples collected under the REMP. It does not include the data from the quality assurance program discussed previously. Atmospheric Air Particulates (Tables C-1, C-2, c-3) Air particulate samples were analyzed for alpha and beta emitters, sr-89 and -90, and gamma emitters. The weekly air particulate samples were analyzed for gross alpha and gross beta. Quarterly composites of the weekly samples from each station were analyzed for Sr-89, Sr-90 and specific gamma emitters. Concentrations were detected in 366 of the 424 weekly samples analyzed for gross alpha emitters ~Table 5-1). Alpha concentra-tions ranged from 0.7 to 4.7 x 10- pCi/m with the grand average for all stations being 1.9 x 10- 3 pCi/m 3 . Three :: analyses exhibited high uncertainties due to low sample volumes. Analysis of weekly air particulate samples for gross beta (Table C-2) indicated concentrations ranging from 6.0 x lo-3 to 44 x 10-3 gCi/m3 with the grand average for all stations being 24 x lo-3 pCi/m3. Figure 1 indicates the relation between gross beta activity in air particulates and precipitation for the preoperational and operational periods, including the effects of atmosph~ric weapons testing. Of the 32 monthly-composited samples analyzed for strontium-891. only one (control station) had a detectable level of 1.1 x 10-j pCi/m3. There was no Sr-90 detectable activity. LLD's for sr-89 ranged from 0.2 x lo-3 to 2.0 x lo-3 pCi/m3 and, for sr-90, from Ool x lo-3 to 0.6 x lo-3 pCi/m3. Results of gamma spectrometry indicated detectable levels of Be-7 in al~ of the 32 monthly composites with a maximum of 79 x 10- 3 pCi/m . Be-7 is a naturally occurring radionuclide attributed to cosmic ray activity in the atmosphere. Traces of cr-51, Mn-54, Co-58, Fe-59, Te-129m, Ra-226 and Th-232 were detected in 5 samples; all of these activities were below the maximum LLD's for these radionuclideso Air Iodine (Table C-4) Cartridges for the adsorption of air iodine were connected in series after each of the air particulate filters. The adsorption media in these cartridges is triethylenediamine (TEDA) impreg-nated charco~l. Al~ results for I-131 ranged from <4.1 x io-3 to <56 x 10- pCi/m . In addition, one did not meet minimum sensitivity of 60 x lo-3 pCi/m3. 11
FIGURE 1 COMPARISON OF AVERAGE CONCENTRATIONS OF BETA EMITTERS IN PRECIPITATION AND IN AIR PARTICULATES, 1973 THROUGH 1984 Legend
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FIGURE IA COMPARISON OF AVERAGE CONCENTRATIONS OF' BETA EMITTERS IN PRECIPITATION AND IN AIR PARTICULATES 1983 THROUGH 1984 1000 Legend
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Precipitation (Tables C-6, C-7) Although not required by the Salem ETS, precipitation samples were collected at 2F2 in the town of Salem. Monthly samples were analyzed for gross alpha, gross beta, and tritium. Alpha activities in 4 samples ranged from 0.8 to 2.4 pCi/L, with LLD's in 8 samples from 0.8 to 1.9 pCi/L. Beta activity in eleven of the monthly samples ranged from 1.0 to 4.0 pCi/L, with an LLD in one sample of <2.7 pCi/L. Tritium was detected in three samples at levels ranging from 140 to 150 pCi/L; this is below ihe required sensitivity of 200 pCi/L. Quarterly composites were analyzed for radiostrontium and gamma emitters. Neither Sr-89 nor Sr-90 was detected. Be-7 at concentrations of 25 to 39 pCi/L was found in the quarterly samples. In addition, Ra-226 at 5.6 pCi/L and Th-232 at 7.8 pCi/L was seen in the fourth quarterly sample. Direct Radiation (Tables C-8, C-9) A total of 41 locations were monitored for direct radiation during 1984, including 6 on-site locations, 29 off-site locations within the 10 mile zone, and 6 control locations beyond 10 miles. Monthly and quarterly measurements were made at the 6 on-site stations and at 15 off-site indicator stations, and 3 control stations. An additional 14 quarterly measurements were taken at schools and population centers with 3 additional controls 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 5.8 millirads per standard month, and the corresponding averaged control dose rate was 6.4 millirads per standard month. The average dose rate for the 29 quarterly off-site indicator TLD's was 5.5 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 12 year period through 1984. Figure 2A shows the monthly averages of the off-site indicator stations and the control stations for 1982 through 1984. An increase in ambient radiation levels over those of 1983 for both indicator and control locations was noted for the months of February, May and June while the other months indicated a decrease. The annual averages for both off-site indicators and controls were slightly lower than those in 1983. 14
FIGURE 2 AVERAGE AMBIENT RADIATION LEVELS FROM QUARTERLY TLDS IN THE VICINITY OF ARTIFICIAL ISLAND, 1973 THROUGH 1984 10 Legend 9
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Terrestrial Milk (Tables C-10, C-11, C-12, C-13) Milk samples were collected twice each month at six local dairy farms. Each sample was analyzed for I-131 and the first collec-tion each month was also analyzed for Sr-89 and -90 and gamma emitters. Figure 3A indicates that I-131 was not detected in any sample during 1984. Table C-10 lists the results and shows that sensitivities ranged from <0.1 to <0.2 pCi/L. Strontium-89 was not detected in any of the samples; LLD values ranged from <0.8 to <2.0 pCi/L. Strontium-90 was found in all of the samples analyzed. The Sr-90 annual mean for the indicator locations was 2.4 pCi/L with a range of 1.2 to 5.3 pCi/L; annual mean for the control location was 3.2 pCi/L with a range of 2.2 to 4.9 pCi/L. Gamma spectrometry showed detectable concentrations of K-40 in all samples and Cs-137 in eleven of the sixty indicator locations and none was detected in the twelve samples from the control location. The annual mean concentration of K-40 for the indi-cator locations was 1347 pCi/L with a range of 1200 to 1500 pCi/L; K-40 mean for the control location was 1350 pCi/L with a range of 1300 to 1500 pCi/L. The annual mean of Cs-137 for the ind~cator locations was 3.1 pCi/L with a range of 1.8 to 6.2 pCi/L; preoperational levels ranged from <0.4 to 14 pCi/L with an average of 3.0 pCi/L. Traces of Na-22, Mn-54, La-140, Ra-226 and Th-232 was detected at levels near or below the LLD values in seven of the 72 samples anaryzed. 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 com-posites were analyzed for radiostrontium and gamma emitters. Gross alpha concentrations from 0.9 to 2.0 pCi/L were detected in six of the indicator samples, with LLD sensitivities for the other analyses ranging from <0.6 to <1.9 pCi/L. Gross beta activity was detected in all of the samples. The mean activity for the indicator locations was 10 pCi/L with a range of 2.9 to 17 pCi/L; mean activity for the control location was 8.4 pCi/L with a range of 6.0 to 10 pCi/L. K-40 in each monthly sample was determined by atomic absorption spectroscopy. Mean activity for the indicator locations was 11 pCi/L with a range of 2.8 to 28 pCi/L, and mean activity for the control location was 8.4 pCi/L with a range of 5.5 to 9.3 pCi/L. All tritium results were at LLD levels of <130 to <140 pCi/L. Strontium-89 was detected in one indicator location sample at 0.9 pCi/L; LLD values ranged from <0.4 to <0.6 pCi/L. Sr-90 was not detected in any of the samples; LLD values ranged from <0.4 to <0.5 pCi/L. 17
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r r r r r r _J r r t\ I r r r NI I Jr I I I I I I JFMAMJJASONDJFMAMJJASONDJFMAMJJASONDJFMAMJJASONDJ I I I I I I I I I I I 1983 1984 1985 1986 1987
Gamma spectrometry showed detectable levels of K-40 in six of the eight indicator samples at an average concentration of 12 pCi/L with a range of 11 to 14 pCi/L. One control station sample had detectable K-40 at 6.3 pCi/L which was below the LLD values of <8.6 to <9.9 pCi/L. Traces of Ra-226 were detected in three samples at levels near or below the LLD values of the other nine samples. Potable Water (Tables C-16, C-17) Both caw and treated water samples were collected from the Salem water treatment plant. Each consisted of daily aliquots com-posited into a monthly sample. The raw water source for 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 were analyzed for Sr-89, -90, and gamma emitters. Detectable alpha activity was noted in six raw and four treated water samples with ranges of 1.2 to 4.5 pCi/L (raw), and 1.0 to 1.6 pCi/L (treated). This resulted in an average activity of 2.4 pCi/L for the raw and 1.3 pCi/L for the treated potable waters. Beta activity was observed in all 24 of the monthly samples with ranges of 1.5 to 3.8 pCi/L (raw), and 1.7 to 3.4 (treated), and averages of 2.6 pCi/L (raw) and 2.4 pCi/L (treated). K-40 concentrations for raw and treated samples were practically identical and were lower than the beta activity in all cases. The K-40 average for both the raw and treated samples was 1.5 pCi/L. Tritium activity was observed in four of the twenty-four ranging from.140 to 250 pCi/L. Sr-90 was observed in one of the quarterly raw water composites at 0.3 pCi/L; no Sr-89 was found. LLD's ranged from 0.4 to 0.9 pCi/L for sr-89, and from 0.3 to 0.8 pCi/L for Sr-90. K-40 (via gamma spectrometry) was detected in the second quarter treated water composite at 7.4 pCi/L. Food Products (Table C-18) A variety of food products grown in the area for human consump-tion were sampled. These included sweet corn, peppers, aspara-gus, cabbage, and tomatoes. Each sample was analyzed for sr-89, Sr-90, and gamma emitters. sr-89 was not found in any of the seventeen samples; Sr-89 LLD's ranged from <2.8 to <20 pCi/kg-wet. Sr-90 was detected in eight of the seventeen samples with activities ranging from 1.8 to 32 pCi/kg-wet. These activities were detected in one sweet corn (control location), one pepper (control location), three cabbage (two indicator, one control location), and three tomatoe (two indicator, one control loca-tion) samples. sr-90 LLD's ranged from <1.8 to <6.1 pCi/kg-wet. 20
All samples contained K-40 at concentrations from 1700 to 3000 pCi/kg-wet, with an average for all samples of 2100 pCi/kg-wet. A trace of Ra-226 was seen in one control station pepper sample and a trace of Th-232 was detected in an indicator station cabbage sample. No other gamma emitters were detected in these food products. Game (Table C-19) Two muskrat samples were collected in January. Bones from both samples were analyzed for Sr-89 and -90 while the flesh was analyzed for gamma emitters. Sr-89 was not found in either of the samples; Sr-89 LLD's were <100 and <160 pCi/kg-dry. Sr-90 was found in both samples at levels of 290 and 810 pCi/kg-dry. These levels, while higher than in 1983, were significantly below those seen in the preoperational program. Gamma scans of the flesh indicated the presence of naturally-occurring K-40, in both samples at levels of 2400 and 3000 pCi/kg-wet; and Cs-137 in one sample at 5.6 pCi/kg-wet. Beef and Bovine Thyroid (Table C-19) One beef sample and the thyroid glands were collected in February. Analysis of the flesh for gamma emitters indicated only the presence of naturally-occurring K-40 at a concentration of 2500 pCi/kg-wet, and Ra-226 at a level of 9.3 pCi/kg-wet. Analysis of the thyroid glands for gamma emitters indicated only K-40 at a concentration of 1200 pCi/kg-wet. No detectable concentrations of I-131 were found. Fodder Crops (Table C-20) samples of crops normally use9 as cattle feed were collected at six locations where these products may be a significant element in the food-chain pathway. Five of the locations are milk sampling stations, and the sixth supplied a beef/thyroid sample. Samples collected for wet gamma analysis included hay, corn silage, green chop, and soybeans. K-40 was detected in all of the ten samples at concentrations from 2000 to 14000 pCi/kg-wet, with an ayer~ge of 6700 pCi/ kg-wet. Be-7, from the atmosphere, was found in seven of the samples at concentrations from 260 to 1400 pCi/kg-wet, with an average of 390 pCi/kg-wet. Traces of Ra-226 or Th-232 were detected in hay, and soybeans at one indicator station. Nothing is known of the composition of fertilizers which may have been applied to the soil in which these crops were grown. 21
Aquatic 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, except for the January samples which were unavailable due to icing conditions on the river. One location is at the outfall area, another is downstream from the outfall area, and another is directly west of the outfall area at the mouth of the Appoquinimink River. Two upstream locations are in the Delaware River and at the mouth of the Chesapeake and Delaware Canal, the latter being sampled when the flow is from the Canal into the river. Station 12Cl, at the mouth of the Appoquinimink River, serves as the operational control. All surface water samples were analyzed monthly for gross alpha and gross beta emitters, tritium, and gamma emitters. Quarterly composites were analyzed for Sr-89 and Sr-90. Alpha concentrations were detected in eleven of the 44 indicator samples and in five of the eleven control samples. Levels ranged from 1.6 to 7.0 pCi/L. All the other samples were at or below the LLD, which ranged from <1.3 to <3.9. Beta concentrations for the indicator stations ranged from 3.2 pCi/L to 140 pCi/L with an average of 41 pCi/L, and, for the control station, from 4.3 pCi/L to 88 pCi/L with an average of 37 pCi/L. Nearly all of the beta activity was contributed by K-40, a natural component of salt and brackish waters, as illustrated in Figure 4, which compares averaged gross beta and K-40 concentrations. Tritium analysis for the indicator stations ranged from 130 to 250 pCi/L. The average of the nine indicator samples with detectable levels of tritium was 164 pCi/L. Tritium was detected in two of the eleven control samples and ranged from 130 to 140 pCi/L with an average of 135 pCi/L. Levels for the years 1973 through 1984 are plotted in Figure 5. Gamma spectrometric analysis of surface water samples showed detectable concentrations in 44 of the 55 samples. The average K-40 concentration at the indicator stations was 61 pCi/L with a range of 9.7 to 140 pCi/L. Average K-40 concentration at the control station was 60 pCi/L with a range of 16 to 110 pCi/L. Traces of Mn-54, Co-60, cs-137, La-140, Ra-226 and Th-232 were detected at levels near or below the LLD in 15 of the 55 samples analyzed. Strontium-89 was detected in one of sixteen indicator station samples at 1.3 pCi/L, none was detected in the four control station samples. The LLD sensitivities ranged from <0.5 to <1.4 pCi/L. Sr-90 was not detected in any of the twenty samples; LLD sensitivities ranged from <0.4 to <0.7 pCi/L. 22
FIGURE 4 AVERAGE CONCENTRATIONS OF BETA EMITTERS AND POTASSIUM-40 IN THE DELAWARE RIVER IN THE VICINITY OF ARTIFICIAL ISLAND, 1973 THROUGH 1984 1000 Legend
- GROSS BETA 0 POTASSIU~-40
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FIGURE 4A AVERAGE CONCENTRATIONS OF BETA EMITTERS AND POTASSIUM-40 IN THE DELAWARE RIVER IN THE VICINITY OF ARTIFICl.AL ISLAND, 1983 THROUGH 1984 1000 Legend 0 GROSS BETA POTASSI U t.4-4 0 0 IOO I
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rlGURE 5 AVERAGE CONCENTRATIONS OF TRITIUM IN THE DELAWARE RIVER IN THE VICINITY OF ARTIFICIAL ISLAND, 1973 THROUGH 1984 1000------------.-----..----.--...---......---....----*---i----. U*.*-*~,.l* ....*. *.,, ..
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- a. +-----+----+----+--+--+---+-- ~***-+-----+------+---+---+-----t-----+--1
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- > 4 " ::> 40 Ill~~ lllUoo l!) f- - l!)E~
zIll iI.)~ i' Zill:......._ Ill I.) lJQ IO+-r-'"t'""'T"-+-r--.-.--i-.--.-.-;-..-r---.----r""T'""T""T"+..,...,.-r-+.....--.__,,_,_.---r-+-r--T""T'"+-r-'"t'""'T"-+-r--l"""T-t--T__,~ I 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985
FIGURE 5A AVERAGE CONCENTRATIONS OF TRITIUM IN THE DELAWARE RIVER IN THE VICINITY OF ARTIFICIAL ISLAND, 1983 THROUGH 1984 1000
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Il \ ~
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IO I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I JFMAMJJASONDJFMAMJJASONDJFMAMJJASONDJFMAMJJASONDJ 198 3 1984 1985 198 6 1987
Fish (Tables C-26, C-27) Ediole species of fisl1 were collected semi-annually at three locations and analyzed for tritium and gamma emitters (flesh) and for strontium-89 and -90 (bones). samples included spotted hake, channel catfish, white perch, summer flounder, brown bull-head, weakfish and bluefish. Gamma spectrometry of these samples indicated K-40 in all six samples at an average concentration of 2400 pCi/kg-wet with a range of 1200 to 3300 pCi/kg-wet. cs-137 was noted in one sample at 16 pCi/kg-wet, with LLD sensitivities for the other five samples from <6.2 to <14 pCi/kg-wet. All six bone samples analyzed for Sr-89 were below LLD of <41 to <190 pCi/kg-dry. Five of the six semi-annual samples analyzed for Sr-90 had detectable concentrations ranging from 62 to 1000 pCi/kg-dry with an average of 380 pCi/kg-dry, the sixth sample was <38 pCi/kg-dry. In 1983 the Sr-90 concentration for three of six samples ranged from 110 to 600 pCi/kg-dry with an average of 347 pCi/kg-dry. The maximum level detected during the pre-operational 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: llAl, 400 pCi/L at the downstream station: 7El, and 300 pCi/L at the control station: 12Cl. Only one sample, the control location, had a detectable concentration of tritium for the organic fraction with a result of 120 pCi/L. These results probably cannot be attributed to plant operation since the closest indicator station had a level of tritium in the aqueous fraction comparable to the other two stations and no detectable tritium in the organic fraction. Blue crab (Table C-28) Blue crab samples, collected semi-annually at two locations, were analyzed for gamma emitters, Sr-89 and -90, and tritium in the aqueous fraction. The shells were also analyzed for Sr-89 and -90. A trace of Co-60 in one sample and K-40 in all four samples were the only gamma emitters detected. K-40 levels ranged from 1900 to 2300 pCi/kg-wet with an average of 2100 pCi/kg-wet. Sr-89 was not detected in either the flesh or the shell. Sr-90 was detected in all four of the shell samples at concentrations of 390 to 860 pCi/kg-dry with an average of 610 pCi/kg-dry. Preoperational average for the shell was 614 pCi/kg-dry. 27
Tritium activity in the aqueous fraction of the flesh was detected only in the second semi-annual samples at levels of 300 and 600 pCi/kg-wet with an average of 450 pCi/kg-dry. Benthic Organisms and Sediment (Tables C-29, C-30) As required by the Technical Specifications, benthic organisms were separated from the bottom sediment and analyzed for Sr-89 and -90, and gamma emitters. Sr-89 and -90 were not detected in any of the samples. The gamma emitter Ra-226 was found in one sample. It should be noted that, due to the very small sample sizes for all samples (0.1 gram to 0.25 gram dry), satisfactory strontium and gamma sensitivities could not be achieved. The small sample size was also responsible for the extremely high 2-sigma uncertainty for the gamma emitter found. The benthos samples, which consist of sediment and associated benthic organisms, were collected at the same locations as the benthic organisms, and sample sizes are large enough to obtain more reliable results. Sediment was analyzed for Sr-90 and gamma emitters. The sensitivity requirements of the Salem Environmental Technical Specifications were met. Levels of Sr-90 were below LLD (<19 to <39 pCi/kg-dry) in all eight samples analyzed. Results of gamma spectrometry indicated the presence of naturally-occurring K-40, Ra-226, and Th-232 in all eight samples with averages of 12000, 910, and 770 pCi/kg-dry respectively. Concentrations of the gamma emitters Mn-54, Co-58, Co-60 and cs-137 were also detected. Trace quantities of these isotopes were found in releases from the Salem station during 1984 and reported in the semiannual Radioactive Effluent Release Report [21]. The concentrations of Co-58 and Co-60 at location llAl for the sample collected May 21, 1984 were 300 pCi/kg-dry and 520 pCi/kg-dry, respectively. These levels were ten times higher than levels measured at control location 12Cl, which were <29 pCi/kg-dry for co-58 and 40 pCi/kg-dry for co-60. In accordance with our Technical Specifications these results were reported to the USNRC after the results were confirmed by reanalysis. There was no indication of unusual levels of these radionuclides in any of the other estuarine samples for either semiannual period. 28
PROGRAM DEVIATIONS The January surface water sample from all five locations was unavailable due to icing conditions on the river. The second semi-annual collection of mu~krat samples was not obtained. Muskrats are normally trapped during November and December each year. However, in 1984, because of weather con-ditions and the poor quality of the pelts, muskrats were *not available from the trappers. The second semi-annual collection of beef and bovine thyroid . samples was not obtained. Farmers from whose animals the samples are normally obtained did not slaughter from July through December 1984. Direct radiation measurement results from location 6S2 for September and the third quarter are unavailable; TLDs were missing from the field location. CONCLUSIONS The Radiological Environmental Monitoring Program for Salem Generating Station was conducted during 1984 in accordance with the SGS Environmental Technical Specifications. The objectives of the program were met during this period. The data collected assists in demonstrating that SGS Units One and Two were operated in compliance with Environmental Technical Specifications. From the results obtained, it can be concluded that the levels and fluctuations of radioactivity in environmental samples were as expected for an estuarine environment. Ambient radiation levels were relatively low, averaging about 6.0 mrad/std. month. Except for the Co-58 and co-60 seen in one sediment/benthic organism sample which did not appear in subsequent analyses of any of the estuarine samples, no unusual radiological character-istics were observed in the environs of Artifical Island. The operation of SGS Units #1 and #2 had no significant effect on the radiological characteristics of the environs of Artifical Island. 29
REFERENCES [l] Radiation Management Corporation. "Salem Nuclear Generating Station - Radiological Environmental Monitoring Program - 1973". RMC-TR-74-09, 1974. [2] Radiation Management Corporation. "Artificial Island Radiological Environmental Monitoring Program - 1974 Annual Report". RMC-TR-75-04, 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-77-0_3, 1978. [SJ 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] Public Service Electric and Gas Company. "Environmental Report, Operating License Stage - Salem Nuclear Generating Station Units 1 and 2". 1971. 30
REFERENCES (cont'd.) [14] United States Atomic Energy Commission. "Final Environmental Statement - Salem Nuclear Generating Station, Units 1 and 2". Docket No. 50-272 and 50-311, 1973. [15] Public Service Electric and Gas Company. "Updated Final Safety Analysis Report - Salem Nuclear Generating Station, Units 1 and 2". 1982. [16] Public Service Electric and Gas Company. "Environmental Technical Specifications - Salem Nuclear Generating Station Units 1 and 2", Appendix B to Operating License DPR-70, 1976 (through Amendment 58). [17] Public Service Electric and Gas Company. "Environmental Technical Specifications - Salem Nuclear Generating Station Unit 2", Appendix B to Facility Operating License No. DPR-75, 1981 (through Amendment 27). [18] U. S. Environmental Protection Agency. "Prescribed Procedures for Measurement of Radioactivity in Drinking Water." EPA-600/4-80-032, August, 1980. [19] PSE&G Research Corporation, Research and Testing Laboratory. "Environ-mental Division Quality Assurance Manual." September, 1980. [20] PSE&G Research Corporation, Research and Testing Laboratory. "Environ-mental Division Procedures Manual." February, 1981. ~. [21] Public Service Electric and Gas Company. "Radioactive Effluent Release Report, RERR Salem G~nerating Station, Units 1 and 2". 1984. 31
APPENDIX A PROGRAM
SUMMARY
33
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALFJI NUCLEAR GENERATING STATION DOCKET NO. 50-272/-311 SALEM COUNTY, NEW JERSEY JANUARY 1, 1984 to DECEMBER 31, 1984 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION(S) NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Air Particulates Alpha <124 0.6 2.0 (315/371) 16El 4.1 mi NNW 2.2 (50/53) 2.0 (51/53) 0 110- 3 pCi/m 3 ) (0. 7-4. 7) (0. 8-4. 7) (0. 8-3. 71 Beta 424 3.0*** 24 (371/371) l6El 4.1 mi NNW 26 (53/53) 24 (53/53) 0 (10-44) (12-43) (6. 0-41) Sr-89 32 0.2 <LLD 3H3 110 mi NE 1.1 (1/4) 1.1 (1/4) 0 (1.11 (1.1) Sr-90 32 0.1 <LLD <LLD <LLD 0 Gamma Be-7 32 64 (28/28) 5Dl 3.5 mi E 73 (4/4) 60 (4/41 0 (52-79) (63-79) (52-69)
.Cr-51 28 1.9 2.0 (1/24) 2S2 0.4 mi NNE 2.0 (1/4) <LLD 0 (2.0) (2.0) w Mn-Soil 32 0.1 o. 7 (1/28) 16El 4.1 mi NNW 0.7 (1/4) <LLD 0 U1 (0.7) (0. 7)
Co-58 32 '0.2 0.3 (1/28) 2S2 0.4 mi NNE 0.3 11/4) <LLD 0 (0.3) (0.3) Fe-59 32 0.3 1.0 (l/28) 5Sl 1.0 mi E 1.0 (1/4) <LLD 0 (1.0) (1.0) Te-129m 28 2.5 15 (l/24) 5Sl 1.0 mi E 15 (l/41 <LLD 0 (15) (15) Ra-226 32 0.4 o. 9 (1/28) 16El 4.1 mi NNW 0.9 (1/4) <LLD 0 (0.9) (0.9) Th-232 28 1.0 1.4 (2/24) 16El 4.1 mi NNW 1.6 (1/4) <LLD 0 (l.3-1. 6) (1.6) Air Iodine 1-131 424 4.1 <LLD <LLD <LLD 0 uo-3 pCi/m3)
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272/-311 SALEM COUNTY, NEW JERSEY JANUARY 1, 1984 to DECEMBER 31, 1984 ANALYSIS AND LOWER NUMBER OF TOTAL NUMBER LIMIT OF ' ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION{SI NONROUTINE MEDIUM OR PATHWAY SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Precipitation Alpha 12 0.8 1.5 14/12) 2F2 8. 7 mi NNE 1.5 (4/12) No Control 0 (pCi/L) (0.8-2.4) (0.8-2.4) Location Beta 12 2.7 2.8 (11/121 2F2 B.7 mi NNE 2.8 111/121 No Control 0 (l.0-4.0) (l.0-4.0) Location H-3 12 130 143 13/12) 2F2 8.7 mi NNE 143 13/12) No Control 0 (140-150) (140-150) Location Sr-89 4 o.s <LLD <LLD No Control 0 Location sr-90 4 0.4 <LLD <LLD No Control 0 Location Gamma Be-7 4 34 14/4) 2F2 8.7 mi NNE 34 (4/41 No Control 0 (25-39) (25-39) Location w Ra-226 4 1.3 5.6 11/4) 2F2 8.7 mi NNE 5.6 (1/4) No Control 0 O'I (5.6) (5.6) Location Th-232 4 2.2 7.8 11/41 2F2 B.7 mi NNE 7.8 11/4) No Control 0 (7.8) (7.8) Location Direct Radiation Gamma 287 (mrad/std. month) Dose (monthly) 5.9 (251/251) llSl O. 09 mi SW 6.8 (12/12) 6.4 (36/36) 0 (3.5-11.31 (4. 7-11.3) (5.2-8.5) Gamma 163 Dose (qtrly.) 5. 5 (139/139) 1G3 19 mi N 6. 7 (4/4) 6.1 (24/24) 0 (3.5-8.7) (6.0-7.2) (5.0-7.2)
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272/-311 SALEH COUNTY, NEW JERSEY JANUARY 1, 1984 to DECEMBER 31, 1984 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION!S! NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Milk I-131 144 0.1 <LLD <LLD <LLD 0 (pCi/L) Sr-89 72 0.8 <LLD <LLD <LLD 0 Sr-90 72 2.4 (60/60) 5F2 7.0 mi E 3.8 (12/121 3.2 (12/12) 0 (l.2-5.3) (1. 8-5. 31 (2.2-4.9) Gamma Na-22 72 0.5 <LLD 3Gl 17 mi NE 2.1 (1/12) 2.1 (1/12) 0 (2.1) (2.1) K-o<<O 72 1347 (60/60) 2F4 6.3 mi NNE 1383 (12/121 1350 (12/12) 0 (1200-1500) (1300-14001 (1300-1500) Mn-54 72 0.8 2.4 (1/60) 14Fl 5.5 mi WNW 2.4 (1/12) <LLD 0 (2.4) (2.4) w Cs-137 72. 1.3 3.1 (11/60) 5F2 7.0 mi E 3.4 (8/12) <LLD 0 ......J (1. 8-6. 2) (1. 8-6. 21 La-140 72 0.6 2.4 (1/60) 5F2 7.0 mi E 2.4 (1/12) <LLD 0 (2.41 (2.41 Ra-226 72 2.5 5.8 (3/60) 15Fl 5.4 mi NW 6.5 (1/12) <LLD 0 (5.1-6. 5) (6. 5)
'1'11-232 72 3.6 13 (1/60) 5F2 7.0 mi E 13 (1/12) <LLD 0 (13) (13)
Well Water Alpha 36 0.6 1.4 (6/24) 2S3 700 ft NNE 1.5 (4/12) <LLD 0 (pCi/L) (0. 9-2.0) (1.1-2.0) Beta 36 1.0**" 10 (24/241 5Dl 3.5 mi E 13 (12/12) 8.4 (12/121 0 (2.9-17) (12-14) (6.0-10) K-40 36 11 (24/24) 5Dl 3.5 mi E 14 (12/12) 8.4 (12/121 0 (2.8-28) (6.4-28) (5.5-9.3) H-3 36 130 <LLD <LLD <LLD 0 Sr-89 12 0.4. 0.9 (1/8) 2S3 700 ft NNE 0.9 (1/81 <LLD 0 (0.9) (0.9) Sr-90 12 0.4 <LLD <LLD <LLD 0 Gamma K-40 12 8.4 12 (6/8) 5Dl 3. 5 mi E 13 (3/41 6.3 (1/41 0 (11-141 (12-141 (6.3) Ra-226 12 0.7 1.3 (3/01 2S3 700 ft NNE 2.1 (1/41 1.3 (1/4) 0 (0.6-2.1) (2.11 (1.3)
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM NUCLEAR GENERATING STATION, DOCKET NO. 50-272/-311 SALF.H COUNTY, NEW JERSEY JANUARY 1, 1984 to DECEMBER 31, 1984 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST HEAN CONTROL LOCATION(S! NONROUTINE SAMPLED OF ANALYSES DETECTION HEAN** NAME HEAN HEAN REPORTED (UNIT OF ,MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Potable Water Alpha 24 0.9 2.0 (10/24) 2F3 8.0 mi NNE 2.0 (10/24) No Control 0 Raw-Treated (l.0-4.5) (1.0-4.5) Location (pCi/L) Beta 24 1.0* 1" ' 2. 5 (24/24) 2F3 8.0 mi NNE 2. 5 (24/24) No Control 0 (1.5-3,8) (1. 5-3. 8) Location K-40 2~ 1. 5 (24/24) 2F3 e.o mi NNE 1. 5 (24/24) No Control 0 (1.1-2.0) (1.1-2.0) Location 111-3 24 120 172 (4/24) 2F3 8.0 mi NNE 172 (4/24) No Control 0 (140-250) (140-250) Location Sr-89 8 0.4 <LLD <LLD No Control 0 Location Sr-90 8 0.3 0.3 '(1/8) 2F3 8.0 mi NNE 0.3 (1/8) No Control 0 (0.3) (0.3) Location Ganuna w K-40 8 5.9 7.4 (1/8) 2F3 8.0 mi NNE 7.4 (1/8) No Control 0 CX> (7.41 (7.4) Location Fruit ' Vegetables Sr-89 17 2.8 <LLD <LLD <LLD 0 (pCi/kg-wet) sr-90 17 1.8 15 (4/10) 4Fl 5.1 mi ENE 32 (1/2) 6.9 (4/7) 0 (2. 7-32) (32) (1.8-12) Gamma K-40 17 2140 (10/10) 4Fl 5.1 mi ENE 2300 (2/2) 2114 (7/7) 0 (1700-2700) (1900-2700) (1700-30001 14F3 5.4 mi WNW 2300 (2/2) (2000-26001 Ra-226 17 1.0 <LLD 3H5 25 mi NE 49 (1/41 49 (1/7) 0 (491 (491
'ftl-232 17 4.8 16 (1/10) 4Fl 5.1 mi ENE 16 (1/21 <LLD 0 (16) (16)
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272/-311 SALEM COUNTY, NEW JERSEY JANUARY 1, 1984 to DECEMBER 31, 1984 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER' LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION{S! NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Game Sr-89 2 100 <LLD <LLD <LLD 0 (pCi/kg-dry) (bones) Sr-90 2 810 (1/1) 3El 4.1 mi NE 810 (1/11 290 (1/11 0 (bones) (810) (810) (2901 (pCi/kg-wet) Gamma (flesh) K-40 2 3000 (1/11 3El 4 .1 mi NE 3000 (1/11 2400 (1/1) 0 (30001 (30001 (24001 Cs-137 2 7.7 <LLD llDl 3. 5 mi SW 5.6 (1/11 5. 6 (1/11 0 (5. 61 (5.6) (J.J, Beef Gamma "° (pCi/kg-wetl K-40 1 2500 (1/11 (25001 3El 4.1 mi NE 2500 (1/11 (25001 No Control Location 0 Ra-226 1 9. 3 (1/1) 3El 4.1 mi NE 9.3 (1/11 No Control 0 (9.3) (9.3) Location Bovine Thyroid Gamma (pCi/kg-wet) K-40 1 1200 (1/1) 3El 4.1 mi NE 1200 (1/11 No Control 0 (12001 (1200) Location Fodder Crops Gamma (pCi/kg-wet) Be-7 10 130 527 (6/81 15Fl 5.4 mi NW 830 (2/31 260 (1/21 0 (260-14001 (260-1400) (2601 K-40 10 6287 (8/81 3El 4.1 mi NE 13000 (1/11 8350 (2/21 0 (2000-130001 (13000) (2700-14000) Ra-226 10 14 41 (1/81 15Fl 5.4 mi NW 41 (1/3) <LLD 0 (41) (41) Th-232 10 27 95 (1/8) 15Fl 5.4 mi NW 95 (1/3) <LLD 0 (95) (95)
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272/-311 SALEM COUNTY, NEW JERSEY JANUARY 1, 1984 to DECEMBER 31, 1984 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION!S! NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERPORMED (LLD)" I RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Surface Water Alpha 55 1.3 3.1 (11/441 12Cl 2.5 mi WSW 5.2 15/11) 5.2 15/11) 0 (pCi/L) 11.6-5. 2) (3.4-7.0) (3.4-7. 0) Beta 55 3.0 41 (43/44) 7El 4.5 mi SE 57 111/11) 37 (11/11) 0 (3.2-140) (8. 3-140) (4.3-88) H-3 55 120 16.Q (9/44) 1F2 7,1 mi N 197 13/11) 135 (2/11) 0 (130-250) (150-250) (130-140) Sr-89 20 0.5 1.3 (l/16) 16Fl 6.9 mi NNW l. 3 11/4) <LLD 0 (1,3) 11.3) Sr-90 20 0.4 <LLD <LLD <LLD 0 Gamma K-40 55 6.7 61 (34/44) 7El 4.5 mi SE 74 (10/11) 60 (7/11) 0 (9. 7-140) (20-140) (16-110) ~ Mn-54 55 0.3 0,7 (l/44) llAl 0.2 mi SW o. 7 (l/11) <LLD 0 0 (0. 7) I0.7) Co-60 55 0.2 0.6 (l/44) ,7El 4.5 mi SE 0.6 (l/11) <LLD 0 (0,6) (0.6) C!!-137 55 0.3 <LLD 12Cl 2.5 mi WSW o. 5 (l/11) 0,5 (l/11) *o (0.5) (0.5) La-140 55 0.3 1.2 (l/44) llAl 0.2 mi SW 1.2 (l/11) <LLD 0 (1.2) 11.2) Ra-226 55 0.5 1.0 (6/44) 7El 4.5 mi SE 1.2 (2/11) 1.2 (2/11) 0 (0. 6-1.5) (0. 9-1. 5) (l.0-1.3)
*llAl 0.2 mi SW 1.2 (l/11) 11.21 Th-232 55 1.3 !. 7 15/44) lF2 7.1 mi N 2.0 (2/11) 1.6 (2/11) 0 (0.9-2.1) (2.0-2.1) (l.2-1.9)
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272/-311 SALEM COUNTY, NEW JERSEY JANUARY 1, 1984 to DECEMBER 31, 1984 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION(S! - NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS F.dible Fish Sr-89 6 41 <LLD <LLD <LLD 0 (pCi/kg-dry) (bones) Sr-90 6 38 334 (3/41 12Cl 2.5 mi WSW 615 (1/2) 615 (1/21 0 (bones) (62-730) (230-1000) (230-1000) (pCi/kg-wet) H-3 6 50 400 (2/41 7El 4.5 mi SE 400 (1/2) 300 (1/2) 0 (aqueous) (400-400) (400) (300) llAl 0.2 mi SW 400 (1/2) (400) H-3 6 50 <LLD 12Cl 2.5 mi WSW 120 (1/21 120 (1/2) 0 (organic) (120) (120) Gamma K-40 6 2600 (4/4) 7El 4.5 mi SE 3300 (2/2) 1900 (2/2) 0 .i:.. (1200-3300) (3300-3300) (1400-2400) I-' Cs-137 6 6.2 16 (1/4) llAl 0.2 mi SW 16 (1/2) <LLD 0 (16) (16) Blue Crabs Sr-89 ~ 88 <LLD <LLD <LLD 0 (pCi/kg-dry) (shells) Sr-90 4 600 (2/2) 12Cl 2.5 mi WSW 625 (2/2) 625 (2/21 0 (shells) cseo-6201 (390-860) (390-860) (pCi/kg-wet) H-3 4 50 600 (1/2) llAl 0.2 mi SW 600 (1/2) 300 (1/2) 0 (flesh) (600) (600) (300) Sr-89 4 46 <LLD <LLD <LLD (flesh) Sr-90 26 <LLD <LLD <LLD 0 (flesh) "' Gamma K-40 4 2200 (2/21 llAl 0.2 mi SW 2200 (2/2) 1950 (2/21 0 (2100-2300) (2100-2300) (1900-2000) C0-60 4 16 24 (1/2) llAl 0.2 mi SW 24 (1/2) <LLD 0 (24) (24)
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272/-311 SALEM COUNTY, NEW JERSEY JANUARY 1, 1984 to DECEMBER 31, 1984 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION{S! NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLDJ6 (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS
*Benthic Organisms Sr-89 8 2600 <LLD - <LLD <LLD 0 (pCi/kg-dry)
Sr-90 8 1800 <LLD - <LLD <LLD 0 Gamma Ra-226 8 24000 23000 (1/6) llAl 0.2 mi SW 23000 (1/2) <LLD 0 (230001 (23000) Sediment Sr-90 8 19 <LLD - <LLD <LLD 0 (pCi/kg-dry) Gamma .i:.. "-l Be-7 8 140 877 (3/6) llAl O. 2 mi SW 1300 (1/2) <LLD (330-1300) (1300) K-40 8 - 11783 (6/6) (4700-15000) l6Fl 6.9 mi NNW 15000 (2/2) (15000-15000) 13000 (2/2) (12000-14000) 0 Mn-5~ 8 17 47 (3/6) llAl O. 2 mi SW 87 (1/2) 25 (l/2) 0 (22-87) (87) (25) Co-58 8 22 158 (3/61 llAl 0.2 mi SW 186 (2/2) <LLD l (73-3001 (73-300) Co-60 8 32 184 (6/61 llAl O. 2 mi SW 350 (2/2) 40 (1/2) (22-5201 (180-520) (401 Cs-137 8 20 108 (5/6) llAl 0.2 mi SW 180 (1/2) 26 (2/2) 0 (26-180) (180) (19-321 Ra-226 8 - 883 (6/61 (430-13001 7El 4.5 mi SE 1140 (2/2) (980-1300) 995 (2/21 (790-1200) 0 Th-232 8 - 742 (6/61 16Fl 6.9 mi NNW 930 (2/2) 845 (2/2) 0 (340-980) (900-960) (770-920)
- LLD listed is the lowest calculated LLD during the reporting period.
** Mean calculated using values above LLD only. Fraction of measurements above LLD are in parentheses.
**o Typical LLD value.
APPENDIX B SAMPLE DESIGNATION AND LOCATIONS 43
APPENDIX B Sample Designation The PSE&G Research Corporation identifies samples by a three part code. The first two letters are the power station identification code, in this case "SA". The next three letters are for the media sampled. AIO = Air Iodine GAM = Game APT = Air Particulates IDM = Immersion Dose (TLD) ECH = Hard Shell Blue.Crab MLK = Milk ESB = Benthic Organisms PWR = Potable Water (Raw) ESF = Edible Fish PWT = Potable Water (Treated) ESS = Sediment RWA = Rain Water FPB = Beef SWA = Surface Water FPV = Food Products, Various THB = Bovine Thyroid FPG = Grains VGT = Fodder Crops; Vegetation FPL = Green Leafy Vegetables WWA = Well Water The last four symbols are a location code based on direction and distance from the site. Of these, the first two represent each of the sixteen angular sectors of 22.5 degrees centered about the reactor site. Sector.one is divided evenly by the north axis and other sectors are numbered in a clock-wise direction; i..e., 2=NNE, 3=NE, 4=ENE, etc. The next digit is a letter which represents the radial distance from the plant: s = On-site location E = 4-5 miles off-site A = 0-1 miles off-site F = 5-10 miles off-site B = 1-2 miles off-site G = 10-20 miles off-site c = 2-3 miles off-site H = >20 miles off-site D = 3-4 miles off-site The last number is the station numerical designation within each sector and zone; e.g., 1,2,3, *** For example, the designation SA-WWA-5Dl woµld 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). The number 1 indicates that this is sampling station tl in that particular sector.
45
Sampling Locations All 1984 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 5Sl 1.0 mi. E of vent; site access road AIO,APT,IDM 6S2 0.2 mi. ESE of vent; observation bldg. IDM 7Sl 0.12 mi. SE of vent; station personnel gate IDM lOSl 0.14 mi. SSW of vent; site shoreline IDM llSl- 0.09 mi. SW of vent; site shoreline IDM llAl 0.2 mi. SW of vent; outfall area ECH,ESB,ESF, ESS,SWA l2Cl 2.5 mi. WSW of vent; west bank of Delaware River ECH,ESB,ESF, ESS,SWA 4D2 3. 7 mi. ENE of vent; Alloway c'reek Neck Road IDM 5Dl 3.5 mi. E of vent; local farm AIO,APT,FPV, IDM,WWA lODl 3.9 mi. SSW of vent; Taylor's Bridge Spur AIO,APT,IDM llDl 3.5 mi. SW of vent GAM l4Dl 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,FPG,GAM,IDM, THB,WWA 7El 4.5 mi. SE of vent; l mi. W of Mad Horse Creek ESB,ESF,ESS,SWA 9El 4.2 mi. s of vent IDM 11E2 5.0 mi. SW of vent IDM 46
TABLE B-1 (cont'd) STATION CODE STATION LOCATION SAMPLE TYPES 12El 4.4 mi. WSW of vent; Thomas Landing IDM 13El 4.2 mi. W of vent; Diehl House Lab IDM 13E3 4.9 mi. w of vent; local farm MLK 16El 4.1 mi. NNW of vent; Port Penn AIO,APT,IDM
!Fl 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 2F5 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 4Fl 5.1 mi. ENE of vent; local farm FPL,FPV SF! 6.5 mi. E of vent FPV,IDM 5F2 7.0 mi. E of vent; local farm MLK,VGT 6Fl 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 llFl 6.2 mi. SW of vent; Taylor 1 s Bridge Delawa.re IDM 12Fl 9.4 mi. WSW of vent; Townsend Elementary School IDM 13Fl 9.8 mi. W of vent; Middletown, Delaware IDM 13F2 6.5 mi. W of vent; Odessa, Delaware IDM 47
TABLE B-1 (cont'd) STATION CODE STATION LOCATION SAMPLE TYPES 13F3 9.3 mi. W of vent; Redding Middle School, IDM Middletown, DE 13F4 9.8 mi. W of vent; Middletown, Delaware IDM 14Fl 5.5 mi. WNW of vent; local farm MLK,VGT 14F2 6.6 mi. WNW of vent; Boyds Corner IDM 14F3 5.4 mi. WNW of vent; local farm FPV 15Fl 5.4 mi. NW of vent; local farm FPG,MLK,VGT 15F3 5.4 mi. NW of vent IDM 16Fl 6.9 mi. NNW of vent; C&D Canal ESB,ESS,SWA 16F2 8.1 mi. NNW of vent; Delaware City Public School IDM lGl 10.3 mi. N of*vent; local farm FPV lG3 19 mi. N of vent; Wilmington, Delaware IDM 3Gl l 7*mi. NE of vent; local farm FPG,IDM,MLK,VGT lOGl 12 mi. SSW of vent; Smyrna, Delaware IDM l6Gl 15 mi. NNW of vent; Greater Wilmington Airport IDM 3Hl 32 mi. NE of vent; National Park, N.J. IDM 3H3 110 mi. NE of vent; Research and Testing AIO,APT,IDM Laboratory 3H5 25 mi. NE of vent; local farm FPL,FPV 48
MAP B-1 ON SITE SAMPLING LOCATIONS ARTIFICIAL 15 LAND 0 SCALI Of IAI LIS 49
'MAP 8-2 OFF-SITE SAMPLING LOCATIONS ARTIFICIAL ISLAND
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11111 \ 50
APPENDIX C 1984 DATA TABLES 51
DATA TABLES Appendix C presents the analytical results of the 1984 Artificial Island Radiologtcal Environmental Monitoring Program for the period of January 1 to December 31, 1984. TABLE OF CONTENTS TABLE NO. TABLE DESCRIPTION PAGE ATMOSPHERIC ENVIRONMENT AIR PARTICULATES C-1 1984 Concentrations of Gross Alpha Emitters ******************** 56 C-2 1984 Concentrations of Gross Beta Emitters *******.************* 58 C-3 1984 Concentrations of Strontium-89 and -90 and Gamma Emitters in Quarterly* Composites...................................... 60 AIR IODINE C-4 1984 Concentrations of Iodine-131 ****************************** 62 DATES C-5 1984 Sampling Dates for Air Samples **************************** 64 PRECIPITATION C-6 1984 Concentrations of Gross Alpha and Gross Beta Emitters and Tritium. Cl 0 0 e 0 Cl 0 0 0 0 0 0 0 0 ID *********** (I *** 0 Cl ** ~ ****** Cl *** Cl **** 0 0
- 69 C-7 1984 Concentrations of Strontium-89 and -90 and Gamma Emitters in Quarterly CompositeSoooooo~ooo*ooeeeo**o****************** 70 DIRECT RADIATION THERMOLUMINESCENT DOSIMETERS C-8 1984 Quarterly TLD Results.a*********************************** 71 C-9 1984 Monthly TLD Results *.*...**..*...*...*****.*.*..*..*****.* 72 53
DATA TABLES (cont'd.) TABLE NO. TABLE DESCRIPTION PAGE TERRESTRIAL ENVIRONMENT MILK c-10 1984 Concentrations of Iodine-131 ****************************** 74 C-11 1984 Concentrations of Strontium-89 and -90 ******************** 75 C-12 1984 Concentrations of Gamma Emitters ************************** 76 C-13 1984 Sampling Dates for Milk Samples *************************** 78 WELL WATER C-14 1984 Concentrations of Gross Alpha and Gross Beta Emitters; Potassium-40 and Tritium **..****** o * * * *
- e * * * * * * * * * * * * * * * * * * *
- 80 C-15 1984 Concentrations of Strontium-89 and -90 and Gamma Emitters in Quarterly Composites .************* o * * * * * * * * * * * * * * * * * * * * * *
- 82 POTABLE WATER C-16 1984 Concentrations of Gross Alpha and Gross Beta Emitters; Potassium-40 and Tritium ..... o * *.***** " * * * * * * * * * * * * * * * *
- o *** o. 83 C-17 1984 Concentrations of Strontium-89 and -90 and Gamma Emitters in Quarterly Composites *** o o o o o o o o o o o o o o o o e o o o o o o o o
- o o o o o e o o o 84 FOOD PRODUCTS C-18 1984 Concentrations of Strontium-89 and -90 and Gamma Emitters in Vegetables 0
- ID Cl
- Cl 0 0 0 G 0 0 0 *. 0 0 0 0 0 0 e 13 0 0 ** 0 ****** D 0 ** 0 **** Cil *** 0 0 85 C-19 1984 Concentrations of Strontium-89 and -90 and Gamma Emitters in Gameu Meat and Bovine Thyroid............................. 86 FODDER CROPS C-20 1984 Concentrations of Gamma Emitters ******************* ******** 87 54
DATA TABLES (cont'd.) TABLE NO. TABLE DESCRIPTION PAGE AQUATIC ENVIRONMENT SURFACE WATER C-21 1984 Concentrations of Gross Alpha Eini tters .................... 88 C-22 1984 Concentrations of Gross Beta Emitters ..................... 89 C-23 1984 Concentrations of Tri ti um ***..*...***.***********.******.. 90 C-24 1984 Concentrations of Strontiurn-89 and -9 0 . . . . . . . . . . . . . . . . . . . . 91 C-25 1984 Concentrations of Gamma Emitters . . . . . . . . . . . . . . . . . . . . . . . . . . 92 EDIBLE FISH C-26 1984 Concentrations of Strontium-89 and -90 and Tritium ******** 94 C-27 1984 Concentrations of Gamma Emitters . . . . . . . . . . . . . . . * . . . . . . . . . . 95 BLUE CRABS C-28 1984 Concentrations of Strontiurn-89 and 90; Gamma Emitters and Tritium...................................................... 96 BENTHIC ORGANISMS C-29 1984 Concentrations of Strontium-89 and -90 and Gamma Emitters 97 SEDIMENT C-30 1984 Concentrations of Strontiurn-90 and Gamma Emitters ********* 98 SPECIAL TABLES LLDs C-31 1984 PSE&G Research Corporation LLDs for Gamma Spectrometry **** 99 55
TABLE C-1 1984 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN AIR PARTICULATES Results in Units of io-3 pCi/m3 +/- 2 sigma STATION NO. MONTH" SA-APT-2S2 SA-APT-5Sl SA-APT-5Dl** SA-APT-lODl SA-APT-16El SA-APT-lFl SA-APT-2F2 SA-APT-3H3 AVERAGE (Control) JANUARY 2.6+/-0.8 1.6+/-0.6 1.2+/-1.0 1.4+/-0.6 1.5+/-0.6 2.0+/-0.7 2. 2+/-0. 8 1.9+/-0.7 1.8+/-0.9 2.8+/-1.0 1.9+/-0.8 <l.0 2.7+/-0.9 2.9+/-0.9 1.5+/-0.9 1. 7+/-1.1 2 .6+/-0.9 2.ltl.4 2 .5+/-0. 9 2.1+/-0.8 <2.0 2.4+/-1.0 2.7+/-1.0 <1.1 <1.4 1.6+/-0.7 2.0+/-1.l 4.0+/-1.0 3.7+/-0.9 2.4+/-1.2 3.4+/-1.0 4.7+/-1.0 3.6+/-1.0 4.3+/-1.0 2.7+/-0.9 3.6+/-1.5 1.6+/-0. 7 1.4+/-0.6 <2.0 1.0+/-0.6 1.6+/-0. 7 1.3+/-0. 7 0.9+/-0.7 1.8+/-0.8 1.4+/-0.8 FEBRUARY 2.1+/-0.8 1.8+/-0. 7 <0.8 1.0+/-0.8 <0.8 1.3+/-0.7 1.4+/-1.1(11 1.2+/-0.6 1.3+/-0.9 2.0+/-0.7 2.1+/-0.6 1.9+/-1.0 1.5+/-0.6 2.7+/-0.9 2.2+/-0.7 2.3+/-0.8 3.1+/-0.8 2.2+/-1.0 1.1+/-0.6 0.8+/-0.6 1.7+/-1.0 1.0+/-0.7 0.9+/-0.6 <l. 0 <l. 0 <0.8 1.0+/-0.6 1.7+/-0.8 1. 3:!:0. 7 l.0+/-0. 9 <0.6 1.3+/-0.7 1.3+/-0.7 1.1+/-0.7 1.8+/-0.7 1. 3+/-0.8 MARCH 1.2+/-0.6 l.3+/-0.6 <l.0 <0.8 1.6+/-0.8 1.1+/-0.6 1.4+/-0.7 2.5+/-1.0 1.4+/-1.0 2.3+/-0.8 2.8+/-0.8 1.6+/-1.2 3.6+/-1.0 3.8+/-1.0 2.3+/-0.9 4.4+/-1.l 3.1+/-0.9 3.0+/-1.8 1.2+/-0. 7 0.9+/-0.6 1.3+/-1.0 <1.0 1.6+/-0.8 1.6+/-0.8 1.1+/-0.8 1.4+/-0. 7 1.3+/-0.5 U1 1.5+/-0.8 1.1+/-0. 7 2.1+/-1.1 1.2+/-0.7 1.6+/-0.8 1.0+/-0.7 1. 7+/-0.8 1.4+/-0.8 1.4+/-0.7 °' APRIL 1.4+/-0.7 1.2+/-0.6 <2.0 <0.7 1.7+/-0.7 1.5+/-0.8 2. 7+/-1.0 0.9+/-0.6 1.5+/-1.3 1.1+/-0.8 1.2+/-0.7 <1.0 <0.9 1.0+/-0.8 1.0+/-0.B 1.5+/-0.9 1.2+/-0.8 1.1 0.4 1.4+/-0.8 1.2+/-0. 7 <1.0 1.5+/-0.9 <l. 2 <l. 0 1.4+/-0.8 1. 7+/-0.8 1. 3 0.5 1.0+/-0.6 1.3+/-0.6 <l. 0 0.7+/-0.5 0. 8+/-0. 6 1.6+/-0. 7 <0.7 1.0+/-0.6 1. 0 0.6 1.6+/-0.9 1. 7:!:0. 7 <1.0 1.8+/-0.9 2.3+/-0.9 1.6+/-0.8 2.0+/-0.9 1.4+/-0.B 1. 7 0.8 MAY 2.9+/-1.3 2.6+/-0.9 <l.0 2.4+/-0.9 2.8 0.9 2.8+/-1.0 2.1+/-0.9 1.4+/-0. 7 2.2 l. 4 2.6+/-1.0 1.6+/-0.7 <0.9 2.4+/-0.8 2.3 0.8 1.3+/-0.7 4.0:1:2,5<1> 2.0+/-0.7 2.1 1. 9 2.4+/-0.B 2.9+/-0.B <l.0 2.5+/-0.9 2.1 0.9 2.0+/-0.8 2.0+/-0.8 1.6+/-0.6 2 .1 1. 2 1.9+/-0. 7 1.9+/-0. 7 0.9+/-0.8 2.5+/-0.8 1.9 0.7 1.5+/-0.8 1.5+/-0.8 2.2+/-0.B l. 8 l. 0 JUNE 1.5 0.8 2.1+/-0.9 <l.0 1.7+/-0.9 l. 2 0.9 1.4+/-0.8 1.8+/-0.9 1.5 0.8 l. 5 0.7 3.6 0.9 2.4+/-0.8 2.1+/-1.1 3.5+/-0.9 3.2 0.8 3.5+/-1.0 4.2+/-1.1 3.3 0.9 3.2 l. 4
- 1. 3 0.8 1.8+/-0.9 1.3+/-1.0 <1.2 2.3 1.1 1.4+/-0.9 1.4+/-0.9 l.4 0.8 l. 5 0.7 2.0 0.8 1.8+/-0. 7 1. 4+/-1. 0 1.6+/-0.8 2.3 0.8 1.0+/-0. 7 <l.0 1. 7 0.7 l. 6 0.9
- 1. 7 0.8 1.9+/-0.8 <1.0 1.2+/-0. 8 2.5 1.0 l. 7+/-0.9 1.9+/-0.9 2.0 l. 0 l. 7 0.9
TABLE C-1 (cont'd) 1984 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN AIR t>ARTICULATES Results in Units of lo-3 pCi/m3 +/- 2 sigma STATION NO. MONTH* SA-APT-2S2 SA-APT-5Sl SA-APT-501** SA-APT-lODl SA-APT-16El SA-APT-lFl SA-APT-2F2 SA-APT-3H3 AVERAGE (Control) JULY 2. 6+/-0.8 1.8+/-0. 7 <2.0 2.0+/-0.8 l.9+/-0.8 2.4+/-0.9 2.6+/-0.9 2.6+/-0.8 2.2+/-0.7
- 3. l+/-O. 9 4.1+/-1.0 l.6+/-1.l 3.4+/-0.9 3.0+/-0. 8 2.7+/-0.8 2.4+/-0.8 2.4+/-0.7 2.8+/-1.5 2.3+/-0. 9 l.6+/-0. 7 <l.0 <l.0 l.3+/-0.8 l.2+/-0.9 l.7+/-0;9 2.0+/-0.8 1.5+/-0.9
<l. l <l.l <l.0 <l.2 l.6+/-l.O <l. 3 l.6+/-1.0 l.0+/-0. 7 AUGUST 2.5+/-0.9 l.4+/-0. 7 l.3+/-1.l l.3+/-0.9 2.0+/-0.9 2.2+/-1.0 1.5+/-0.8 2.8+/-0.9 l. 9+/-1. 2 3.2+/-1.0 2.6+/-0.9 2.1+/-1.2 2.1+/-0.8 2.9+/-1.0 2.5+/-1.0 2.6+/-1.0 2.7+/-0.9 2.6+/-0.7 l.9+/-0. 7 3.3+/-0.9 <0.8 l.9+/-0.9 3.0+/-1.0 2.7+/-1.0 2. 6+/-1.0 2.2+/-0.7 2.3+/-1.6 l.5+/-0.6 l.9+/-0. 7 <l.0 2.0+/-0.8 2 .O:tO. 7 1.5+/-0.7 1. 6:!:0. 7 2.1+/-0.8 1.7+/-0.7 SEPTEMBER 3.3+/-0.9 2.3+/-0.7 2.0+/-1.3 2.8+/-0.9 3.1+/-0.9 2.5+/-0.8 2.0+/-0.8 2.9+/-0.8 2.6+/-1.0 1.5+/-0.8 <0.6 <2.0 0 .9+/-0.6 1.3+/-0. 7 0 .9:!:0. 6 1.4+/-0.8 0.8+/-0.6 1.2+/-0.9 l.6+/-0.6 1.2+/-0.6 <2.0 1.8+/-0. 8 1.3+/-0.6 1.7+/-0.7 1.8+/-0.8 1.3+/-0.6 1.6+/-0.6 1.4+/-0.6 l. 7+/-0. 7 <1.0 2.2+/-0.8 l.8+/-0.7 l.2:!:0.6 l.4+/-0.6 l.9+/-0.8 1.6+/-0.8 U1 1.0+/-0.8 <0.9 l.6+/-1.l <1.0 <l. 0 1.2+/-0.8 l.2+/-0.9 2.0+/-0.8 1.2+/-0.8
-...] OCTOBER 2.4+/-0.8 2.5+/-0.8 <l.0 3.2+/-1.0 l.5+/-0.8 2 .2:!:0. 8 2.5+/-0.8 3.4+/-0.9 2.3+/-1.6 3.0+/-1.0 2.6+/-1.0 l.2+/-0.9 3.6+/-1.l 4.2+/-1.3 2.8+/-1.l 2.9+/-1.l 3.1+/-1.0 2.9+/-1.7 2.9+/-1.0 2.9+/-1.0 <l.0 2.5+/-1.0 2.8+/-1.1 2 .9+/-1.0 2.5+/-1.0 3.7+/-1.9(1) 2.6+/-1.5 l.4+/-0.6 l. 7+/-0. 7 2. 7+/-1.2 l.2+/-0.6 1.6+/-0.7 1.0+/-0.6 1.4+/-0.8 l.6+/-0.7 1.6+/-1.0 NOVEMBER l.9+/-0.8 l. 7+/-0.8 l.1+/-0.5 0.9+/-0.7 l.7+/-0.9 l.8+/-0.8 2.2+/-0.9 l.7+/-0.7 1.6+/-0.8 2.2+/-0.7 2.0+/-0.7 l. 8+/-1.0 l.9+/-0. 7 2. 4+/-0. 7 2. 3+/-0. 8 2.4+/-0.8 l.7+/-0.6 2.1+/-0.5 3.1+/-1.l 3.4+/-1.2 1.8+/-1.l 2.3+/-0.9 3.0+/-1.0 l.6+/-0.9 3.6+/-1.2 2.6+/-0. 9 2. 7+/-1.5 2.4+/-0.9 3.0+/-1.l 3.0+/-1.3 3.2+/-1.0 4.3+/-1.1 2.8:!:1.0 2. 4+/-1.0 2.2+/-0.8 2.9+/-1.3 DECEMBER 2.4+/-0.9 2.0+/-0.9 <l.0 1.5+/-0.8 2.0+/-1.0 2.1+/-0.9 2.0+/-0.9 2.8+/-0.9 2.0+/-1.1 1.6+/-0. 7 2.4+/-0.8 2.0+/-1.l 2.3+/-0.8 3.0+/-0.8 2 .1+/-0. 9 2.0+/-0.9 2.7+/-0.8 2.3+/-0.9 2.2+/-0.8 2.4+/-0.8 <l.0 2.0+/-0. 8 2.5+/-0.9 2.6+/-0.9 2.7+/-0.9 1.8+/-0. 7 2.2+/-1.1 1.8+/-0.7 1.3+/-0.6 2.5+/-1.2 1.0+/-0. 7 l. 7+/-0. 7 1.5+/-0.7 l.4+/-0.7 l.3+/-0.6 1.6+/-0.9
<l. l 1.2+/-0.8 <1.0 <1.0 1.6+/-0.8 <l. l <l.0 <1.2 AVERAGE 2.0+/-1.5 l.9+/-1. 5 1.8+/-1.7 2.1+/-1.8 1.8+/-1.4 2.0+/-1.7 2.0+/-1.4 Grand Average l. 9+/-1. 6
- Sampling dates can be found in Table C-5.
** Results by Teledyne Isotopes.
( 1) High uncertainty due to low sample volume.
TABLE C-2 1984 CONCENTRATIONS OF GROSS BETA EMITTERS IN AIR PARTICULATES Results.in Units of lo-3 pCi/m3 +/- 2 sigma STATION NO. MONTH* SA-APT-2S2 SA-APT-5Sl SA-APT-5Dl** SA-APT-lODl SA-APT-16El SA-APT-lFl SA-APT-2F2 SA-APT-3H3 AVERAGE (Control) JANUARY 36+/-3 37+/-3 34+/-4 36:1:3 39 3 36 3 40 4 36+/-3 37 4 35+/-3 35+/-3 30+/-3 30+/-3 31 3 32 3 35 4 32:1:3 32 4 26+/-3 26:!:3 21+/-3 29+/-3 30 3 26 3 27 4 26+/-2 26 5 38+/-3 42+/-3 39+/-4 39+/-3 42 3 40 3 41 3 38+/-3 40 3 25+/-3 24+/-2 21+/-3 23+/-3' 23 3 27 3 24 3 29+/-3 24 5 FEBRUARY 23 2 23+/-2 16 3 22 3 23 3 23 3 27 4 2 4:1: 2 23 6 24 3 22+/-2 21 3 22 2 26 3 24 2 24 3 28+/-2 24 5 15 2 14+/-2 17 3 16 2 16 2 14 2 17 3 .16+/-2 16 2 19 3 19+/-3 21 3 20 3 19 3 19 3 20 3 21+/-3 20 2 MAH CH 18 2 15+/-2 15 3 17 3 14 3 13 2 15 3 11+/-3 15 4 26 3 28+/-3 30 3 29 3 30 3 29 3 29 3 29+/-3 29 2 21 2 19+/-2 18 3 16 2 20 2 21 2 21 3 18+/-2 19 4 U1 17 2 17+/-2 18 3 18 2 19 2 16 2 20 2 14+/-2 17 4 CX> APRIL 13 2 10+/-2 13 3 11 2 13 2 12 2 14 3 6+/-2 12 5 15 2 15+/-2 13 3 15 2 16 2 14 2 14 2 14+/-2 14 2 14 2 12+/-2 13 3 12 2 12 2 13 2 15 2 13+/-2 13 2 13 2 13+/-2 14 2 13 2 13 2 43 3 12 2 14+/-2 17 21 16 3 16+/-2 16 3 19 3 20 3 16 3 18 3 15+/-2 17 4 MAY 24 4 23+/-3 20 3 22 3 24 3 31 3 24 3 22 2 24 6 24 3 19+/-2 21 3 19 2 21 2 17 2 16 7 ( ll 18 2 19 5 23 3 22+/-2 24 3 24 3 24 3 23 3 23 3 19 2 23 3 22 2 22+/-2 19 2 19 2 23 2 21 2 21 2 20 2 21 3 JUNE 15 3 17+/-3 12 3 15 3 14 3 17 3 16 3 11 2 15 4 41 3 41+/-3 35 3 38 3 43 3 42 3 43 3 41 3 40 5 21 3 2l:t2 23 3 17 3 18 3 19 3 20 3 21 2 20 4 22 2 2l:t2 17 3 21 2 24 2 21 3 23 3 19 2 21 4 20 3 19+/-2 19 3 18 3 17 3 17 3 21 3 20 3 19 3
TABLE C-2 (cont'd) 1984 CONCENTRATIONS OF GROSS BETA EMITTERS IN AIR PARTICULATES Results in Units of lo-3 pCi/m3 +/- 2 sigma STATION NO. MONTH* SA-APT-2S2 SA-APT-5Sl SA-APT-501** SA-APT-1001 SA-APT-16El SA-APT-lFl SA-APT-2F2 SA-APT-3H3 AVERAGE (Control) JULY 23+/-3 24+/-2 17+/-3 22+/-3 24+/-3 23+/-3 22+/-3 21+/-3 22+/-4 32+/-3 30+/-3 24+/-3 29+/-3 30+/-3 25+/-3 32+/-3 28+/-3 29+/-6 23+/-3 20+/-2 21+/-3 17+/-3 17+/-2 20+/-3 20+/-3 22+/-2 20+/-4 15+/-2 13+/-2 17+/-3 14+/-2 18+/-3 14:!:3 14+/-3 15+/-2 15 :!:3 AUGUST 21+/- 2 20+/-2 21+/-3 21+/-3 24+/-3 21+/-3 23+/-3 31+/-3 23+/-7 34+/-3 32+/-3 30+/-4 31+/-3 31+/-3 35+/-3 34:!:3 31+/-3 32:!:4 24+/-3 25+/-2 25+/-3 24+/-3 25+/-3 21+/- 3 2 7+/- 3 24+/-2 24+/-3 20+/-2 21+/-2 19+/-3 19+/-3 23+/-2 18+/-2 2 3:!: 3 17+/-2 20+/-4 SEPTEMBER 36+/-3 33+/-3 32+/-3 3 4:!: 3 40+/-3 34+/-3 40+/-4 30+/-2 35+/-7 20+/-3 19+/-3 21+/- 3 19+/-3 22+/-3 17 +/-3 22+/-3 17+/-2 20+/-4 20+/-2 20+/-2 18+/-3 18+/-3 21+/-3 20+/-3 24+/-3 23+/-2 20+/-4 30+/-3 33+/-3 24+/-3 34+/-3 3 7+/- 3 29+/-3 34+/-3 29+/-3 31+/-8 U1 25+/-3 23+/-3 26+/-3 20+/-3 23+/-3 18+/-3 27+/-3 32+/-3 24+/-9 \.0 OCTOBER 27+/-3 27+/-3 23+/-3 26+/-3 30:!:3 28:!:3 23+/-2 24+/-2 26:!:5 31+/-3 34+/-3 33+/-3 34:!:3 37+/-4 34:!:4 37+/-4 34+/-3 34+/-4 33+/-3 29+/-3 31:!:4 33+/-3 35+/-4 31+/-3 35+/-3 32+/-611) 32+/-4 22+/-2 24+/-3 26+/-3 24+/-2 25+/-2 25+/-3 27+/-3 31+/-3 26+/-5 NOVEMBER 27+/-3 28+/-3 26+/-2 25+/-3 33+/-4 25+/-3 28+/-3 23+/-2 27+/-6 21+/-2 26+/-2 25+/-3 21+/-2 23+/-2 23+/-2 27+/-3 23+/-2 24+/-4 32+/-3 31+/-4 28+/-4 26+/-3 32+/-3 32+/-3 30+/-4 30+/-3 30+/-4 25+/-3 33+/-4 27+/-3 25+/-3 29+/-3 23+/-3 24+/-3 21+/-3 26+/-8 DECEMBER 32+/-3 31+/-3 33+/-4 29+/-3 31+/-3 31+/-3 35+/-3 39+/-3 33+/-6 26+/-2 30+/-3 31+/-3 32+/-3 35+/-3 29+/-3 29+/-3 30+/-3 30+/-5 41+/-3 40+/-3 38+/-4 38+/-3 41+/-3 36:!:3 37 +/-3 34+/-3 38:!:5 42+/-3 44+/-3 37+/-4 38+/-3 39+/-3 40+/-3 39+/-3 37+/-3 40:!:5 21+/-3 18+/-2 23+/-3 20+/-2 21+/-2 22+/-3 22+/-3 22+/-3 21+/-3 AVERAGE 25+/-15 24+/-16 23+/-14 24+/-15 26+/-17 24+/-16 26+/-16 24+/-16 Grand Average 24+/-16
- Sampling dates can be found in Table C-5.
** Results by Teledyne Isotopes.
(1) High uncertainty due to low sample volume.
TABLE C-3 1984 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND GAMMA EMITTERS** IN QUARTERLY COMPOSITES OF AIR PARTICULATES Results in Units of io-3 pci/m3 +/- 2 sigma STATION NO, AND DATES Sr-89 sr-90 Be-7 Cr-51 Mn-54 Co-58 Fe-59 Te-129m Ra-226 Th-232 SA-APT-2S2 12-27-83 to 3-26-84 <0.3 <0.2 57+/-4 <2.8 <0.3 <0.4 <0.9 < 4.4 <0.7 <l. 2 3-26-84 to 7-02-84 <0.6 <0.4 73+/-5 2.0tl.3 <0.4 0.3+/-0.2 <0.7 < 4.3 <0.9 <l. l 7-02-84 to 10-01-84 <0.3 <0.2 71+/-5 <2.8 <0.3 <0.4 <0.9 <14 <1.0 <l. 6 10-01-64 to 1-02-65 <0.2 <0.2 62+/-4 <2.5 <0.3 <0.3 <0.6 <12 <0.9 <l. 5 SA-APT-5Sl 12-27-63 to 3-26-64 <0.3 <0.2 52+/-4 <2.5 <0.4 <0.4 <0.6 15+/-10 <1.0 <l. 6 3-26-64 to 7-02-64 <0.4 <0.3 69+/-5 <3.9 <0. 3 <0.5 <0.9 <15 <1.1 <2.5 7-02-64 to 10-01-64 <0.3 <0.2 64+/-5 <3.7 <0.3 <0.5 1.0+/-0.6 < 3.7 <l. l 1.3+/-0.8 0\ 0 10-01-64 to 1-02-65 <0.2 <0.2 65+/-5 <3.9 <0.4 <0.5 <0.9 <17 <1.0 <l. 5 SA-APT-5Dl * "* 12-27-63 to 3-26-64 <1.0 <0.2 73+/-9 ( 1) <0.4 <0.6 <2.0 ( 1) <9.0 ( 1) 3-26-64 to 7-02-64 <2.0 <0.2 76+/-5 (1) <0.3 <0.3 <0.8 (1) <5.0 ( 1) 7-02-64 to 10-01-64 <2.0 <0.4 79+/-8 ( l) <0.4 <0.4 <l.0 ( 1) <7.0 ( 1) 10-01-64 to 1-02-65 <0. 1. <0.1 63+/-11 ( l) <0.6 <l. 0 (2.0 ( 1) <10 ( 1) SA-APT-10Dl 12-27-63 to 3-27-64 <0.4 <0.3 55+/-5 <3.2 <0.3 <0.2 <0.9 <17 <1.1 <l. 9 3-27-64 to 7-03-64 <0.6 <0.6 64+/-5 <2.2 <0.5 <0.4 <1.0 <11 <0.9 <2.0 7-03-64 to 10-02-64 <0.3 <0.2 63+/-5 <2.6 <0.3 <0.4 <0.3 <11 <1.0 <l. 4 10-02-64 to 1-03-65 <0.2 <0.2 54+/-5 <2.6 <0.4 <0.4 <0.9 <16 <1.1 <l. 9
-~~~~~--------------------------------- ........................
TABLE C-3 (cont'd) 1984 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 Cr-51 Mn-54 Co-58 Fe-59 Te-129m *Ra-226 Th-232 SA-APT-16El 12-27-83 to 3-27-84 <0.4 <0.3 56+/-5 <3.7 0.7+/-0.3 <0.5 <l. 0 <16 <l.0 <l. 5 3-27-84 to 7-03-84 <0.4 <0.3 66:!:5 <l.9 <0.3 <0.4 <l. l < 6.3 <l.0 <l. 6 7-03-84 to 10-02-84 <0.3 <0.2 63+/-5 <2.5 <0.5 <0.2 <l.0 < 4.8 <l. 2 <l. 8 10-02-84 to 1-03-85 <0.2 <0.2 65:!:5 <2.9 <0.4 <0.6 <0.6 <15 0.9+/-0.5 1.6+/-1.0 SA-APT-lFl 12-27-83 to 3-26-84 <0.3 <0.2 5 5 :!:4 <3.0 <0.4 <0.4 <0.7 < 3.2 <l.0 <l. 3 3-26-84 to 7-02-84 <0.3 <0.2 60:!:5 <4.6 <0.1 <0.4 <l.0 < 6.9 <l.0 <l. 9 7-02-84 to 10-01-84 <0.3 <0.2 65+/-6 <3.7 <0.3 <0.6 <0.8 <11 <l.0 <l. 9 0\ ~ 10-01-84 to 1-02-85 <0.2 <0.2 58+/-4 <2.6 <0.3 <0.4 <0.7 <13 <l.0 <l. 2 SA-APT-2F2 12-27-83 to 3-26-84 <0.4 <0.3 56+/-5 <2.7 <0.5 <0.3 <l. 0 <17 <l.0 <l. 8 3-26-84 to 7-02-84 <0.4 <0.3 73+/-5 <4.5 <0.5 <0.4 <l.0 < 4.8 <0.4 <l. 7 7-02-84 to 10-01-84 <0.3 <0.3 72+/-5 <4.7 <0.4 <0.4 <0.8 <15 <l.l <l. 7 10-01-84 to 1-02-85 <0.3 <0.2 60+/-5 <2.8 <0.4 <0.4 <0.7 <18 <l. 0 <l. 6 SA-APT-3H3 (Control) 12-27-83 to 3-26-84 <0.3 <0.2 57+/-5 <2.1 <0.4 <0.4 <0.8 <15 <0.9 <l. 8 3-26-84 to 7-02-84 1.1+/-0.2 <0.3 62+/-4 <2.4 <0.3 <0.3 <0.8 < 2.5 <0.8 <l. 4 7-02-84 to 10-01-84 <0.3 <0.2 69+/-5 <2.8 <0.3 <0.2 <0.5 <15 <0.8 <l. 4 10-01-84 to 1-02-85 <0.2 <0.2 52+/-3 <2.3 <0.3 <0.3 <0.6 <11 <0.6 <l. 0 AVERAGE 63+/-15
- 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.
*** Results by Teledyne Isotopes.
( 1) Not analyzed by Teledyne Isotopes.
TABLE C-4 1984 CONCENTRATIONS OF IODINE-131" IN FILTERED AIR Results in Units of io-3 pCi/m3 STATION NO. MONTH** SA-AI0-252 SA-AI0-5Sl SA-AI0-501*** SA-AI0-1001 SA-AI0-16 El SA-AIO-lFl SA-AI0-2F2 SA-AI0-3H3 (Control) JANUARY < 9.1 < 6.7 <40 < 6.2 < 7.7 < 6.4 <19 < 6.4
< 9.0 < 5.4 <20 <*7.4 < 7.6 < 9.6 <12 < 5.6
< 8.3 < 7.6 <20 < 9.9 < 8.4 < 9.8 <12 < 4.1
<13 <15 <20 <13 <16 <28 <17 < 7.6
<16 <21 <20 <19 <33 <23 <26 <21 FEBRUARY <17 <13 <10 <22 <17 <15 <38(1) <17
<17 <17 <30 <12 <23 <17 <21 <15
<17 <19 <20 <23 <18 <17 <25 <16
<21 <17 <10 <18 <26 <24 <26 <19 MARCH <15 <14 <10 <23 <25 <25 <18 <22
<14 <16 <20 <15 <20 <18 <17 <12
<16 <16 <30 <24 <17 <19 <21 <13
<14 < 8.9 <20 <18 <13 <13 <14 <18
°' "' APRIL <17
<16
<16
<20
<50
<30
<27
<18
<24
<21
<25
<26
<21
<19
< 7.1
<12
<14 < 5.0 <20 <19 <21 <16 <20 <13
<22 <16 <10 <15 < 6.7 <17 <15 < 5.7
<20 <17 <10 < 7.9 <17 <15 <25 <14 MAY <20 <10 <20 < 7.8 <19 <20 <18 <14
<21 < 6.1 <20 <14 <17 <20 <110 (l) <13
<17 <13 <30 <20 <25 <13 <20 <19
<11 < 8.2 <10 <13 < 9.3 <18 <16 < 5.4 JUNE <19 <21 <20 <23 <32 <19 <24 <16
<15 <12 <20 <16 <18 <27 <15 <13
<18 <12 <20 <17 <21 <19 <14 <10
< 6.5 <13 <20 < 7. !? <14 <11 <24 <16
<15 <11 <40 < 8.7 <20 <19 <19 <15
TABLE C-4 (cont'd) 1984 CONCENTRATIONS OF IODINE-131* IN FILTERED AIR Results in Units of lo-3 pCi/m3 STATION NO. MONTH . . SA-AI0-2S2 SA-AI0-5Sl SA-AI0-5Dl*** SA-AIO-lODl SA-AI0-16El SA-AIO-lFl SA-AI0-2F2 SA-AI0-3H3 (Control) JULY <17 <18 <40 <24 <16 <26 <26 <20
<19 <23 <20 <23 <18 <13 < 8.2 <15
<20 <19 <10 <14 <16 < 9.1 <15 <15
<11 <is <50 < 8.0 <31 <27 <17 <21 AUGUST <12 <16 <30 <18 <20 <19 <23 <16
<16 < 6.7 <20 <17 <14 <12 <15 <17
<17 <12 <10 <20 <21 <20 <19 < 6.1
<12 <16 <20 <14 <18 <15 <13 <16 SEPTEMBER <17 <18 < 8.0 <20 <17 <12 <13 <15
<18 <20 <10 <15 <12 < 9.3 <28 <18
<15 <18 <10 <24 <21 <19 <20 <13
<15 < 8.5 <20 <13 <14 < 5.7 <15 <16 0\ <16 < 9.6 <20 <21 <23 <20 <25 <13 (J.)
OCTOBER <11 <12 <20 <20 <14 < 5.9 < 5.9 <14
<21 <21 <20 < 7.0 <21 <18 <22 < 6.7
<10 <18 <40 <23 <22 <17 <15 <56(1)
<15 <17 <20 <13 <13 <21 <19 <15 NOVEMBER <17 <15 <20 <21 <19 <14 < 7 .4 <14
<17 <17 <20 < 6.2 <15 < 6"6 <17 <14
<22 <24 <40 <20 <19 <18 <24 < 5.7
<15 <16 < 9.0 < 6.7 <14 <17 <10 <18 DECEMBER <19 <26 <10 <19 <20 <18 <16 <14
<14 <21 <20 <20 < 5.3 <23 <13 <12
<16 <15 < 9.0 <14 <16 <26 <21 <12
<11 < 6.3 <30 <16 <15 <21 <12 <14
<22 <19 <30 <10 <14 <14 <13 <15
- I-131 results are corrected for decay to sample stop date.
** sampling dates can be found in Table C-5.
*** Results by Teledyne Isotopes.
(1) High LLD due to low sample volume.
TABLE C-5 1984 SAMPLING DATES FOR AIR SAMPLES STATION NO. MONTH 2S2 5Sl 501 1001 16El !Fl 2F2 3HJ JANUARY 12-27-83 12-27-83 12-27-83 12-27-83 12-27-83 12-27-83 12-27-83 12-27-83 to to to to to to to to 1-03-84 1-03-84 1-03-84 l-03-84 1-03-84 1-03-84 1-03-84 1-03-84 1-03-84 1-03-84 1-03-84 1-03-84 1-03-84 1-03-84 1-03-84 l-03-84 to to to to to to to to 1-09-84 1-09-84 1-09-84 1-10-84 1-10-84 1-09-84 1-09-84 1-09-84 1-09-84 1-09-84 1-09-84 1-10-84 1-10-84 1-09-84 1-09-84 1-09-84 to to to to to to to to 1-16-84 1-16-84 1-16-84 1-16-84 1-16-84 1-16-84 1-16-84 1-16-84 1-16-84 1-16-84 1-16-84 1-16-84 1-16-84 1-16-84 1-16-84 1-16-84 to to to to to to to to 1-23-84 1-23-84 1-23-84 1-24-84 1-24-84 1-23-84 1-23-84 1-23-84 0\ 1-23-84 1-23-84 1-23-84 1-:-24-84 1-24-84 1-23-84 1-23-,84 1-23-84 ~ to to to to to to to to 1-30-84 1-30-84 1-30-84 1-31-84 1-31-84 1-30-84 1-30-84 1-30-84 FEBRUARY 1-30-84 1-30-84 1-30-84 1-31-84 1-31-84 1-30-84 1-30-84 1-30-84 to to to to to to to to 2-06-84 2-06-84 2-06-84 2-06-84 2-06-84 2-06-84 2-03-84* 2-06-84 2-06-84 2-06-84 2-06-84 2-06-84 2-06-84 2-06-84 2-07-84 2-06-84 to to to to to to to to 2-14-84 2-14-84 2-14-84 2-14-84 2-14-84 2-14-84 2-14-84 2-14-84 2-14-84 2-14-84 2-14-84 2-14-84 2-14-84 2-14-84 2-14-84 2-14-84 to to to to to to to to 2-21-84 2-21-84 2-21-84 2-21-84 2-21-84 2-21-84 2-21-84 2-21-84 2-21-84 2-21-84 2-21-84 2-21-84 2-21-84 2-21-84 2-21-84 2-21-84 to to to to to to to to 2-27-84 2-27-84 2-27-84 2-28-84 2-28-84 2-27-84 2-27-84 2-27-84 MARCH 2-27-84 2-27-84 2-27-84 2-28-84 2-28-84 2-27-84 2-27-84 2-27-84 to to to to to to to to 3-05-84 3-05-84 3-05-84 3-05-84 3-05-84 3-05-84 3-05-84 3-05-84 3-05-84 3-05-84 3-05-84 3-05-84 3-05-84 3-05-84 3-05-84 3-05-84 to to to to to to to to 3-12::-84 3-12-84 3-12-84 3-13-84 3-13-84 3-12-84 3-12-84 3-12-84
TABLE C-S (cont'd) 1984 SAMPLING DATES FOR AIR SAMPLES STATION NO. MONTH 2S2 SS! SD! 1001 16El lFl 2F2 3H3 MARCH 3-12-84 3-12-84 3-12-84 3-13-84 3-13-84 3*12-84 3-12-84 3-12-84 to to to to to to to to 3-19-84 3-19-84 3-19-84 3-19-84 3-19-84 3-19-84 3-19-84 3-19-84 3-19-84 3-19-84 3-19-84 3-19-84 3-19-84 3-19-84 3-19-84 3-19-84 to to to to to to to to 3-26-84 3-26-84 3-26-84 3-27-84 3-27-84 3-26-84 3-26-84 3-26-84 APRIL 3-26-84 3-26-84 3-26-84 3-27-84 3-27-84 3-26-84 3-26-84 3-26-84 to to to to to to to to 4-02-84 4-02-84 4-02-84 4-02-84 4-02-84 4-02-84 4-02-84 4-02-84 4-02-84 4-02-84 4-02-84 4-02-84 4-02-84 4-02-84 4-02-84 4-02-84 to to to to to to to to 4-09-84 4-09-84 4-09-84 4-10-84 4-10-84 4-09-84 4-09-84 4-09-84 O\' 4-09-84 4-09-84 4-09-84 4-10-84 4-10-84 4-09-84 4-09-84 4-09-84 U1 to to to to to to to to 4-16-84 4-16-84 4-16-84 4-16-84 4-16-84 4-16-84 4-16-84 4-16-84 4-16-84 4-16-84 4-16-84 4-16-84 4-16-84 4-16-84 4-16-84 4-16-84 to to to to to to to to 4-23-84 4-23-84 4-23-84 4-24-84 4-24-84 4-23-84 4-23-84 4-23-84 4-23-84 4-23-84 4-23-84 4-24-84 4-24-84 4-23-84 4-23-84 4-23-84 to to to to to to to to 4-30-84 4-30-84 4-30-84 4-30-84 4-30-84 4-30-84 4-30-84 4-30-84 MAY 4-30-84 4-30-84 4-30-84 4-30-84 4-30-84 4-30-84 4-30-84 4-30-84 to to to to to to to to S-07-84 S-07-84 S-07-84 S-07-84 S-07-84 5-07-84 S-07-84 5-07-84 S-07-84 S-07-84 S-07-84 S-07-84 S-07-84 S-07-84 S-07-84 5-07-84 to to to to to to to to S-14-84 S-14-84 S-14-84 S-lS-84 S-lS-84 S-14-84 S-10-84* 5-14-84 S-14-84 S-14-84 S-14-84 S-lS-84 5-lS-84 S-14-84 S-14-84 5-14-84 to to to to to to to to S-21-84 S-21-84 S-21-84 S-21-84 5-21-84 S-21-84 S-21-84 5-21-84 S-21-84 S-21-84 S-21-84 S-21-84 S-21-84 S-21-84 S-21-84 5-21-84 to to to to to to to to S-29-84 S-29-84 S-29-84 S-30-84 S-30-84 S-29-84 S-29-84 5-29-84
TABL,E c-5 (cont'd) 1984 SAMPLING DATES FOR AIR SAMPLES STATION- NO. MONTH 2S2 5Sl 5Dl lODl 16El !Fl 2F2 3H3 JUNE 5-29-84 5-29-84 5-29-84 5-30-84 5-30-84 5-29-84 5-29-84 5-29-84 to to to to to
- to to to 6-04-84 6-04-84 6-04-84 6-04-84 6-04-84 6-04-84 6-04-84 6-04-84 6-04-84 6-04-84 6-04-84 6-04-84 6-04-84 6-04-84 6-04-84 6-04-84 to to to to to to to to 6-11-84 6-11-84 6-11-84 6-12-84 6-12-84 6-11-84 6-11-84 6-11-84 6-11-84 6-11-84 6-11-84 6-12-84 6-12-84 6-11-84 6-11-84 6-11-84 to to to to to to to to 6-18-84 6-18-84 6-18-84 6-18-84 6-18-84 6-18-84 6-18-84 6-18-84 6-18-84 6-18-84 6-18-84 6-18-84 6-18-84 6-18-84 6-18-84 6-18-84 to to to to to to to to 6-25-84 6-25-84 6-25-84 6-26-84 6-26-84 6-25-84 6-25-84 6-25-:-84 0\ 6-25-84 6-25-84 6-25-84 6-26-84 6-26-84 6-25-84 6-25-84 6-25-84 0\ to to to to to to to to 7-02-84 7-02-84 7-02-84 7-03-84 7-03-84 7-02-84 7-02-84 7-02-84 JULY 7-02-84 7-02-84 7-02-84 7-03-84 7-03-84 7-02-84 7-02-84 7-02-84 to to to to to to to to 7-09-84 7-09-84 7-09-84 7-09-84 7-09-84 7-09-84 7-09-84 7-09-84 7-09-84 7-09-84 7-09-84 7-09-84 7-09-84 7-09-84 7-09-84 7-09-84 to to to to to to to to 7-16-84 7-16-84 7-16-84 7-17-84 7-17-84 7-16-84 7-16-84 7-16-84 7-16-84 7-16-84 7-16-84 7-17-84 7-17-84 7-16-84 7-16-84 7-16-84 to to to .to to to to to 7-23-84 7-23-84 7-23-84 7-24-84 7-24-84 7-23-84 7-23-84 7-23-84 7-2.3-84 7-23-84 7-23-84 7-24-84 7-24-84 7-23-84 7-23-84 7-23-84 to to to to to to to to 7-30-84 7-30-84 7-30-84 7-31-84 7-31-84 7-30-84 7-30-84 7-30-84 AUGUST 7-30-84 7-30-84 7-30-84 7-31-84 7-31.-84 7-30-84 7-30-84 7-30-84 to to to to to to to to 8-06-84 8-06-84 8-06-84 8-06-84 8-06-84 8-06-84 8-06-84 8-06-84 8-06-84 8-06-84 8-06-84 8-06-84 8-06-84 8-06-84 8-06-84 8-06-84 to to to to to to to to 8-13-84 8-13-84 8-13-84 8-14-84 8-14-84 8-13-84 8-13-84 8-13-84
TABLE C-5 (cont'd) 1'984 SAMPLING DATES FOR AIR SAMPLES STATION NO. MONTH 2S2 5Sl 5Dl lODl 16El lFl 2F2 3H3 AUGUST 8-13-84 8-13-84 8-13-84 8-14-84 8-14-84 8-13-84 8-13-84 8-13-84 to to to to to to to to 8-20-84 8-20-84 8-20-84 8-20-84 8-20-84 8-20-84 8-20-84 8-20-84 8-20-84 8-20-84 8-20-84 8-20-84 8-20-84 8-20-84 8-20-84 8-20-84 to to to _to to to to to 8-28-84 8-28-84 8-28-84 8-29-84 8-29-84 8-28-84 8-28-84 8-27-84 SEPTEMBER 8-28-84 8-28-84 8-28-84 8-29-84 8-29-84 8-28-84 8-28-84 8-27-84 to to to to to to to to 9-04-84 9-04-84 9-04-84 9-04-84 9-04-84 9-04-84 9-04-84 9-04-84 9-04-84 9-04-84 9-04-84 9-04-84 9-04-84 9-04-84 9-04-84 9-04-84 to to to to to to to to 9-10-84 9-10-84 9-10-84 9-11-84 9-11-84 9-10-84 9-10-84 9-10-84 9-10-84 9-:10-84 9-10-84 9-11-84 9-11-84 9-10-84 9-10-84 9-10-84 °' ....J to to to to 9-17-84 to 9-17-84 to 9-17-84 to 9-17-84 to 9-17-84 9-17-84 9-17-84 9-17-84 9-17-84 9-17-84 9-17-84 9-17-84 9-17-84 9-17-84 9-17-84 9-17-84 to to to to to to to to 9-25-84 9-25-84 9-25-8.4 9-26-84 9-26-84 9-25-84 9-25-84 9-24-84 9-25-84 9-25-84 9-25-84 9-26-84 9-26-84 9-25-84 9-25-84 9-24-84 to to to to to to to to 10-01-84 10-01-84 10-01-84 10-02-84 10-02-84 10-01-84 10-01-84 10-01-84 OCTOBER 10-01-84 10-01-84 10-01-84 10-02-84 10-02-84 10-01-84 10-01-84 10-01-84 to to to to to to to to 10-09-84 10-09-84 10-09-84 10-09-84 10-10-84 10-09-84 10-09-84 10-09-84 10-09-84 10-09-84 10-09-84 10-09-84 10-10-84 10-09-84 10-09-84 10-09-84 to to to to to to to to 10-15-84 10-15-84 10-15-84 10-16-84 10-16-84 10-15-84 10-15-84 10-15-84 10-15-84 10-15-84 10-15-84 10-16-84 10-16-84 10-15-84 10-15-84 10-15-84 to to to to to to to to 10-22-84 10-22-84 10-22-84 10-22-84 10-22-84 10-22-84 10-22-84 10-17-84* 10-22-84 10-22-84 10-22-84 10-22-84 10-22-84 10-22-84 10-22-84 10-22-84 to to to to to to to to 10-29-84 10-29-84 10-29-84 10-30-84 10-30-84 10-29-84 l,0-29-84 10-29-84
TABLE C-5 (cont'd) 1984 SAMPLING DATES FOR AIR SAMPLES STATION NO. MONTH 2S2 5Sl 5Dl lODl 16El lFl 2F2 3H3 NOVEMBER 10-29-84 10-29-84 10-29-84 10-30-84 10-30-84 10-29-84 10-29-84 10-29-84 to to to to to to to to 11-05-84 11-05-84 11-05-84 11-05-84 11-05-84 11-05-84 11-05-84 11-05-84 11-05-84 11-05-84 11-05-84 11-05-84 11-05-84 11-05-84 11-05-84 11-05-84 to to to to to to to to 11-13-84 11-13-84 11-13-84 11-13-84 11-13-84 11-13-84 11-13-84 11-13-84 11-13-84 11-13-84 11-13-84 11-13-84 11-13-84 11-13-84 11-13-84 11-13-84 to to to to to to to to 11-19-84 11-19-84 11-19-84 11-20-84 11-20-84 11-19-84 11-19-84 11-19-84 11-19-84 11-19-114 11-19-84 11-20-84 11-20-84 11-19-84 11-19-84 11-19-84 to to to to to to to to 11-26-84 11-26-84 11-26-84 11-27-84 11-27-84 11-26-84 11-26-84 11-26-84 DECEMBER 11-26-84 11-26-84 11-26-84 11-27-84 11-27-84 11-26-84 11-26-84 11-26-84 °' 00 to 12-03-84 to 12-03-84 to 12-03-84 to 12-03-84 to 12-03-84 to 12-03-84 to 12-03-84 to 12-03-84 12-03-84 12-03-84 12-03-84 12-03-84 12-03-84 12-03-84 12-03-84 12-03-84 to to to to to to to to 12-10-84 12-10-84 12-10-84 12-11-84 12-11-84 12-10-84 12-08-84* 12-10-84 12-10-84 12-10-84 12-10-84 12-11-84 12-11-84 12-10-84 12-11-84 12-10-84 to to to to to to to to 12-18-84 12-18-84 12-18-84 12-18-84 12-18-84 12-18-84 12-18-84 12-18-84 12-18-84 12-18-84 12-18-84 12-18-84 12-18-84 12-18-84 12-18-84 12-18-84 to to to to to to to to 12-26-84 12-26-84 12-26-84 12-26-84 12-26-84 12-26-84 12-26-84 12-26-84 12-26-84 12-26-84 12-26-84 12-26-84 12-26-84 12-26-84 12-26-84 12-26-84 to to to to to to to to 1-02-85 1-02-85 1-02-85 1-03-85 1-03-85 1-02-85 1-02-85 1-02-85
- Reduced sampling period due to instrument malfunction.
TABLE C-6 1984 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, AND TRITIUM IN PRECIPITATION STATION NO. SA-RWA-2F2 Results in Units of pCi/L +/- 2 sigma COLLECTION PERIOD ALPHA BETA TRITIUM 12-27-83 to 1-30-84 <0.8 <2.7 <130 1-30-84 to 2-27-84 1.1+/-0.8 3.5+/-0.7 <130 2-27-84 to 3-26-84 <l.4 3.2+/-0.7 140+/-80 3-26-84 to 4-30-84 <0.9 3.7+/-0.7 <130 4-30-84 to 5-30-84 <l.5 1.8+/-0.6 <130 5-30-84 to 7-02-84 <l. 0 2.8+/-0.7 140+/-80 7-02-84 to 7-31-84 1. 7+/-1.l 2.2+/-0.6 <130 7-31-84 to 8-28-84 <l. 9 3.8+/-0.8 <140 8-28-84 to 10-02-84 2.4+/-1.2 4.0+/-0.8 150+/-80 10-02-84 to 10-29-84 <l. 0 1.0+/-0.5 <130 10-29-84 to 11-27-84 <l. 0 3.2+/-1.2 <130 11-27-84 to 1-02-85 0.8+/-0.7 1.9+/-0.7 <140 AVERAGE 2.8+/-1.8 69
TABLE C-7 1984 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND GAMMA EMITTERS** IN QUARTERLY COMPOSITES OF PRECIPITATION STATION NO. SA-RWA-2F2 Results in Units of pCi/L +/- 2 sigma 12-27-83 3-26-84 7-02-84 10-02-84 NUCLIDE to to to to AVERAGE 3-26-84 7-02-84 10-02-84 10-29-84(1) Sr-89 <0.5 <0.5 <0.5 <1.0 -...] 0 Sr-90 <0.4 <0.4 <0.4 <0.4 Be-7 36+/-6 35+/-4 25+/-4 39+/-21 34+/-12 Ra-226 <l. 5 <8.4 <l. 3 5.6+/-2.4 Th-232 <2.4 <2.2 <2.5 7.8+/-4.5
- Sr-89 results are corrected for decay to sample stop date.
** All other gamma emitters searched for were <LLD; typical LLDs are given in Table c-31.
(1) Results are only taken from the October sample due to insufficient rainfall in the remaining two months of the fourth quarter.
TABLE C-8 1984 DIRECT RADIA'rION MEASUREMENTS - QUARTERLY TLD RESULTS Results in mrad/standard month* (Results by Teledyne Isotopes) JANUARY APRIL JULY OCTOBER STATION NO. to to to to AVERAGE MARCH JUNE SEPTEMBER DECEMBER SA-IDM-2S2 5.9+/-0.1 5.3+/-0.3 5. 6+/-0. 2 4.8+/-0.3 5. 4+/- o. 9 SA-IDM-5Sl 4.9+/-0.2 4.4+/-0.3 5.0+/-0.4 4.5+/-0.2 4.7+/-0.6 SA-IDM-652 5.1+/-0.l 5.1+/-0.2 (1) 5.1+/-0.2 5.1+/-0.0 SA-IOM-7Sl 6.2+/-0.2 5.9+/-0.2 6.6+/-0.2 6.2+/-0.2 6.2+/-0.6 SA-IDM-lOSl 5.8+/-0.1 5.4+/-0.1 6. 8+/-0. 7 6.3+/-0.3 6.1+/-1. 2 SA-IOM-llSl 4.9+/-0.1 4.7+/-0.l 6.7+/-0.2 8.7+/-0.3 6.2+/-3.7 SA-IDM-402 6.1+/-0.5 5.7+/-0.4 6.1+/- 0. 4 5.4+/-0.3 5.8+/-0.7 SA-IDM-501 5.3+/-0.2 5.1+/-0.1 5.8+/-0.2 5.1+/-0.l 5.3+/-0.7 SA-IDM-1001 6.0+/-0.5 5.4+/-0.3 6.1+/-0.l 5.3+/-0.2 5.7+/-0.8 SA-IOM-1401 5.3+/-0.3 5.4+/-0.3 6.1+/-0.2 5.1+/-0.2 5.5+/-0.9 SA-IOM-2El 5. 5+/-0.1 5.1+/-0.5 6.0+/-0.6 5. 2+/- o. 6 5. 4+/- o*. 8 SA-IDM-3El 5.2+/-0.2 5.0+/-0.3 5. 6+/-0. 4 4.9+/-0.3 5.2+/-0.6 SA-IDM-9El 6.6+/-0.2 6 2+/-0. 8 0 6.8+/-0.5 6.1+/-0.l 6.4+/-0.7 SA-IOM-11E2 6.5+/-0.4 6. 1+/-0. 3 7.1+/-0.6 5.9+/-0.3 6.4+/-1.0 SA-IDM-12El 6 4+/- 0.1 0 5.7+/-0.l 6.6+/-0.1 5.6+/-0.2 6.1+/-1.0 SA-IOM-13El 5.2+/-0.2 5.0+/-0.5 5.7+/-0.2 4.8+/-0.3 5.2+/-0.8 SA-IDM-16El 5. 6+/-0.1 .5.6+/-0.8 6.4+/-0.3 5. 3+/- 0.1 5. 7+/-0. 9 SA-IOM-lFl 5. 0+/-0. 5 5. 1+/-0. 6 6.0+/-0.3 5.2+/-0.1 5.3+/-0.9 SA-IOM-2F2 4.2+/-0.l 4.8+/-0.5 4. 8+/- 0. 2 3.8+/-0.1 4.4+/-1.0 SA-IDM-2F5 6.1+/-0. l 5.4+/-0.1 6.3+/-0.1 5.3+/-0.l 5. 8+/-1. 0 SA-IDM-2F6 5.5+/-0.3 5.1+/-0.2 6. 0+/- 0. 3 5. 0+/-0. l 5. 4+/- o. 9 SA-IOM-3F2 5.7+/-1.l 4.6+/-0.2 5.4+/-0.3 4.8+/-0.0 5.1+/-0.8 SA-IDM-3F3 5.3+/-0.2 4.4+/-0.2 5. 5+/-0.1 4. 5+/- 0.1 4.9+/-0.9 SA-IOM-5Fl 5.0+/-0.l 4.7+/-0.l 5.7+/-0.3 4.9+/-0.2 5.1+/-0.8 SA-IOM-6Fl 4.5+/-0.2 4.2+/-0.0 5.1+/-0.3 4. 0+/- 0. 2 4.4+/-1.0 SA-IDM-7F2 4.0+/-0.1 3.5+/-0.1 4.3+/-0.2 3.8+/-0.2 3. 9+/- o. 7 SA-IOM-10F2 6.3+/-0.l 5. 5+/-0. 5 6. 7+/-0.1 5. 8+/- 0. 2 6.1+/-1.1 SA-IDM-llFl 5.9+/-0.1 5.7+/-0.2 6. 6+/-0.1 5.2+/-0.4 5. 8+/-1. 2 SA-IDM-12Fl 6.2+/-0.l 5.2+/-0.3 6. 2+/- 0.1 4. 9+/- o. 3 5. 6+/-1. 4 SA-IDM-13F2 5.8+/-0.l 5.2+/-0.4 6.1+/-0.3 5.0+/-0.4 5.5+/-1.0 SA-IOM-13F3 6. 2+/-0. 2 5. 5+/-0. 2 6.4+/-0.2 5.2+/-0.2 5. 8+/-1. l SA-IDM-13Fl/4** 5.6+/-0.l 5.4+/-0.4 6.1+/-0.l 5.3+/-0.2 5.6+/-0.7 SA-IDM-14F2 5. 9+/-0.1 5.1+/-0.4 6.1+/-0.4 5. 2+/- o. 2 5. 6+/-1. 0 SA-IOM-15F3 6.6+/-0.2 6.1+/-0.5 1.1:1:0.5 5.6+/-0.3 6. 3+/-1.3 SA-IOM-16F2 5.7+/-0.l 4. 8+/-0. 5 5.7+/-0.3 4.7+/-0.0 5.2+/-1.l SA-IDM-1G3 (C) 6.8+/-0.2 6.7+/-0.2 7.2+/-0.3 6.0+/-0.3 6. 7+/-1. 0 SA-IDM-3Gl (C) 5.6+/-0.1 5. 8+/-0. 3 6. 7+/-0.3 5.3+/-0.2 5.8+/-1.2 SA-IDM-10Gl (C) 6. 6+/-0. 2 6.0+/-0.3 6.8+/-0.5 5~5+/-0.3 6. 2+/-1. 2 SA-IDM-16Gl (C) 6.9:t0.2 6.1+/-0.3 7 .2:1: 0 .3 5.9+/-0.2 6.5+/-1.2 SA-IDM-3Hl (C) 5. 5+/-0. 2 5.0+/-0.6 6.6+/-0.2 5.4+/-0.2 5. 6+/-1.4 SA-IDM-3H3 (C) 5.7+/-0.2 5.7+/-0.2 6. 5+/-0 3 0 5. 4+/- 0. 2 5. 8+/- o. 9 AVERAGE 5. 7+/-1.3 5.3+/-1.2 6.2+/-1.3 5. 3+/-1. 6 Grand Average 5. 6+/-1. 5
- The standard month = 30.4 days.
** Effective 3-27-84, Loe. 13Fl has been moved to a new location (13F4).
(1) TLD missing from field location. (C) Control station 71
TABLE C-9 1984 DIRECT RADIATION MEASUREMENTS - MONTHLY TLD RESULTS Results in mrad/standard month* (Results by Teledyne Isotopes) STATION NO. JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-IDM-2S2 6.l:t0.6 6.7+/-0.3 5.4:t0.3 6. l:t 0. 2 6. 5+/-0. 6 7.5:tl.O SA-IDM-5Sl 4.3+/-0.2 6.l:tO.l 4.6+/-0.l 4.9+/-0.l 5.8+/-0.2 6.3+/-0.3 SA-IDM-6S2 4.4+/-0.l 6.5+/-0.3 5. ~:tO. l 5. 5+/-0. l 6.4:tl.2 6. 9+/-0. 6 SA-IDM-7Sl 5.3+/-0.2 7.7+/-0.l 5.9+/-0.4 6.6+/-0.5 7.0+/-0.2 7.8+/-0.2 SA-IDM-lOSl 5.4+/-0.l 6.8+/-0.2 5.8+/-0.3 5.9+/-0.l 6. 6:t 0. 2 7. 7:t0.4 SA-IDM-llSl 4.8+/-0.8 5.7+/-0.l 4.7+/-0.l 5.4+/-0.6 5.8+/-0.4 6.8+/-0.9 SA-IDM-501 4 .4:t0. 3 6. 6+/- 0. 2 5.1+/-0.2 5.4+/-0.2 6. 2+/- 0. 2 7. O:tO. 2 SA-IDM-1001 5.0:t0.4 6.9+/-0.3 6.0+/-0.4 6.4+/-0.l 6. 5+/-0. 3 7.4:t0.2 SA-IDM-1401 5.4+/-0.l 6. 8+/-0. 5 5.4+/-0.2 6. 2+/- o. 3 6. 5+/- 0. 3 7. 6:t 0. 2 SA-IDM-2El 5.4+/-0.4 6.7+/-0.2 5.1+/-0. 3. 5.5+/-0.l 6.3+/-0.4 7.4+/-1.5 SA-IDM-3El 5. 3:t 0 3 0 6.4+/-0.1 4.9+/-0.2 5. 6+/-0. 7 6.0+/-0.l 6. 8+/- 0. 3 -..J SA-IDM-13El 4.9+/-0.6 6.4+/-0.2 5.l:t0.4 5.7+/-0.2 5.9+/-0.4 6.9+/-0.2 SA-IDM-16El 5.2+/-0.8 7.2+/-0.3 5.7:t0.3 6.0:t0.2 6. 3+/- o. 5 7. 5+/- 0.1 "' SA-IDM-lFl 5.5+/-0.l 6.5+/-0.2 5.8+/-0.5 6.l:t0.2 6.8+/-0.7 7.3+/-1.l SA-IDM-2F2 4. 6+/-0. l 5. 6+/- o. 2 4. S:t O. 9 4. 4+/- o. l 5.2+/-1.0 6. O:t 0. 2 SA-IDM-2F6 6.0:tO.l 6.6+/-0.2 5.2+/-0.3 5.7+/-0.2 6.8+/-0.5 7.l:t0.4 SA-IDM-5Fl 4.3+/-0.3 6. 2+/- 0.1 4 8+/- 0. 2 0 5.2+/-0.2 5. 9+/- 0. 2 6. 6:t o. 3 SA-IDM-6Fl 3.6+/-0.4 5.5+/-0.2 4.4+/-0.2 4.5+/-0.l 5.6+/-0.2 6.0:t0.3 SA-IDM-7F2 3. 5+/-0. 2 5. 6+/-0. 5 3.8+/-0.2 4. 3+/- 0. 3 4. 9+/- 0. 3 . 5. 5+/-0. 4 SA-IDM-llFl 5.6+/-0.2 7.1+/-0.5 5.9+/-0.l 6. 5+/-0. 2 6.7+/-0.2 7.8+/-0.0 SA-IDM-l3Fl/4** 5.3+/-0.4 6. 5+/- 0. 2 5.4+/-0.2 6. 2+/- 0 3 0 6. 6+/- o. 2 7. 6+/- o. 9 SA-IDM-3Gl (C) 6.1+/-0.l 7.2+/-0.2 5.7+/-0.3 5.8+/-0.2 6.2+/-0.2 7.7+/-0.4 SA-IDM-3Hl (C) 6. 0+/-0. 3 6.9+/-0.2 5.3+/-0.2 . 5.8+/-0.l 7. 0+/- 0. 2 7. 3:t 0. 2 SA-IDM-3H3 (C) 5.2+/-0.4 7.3+/-0.2 5.9+/-0.2 6.3+/-0.3 7.1+/-0.2 8.0:tl.O AVERAGE 5.l:tl.4 6.6+/-1.l 5.2+/-1. l 5.7+/-1.3 6.3+/-1.1 7.l:tl.3
TABLE C-9 (cont'd) 1984 DIRECT RADIATION MEASUREMENTS - MONTHLY TLD RESULTS Results in mrad/standard month* (Results by Teledyne Isotopes) STATION NO. JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE SA-IDM-282 5.6+/-0.3 7.1+/-0.3 5. 5+/- o. 5 5.0+/-0.1 4.6+/-0.4 5.9+/-0.3 6.0+/-1.7 SA-IDM-5Sl 5~3+/-0.3 6.6+/-0.7 5.1+/-0.2 4.8+/-0.2 4.8+/-0.8 5.5+/-0.2 5. 3+/-1.4 SA-IDM-682 5. 9+/-0. 4 6. 9+/- 0. 4 (1) 5. 4+/- 0. 2 5. 2+/- o. 5 5.8+/-0.3 5.8+/-1.6 SA-IDM-7Sl 6. 5+/-0. 4 8. l:t:0.4 6.7+/-0.2 6.4+/-0.2 6.3+/-0.6 6.9+/-0.5 6.8+/-1.6 SA-IDM-lOSl 6. O:t:O. 5 8. 0+/-0.1 6. 5+/- 0.1 6. 8+/- 0. 2 6. 3+/- o. 9 6.1+/-0.4 6.5+/-1.5 SA-IDM-llSl 5.4+/-0.6 8.5+/-0.4 8.3+/-0.5 11.3+/-0.6 9.3+/-2.4 5.7+/-0.5 6.8+/-4.2 SA-IDM-5Dl 5. 7+/-0. 5 7. 0+/-0. 5 5. 6+/-0. 2 5. 0+/- o. 3 4.8+/-0.4 5. 8+/-0. 3 5. 7+/-1. 7 SA-IDM-lODl 6.4+/-0.3 8.1+/-0.4 6.3+/-0.l 5.7+/-0.2 5.5+/-0.5 6.1+/-0.6 6.4+/-1.7 SA-IDM-14Dl 6. 0+/-0. 3 7.4+/-0.4 6.0+/-0.2 5.5+/-0.6 5. 5+/- o. 5 6.0+/-0.1 6.2+/-1.5 SA-IDM-2El 5.8+/-0.2 7.1+/-0.3 5.8+/-0.3 5.5+/-0.2 5.0+/-0.2 6.0+/-0.4 6.0+/-1.5 SA-IDM-3El 5.6+/-0.3 7.0+/-0.2 '5.4+/-0.4 4. 9+/- 0. 2 4.9+/-1.0 5. 5+/- o. 3 5. 7+/-1. 4 SA-IDM-13El 5.9+/-0.2 7.1+/-0.l 5.9+/-1.2 5.1+/-0.4 4.9+/-0.4 5.7+/-0.4 5.8+/-1.5 ..;J w SA-IDM-16El 6.3+/-0.4 7.6+/-0.2 5. 9+/- 0.1 5. 3+/- 0. 3 5. 2+/- 0. 3 6.1+/-0.3 6.2+/-1. 7 SA-IDM-lFl 5.8+/-0.3 7.6+/-0.2 6.0+/-1.0 5.4+/-0.3 5.0+/-0.3 5.7+/-0.4 6.1+/-1. 6 SA-IDM-2F2 4. 7+/-0. 2 5. 9+/-0.1 4.4+/-0.2 4. 3+/- o. 2 4. 2+/- 0. 3 4. 8+/- 0.1 4.9+/-1.3 SA-IDM-2F6 6.2+/-0.5 7.1+/-0.4 5.5+/-0.3 5.4+/-0.2 5.1+/-0. 2 6.1+/-0.3 6.1+/-1.4 SA-IDM-5Fl 5. 6+/-0.4 6.8+/-0.4 5.4+/-0.2 5.1+/-0.1 4.9+/-0.6 5.7+/-0.3 5.5+/-1.5 SA-IDM-6Fl 5.0+/-0.2 6.1+/-0. 2 4.7+/-0.4 4.6+/-0.l 4.8+/-0.3 5.0+/-0.1 5. 0+/-1.4 SA-IDM-7F2 4.6+/-0.2 5.8+/-0.6 4.1+/-0. 2 4.1+/-0. 2 4.3+/-0.6 4.8+/-0.2 4.6+/-1.5 SA-IDM-llFl 6.3+/-0.2 8.2+/-0.6 6.1+/-0.4 6.0+/-0.3 5.8+/-0.3 6.1+/-0.4 6.5+/-1.6 SA-IDM-13F4 6.4+/-0. 6 7.5+/-0.2 5.8+/-0.2 5.3+/-0.4 5.4+/-0.4 6. 0+/-0. 3 6.2+/-1. 5 SA-IDM-3Gl (C) 6.3+/-0.8 7.7+/-0.3 6.4+/-1.3 5.7+/-0.1 5.5+/-0.4 6.1+/-0.3 6. 4+/-1. 5 SA-IDM-3Hl (C) 5. 9+/-0. 7 7.6+/-0.4 5. 9+/- 0. 2 5.9+/-0.3 5. 9+/- 0. 2 6. 2+/-0. 3 6.3+/-1.4 SA-IDM-3H3 (C) 6.6+/-0.9 8.5+/-0.2 6.1+/-0. 3 5.8+/-0.3 6.3+/-0.3 6.5+/-0.3 6.6+/-1.9 AVERAGE 5. 8+/-1.1 7.3+/-1.5 5. 8+/-1. 7 5.6+/-2.7 5.4+/-2.0 5.8+/-1.0
';)
Grand Average 6.0+/-2.0
- The standard month = 30.4 days.
** Effective 3-27-84, Loe. 13Fl has been moved to a new location (13F4).
- l ~
(1) TLD missing from field location. (C) Control station
TABLE C-10 1984 CONCENTRATIONS OF IODINE-131
- IN MILK Results in Units of pCi/L STATION NO.""' JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-MLK-13E3 <0.l <0.1 <0.1 <0.1 <0.1 <0.l
<0.2 <0.2 <0.1 <0.1 <0.1 <0.1 SA-MLK-2F4 <0.l <0.2 <0.1 <0.1 <0.1 <0.1
<0.2 <0.2 <0.l <0.1 <0.1 <0.1 SA-MLK-5F2 <0.1 <0.2 <0.1 <0.1 <0.l <0.1
<0.2 <0.2 <0.l <0.1 <0.1 <0.1 SA-MLK-14Fl <0.1 <0.2 <0.l <0.1 <0.1 <0.1
<0.2 <0.2 <0.1 <0.1 <0.1 <0.1 SA-MLK-15Fl <0.1 <0.2 <0.l <0.1 <0.1 <0.1
<0.2 <0.2 <0.1 <0.1 <0.1 <0.1 SA-MLK-3Gl <0.l <0.1 <0.1 <0.1 <0.1 <0.1 (Control) <0.2 <0.2 <0.1 <0.1 <0.1 <0.1
-..J .i::. STATI.ON NO. u JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER SA-MLK-13E3 <0.1 <0.1 <0.l <0.1 <0.1 <0.2
<0.l <0.1 <0.2 <0.1 <0.1 <0.1 SA-MLK-2F4 <0.l <0.2 <0.1 <0.1 <0.1 <0.2
<0.1 <0.1 <0.1 <0.1 <0.1 <0.1 SA-MLK-5F2 <0.1 <0.2 <0.1 <0.1 <0.1 <0.2
<0.1 <0.1 <0.1 <0.1 <0.1 <0.1 SA-MLK-14Fl <0.1 <0.2 <0.1 <0.1 <0.1 <0.2
<0.1 <0.1 <0.l <0.1 <0.l <0.1 SA-MLK-15Fl <0.l <0.2 <0.1 <0.2 <0.l <0.2
<0.1 <0.1 <0.l <0.1 <0.1 <0.1 SA-MLK-3Gl <.0.1 <0.1 <0.1 <0.1 <0.1 <0.2 (Control) <0.1 <0.1 <0.1 <0.1 <0.1 <0.1
- I-131 results are corrected for decay to midpoint of collection period.
~* sampling dates can be found in Table C-13.
TABLE C-11 1984 CONCENTRATIONS OF STRONTIUM-89* and -90 IN MILK Results in Units of pCi/L +/- 2 sigma STATION NO.** NUCLIDE JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-MLK-l3E3 sr-89 <l.0 <l.2 <l.2 <l.3 <l. l <1. 4 Sr-90 2.5+/-0.4 2.9+/-0.5 2.6+/-0.5 3.2+/-0.6 2.4+/-0.4 2.7+/-0.6 SA-MLK-2F4 sr-89 <l.0 <l.0 <l. l <l. 3 <l. l .<l.6 Sr-90 1.6+/-0.4 l.9+/-0.4 l.2+/-0.4 3.4+/-0.6 2.1+/-0.4 l.6+/-0.6 SA-MLK-5F2 sr-89 <l.l <l.2 <l.2 <l.2 <l. 2 <l. 7 sr-90 2.7+/-0.4 3.l!+/-0.5 3.2+/-0.4 l.8+/-0.5 4.1+/-0.5 5.3+/-0.7 SA-MLK-14Fl sr-89 <l.2 <l.4 <l. 2 <l. 3 <l. l <l.4 sr-90 2.0+/-0.4 2.5+/-0.5 2.2+/-0.5 2.7+/-0.6 2.5+/-0.4 2.3+/-0.6 SA-MLK-15Fl Sr-89 <l.0 <l.4 <l. l <l. 2 <l. l <1. 3 sr-90 1.4+/-0.4 2.6+/-0.6 1.8+/-0.4 2.3+/-0.5 l.4+/-0.4 2.0+/-0.5 SA-MLK-3Gl sr-89 <l.2 <l.2 <l.3 <l. 3 <l. 2 <1.8 (Control) sr-90 2.9+/-0.4 3.5+/-0.5 3.7+/-0.5 3.1+/-0.6 3.1+/-0,5 3.3+/-0.7 -.J U1 STATION NO.** NUCLIDE JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE SA-MLK-l3E3 sr-89 <l.l <l.0 <l.5 <l.l <1.0 <0.8 sr-90 2.1+/-0.5 2.1+/-0.4 2.2+/-0.6 2.2+/-0.4 2.0+/-0.4 l.9+/-0.4 SA-MLK-2F4 sr-89 <l.0 <l.O <1.5 <1.0 <l.0 <0.8 sr-90 1.3+/-0.4 l.3+/-0.4 l.2+/-0.4 l.5+/-0.4 1.8+/-0.4 l.5+/-0.3 1.7+/-1.2
'SA-MLK-5F2 sr-89 <l.4 <l. 3 <l. 7 <l.3 <l.4 <l.O sr-90 4.9+/-0.6 4.2+/-0.6 4.3+/-0.7 4.5+/-0.6 4.4+/-0.6 2.5+/-0.4 3.8+/-2.1 SA-MLK-14Fl sr-89 <l.l <l.l <l. 4 <l.l <l.l <0.9 Sr-90 l.9+/-0.5 2. l+/-O. 4 l.9+/-0.4 2.4.+/-0.5 2.1+/-0.4 l.7+/-0.4 2.2+/-0.6 SA-MLK-15Fl sr-89 <l.3 <l.0 <2.0 <1. l <l. l <1.2 sr-90 2.1+/-0.6 l.8+/-0.4 2.0+/-0.8 1.9+/-0.4 1.6+/-0.5 2.3+/-0.4 1.9+/-0.7 SA-MLK-3Gl Sr-89 <l.3 <l.2 <l.6 <1. 2 <l.2 <0.9 (Control) sr-90 4.9+/-0.6 3.8+/-0.5 3.3+/-0.6 3.0+/-0.5 2.3+/-0,5 2.2+/-0.4 3.3+/-1.4 Grand Average sr-89 Sr-90 2.5+/-1.9
- Sr-89 results are corrected for decay to midpoint of collection period.
** sampling dates can be found in Table C-13.
Strontium analysis performed only on first milk collection of each month.
TABLE c-12 19Bt CONCENTRATIONS OF GAMMA EHITTERS6 IN HILK Results in Units of pCi/L :I: 2 sigma STATION N0.6<> NUCLIDE JANUARY FEBRUARY MARCH APRIL HAY JUNE SA-HLK-13E3 Na-22 <2.l <3.2 <2.9 < 2. 9 <3.5 <0. 5 K-40 1400:t55 1400:t68 1300:t67 1200:t57 1300:t65 l300:t58 Hn-54 <1.5 < 2 .1 < 2. 8 <l. 9 <2.1 <2.1 Cs-137 2.3+/-1. 5 <2.6 < 2. 4 <2.3 <2.3 <l. 4 La-140 <2. 0 <2.6 < 2. 8 <1.3 <2.3 <2.6 Ra-226 <6.0 5.l:t2.2 < 9. e <9.2 <4.8 <4.8 Th-232 < 7. 3 <9. 3 <9.7 < 7. 6 <10 < 8. 0 SA-HLK-2F4 Na-22 <3. l <2.6 <2.2 <3.7 <3.6 <3.5 K-40 1400:t6l 1400%59 1400t55 1400+/-67 1400+/-70 1400t6!1 Hn-54 <2.3 <2.5 < 2.1 <2.3 <2.3 <2.3 Cs-137 < 2. 3 <2.5 <l. 8 < 2. 6 <2.4 2.3tl.3 La-140 <2.3 <l. 9 <2.0 <2.8 <2.6 <2.9 Ra-226 < 5. < 9. 4 < 6. 9 5. 8t 2. 4 <4.8 < 5.1 Th-232 < 8. 0 <7.4 < 9 .1 < 9. 3 < 9. 3 < 9. 3 SA-HLK-5F2 Na-22 <3.0 <4.7 <2.7 <2.3 < 3. 5 < 2. 9 K-40 1200:t65 1200+/-53 1300t57 1400t59 1400t59 1400t53 Mn-54 <2. 6 < 2. 2 <l. 8 <0.9 <2.1 <2.7 Cs-137 <2.3 <3.7 <2.3 2.3tl.4 <2.1 4.ltl.7 La-140 < 2. 3 < 2. 3 <l. 8 < 2 .1 < 2. 2 <l. 5 Ra-226 <9.3 < 9. 0 < 9. 9 < 9. 0 < 4. 6 < 5. 8 Th-232 13:!: 6 <11 <8. 8 <8.2 < 8. 7 <9.0 SA-HLK-14Fl Na-22 <2.8 <2.9 <2.5 <3.1 <l. 6 <l. 3 ...J K-40 1400t56 l400t55 1400t55 1300t54 1300+/-58 1400t54 Hn-54 <2.6 <2. 3 < 2 .1 <2.1 <l. 0 <l. 8 °' Cs-137 La-14 0
<2.8
<2.6
<2.8
<2.5
<2.7
<2.0
< 2. 4
<l. 9
<2.2
<l. 2
<2.1
<l. 8 Ra-226 < 7. 2 <7.5 < 7. 9 <6.8 <4.2 <4.6 Th-232 <11 <8.6 <10 <8.3 <10 <8.2 SA-HLK-15Fl Na-22 < 3 .1 <3.5 < 3. 4 <2.9 <l. 7 <4.1 K-40 1300t58 1300+/-67 1300+/-67 1200t66 l300t66 1300t68 Hn-54 < 2. 2 <2.4 < 2 .1 <1.1 <2.4 <l. 9 Cs-13 7 2.7:tl.4 < 2. 0 <2.4 <2.5 <2.6 <3.3 La-140 < 2. 2 <3.0 <2.6 < 3. 3 <2.8 <l. 7 Ra'-226 <9. 8 <9.6 < 9. 0 <9.7 <9.4 6. 5:!: 3. 4 Th-232 < 7.1 < 8. 6 <9 .1 <8.2 < 8. 3 <8.3 SA-HLK-3Gl Na-22 <3.5 <2.8 <3.0 2.1+/-1.2 <2.6 <l. 5 (Control) K-40 1500+/-69 l300t68 1400t59 1400+/-68 1300+/-54 1300:1:57 Hn-54 <2.3 <2.2 <l. 7 < 2. 2 <2.4 <l. 0 Cs-137 <2.6 < 2. 2 <l. 9 <2.7 < 2. 2 <l. 8 La-140 <2.2 <2.6 <l. 7 <2.8 <2.4 <l. 9 Ra-226 <6.l <9. 2 < 9. 7 < 5.1 < 5. 9 <5.0 Th-232 <9.3 <10 <9.2 < 9. 3 < 8. 8 < 6. 7 A.VERAGE K-40 1400t210 1300tl60 1400+/-110 1300+/-200 l300tl00 1400tll0
TABLE C-12 (cont'd) 1984 CONCENTRATIONS OF GAMMA EMITTERS* IN MILK Results in Unite of pCi/L :1: 2 sigma STATION NO.*" NUCLIDE JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE SA-MLK-13E3 Na-22 <3.0 <3.5 <l. 6 <2.0 < 2. 7 < 2. 7 K-40 1300:1:58 1500:1:68 1400:1:54 1400:1:60 1400:1:59 1400:1:59 1400:1:160 Mn-54 <l.l <2. 3 <l. 8 <l. 7 < 2. l <O. 9 Ce-137 <2.4 <2. 6 < 2. 6 < 2. 4 < 2. 2 <2.5 La-140 <l. 2 <2.4 < 0. 6 <l. 3 <l.l <2.l Ra-226 <4.7 <4.8 < 4. 4 <3.9 < 3. 8 <4.6 Th-232 <8. 2 <9.8 <3. 6 < 6. 0 < 9. 6 < 7. 8 SA-HLK-2F4 Na-22 < 3. 2 < 3. l < 3. 3 <2.9 <2.8 <3.3 K-40 1400:t69 1400:1:69 1300:1:64 1400:1:59 1300:1:61 1400:1:68 1400:1:78 Mn-54 <1.2 < 2. l <2.3 <l. 0 < 2. 3 <2.3 Ce-137 < 2. 5 <2.8 <2.4 <2.0 <2.6 <2. 4 La-140 < 2 .1 <3.8 < 2. 3 <3.0 < 2. 9 <2.3 Ra-226 <5. 5 < 5. l <4. 8 <4.4 <4. 8 <4.8 Th-232 < 8. 2 < 9. 2 < 8. 9 < 8. 3 < 9. 9 <9.3 SA-MLK-5F2 Na-22 <2.7 <2.4 <2.6 <3.5 < 3. 2 <2. 3 K-40 1300:1:55 1400:1:58 1200:1:56 1300:1:66 1300:1:64 1300:1:52 1300+/-160 Mn-54 Ce-137
< o. 0 4.2tl.7
<2.4
- 3. l:t l. 9
<2.3 6.2tl.9
<2.5 3.0tl.7
< 2. 5
- 2. ltl.3
<l. 8 1.8:1:1.0 3.1+/-2.6 La-1~0 <l. 8 2.4:1:1.4 < 2. l < 3 .1 < 3. 0 <l. 6 Ra-226 <5.7 <4.3 < 3. 9 < 5. 3 < 4. 4 <2.5 Th-232 < 1. 0 <8.8 < 6. 8 <10 < 9. 9 < 8. 0 SA-MLK-14Fl Na-22 <3.0 < 3. 0 < 3. 4 < 2. 7 < 2. 0 <2.8 "1 K-40 1400:1:59 1300t54 1400:1:66 1400:1:54 1300:1:54 1500t60 1400:1:120
-...J Hn-5<1 2.4:tl.4 <l. l < 2. 3 <l. 9 < i. 8 <l. 6 Ce-137 <2.4 <2.0 <2.6 < 2. 2 <2.0 <l. 3 La-140 <.3. 3 <l. 5 <2.6 <2.7 < l. l <l. 5 Ra-226 <4.8 <4.7 <4. 8 < 5. 2 < 5. 0 < 5. 2 Th-232 < 7. 4 < 7. 9 <9.3 <8.6 <5.3 <8.2 SA-MLK-15Fl Na-22 <3.3 <2.5 <2.9 <l.4 < 3. 2 <3.6 K-40 1300:1:53 l<<OO:t68 1300+/-58 1400+/-55 1400t66 1200:1:53 1300+/-130 Hn-54 <L 8 <2.4 <l. l <l. 2 <2.3 <l. 9 Ce-137 <l. 9 < 2. 2 <2.0 <l. 9 <2.6 <2.7 La-140 < 2. 6 <2.9 <2.0 <2.4 <2.7 <2.6 Ra-226 <5.5 < 5. 4 < 4. 9 <4.l <4.8 < 5. 6 Th-232 < 9. 0 < 8. 6 <8.0 < 0. s < 9. 3 < 8. 7 SA-HLK-3Gl Na-22 < 3. 3 < 2. 3 < 3. 3 <3.7 <l. 7 <2.6 (Control) K-40 1300t67 1400:1:59 1300:1:67 1300:1:66 1300+/-68 1400+/-69 1400:1:130 Mn-54 < 2. 2 <0.9 <2.3 <l. 6 < 2. 4 <2.5 Ce-137 <2.6 <2.3 <2.6 <2.1 < l. 8 <2.2 La-140 <2. 6 <l. 7 <2.9 <2.4 < 2. 7 <3.1 Ra-226 <5.1 <4.9 < 5.1 < 5. 0 <4.7 < 5. 5 Th-232 <8.9 <7.6 <12 < 9. 5 < 9. 0 <9. 4 AVERAGE K-40 1300:1:100 1400+/-130 1300tl50 1400:1:100 1~00+/-100 1400:1:210 Grand Average K-40 1300:1:140
- All other gamma emitters searched for were <LLD; typical LLDe are given in Table C-31.
** Sampling dates can be found in Table C-13.
Gamma analysis performed only on first milk collection of each month.
TABLE C-13 1984 SAMPLING DATES FOR MILK SAMPLES STATION NO. MONTH l3E3 2F4 5F2 14Fl 15Fl 3Gl JANUARY 'l-03-84 1-01-84 1-02-84 1-02-84 1-02-84 1-03-84 to to to to to to 1-04-84 1-03-84 1-03-84 1-03-84 ' 1-03-84 1-04-84 1-15-84 1-16-84 1-16-84 1-15-84 1-16-84 1-15-84 to to to to to to 1-16-84 1-17-84 1-16-84 1-16-84 1-16-84 1-16-84 FEBRUARY 2-06-84 2-05-84 2-06-84 2-05-84 2-05-84 2-06-84 to to to to to to 2-07-84 2-06-84 2-07-84 2-06-84 2-06-84 2-07-84 2-20-84 2-21-84 2-21-84 2-21-84 2-21-84 2-20-84 to to to to to to 2-21-84 2-22-84 2-22-84 2-22-84 2-22-84 2-21-84 MARCH 3-05-84 3-04-84 3-03-84 3-04-84 3-04-84 3-05-84 -.J to to to to to to co 3-06-84 3-05-84 3-05-84 3-05-84 3-05-84 3-06-84 3-19-84 3-18-84 3-18-84 3-18-84 3-18-84 3-19-84 to to to to to to 3-20-84 3-19-84 3-19-84 3-19-84 3-19-84 3-20-84 APRIL 4-02-84 4-01-84 4-01-84 4-01-84 4-01-84 4-02-84 to to to to to to 4-03-84 4-02-84 4-02-84 4-02-84 4-02-84 4-03-84 4-16-84 4-15-84 4-15-84 4-15-84 4-15-84 4-16-84 to to to to to to 4-17-84 4-16-84 4-16-84 4-16-84 4-16-84 4-17-84 MAY 5-06-84 5-07-84 5-07-84 5-07-84 5-07-84 5-06-84 to to to to to to 5-08-84 5-08-84 5-08-84 5-08-84 5-08-84 5-07-84 5-20-84 5-21-84 5-21-84 5-21-84 5-21-84 5-20-84 to to to to to to 5-21-84 5-22-84 5-22-84 5-22-84 5-22-84 5-21-84 JUNE 6-03-84 6-04-84 6-04-84 6-04-84 6-04-84 6-03-84 to to to to to to 6-04-84 6-05-84 6-05-84 6-05-84 6-05-84 6-04-84 6-1 7-84 ' 6-18-84 6-18-84 6-18-84 6-18-84 6-17-84 to to to to to to 6-18-84 6-19-84 6-19-84 6-19-84 6-19-84 6-18-84
TABLE C-13 (cont'd) 1984 SAMPLING DATES FOR MILK SAMPLES STATION NO. MONTH 13E3 2F4 5F2 14Fl 15Fl 3Gl JULY 7-09-84 7-08-84 7-08-84 7-08-84 7-08-84 7-09-84 to to to to to to 7-10-84 7-09-84 7-09-84 7-09-84 7-09-84 7-10-84 7-23-84 7-22-84 7-22-84 7-22-84 7-22-84 7-23 to to to to to to 7-24-84 7-23-84 7-23-84 7-23-84 7-23-84 7-24-84 AUGUST 8-06-84 8-05-84 8-05-84 8-05-84 8-05-84 8-06-84 to to to to to to 8-07-84 8-06-84 8-06-84 8-06-84 8-06-84 8-07-84 8-20-84 8-19-84 8-19-84 8-19-84 8-19-84 8-20-84 to to to to to to 8-21-84 8-20-84 8-20-84 8-20-84 8-20-84 8-21-84 SEPTEMBER 9-03-84 9-04-84 9-04-84 9-04-84 9-04-84 9-03-84 -.] to to to to to to l.O 9-04-84 9-05-84 9-05-84 9-05-84 9-05-84 9-04-84 9-17-84 9-16-84 9-16-84 9-16-84 9-16-84 9-17-84 to to to to to to 9-18-84 9-17-84 9-17-84 9-17-84 9-17-84 9-18-84 OCTOBER 10-09-84 10-08-84 10-08-84 10-08-84 10-08-84 10-09-84 to to to to to to 10-10-84 10-09-84 10-09-84 10-09-84 10-09-84 10-10-84 10-21-84 10-22-84 10-22-84 10-22-84 10-22-84 10-21-84 to to to to to to 10-22-84 i0-23-84 10-23-84 10-23-84 10-23-84 10-22-84 NOVEMBER 11-04-84 11-03-84 11-03-84 11-03-84 11-03-84 11-04-84 to to to to to to 11-05-84 11-05-84 11-04-84 11-04-84 11-04-84 11-05-84 11-18-84 11-19-84 11-19-84 11-19-84 11-19-84 11-18-84 to to to to to to 11-19-84 11-20-84 11-20-84 11-20-84 11-20-84 11-19-84 DECEMBER 12-02-84 12-03-84 12-03-84 12-03-84 12-03-84 12-02-84 to to to to to to 12-03-84 12-04-84 12-04-84 12-04-84 12-04-84 12-03-84 12-18-84 12-17-84 12-17-84 12-17-84 12-17-84 12-16-84 to to to to to to 12-19-84 12-18-84 12-18-84 12-18-84 12-18-84 12-18-84
TABLE C-14 1984 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMI'fTERS, POTASSIUM-40 AND TRITIUM IN WELL WATER Results in Units of pCi/L +/- 2 sigma STATION NQ. RADIOACTIVITY 1-09-84 2-06-84 3-12-84 4-09-84 5-14-84 6-11-84 SA-WWA-2S3 Alpha <Ll <0.8 <1.*1 <1.6 <1.4 <1.2 Beta 6.3+/-0.9 6.2+/-0.9 6.4+/-1.0 8.8+/-1.0 8.3+/-1.2 7.3+/-1.0 K-40 7.5+/-0.8 6.1+/-0.6 7.0+/-0.7 8.5+/-0.8 12+/-1 7.3+/-0.7 H-3 <130 <130 <130 <130 <130 <130 00 SA-WWA-5Dl 0 Alpha <Ll <0.9(1) <1.l <l. 7 <l. 2 <1.2 Beta 14+/-1 14+/-1 12+/-1 12+/-1 12+/-1 14+/-1 K-40 13+/-1 14+/-1 13+/-1 13+/-1 13+/-1 13+/-1 H-3 <130 <130 <130 <130 <130 <130 SA-WWA-3El (Control) Alpha <l.0 <l.0 <l.l <l. 7 <1.3 <l.3 Beta 8.6+/-1.0 8.3+/-1.0 8.8+/-1.1 8.7+/-1.0 6.0+/-1.l 10+/-1 K-40 9.3+/-0.9 9.3+/-0.9 8.8+/-0.9 8.7+/-0.9 8.9+/-0.9 8.8+/-0.9 H-3 <130 <130 <130 <130 <130 <130
TABLE C-14 (cont 1 d) 1984 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, POTASSIUM-40 AND TRITIUM IN WELL WATER Results in Units of pCi/L +/- 2 sigma STATION NO. RADIOACTIVITY 7-16-84 8-13-84 9-10-84 10-15-84 11-13-84 12-10-84 AVERAGE SA-WWA-2S3 Alpha <1.4 1.4+/-1.2 2.0+/-1.5 1.6+/-1.0(2) <l. 2 l.1+/-0.9 Beta 4.7+/-0.8 2.9+/-0.7 7. 7+/-1. 0 17+/-2 13+/-1 5.3+/-0.9 7.8+/-7.6 K-40 3.7+/-0.4 2.8+/-0.3 7.4+/-0.7 19+/-2 12+/-1 5.3+/-0.5 8.2+/-8.8 H-3 <130 <130 <140 <130 <140 <130 00' ...... SA-WWA-5Dl Alpha <1.5 <l. 5 <l. 7 0.9+/-0.8 <1.1 1.4+/-1..0 Beta 13+/-1 14+/-1 12+/-1 12+/-1 14+/-1 13+/-1 13+/-2 K-40 6.4+/-0.6 28+/-3 14+/-1 14+/-1 13+/-1 13+/-1 14+/-10 H-3 <140 <140 <130 <140 <130 <140 SA-WWA-3El (Control) Alpha <1.4 <1.5 <l.9 <0.6 <l. 4 <l.l Beta 9.6+/-1.1 8.2+/-1.0 8.3+/-1.l 8.1+/-1.0 8.3+/-1.0 8.5+/-1.0 8.4+/-1.9 K-40 5.5+/-0.6 7.8+/-0.8 7.6+/-0.8 9.1+/-0.9 8.5+/-0.8 8.3+/-0.8 8.4+/-2.l H:-3 <130 <140 <140 <130 <130 <140 (1) Station SA-WWA-5Dl was collected on 2-07-84. (2) Station SA-WWA-2S3 was collected on 10-16-84.
TABLE C-15 1984 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND GAMMA EMITTERS** IN QUARTERLY COMPOSITES OF WELL WATER Results in Units of pCi/L +/- 2 sigma 1-09-84 4-09-84 7-16-84 10-15-84 STATION NUMBER to to to to RADIOACTIVITY 3-12-84 6-11-84 9-10-84 12-10-84 SA-WWA-2S3 Sr-89 <Oo5 <Oo5 0.9+/-0.4 <0.4(1) Sr-90 <Oo5 <0.4 <0.5 <0.4 K-40 11+/-6 12+/-5 <9.4 14+/-6 00 Ra-226 <loO 2.1+/-0.5 <6.8 <l. 2 N SA-WWA-5Dl Sr-89 <0.5 <0.5 <0.6 <0.5 Sr-90 <0.4 <0.4 <0.4 <0.4 K-40 <8.4 12+/-6 14+/-6 12+/-6 Ra-226 1.2+/-0.6 <l. 4 <l. 4 0.6+/-0.4 SA-WWA-3El (Control) Sr-89 <0.5 <0.5 <0.6 <0.4 Sr-90 <0.4 <0.4 <0.4 <0.4 K-40 <8.6 <9.9 <9.0 6.3+/-4.l Ra-226 <0.8 <1.3 1.3+/-0. 7 <0.7
- Sr-89 results are corrected for decay to sample stop date.
** All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-31.
(1) Collection period for station SA-WWA-2S3 was 10-16-84 to 12-10-84.
TABLE C-16 1984 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, POTASSIUM-40 AND TRITIUM IN RAW AND TREATED POTABLE WATER STATION NO. SA-PWR/T-2F3 Results in Units of pCi/L :t 2 sigma RADIOACTIVITY JANUARY FEBRUARY MARCH APRIL MAY JUNE Alpha (Raw) <1.2 3.3+/-1.6 <2. 0 <1.4 <l. 7 1.9+/-1.6 (Treated) <l.2 <1.1 <1.6 1.3+/-1.0 1. 6+/-1. 2 <1.5 Beta (Raw) 3.8+/-0.7 2.3+/-0.7 3.0:t0.6 3. 5+/-0. 7 3.1+/-0.7 3.0:t0.7 (Treated) 3.4+/-0.7 2.4+/-0.7 2.5+/-0.6 2.1+/-0.6 2.5+/-0.6 2.6+/-0.7 K-40 (Raw) 2.0:t0.2 1. 5+/-0. 2 1.4+/-0.1 1. 5+/-0. 2 1. 7+/-0. 2 1. 9+/-0. 2 CX> (Treated) 2.0+/-0.2 1. 5+/-0. 2 1.4+/-0.1 1.4+/-0.1 1.4+/-0.l 1.8+/-0.2 w H-3 (Raw) <130 <130 <130 <130 <130 <130 (Treated) <140 <130 <130 250+/-80 <120 140+/-80 RADIOACTIVITY JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE Alpha (Raw) 4.5+/-2.5 <2.6 2.2+/-1.6 <1.4 1. 5+/-1.2 1.2+/-0.8 (Treated) 1.4+/-1.2 <1.9 1.0:t0.7 <1.2 <1.0 <0.9 Beta (Raw) 2.9+/-0.7 2.2+/-0.7 1.9+/-0.6 2.4+/-0.6 2.1+/-0.6 1. 5+/-0. 7 2.6+/-1.4 (Treated) 2.5+/-0.7 1.7+/-0.6 1. 8+/-0. 6 2.6+/-0.6 2.l:t0.6 2. 7+/-0. 8 2.4+/-0.9 K-40 (Raw) 1.6+/-0.2 1.l:tO.l 1.4+/-0. l 1.2+/-0.1 1.4+/-0. l 1.4+/-0.1 1.5+/-0.5 (Treated) 1. 6+/-0. 2 1. 3+/-0.1 1. 5+/-0. 2 1.4+/-0.1 1. 5+/-0. l 1. 6+/-0. 2 1.5+/-0.4 H-3 (Raw) <130 <130 <140 140+/-80 <140 <140 (Treated) <140 <130 <140 160+/-80 <140 <140
TABLE C-17 1984 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND GAMMA EMITTERS**
.IN QUARTERLY COMPOSITES OF POTABLE WATER I
Results in Units of pCi/L +/- 2 sigma 1-01-84 4-01-84 7-01-84 10-01-84 STATION NUMBER to to to to RADIOACTIVITY 3-31-84 6-30-84 9-30-84 12-31-84 SA-PWR-2F3 (Raw) Sr-89 <0.7 <0.7 <0.9 <0.4 Sr-90 <0.6 <0.6 <0.8 0.3+/-0.1 co 1f>. K-40 <9.8 <9.1 <7.7 <5.9 SA-PWT-2F3 (Treated) Sr-89 <0.8 <0.7 <0.6 <0.4 Sr-90 <0.7 <0.6 <0.5 <0.3 K-40 <8.9 7.4+/-3.0 <8.5 <7.0
- Sr-89,results are corrected for decay .to sample stop date.
** All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-31.
\
TABLE C-18 1984 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND GAMMA EMITTERS** IN VEGETABLES Results in Units of pCi/kg (wet) +/- 2 sigma COLLECTION STATION NO. DATE(S) SAMPLE TYPE Sr-89 Sr-90 K-40 Ra-226 Th-232 SA-FPV-5Dl 8-01-84 Corn < 6.2 < 3.7 2400+/-290 <28 <81 SA-FPV-5Dl 8-01-84 Tomatoes < 3.5 3.3+/-0.9 1800+/-55 < 2.9 < 6. 6 SA-FPV-2El 5-1'3-84 Asparagus < 4.1 < 3. 0 2200+/-77 < 4.0 <11 SA-FPL-1F3 8-01-84 Cabbage < 8.3 21+/-2 2200+/-120 <11 <20 SA-FPV-1F3 8-01-84 Peppers < 3.2 < 1.8 1700+/-190 <25 <42 SA-FPV-4Fl 8-01-84 Peppers < 3.4 < 1.8 1900+/-250 <30 <51 CX> SA-FPL-4Fl 8-01-84 cabbage < 9. 9 32+/-3 2700+/-130 < 9.1 16+/-9 U1 SA-FPV-5.Fl 8-13-84 Tomatoes < 2.8 < 1.9 1900+/-56 < 1.0 < 6.5 SA-FPV-14F3 8-01-84 Corn < 8.3 < 5.0 2600+/-280 <36 <60 SA-FPV-14F3 7-31 & 8-1-84 Tomatoes < 2.8 2.7+/-0.7 2000+/-61 < 1.1 < 6. 4 SA-FPV-lGl (C) 8-01-84 Corn <20 12+/-5 3000+/-340 <44 <64 SA-FPV-lGl (C) 7-31 & 8-1-84 Peppers < 3. 8 2.7+/-1.0 1800+/-210 <17 <47 SA-FPV-lGl(C) 7-31-84 Tomatoes < 2. 9 1.8+/-0.7 1700+/-43 <13 < 4.8 SA-FPV-3H5(C) 8-01-84 Tomatoes < 4.1 < 2.4 2000+/-54 < 3.0 < 5. 2 SA-FPV-3H5(C) 8-02-84 Corn <10 < 6.1 2700+/-290 <41 <73 SA-FPV-3H5(C) 8-01-84 Peppers < 3.9 < 2.2 1700+/-210 49+/-22 <55 SA-FPL-3H5(C) 8-01-84 Cabbage < 7. 0 11+/-2 1900+/-97 <11 <17 AVERAGE 2100+/-800
- Sr-89 results are corrected for decay to sample stop date.
** All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-31.
(C) Control station
TABLE C-19 1984 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND GAMMA EMITTERS** IN GAME, MEAT AND BOVINE THYROID Results in Units of Results in Units of pCi/kg (dry) +/- 2 sigma pCi/kg (wet) +/- 2 sigma COLLECTION STATION NOo DATE(S) SAMPLE TYPE Sr-89 Sr-90 K-40 Cs-137 Ra-226 SA-GAM-llDl 1-27-84 Muskrat <100 290+/-33 2400+/-140 5.6+/-2.8 <9. 6 (Control) SA-GAM-3El 1/12-16/84 Muskrat <160 810+/-46 3000+/-180 <707 <14 co SA-FPB-3El 2-13-84 Beef (1) (1) 2500+/-150 <6. 7 9.3+/-5.7 0\ SA-THB-3El 2-13-84 Bovine Thyroid (1) (1) 1200+/-480 <39 <96 AVERAGE Muskrat 550+/-740 2700+/-850 Beef 2500+/-150 Bovine Thyroid 1200+/-480
- Sr-89 results are corrected for decay to sample stop date"
** All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-31.
(1) Strontium-89 and -90 analysis not required.
TABLE C-20 1984 CONCENTRATIONS OF GAMMA EMITTERS* IN FODDER CROPS Results in Units of pCi/kg (wet) +/- 2 sigma COLLECTION STATION NO. DATE(S) SAMPLE TYPE Be-7 K-40 Ra-226 Th-232 SA-FPG-3El 10-15-84 .Soybean <130 13000+/-530 <280 <69 SA-VGT-2F4 9-04-84 Corn Silage 380+/-79 2300+/-200 <180 <37 SA-VGT-2F4 9-17-84 Sudex Hay 400+/-60 3900+/-210 <14 <35 CX> SA-VGT-5F2 10/06-07/84 Corn Silage 410+/-92 2900+/-200 <15 <38 -...J SA-VGT-14Fl 9-05-84 Green Chop 310+/-79 2000+/-170 <140 <35 SA-VGT-l5Fl 9-04-84 Green Chop 260+/-67 4200+/-240 <18 <38 SA-VGT-15Fl 9-08-84 Hay 1400+/-190 9000+/-480 41+/-24 <88 SA-FPG-l5Fl 10-22-84 Soybean <180 13000+/-580 <46 95+/-56 SA-VGT-3Gl(C) 9-04-84 Green Chop 260+/-59 2700+/-170 <97 <27 SA-FPG-3Gl(C) 10-21-84 Soybean <160 14000+/-640 <44 <92 AVERAGE 390+/-740 6700+/-10000
- All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-31.
(C) Control station
'.l'ABLE C-21 1984 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma STATION NO. l----e4U) 2-16-84 3-06-84 4-10-84 5-11-84 6-05-84 SA-SWA-llAl <2.3 <1.7 <l. 7 4.8+/-2.7 <3.1 SA-SWA-12Cl 6.6+/-3.8 4.4+/-2.8 <l.6 <2.1 <3.6 (Control)
SA-SWA-7El <3.1 1.6+/-1.3 <1.4 <1.8 <2.9 SA-SWA-1F2 <2.3 2.8+/-1.6 <l. 7 <1.5 <2.5 SA-SWA-16Fl <3.9 3. 6+/- 2. 3 5.2+/-2.7 <l.9 <2. 0 AVERAGE 2.8+/-2.4 00 (J) STATION NO. 7-12-84 8-06-84 9-07-84 10-10-84 11-06-84 12-03-84 SA-SWA-llAl <3.0 1. 7+/-1.3 4. 2+/- 2.1 <l. 6 <2.1 < 3. 5 SA-SWA-12Cl <2.6 3.4+/-2.4 7.0+/-3.6 <1.3 <2.9 4.9+/-2.6 (Control) SA-SWA-7El <2.2 2 .1+/-1. 3 <2.1 <l. 8 <L8 <3.4 SA-SWA-1F2 <2.6 <1.6 <2.1 <1.4 <2.1 2.2+/-1.6 SA-SWA-16Fl <2.8 <1.7 <3.6 2.1+/-1.5 <2.3 4.0+/-3.0 AVERAGE 2.1+/-1.3 Grand Average 3.6+/-2.0 (1) Unable to collect January sample due to icing conditions on the river.
TABLE C-22 1984 CONCENTRATIONS OF GROSS BETA EMITTERS IN SURFACE WATE!R Results in Units of pCi/L :t 2 sigma STATION NO. 1----84 (1) 2-16-84 3-06-84 4-10-84 5-11-84 6-05-84 SA-SWA-llAl 50+/-6 14+/-3 11+/-2 14+/-3 12+/-3 SA-SWA-12Cl 49+/-5 18+/-3 9.2+/-2.3 6.3+/-2.4 4.3+/-2.0 (Control) SA-SWA-7El 46+/-6 35+/-5 25+/-4 18+/-4 8.3+/-2.4 SA-SWA-1F2 22+/-4 6. 2+/-2. 4 5.3+/-1.9 3.6+/-2.2 3.2+/-1. 9 SA-SWA-16Fl 24+/-4 6.6+/-2.4 8. 8+/-2.3 <3.0 3. 7+/-1. 9 AVERAGE 38+/-28 16+/-24 12+/-15 9. 0+/-13 6. 3+/- 7. 5 CD \0 STATION NO. 7-12-84 8-06-84 9-07-84 10-10-84 11-06-84 12-03-84 AVERAGE SA-SWA"".'llAl 12+/-3 22+/-4 98+/-9 74+/-10 110+/-10 110+/-10 48+/-84 SA-SWA-12Cl 7.0+/-2.2 30+/-5 64+/-7 58+/-8 88+/-9 73+/-8 37+/-61 (Control) SA-SWA-7El 32+/-4 38+/-5 98+/-10 104+/-12 140+/-12 84+/-10 57+/-85 SA-SWA-1F2 3.8+/-1.9 9.9+/-2.9 43+/-6 58+/-8 66+/-7 52+/-6 25+/- 50 SA-SWA-16Fl 4.4+/-1.9 19+/-4 48+/-6 54+/-8 81+/-8 72+/-8 29+/-58 AVERAGE 12+/-23 24+/-21 70+/-53 70+/-41 97+/-58 78+/-42 Grand Average 39+/-71 (1) Unable to collect January sample due to icing conditions on the river.
TABLE C-23 1984 CONCENTRATIONS .OF TRITIUM IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma STATION NO. l----04U) 2-16-84 3-06-84 4-10-84 5-11-84 6-05-84 SA-SWA-llAl 130+/-80 150+/-80 <130 <130 <120 SA-SWA-12Cl <130 <130 <130 <130 <140 (Control} SA-SWA-7El <130 <130 <130 <130 <130 SA-SWA-1F2 <130 <130 <130 190+/-80 <130 \0 0 SA-SWA-16Fl <130 <130 <130 <120 . <140 STA'l'ION NO. 7-12-84 8-06-84 9-07-84 10-10-84 11-06-84 12-03-84 SA-SWA-llAl <140 160+/-80 <130 140+/-80 <130 180+/-80 SA-SWA-12Cl 140+/-80 <140 130+/-80 <130 <140 <140 (Control) SA-SWA-7El <130 130+/-80 <130 <140 <130 <130 SA-SWA-1F2 250+/-80 <140 150+/-80 <140 <130 <130 SA-SWA-16Fl <140 <140 <140 <130 <130 <140 (1) Unable to collect January sample due to icing ~onditions on the river.
TABLE C-24 1984 CONCENTRATIONS OF STRONTIUM-89* AND -90 IN SURFACE WJ~TER Results in Units of ~Ci/L +/-. 2 sigma 2-16-84** 4-10-84 7-12-84 10-10-84 STATION NO. to to to to 3-06-84 6-05-84 9-07-84 12-03-84 Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 SA-SWA-llAl <0.9 <0.6 <0.6 <0. 5 <L2 <0. 5 <0. 5 <0 .4 SA-SWA-12Cl <1.0 <0.7 <0.6 <0.5 <1.4 <0.6 <0.6 <0. 5 (Control) l.O I-' SA-SWA-7El <0.8 <0.6 <0.6 <O. 4 <0.8 <0. 4 <0.5 <0.4 SA-SWA-1F2 <0.6 <0.5 <0.6 <0.5 <0.8 <0.5 <0. 5 <0. 4 SA-SWA-16Fl <0.6 <0.5 <0.6 <0.5 1.3+/-0.4 <0.5 <0.6 <0.5
- Sr-89 results are corrected for decay to sample stop date.
** Unable to collect January sample due to icing conditions on the river.
TABLE C-25 1984 CONCENTRATIONS OF GAMMA EMITTERS* IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma STATION NO. NUCLIDE i----041 1 > 2-16-84 3-06-84 4-10-84 5-11-84 6-05-84 SA-SWA-llAl K-40 53+/-8 21+/-6 11+/-5 14+/-6 14+/-5 Mn-54 <0.6 <0.5 0.7+/-0.3 <0.5 <0.5 co-60 <0.6 <0.6 <0.6 <0.8 <0.7 Cs-137 <0.6 <0.5 <0.6 <0.5 <0.5 La-140 <2.9 <l.4 <0.9 <0.9 <1.3 Ra-226 <11 <l.0 <1.0 <1.0 <1.0 Th-232 <1.8 <1.9 2.1+/-1.l <2. 4 1.4+/-0.8 SA-SWA-12Cl K-40 39+/-8 16+/-7 <8.1 <7.1 <8.8 (Control) Mn-54 <0.5 <0.6 <0.5 <0.5 <0.4 Co-60 <0.6 <0.6 <0.6 <0.5 <0.7 Cs-137 <0.6 <0.3 <0.4 <0.5 <0.4 La-140 <1.2 <0.8 <1.4 <0.6 <1.1 Ra-226 <!. 2 l.3+/-0.6 <l. 2 <0.8 <8.2 Th-232 <1.9 <l. 9 1.9+/-1.0 <!. 7 <2.3 SA-SWA-7El K-40 88+/-9 47+/-9 28+/-7 20+/-6 <9.3 \0 Mn-54 <0.6 <0.5 <0.6 <0.3 <0.5 N co-60 <0.7 0.6+/-0.4 <0.7 <0.5 <0.6 Cs-137 <0.6 <0.6 <0.4 <0.5 <0.3 La-140 <2.1 <2.3 <l. 3 <0. 5 <l. 7 Ra-226 <13 0.9+/-0.6 <l. 0 <1.1 <1.2 Th-232 <3.1 <1.6 <2.4 <l. 7 <l. 7 SA-SWA-1F2 K-40 31+/-7 <8.3 <6.7 <10 <9.6 Mn-54 <0.4 <0.4 <0.4 <0.6 <0.4 Co-60 <0.7 <0.2 <0.5 <0.8 <0.5 Cs-137 <0.4 <0.5 <0.5 <0.6 <0.4 La-140 <1.1 <2.1 <1.6 <1.0 <0.6 Ra-226 <9.1 <0.9 1.1+/-0.6 <1.2 <8.2 Th-232 <2.3 <1.3 <1.6 <2.3 <2.2 SA-SWA-16Fl K-40 23+/-7 <11 9.7+/-5.4 <8.7 <10 Mn-54 <0.7 <0.5 <0.5 <0.4 <0.6 co-60 <0.7 <0.5 <0.6 <0.7 <0.4 cs-137 <0.9 <0.6 <0.5 <0.4 <0.6 La-140 <3.2 <1.0 <l. 2 <0.3 <l. 7 Ra-226 <1.2 <1.1 0.8+/-0.4 <1.0 <1.1 Th-232 <2.4 <2.2 0.9+/-0.6 <2.0 <2.0 AVERAGE K-40 47+/-51 21+/-31 13+/-17
TABLE C-25 (cont'd) 1984 CONCENTRATIONS OF GAMMA EMITTERS* IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma STATION NO. NUCLIDE 7-12-84 8-06-84 9-07-84 10-10-84 11-06-84 12-03-84 AVERAGE SA-SWA-llAl K-40 19+/-4 47!6 87+/-9 130+/-10 120+/-11 120+/-12 58+/-96 Mn-54 <0.5 <0.5 <0.3 <0.4 <0.5 <0.6 co-60 <0.6 <0.6 <0.3 <0.7 <0.8 <0.4 Cs-137 <0.5 <0.5 <0.6 <0.6 <0.7 <0.5 La-140 <0.7 <l. 3 1.2+/-0.6 <0.4 <1.0 <1.4 Ra-226 <0.5 <0.5 <8.6 <9.0 1.2+/-0.7 <1.3 Th-232 <1.9 <1.9 <2.3 <l. 9 <2.8 <2.2 SA-SWA-12Cl K-40 <10 29+/-7 65+/-9 82+/-9 110+/-10 76+/-9 41+/-73 (Control) Mn-54 <0.4 <0.6 <0.6 <0.6 <0.5 <0.5 co-60 <0.4 <0.9 <0.5 <0.9 <0. 7 <0.7 cs-137 <0.5 <0.6 0.5!0.3 <0.6 <0.5 <0.5 La-140 <1.2 <l. 0 <1.1 <l. 2 <l. 3 <0.8 Ra-226 <1.3 <12 <9.8 <l. 3 1.0+/-0.4 <l. 3 Th-232 <l.5 <3.0 <2.0 <2.0 1.2+/-0. 7 <1.9 SA-SWA-7El K-40 42+/-6 56+/-9 110+/-10 81+/-10 140+/-12 130+/-9 68+/-89 ID Mn-54 <0.5 <0.6 <0.6 <0.6 <0.4 <0.5 w Co-60 <0.7 <0.6 <0.7 <0.5 <0.7 <0.6 cs-137 <0.5 <0.5 <0.6 <0.5 <0.3 <0.4 La-140 <1. 3 <l. l <0.4 <l. l <0.9 <0.7 Ra-226 <0.5 <1.2 <l. 2 <1.1 1.5+/-0. 7 <0.5 Th-232 <1.9 <2.0 <2.0 <2.3 <2.0 <l. 6 SA-SWA-1F2 K-40 <9.5 21+/-5 58+/-9 86+/-10 86+/-9 59+/-8 35+/-63 Mn-54 <0.4 <0.6 <0.3 <0.5 <0.3 <0.5 co-60 <0.6 <0.6 <0.6 <0.7 <0.2 <0.7 Cs-137 <0.5 <0.5 <0.4 <0.5 <0.6 <0.5 La-140 <0.8 <l. l <0.9 <l. 3 <l. 2 <0.7 Ra-226 <l.2 <0.5 <l. 2 <1.0 <l. l <1.0 Th-232 2.1+/-1.3 <l. 9 <l. 9 <l. 9 2.0+/-1.2 <l.9 SA-SWA-16Fl K-40 <12 24+/-7 55+/-8 84+/-10* 84+/-10 79+/-7 36+/-65 Mn-54 <0.5 <0.5 <0.5 <0.6 <0.4 <0.5 Co-60 <0.5 <0.6 <0.7 <0.7 <0.6 <0.6 cs-137 <0.8 <0.5 <0.5 <0.5 <0.6 <0.4 La-140 <1.0 <0.9 <1.1 <l.0 <1.0 <0.6 Ra-226 <l. 4 <1.1 <1.0 0.6+/-0.3 <l.0 <0.5 Th-232 <2.2 <2.2 <l. 9 <l. 9 <l. 8 <l. 6 AVERAGE K-40 35+/-31 75+/-46 93+/-42 108+/-47 93+/-61 Grand Average K-40 48+/-80
- All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-31.
( l) Unable to collect January sample due to icing conditions on the river.
TABLE C-26 1984 CONCENTRATIONS OF STRONTIUM~89* AND -90 AND TRITIUM IN EDIBLE FISH TRITIUM (FLESH)** STRONTIUM (BONES) AQUEOUS FRACTION ORGANIC FRACTION pCi/kg * (dry) :t 2 sigma pCi/kg (wet) :t 2 sigma STATION NOo COLLECTION PERIOD Sr-89 Sr-90 H-3 H-3 SA-ESF-llAl 6-04-84 to 6-11-84 <190 730+/-57 <50 <100 9-04-84 to 10-29-84 <67: 210+/-20 400+/-100 <50 SA-ESF-12Cl 6-08-84 to 6-25-84 <140 1000+/-50 <50 <100 (Control) 9-09~84 to 10-18-84 <120 230+/- 31 300+/-100 120+/-50 SA-ESF-7El 6-21-84 to 6-22-84 <38 <50 <100 9-09-84 to 10-18-84 62+/-10 400+/-100 <50 AVERAGE 380+/-790
- Sr-89 results are corrected for decay to sample'stop date"
- Tritium results by Controls for Environmental Pollution, Inc.
TABLE C-27 1984 CONCENTRATIONS OF GAMMA EMITTERS* IN EDIBLE FISH Results in Units of pci/kg (wet) +/- 2 sigma STATION NO. COLLECTION PERIOD K-40 cs-137 SA-ESF-llAl 06-04-84 to 06-11-84 2600+/-220 16+/-8 09-04-84 to 10-29-84 1200+/-110 < 6.2 SA-ESF-12Cl 06-08-84 to 06-25-84 2400+/-240 <13 (Control) 09-09-84 to 10-18-84 1400+/-110 < 6.6 SA-ESF-7El 06-21-84 to 06-22-84 3300+/-230 <14 09-09-84 to 10-18-84 3300+/-230 <13 AVERAGE 2400+/-1800
- All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-31.
TABLE C-28 1984 CONCENTRATIONS OF STRONTIUM-89* AND -90p GAMMA EMITTERS** AND TRITIUM IN BLUE CRABS Results in Units of pCi/kg (wet) +/- 2 sigma COLLECTION AQUEOUS FRACTION STATION NO. PERIOD SAMPLE Sr-89 Sr-90 K-40 Co-60 H-3*** SA-ECH-llAl 6/18-19/84 Flesh <57 <26 2100+/-340 <28 <50 Shell (1) <110 620+/-40 (2) (2) (2) 10/25-26/84 Flesh <46 <28 2300+/-230 24+/-12 600+/-300 Shell (l) <89 580+/-29 (2) (2) (2) '° 0\ SA-ECH-12Cl 6/18-19/84 Flesh <59 <28 1900+/-300 <27 <50 (Control) Shell (1) <120 860+/-46 (2) ' (2) (2) 10/22-23/84 Flesh <49 <28 2000+/-200 <16 300+/-100 Shell (1) <88 390+/-27 (2) (2) (2) AVERAGE Flesh 2100+/-340 Shell 610+/-390
- 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-3lo *** Tritium results by Controls for Environmental Pollution, Inc.
(1) Strontium results in units of pCi/kg (dry). (2) Gamma ancf tritium analysis not required.
TABLE C-29 1984 CONCENTRATIONS OF SR-89* AND -90 AND GAMMA EMITTERS** IN BENTHIC ORGANISMS Results in Units of pCi/kg (dry) +/- 2 sigma COLLECTION STATION NO. DATE Sr-89 Sr-90 Ra-226 SA-ESB-llAl 5-21-84 <7900 <5100' <43000 10-17-84 <9400 <5600 23000 +/-140 oo* SA-ESB-12Cl 5-21-84 <2600 <1800 <24000 \0 ...J (Control) 10-17-84 <13000 <8000 <42000 SA-ESB-7El 5-21-84 <3400 <2100 <-51000 10-17-84 <7800 <4600 <40000 SA-ESB-16Fl 5-21-84 <8800 . <6000 <66000 10-17-84 <14000 <8700 <47000 NOTE: Analyses performed on benthic organisms have extremely high uncertainties and sensitivities due to the unavailability of an adequate sample. Sample sizes ranged from approximately 0.1 grams to 0.25 grams dry.
- Sr-89 results are corrected for decay to sample stop date.
** All other gamma emitters searched for were <LLD; typical LLDs are given in Table c-31.
TABLE C-30 1984 CONCENTRATIONS OF STRONTIUM-90 AND GAMMA EMITTERS* IN SEDIMENT** Results in Units of pCi/kg (dry) :!: 2 sigma STATION NO. DATE sr-90 Be-7 K-40 Mn-54 Co-58 Co-60 cs-137 Ra-226 Th-232 SA-ESS-llAl 5-21-84 <32 1300+/-220 15000+/-600 87+/-22 300+/-30 520:!:29 180+/-30 890+/-370 750+/-100 10-17-84 <22 <140 4700+/-300 <17 73+/-15 180+/-16 <20 430+/-210 340+/-53 SA-ESS-12Cl (Control) 5-21-84 <30 <230 12000+/-490 25+/-15 <29 40+/-14 32+/-17 1200+/-320 770:!:82 10-17-84 <21 <180 14000+/-530 <22 <22 <32 19+/-11 790+/-240 920+/-72 l.O co SA-ESS-7El 5-21-84 <39 <180 10000+/-450 22+/-13 <26 53+/-20 35+/-19 1300+/-300 980+/-81 10-17-84 <19 <160 11000+/-470 <20 <22 22+/-13 26+/-10 980+/-210 520+/-59 SA-ESS-16Fl 5-21-84 <35 330+/-.200 15000+/-590 <31 <30 69+/-18 150+/-24 910+/-360 960+/-92 10-17-84 <25 1000+/-140 15000+/-520 32+/-18 100+/-20 260+/-21 150+/-23 790+/-310 900+/-82 AVERAGE 12000+/-7100 150+/-340 76+/-140 910+/-530 770+/-460
- 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.
TABLE t-31 1984 PSE&G RESEARCH CORPORATION LLDs FOR GAMMA SPECTROMETRY WELL/POTABLE FOOD MEAT AND FODDER AIR PARTICULATES PRECIPITATION MILK WATER PRODUCTS GAME CROPS (pCi/L) (pCi/L) (pCi/L) (pCi/kg-wet) (pCi/kg-wet) (pCi/kg-wetJ NUCLJDES 110-3pci/m3l 13 Filters lOOml 3.5 Lit~r lOOml lOOml 400ml lOOml lOOml GEOMETRY: 4.3 14 4.0 B.O 120 43 78 Be-7 3.0 0.54 0.62 1.8 0.50 1. 2 15 6.0 10 Na-22 K-40 2.8 5.2 12 4.6 9.5 140 54 100 cr-51 0.51 1.4 0.41 1.0 14 5.0 8.5 Mn-54 0.38 Co-58 0.39 0.52 1. 6 0.43 0.99 15 5.0 9.3 1.2 3.2 1.1 2.4 32 12 23 Fe-59 0.83 co-60 0.46 0.57 2.0 0.52 1.1 16 5.5 9.4 0.86 1.0 3.3 0.93 2.0 31 10 17 Zn-65 0.43 0.59 1. 7 0.53 1.1 16 6.0 11 Nb-95 0.93 2.0 28 10 19 \0 Zr-95 o. 71 l.0 3.0 \0 12 55 20 48 51 1300 990 6800 Mo-99 0.39 0.57 1.4 0.50 1. 0 16 5.7 11 Ru-103 Ru-106 4.0 4.9 14 4.4 10 130 47 Bl 0.67 0.82 l. 5 0.72 1. 6 14 8.0 14 Ag-110m Sb-125 0.90 l. 4 4.1 1. 2 2.6 39 13 22 22 63 19 40 620 220 410 Te-129m 14 I-131 0.46 1.1 1. 8 1. 0 1. 7 30 13 37 3.8 2.1 3.4 3.9 99 62 340 Te-132 0.89 Cs-134 0.51 0.65 1. 7 0.56 1. 3 13 6.3 11 0.49 0.78 1. 9 0.70 1. 3 22 8.5 20 Cs-136 0.35 0.50 1. 7 0.43 1.0 17 4.8 B.O Cs-137 3.0 6.2 2.7 5.0 82 33 76 Ba-140 1.6 La-140 0.73 1. 3 2.3 1.1 2.2 32 14 83 0.65 2.4 0.59 1. 2 19 6.7 13 ce-141 0.42 Ce-144 1.4 2.1 10 1. 7 4.1 79 20 35 0.86 1.2 4.0 1.0 2.2 32 11 19 Ra-226 Th-232 1. 7 2.0 6.8 1. B 3.B 54 19 33 __ _ _ J
TABLE C-31 (cont'd) 1984 PSE&G RESEARCH CORPORATION LLDs FOR GAMMA SPECTROMETRY SURFACE FISH SHELLFISH SEDIMENT AIR WA'l'ER IODINE NUCLIDES (pCi/L) (pCi/kg-wet) (pCi/kg-wet) (pCi/kg-dry) NUCLIDES (10-3pCi/m3) GEOMETRY: lOOml lOOml 400ml lOOml 400ml lOOml lOOml Be-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 F'e-59 1. 2 10 24 41 22 36 Co-60 0.54 5.0 11 19 11 15 Zn-65 0.99 9.0 22 35 22 25 Nb-95 0.58 5.0 12 19 10 15 I-' 0 Zr-95 1.0 8.8 21 35 20 26 0 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-llOm 0.79 7.2 11 28 10 19 Sb-125 1. 3 12 27 46 27 28
'l'e-129m 21 183 480 720 430 600 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 lla-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 analyzed.
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 1984 Artificial Island Radiological Environmental Monitoring Program samples. TABLE OF CONTENTS LAB* PROCEDURE DESCRIPTION PAGE GROSS ALPHA PSE&G Analysis of Air Particulates . . . . . . . . * . . . . . . . . . . . 105 TI Analysis of Air Particulates . . . . . . . . . . . . . . . . . . . . 107 PSE&G An a 1 y sis of water o ********** Cl fl ****************** 108 GROSS BETA PSE&G Analysis of Air Particulates . . . . . . . . . . . . . . . . . . . . 109 TI Analysis of Air Particulates . . . . . . . . . . . . . . . . . . . . 111 PSE&G An a 1 y s is of water .... ., . o o
- Q o o o "
- o *
- o Cl o o o o o o o o c o o 112 POTASSIUM-40 PSE&G Analysis of Water o o o . o Clo" o o . o * *
- o . o . , . o . o o o ** e o ** 113 TRITIUM PSE&G An a 1 y s is of water ......... o **** " * * ., * * * * * * * * * * * *
- 114 CEP Analysis of Aqueous Fraction of Fish and Crab *.. 115 CEP Analysis of Organic Fraction of Fish and Crab **. 116 IODINE-131 PSE&G Analysis of Filtered Air .*.*.*..*.*.***********. 117 TI Analysis of Filtered Air .*..*.****......*....... 118 PSE&G Analysis of Raw Milk *..*.......*......**.*...*.* 119 PSE&G Analysis of Bovine Thyroid **.*.**.****.*.*.***.. 121 103
SYNOPSIS OF ANALYTICAL PROCEDURES (cont'd) TABLE OF CONTENTS LAB* PROCEDURE DESCRIPTION PAGE STRONTIUM-89 AND -90 PSE&G Analysis of Air Particulates ******************** 122 TI Analysis of Air Particulates *****************.** 125 PSE&G Analysis of Raw Milk ... D *** Cl ** 0. Cl 0. 0 Q ** 0. 0 ** Cil *** 127 PSE&G Analysis of Water **...*.**.**. eoci*o********o**** 130 PSE&G Analysis of Vegetation, .Meat and Aquatic Samples 133 PSE&G Analysis of Bone and Shell .... o .- * * * * * * * * *
- o e **** 136 PSE&G Analysis of Soil and Sediment . . . . . . . . . Cl ********* 139 PSE&G Analysis of Samples for Stable Strontium .*.**... 142 GAMMA SPECTROMETRY PSE&G Analysis of Air Particulates .*.*.****.*******.** 144 TI Analysis of Air Particulates .. DCICIOOO*o*oeoooci*ee 145 PSE&G Analysis of Raw Milk* e e o * * * * *
- m *Clo o e e D c
- e o e Cl* c
- e 146 PSE&G Analysis of Water * *.*** G *** Cl ** Q e 0 0 e Q
- 0
- 0 Cil Q
- e
- Cl Cl
- 147 PSE&G Analysis of Solids (combined procedures) ***.*.** 148 ENVIRONMENTAL DOSIMETRY TI Analysis of Thermoluminescent Dosimeters ..****** 150
- PSE&G = PSE&G Research Corporation TI - Teledyne Isotopes CEP - Controls for Environmental Pollution, Inc.
104
SYNOPSIS 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 alphac;tctivity on a low back-ground gas proportional counter. Along with a set of air particulate samples, a clean air filter is included as a blank with an 241 Arn 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 into account the air pressure correction ~ue to the vacuum being drawn! the correction factor of the temperature-corrected gas meter as well as the gas meter efficiency itself. Calculation of Gross Alpha Activity: 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 atmospher.ic 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 (= % efficiency /100) v = Corrected air flow, m3 p = Pressure correction factor Using these corrected air flows, the gross alpha activity is computed as follows: Result (pCi/m3) = (G-B)/T (2.22) * (E) * (V) G = Sample gross counts B = Background counts (from blank filter) T = Count time of sample and blank, mins. E = Fractional 241Arn counting efficiency v = Corrected air flow of sample, m3 2.22 = No. of dpm per pCi 105
2-sigma error (pCi/m3) (l.96*(G+B)l/2)*A (G-B) A = Gross alpha activity, pCi/m3 G = Sample gross counts B = Background counts (from blank filter) Calculation of lower limit of detection: A sample activity is assumed to be LLD if the sample net count is less than 4.66 times the standard deviation of the count on the blank. LLD(pCi/m3) = 4.66 * (B)l/2 (2.22)*(E)*(V)*(T) B = Background counts (from blank filter) E = Fractional 24 1Am counting efficiency v = Corrected air flow of sample, m3 T = Count time of blank, mins. 106
S.YNOPSIS OF TELEDYNE 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 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~
, '2 A = (G/T -B) +/- crm*((G/T +B)/T)~/
( 2. 22*V*Y*D*E) (2.22*V*Y*D*E) Where G = Total sample counts B = Background counts per minute T = Sample count time, minso 2.22 = dpm/pCi v = Sample volume, m3 y = Chemical yield (Y = 1 in this case) D = Decay factor from collection to count date (D =1 in this case) E = Counter efficiency crm = Multiples of counting error If the net activity (G/T -B) is equal to or less than the counting error, then the activity is considered to be the min.imum detectable level, or MDL. where MDL= 3*(2*B/T)l/2 (2.22*V*Y*D*E) Variables are as previously defined 107
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE GROSS ALPHA ANALYSIS OF WATER SAMPLES The sample is thoroughly mixed. Then, a 250ml portion of sample and an equal volume of deionized water blank are acidified with dilute sulfuric acid. Barium carrier is added and the sample heated to S0°C in order to help precipitate bari~m 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 238 u source of the same geometry. The blank is treated in the same manner as the sample. Calculation of Gross Alpha Activity: Result (pCi/L) = (G-B)/T (2.22)*(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) = (l.96*(G+B)l/2)*A (G-B) A = Gross alpha activity, pCi/L G = Sample gross counts B = Background counts (from blank sample)
SYNOPSIS 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 bf air particulate samples 6 a clean air filter is included as a blank with an 90 sr air filter.geometry beta counting standard. The gross beta activity is computed on the basis of total corrected air flow 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 (= % efficiency /100) v = Corrected air flow, m3 p = Pressure correction factor Using these corrected air flows, the gross beta activity is computed as followsg Result (pCi/m3) = (G-B)/T (2.22) * (E) * (V) G = Sample gross counts B = Background counts (from blank filter) T = Count time of sample and bla_nk, mins. E = Fractional 90sr counting efficiency v = Corrected air flow of sample, m3 2.22 = No. of dpm per pCi 109
2-sigrna error (pCi/rn3) = (l.96*(G+B)l/2)*A (G-B) A Gross beta activity, pCi/m3 G Sample gross counts B = Background counts (from blank filter) Calculation of lower limit of detection: A sample activity is assumed to be LLD if the sample net count is less than 4.66 times the standard deviation of the count on the blank. LLD(pCi/m3) = 4.66 * (B) 1 / 2 (2.22)*(E)*(V)*(T) B = Background counts (from blank filter) E = Fractional 90sr counting efficiency v = Corrected air flow of sample, m3 T = Count time of blank, mins. 110
SYNOPSIS OF TELEDYNE 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-thorpn 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/m3) are computed as follows: A = (G/T -B) +/- crm*((G/T +B)/T)l/2 ( 2. 2 2*V*Y*D*E) (2.22*V*Y*D*E) Where G = Total sample counts B = Background counts per minute T = Sample count time, mins. 2.22 = dpm/pCi v = Sample volume, m3 y = Chemical yield (Y = 1 in this case) D = Decay factor from collection to count date (D = 1 in this case) E = Counter efficiency crm = Multiples of counting error If the net activity (G/T -B) is equal to or less than the counting error, then the activity is considered to be the minimum detectable level, or MDL. where MDL= 3*(2*B/T)l/2 (2.22*V*Y*D*E) Variables are as previously defined 111
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE GROSS BETA ANALYSIS OF WATER SAMPLES The sample is mixed thoroughly. Then, a 1.0 liter portion is removed from 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 planchets 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 geometry. 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 dpm per pCi 2-sigma error (pCi/L) = (l.96*(G+B)l/2)*A (G-B) A = Gross beta activity, pCi/L G ~ Sample gross counts B = Background counts (from blank sample) 112
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE ANALYSIS OF WATER POR POTASSIUM 40 Water samples (with the exception of rain water) received by the Research and Testing Laboratory are routinely analyzed for potassium by the Chemical Division. The results, reported in parts per million (ppm), are converted to pCi/L by means of a computer program. Calculation of 40K Activity: 40K Activity (pCi/L) = 0.85*C Oo85 = Proportionality constant for converting ppm to pCi/L C = Potassium concentration, ppm 113
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE ANALYSIS OF WATER FOR TRITIU~ Approximately 50ml of raw sample is mixed with sodium hydroxide and potassium permanganate and is distilled under vacuum. Eight ml of distilled sample is mixed with lOml of Instagel~ liquid scintillation solution, and placed in the liquid scintillation spectrometer for counting. An internal standard is prepared by mixing eight ml of sample, 10 ml of Instagel, and O.lml of a standard with known activity. The efficiency is determined from this. Also prepared is a blank consisting1of eight ml of distilled low-tritiated water and lOml of Instagel, to be used for a background determination. This is done for each pair of samples to be counted. Activity is computed as follows: A (pCi/L) = (G-B)*(lOOO) 2.22*(E)*(V)*(T) A = Activity B = Background count of sample G = Gross count of sample E = Counting Efficiency V = Aliquot volume (ml) T = Count time (min) 2.22 = DPM/pCi 1000 = Number of ml per L 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 95% confidence limit, as follows: l.96*(G/T2+B/T2)1/2*(1000) 2.22*(V)*(E) Samples are designated LLD if the activity is less than the following valueg LLD (pCi/L) = (4.66)*(B)l/2*(1000) 2.22*(V)*(E)*(T) 114
SYNOPSIS OF CONTROLS FOR ENVIRONMENTAL POLLUTION, INC., PROCEDURE TRITIUM ANALYSIS OF AQUEOUS FRACTION OF BIOLOGICAL MATERIALS An aliquot of fish or crab flesh is placed in a round bottom flask, along with 200 ml of benzene, and the water removed via azeotropic distillation. Three milliliters of the extracted water is then mixed with aquasol cocktail (NEF-934 Aquasol~ cocktail, manufactured by New England Nuclear Corpora-tion). - The resultant mixture is comprised of nineteen percent sample in a clear gel-type aquasol and provides a tritium counting efficiency of approximately thirty percent, when counted on a Beckman LS-100 Liquid Scintillation Spec-trometer. The efficiency of the counting system is determined by placing six 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. 115
SYNOPSIS OF CONTROLS FOR ENVIRONMENTAL POLLUTION, INC., PROCEDURE TRITIUM ANALYSIS OF ORGANIC FRACTION OF BIOLOGICAL ~..ATERIALS An aliquot of fish or crab is first oxidized by heating in the presence of oxygen, with the off-gas passing over heated copper oxide. The resulting converted water is then mixed with aquasol cocktail (NEF-934 Aquasol<E>cock-tailv manufactured by New England Nuclear Corporation)o The resultant mixture is comprised of nineteen percent sample in a clear gel-type aquasol and provides a tritium counting efficiency of approximately thirty percent when counted on a Beckman LS-100 Liquid Scintillation Spectro-meter a The efficiency of the counting system is .determined by placing six tritium standards (certified by NBS) before each set of water samples to be counted. The counting 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. A second method, used to verify results, is the wet oxidation method using hydrogen peroxide and the same counting method as described aboveo 116
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE GAM.l"lA ANALYSIS OF AIR IODINE Approximately 300m 3 of air is drawn through a SOml bed of triethylenediarnine (TEDA)-impregnated charcoal granules at a rate which closely corresponds to the breathing rate of an adult male. The contents of the exposed air iodine cartridge are emptied into an aluminum sample can containing SOrnl of fresh TEDA-impregnated charcoal. The can is hermetically sealed and then counted on a gamma detector. Calculation of Gamma Activity: The following are the calculations performed for the gamma activity, 2-sigma error and LLD: Result (pCi/m3) = N*D = R (2.22)*(E)*(A)*(T)*(V) N = Net counts under photopeak D = Decay correction factor
;>..tl*EXP (At2) 1-EXP (-t..tl) tl = Acquisition live time ,
t2 = Elapsed time from sample collec-tion to start of acquisition
- >.. = 0.693/nuclide half life E = Detector efficiency A = Gamma abundance factor (no. of photons per disintegration)
T = Acquisition live time, mins. V = Sample volume, m3 2.22 = No. of dpm per pCi 2-sigma error (pCi/m3) = l.96*CGC+Bc>l/2*R N GC = Gross counts BC = Background counts All other variables are as defined earlier. The LLD (pCi/m3) = 4.66*(GC)l/2*o (2.22)*(E)*(A)*(T)*(V) 117
SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE ANALYSIS OF CHARCOAL FILTERS FOR IODINE-131 Charcoal cartridges are analyzed for I-131 using a lithium~drifted germanium detector interfaced with a 2048 channel pulse height analyzer calibrated at , 1.0 Kev per channel. Teledyne Isotopes employs one of three possible d~ta 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-11 and a Nuclear Data 6620, which perform all the above computations automatically. All resultant spectra are stored on magnetic tape. 118
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE ANALYSIS OF RAW MILK FOR IODINE-131 Stable iodine carrier is equilibrated in a 4-liter volume of raw milk before two separate batches of anion exchange resin are introduced to extract iodine. The iodine is removed from the resin and converted to free iodine. The free iodine is then extracted into carbon tetrachloride and reduced to iodide with sodium bisulfite when back-extracted into water. Then cuprous chloride is added to precipitate cuprous iodide, which is mounted on a membrane filter, sealed in a cut-down x-ray cell, vacuum dried and counted for 120 minutes on a beta-gamma coincidence system. 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 lOOml of raw milk. For each addition, the millivolt reading from the meter is plotted vs. amount of stable iodine added, using Gran's plot paper. The concentration of stable iodide in the sample can be found by plotting a line through the points and extending it to the concentration axis. 'Ihe 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 1311 Activity: 1311 Results (pCi/L) = (G-B)/T (2.22)*(E)*(V)*(Y)*(l.OS)*(H) G = Sample gross counts B = Background counts (from blank sample) T = Count time of sample and blank E = Eo*EXP(-A*M) ~ efficiency equation where Eo = counting efficiency at zero sample thickness A = Self-absorption coefficient M = sample thickness_, mg/cm2 V = Sample volume, liters Y = Chemical recovery = R Rl+R2 where R = mg of I- recovered Rl = mg of 1- carrier added R2 = mg of intrinsic stable I- measured in sample loOS = Correction factor for protein-bound iodine 119
H = J/(1-K)*EXP(L) =correction factor for 13lr decay during counting period J (0.693/8.0S)*(R/1440) R = Count time, minutes 1440 = No. of minutes per day 8.05 = Half-life of 13lr, days K = EXP(-J) L = (0.693/8.0S)*N N = Elapsed time (days) from mid~ point of collection period to beginning of ~cunt time. 120
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE ANALYSIS OF BOVINE THYROID FOR IODINE-131 The thyroid sample is first weighed and then, in combination with ethyl alcohol and 3.0ml iodine carrier, pureed in a blender in order to achieve a reasonably homogeneous sample. The contents are transferred to a sample can and additional alcohol added until the total sample volume reaches lOOml. The.can is then hermetically sealed and counted on a gamma detector. Calculation of 13lI 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 Atl*EXP(At2) 1-EXP(-Atl) tl = Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition A = 0.693/nuclide half life E = Detector efficiency A = Gamma abundance factor (no. of photons per disintegration) T = Acquisition live time, mins. V = Sample quantity, kg wet 2.22 = No. of dpm per pCi 2-sigma error (pCi/kg wet) = l.96*(GC+BC)l/2*R N GC = Gross counts BC = Background counts All other variables are as defined earlier. The LLD (pCi/kg wet) = 4.66*(GC)l/2*D (2.22)*(E)*(A)*(T)*(V) 121
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE RADIOSTRONTIUM ANALYSIS OF AIR FILTERS The air filters are placed in a small beaker and just enough fuming nitric acid is added to cover the filters. A blank, composed of the same number of clean air filters, is prepared in the same way. Stable strontium carrier is then introduced into each sample and sever~! fuming nitric acid leachings are carried out to remove the radiostrontium from the filter media. Once this is done, the resultant nitrates are dissolved in distilled water and the filter residue is filtered out. Radioactive interferences are stripped out by coprecipitation on ferric hydroxide (yttrium strip) followed by 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 89sr are both unknown quantities requiring two simultaneous equations to solve for them. calculation of 90sr Activity: 90sr Results (pCi/m3) = N4/R (2.22)*(E)*(E(l5)/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, mg/cm2 E(lS)/E' = Ratio of 90sr efficiency at thickness value of 1Smg/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 (m3) U = Chemical yield N4 = (N2 = Fl*Nl)/Wl = net counts due to 90sr only Wl = ((1 + Rl*I2) = (1 + Rl*Il)*Fl) Il =l - 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 122
2.667 = Half-life of 90y, days Rl D + E*M + F*M2 (.This is the general form of the regression equation for 90y eff'y/90sr 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 Nl = Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl= 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/m3) = 2* [<X+Y) + (.Xl +Yl) *Fl 2] 1/2* !Wl *W2 l w12 w12 (N2-Fl*Nl) Again, keeping the same variable definitions, the LLD for 90sr (pCi/m3) = 4.66*[(X+Y) + (Xl+Yl) *Fl2 1/2 W!2"" Wl Calculation of 89sr Activity:
- 89sr Results (pCi/m3) = N6/R (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U)*(F9)
= W3 S7 = G + H*M + I*M2 (This is the general form of the normalized 89sr efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.)
N6 .= Nl - N7*(1 + Rl*Il) N7 = (N2 - Fl*Nl)/Wl (This represents counts due to 90sr) E(l5)/E' = Ratio of 89sr 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.S)*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 recourit. 50.5 = Half-life of 89 sr, days All other quantities are as previously defined. The 2-sigma error for 89sr (pCi/rn3) = 2* (S82+s92)1/2 *W3 (Nl - N7*(l+Rl*Il) SS =[(X+~) + (Xl+Yl) *Fl~ 1/2 Wl Wl2 J S9 = (Xl+Yl)l/ 2 All other variables are as previously defined. Keeping the same variable definitions, the LLD for 89sr (pCi/m3) = 4.66*(582+592)1/2 124
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 is 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 9 oy ingrowth period. Centrifuging and discarding the precipitate, standardized yttrium carrier is added to the supernate and the sample is set aside for 5 to 7 days. After this period, the sample is alkalinized with ammonium hydroxide and heated in a hot water bath to form . yttrium hydroxide. After cooling, the sample is centrifuged and the supernate saved for 89 sr determination. The precipitate is dissolved with dilute nitric and hydrochloric acids, and the yttrium precipitated as oxalate using saturated ammonium oxalate solution. The yttrium oxalate is mounted on a tared paper filter, oven dried, weighed and counted on a gas proportional counter. The sample is then recounted the following day to confirm the decay of 90y. 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 80mgfcm 2 aluminum absorber to stop the 90sr beta emissions, thus allowing the 8 9sr betas to be counted alone. The 89sr activity (pCi/m3) is computed as follows: A= (G/T-Bc-Ba) +/- crm*((G/T+Bc+Ba)/T)l/2 (2.22*V*Y*D*E) (2.22*V*Y*D*E) If the net activity (G/T -B) is less than or equal to the 2cr counting error, the activity is considered MDL where MDL= 2*(2*B/T)l/2 (2.22*V*Y*D*E) where G = Total sample counts T = Sample count time, mins. Be = Background rate of counter, cpm Ba = Background addition from 90sr and ingrowth of 90y 2.22 = dpm/pCi V = Sample volume, m3 Y = Chemical yield of strontium D = 8 9sr decay factor from midpoint of collection period to counting date. E = 89 sr counting efficiency with 80 mg/cm 2 aluminum absorber am = Multiples of counting error 125
The 90 sr activity (pCi/m 3 ) is computed as follows: A= (G/T-B) +/- 0m*((G/T+B)/T)l/2 (2.22*V*Y*D*E) (2.22*V*Y*D*E) Y = Chemical 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 definedo 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)l/ 2 126
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE RADIOSTRON'I'IU1'1 ANALYSIS OF RAK MILK Stable strontium carrier is ~irst 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, calcium, magnesium and other cations. These cations are then eluted off with a TRIS-buffered 4N sodium chlorid~ 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 concentratiou of 70% nitric acid, strontium is forced out.of solution somewhat ahead of calcium. Barium chromate precipitation is then performed to remove any traces of radium and radiobarium. Strontium recrystallization is carried out to remove residual calcium which may have been coprecipitated with the initial strontium precipitation. Another recrystallization removes ingrown 90y, 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, a ain, at least 14 days later. The basis for this two-count method is that 0 9 Sr and 89 sr are both unknown quantities requiring two simultaneous equations to solve for them. calculation of 90 sr Activity: 90sr Results (pCi/L) = N4/R (2.22)*(E)*(E(l5)/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, mg/cm 2 E(l5)/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 = 90sr counting standard efficiency v c Sample quantity (liters) U c Chemical yield N4 = (N2 Fl*Nl)/Wl = net counts due to 90sr only Wl = ((1 + Rl*I2) - (1 + Rl*Il)*Fl) Il =1 - EXP ((-0.693/2.667)*tl)
!2 =1 - EXP ((-0.693/2.667)*t2) 127
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 Rl =D+ E*M + F*M 2 (This is the general form of the regression equation for 90y eff'y/90sr eff'y ratio for one particular gas proportional counter, where D, E and Fare regression coefficients.) N2 =X- Y, where X and Y are recount gross counts and background counts, respectively Nl = Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl= 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+~) + (Xl+Yl)*Fl~l/2* CWl*W2) Wl . Wl 2 j (N2-Fl*Nl) Againu keeping the same variable definitions, the LLD for 90sr (pCi/L) = 4.66"'{cx+~> + cx1+n>*Fl~1;2 Lw1 w1 2 J Calculation of 89sr Activity~ 89sr Results (pCi/L) = N6/R (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U)*(F9)
= W3 S7 ~ G + H*M + I*M2 (This is the general form of the normalized 89sr efficiency regression equation for one particular gas proportional counter where G, Hand 1 are regression coefficients.)
N6 =NI ~ N7*(1 + Rl*Il) N7 = (N2 = Fl*Nl)/Wl (This represents counts due to 90sr) 128
E(lS)/E' = Ratio of B9sr 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.S)*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. so.s = Half-life of 89sr, days All other quantities are as previously defined. The 2-sigma error for 89sr (pCi/L) = 2* (S82+s92)1/2 *W3 (Nl - N7*(l+Rl*Il) SB = ~~~~) + !~+Yl *Fl 2 1/2 S9 = (Xl+Yl)l/2 All other variables are as previously defined. Keeping the same variable definitions, the LLD for B9sr (pCi/L) = 4.66*(S82+s92)1/2 129
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE RADIOSTRONTIUM ANALYSIS OF WATER Stable strontium carrier is introduced into a water sample and into a distilled water sample of the same volume which is used as a blank. The sample(s) and blank are then made alkaline and heated to near boiling before precipitating the carbonates. The 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 b~rium 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 90 sr and 89 sr are both unknown quantities requiring two simultaneous equations to solve for them. Since surface waters, as well as some drinking water samples, have been found to contain significant amounts of stable strontium, a separate aliquot 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(l5)/E')*(S6)*(V)*(U)
= W2 where S6 =A+ B*M + C*M2 (This is the general form of the normalized 90 sr efficiency regression equation for one particular gas proportional counter, where A, B and C are regression coefficients.)
M = Thickness density of strontium carbonate precipitate, mg/cm 2 E(lS)/Ei = Ratio of 90sr efficiency at thickness value of 15mg/cm2 to 90 sr counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental st~ontium samples) E = 90sr counting standard efficiency v = Sample quantity (liters) u = Chemical yield N4 = (N2 - Fl*Nl)/Wl = net counts due to 90sr only Wl = ((l + Rl*I2) - (1 + Rl~Il)*Fl) 130
Il =l - EXP ((-0.693/2.667)*tl)
!2 =l - EXP ((-0.693/2.667)*t2) t l = Elapsed time from 90y strip to first count t2 = Elapsed time from 90y strip to second count 2.667 = Half-life of 90y, days Rl =D+ E*M + F*M2 (This is the general form of the regression equation for 90y eff'y/90sr 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 Nl = Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl= 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) + (Xl+Yl) *Flj 1/2* (Wl*W2) -~
~ Wl2 (N2-Fl*Nl)
Again, keeping the. same variable definitions, the LLD for 90sr (pCi/L) =
- 4. 66*[(X+S) + ( Xl +Yl) *Fl~ 1/2 Wl w12 J 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 89sr efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.)
N6 = Nl - N7*(1 + Rl*Il) N7 = (N2 - Fl*Nl)/Wl (This represents counts due to 90sr) 131
E(lS)/E' = Ratio of 89 sr efficiency at thickness value of 15mg/cm 2 to 90 sr counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples) F9 =EXP ((-0.693/50.S)*t) t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount. 50.5 = Half-life of 89sr, days
- All other quantities are as previously defined.
The 2-sigma error for 89sr (pCi/L) = 2* (S82+s92)1/2 *W3 (Nl - N7*(l+Rl*Il) SB = [(X+Y) + (Xl+Yl) *Fl 2 1/2 WIT Wl S9 = (Xl+Yl)l/2 All other variables are as previously defined. Keeping the same variable definitions, the LLD for 89sr (pCi/L) =
- 4. 66* csa2+s92> 112 -
132
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE RADIOSTRONTIUM ANALYSIS OF VEGETATION, MEAT AND AQUATIC SAMPLES The samples are weighed (recorded as "wet" weight) as received, before being placed in an oven to dry at 100°C. At the* completion of the drying period, samples are again weighed (recorded as "dry" weight) and then pulverized. A measured amount .(quantity dependent on desired sensitivity) of the pulverized sample is first charred over a Bunsen burner and then ashed iri 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 SOOml 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 (HN0 3 ). The resultant nitrates are heated to dryness and are dissolved in 20ml distilled water before adding 60ml fuming HN0 3
- 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: 90sr Results (pCi/kg wet) = N4/R (2.22)*(E)*(E(l5)/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, mg/cm2 E(lS)/E' = Ratio of 9os*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 wet) u = Chemical yield N4 = (N2 - Fl*Nl)/Wl = net counts due to 90sr only Wl = ((1 + Rl*I2) - (1 + Rl*Il) *Fl) 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 Rl =D + E*M + F*M2 (This is the general form of the regression equation for 90y eff'y/90sr 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 Nl = Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl =EXP ((-0.693/2.667)*t2) R = Count time of sample and blank Using the same variable definitions as above, the 2-sigma e_rror _for 90sr (pCi/kg wet) "" 2*rjx+-p + (Xl+Yl)*Fl~ 1 1 2 * (Wl*W2) LWl Wl 2 ] (N2-Fl*Nl) Again, keeping the same variable definitions, the LLD for 90sr (pCi/kg wet) = 4.66*[J~~~l + x;~n *Fl 2 1/2 Calculation of 89sr Activity: 89sr Results (pCi/kg wet) = N6/R (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U)*(F9)
= W3 S7 ~ G + B*M + I*M 2 (This is the general form of the normalized 89sr efficiency regression equation for one particular gas proportional counter where G, Hand *r are regression coefficients.)
N6 = Nl - N7*(1 + Rl*Il) N7 = (N2 - Fl*Nl)/Wl (This represents counts due to 90 sr) 134
E(l5)/E' = Ratio of 89sr efficiency at thickness value of 15mg/cm2 to 90sr counti~g 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 = Half-life of 89sr, days All other quantities are as previously defined. The 2-sigma error for B9sr (pCi/kg wet) :::; 2* (S82+s92)1/2 *W3 (Nl - N7*(l+Rl*Il) sa = Dx+Y) + (Xl+Yl) *Fl~ 1/2 LWI7" w12 -J 59 = (Xl+Yl)l/2 All other variables are as previously defined. Keeping the same variable definitions, the LLD for 89sr (pCi/kgwet) = 4.66*(582+592)1/2 135
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE RADIOSTRONTIUM ANALYSIS OF BONE AND SHELL The bone or shell is first physically separated from the rest of the sample before being broken up and boiled in 6N sodium hydroxide (NaOH) solution for a brief time to digest remaining flesh/collagen material adhering to the sample. After multiple rinses with distilled water, the bone/shell is then oven dried and pulverized. An aliquot of the sample is removed, weighed and ashed in a muffle furnace. Then, in the presence of strontium carrier and cesium holdback carrier', the radiostrontium is leached out of the ash by 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.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: 90sr Results (pCi/kg dry) = N4/R (2.22)*(E)*(E(l5)/E')*(S6)*(V)*(U) wher.e 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, Band Care regression coefficients.) M = Thickness density of strontium carbonate precipitate, mg/cm2 E(l5)/E 1 = Ratio of 90sr efficiency at thickness value of 15mg/cm2 to 90 sr counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples) E = 90sr counting standard efficiency V = Sample quantity (kg dry) U = Chemical yield N4 ~ (N2 ~ Fl*Nl)/Wl = net counts due to 90sr only Wl = ((1 + Rl*I2) - (1 + Rl*Il)*Fl) 136
I l = 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 Rl = D + E*M + F*M2 (This is the general form of the regression equation for 90y eff'y/90sr eff'y ratio for one particular gas proportional counter, ~here D, E and F are regression coefficients.) N2 = X - Y, where X and Y are recount gross counts and background counts, respectively Nl = Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl= EXP ((-0.693/2.667)*t2) :J R = Count time of sample and blank Using the same variable definitions as above, the 2-sigma error for 90sr (pCi/kg dry) = 2* [(X+Y) + (Xl+Yl) *Fl~ 1/2* (Wl*W2)
"WIT Wl2 J (N2-Fl*Nl)
Again, keeping the same variable definitions, the LLD for 90sr (pCi/kg dry) = 4.66*f{X+Y) + (Xl+Yl)*Fl~l/2 LWIT w12 J Calculation of 89sr Activity~ 89sr Results (pCi/kg dry) = N6/R (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U)*(F9)
= W3 57 =G + H*M + I*M2 (This is the general form of the normalized 89sr efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.)
N6 = Nl - N7*(1 + Rl*Il) N7 = (N2 - Fl*Nl)/Wl (This represents counts due to 90sr) 137
E(l5)/E 1 = Ratio of 89sr 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) t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount. 50.5 = Half-life of 89sr, days All other quantities are as previously defined. The 2-sigma error for 89sr (pCi/kg dry) = 2* (S82+s92)1/2 *W3 (Nl - N7*(l+Rl*Il) ( Xl+Yi> *Fl~ 1/2 w12 J S9 = (Xl+Yl)l/ 2 All other variables are as previously defined. Keeping the same variable definitions, the LLD for 89sr (pCi/kg dry) = 4.66*(582+592)1/2 138
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE RADIOSTRONTIUM ANALYSIS OF SOIL AND.SEDIMENT After the soil or sediment sample has been dried and pulverized, a SOgm aliquot is added to approximately 1/3 - liter concentrated hydrochloric acid (HCl), containing Sml of strontium carrier (lOmg sr++;ml). A blank containing only 1/3 - liter concentrated HCl and Sml 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 carbonate added to precipitate strontium and calcium carbonate. These carbonates are first filtered and then digested with 6N HN03. Two fuming (90%) HN03 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 two-count method is that 90sr and 89sr 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(l5)/E')*(S6)*(V)*(U)
= W2 where 56 =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, Band Care regression coefficients.)
M = Thickness density of strontium carbonate precipitate, mg/cm2 E(lS)/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 = 90sr counting standard efficiency V = Sample quantity (kg dry) U = Chemical yield N4 = (N2 - Fl*Nl)/Wl = net counts due to 90 sr only Wl = ((1 + Rl*I2) - (1 + Rl*Il)*Fl) 139
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 Rl =D+ E*M + F*M2 (This is the general form of the regression equation for 90y eff'y/90sr 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 Nl = Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl= 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 dry) = _ r 2* £liD.. + (Xl+Yl) *Fl~ 1/2* (Wl*W2) L Wl 2 Wl 2 J (N2-Fl*Nl) Againo keeping the same variable definitions, the LLD for 90sr (pCi/kg dry) = 4.66*[(X+~) + (Xl+Yl)*Fl~l/2 Wl w12 j Calculation of 89sr Activity: 89sr Results (pCi/kg dry) = N6/R (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U)*(F9)
= W3 S7 = G.8 + H*M + I*M2 (This is the general form of the normalized 9sr efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.)
N6 = Nl - N7*(1 + Rl*Il) N7 = (N2 - Fl*Nl)/Wl (This represents counts due to 90sr) 140
E(lS)/E' = Ratio of 89sr 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) t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount.
50.5 = Half-life of 89sr, days All other quantities are as previously defined. The 2-sigma error for 89sr (pCi/kg dry) = 2* (sa2+592)1/2 *W3 (Nl - N7*(l+Rl*Il) sa =f"jx+~> + .lli_l+Yl> *Fl~ 1/2 Lw1 w12 J 59 = (Xl+Yl)l/ 2 All other variables are as previously defined. Keeping the same variable definitions, the LLD for 89sr (pCi/kg dry) = 4.66*(582+592)1/2 141
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE ANALYSIS OF ENVIRONMENTAL SAMPLES FOR STABLE STRONTIUM It has been the practice of the Environmental Division to perform a stable strontium determination on any samples to be analyzed for strontium 90 and 89, if they are likely to contain significant amounts of the stable isotopes. For water samples, this involves removal of a 60-rnl 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 withdraw! 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 (mg/L):ll9 Volume of specimen (ml):25 (removed from lOOOml of diluted leachate) Proportion of sample u~ed 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 =
2.98mg Sr = 119 mg 0.025 Net weight of srco 3 precipitate (mg): 125 Percent of Sr in precipitate: 59.35 Quantity of strontium recovered = (125mg) x (.5935) = 74.2 Corrected Chemical Recovery of strontium = 74.2 = 0.623 119 The calculations follow the same sequence for bone and shell samples. 142
Sample Calculation of Corrected Chemical Recovery of Strontium in Water: Reported concentrations of stable strontium (mg/L): 1.65 Volume of radiochemical water sample (liters): 2.0 Stable strontium in 2 liter sample = (l.65mg/L) x (2.0L)
= 3.30mg Quantity of strontium carrier added to sample (mg): 20.0 Total amount of strontium in sample (mg): 20.0 + 3.30 = 23.3mg Net weight of SrC03 precipitate (mg): 28.9 Percent of Sr in precipitate: 59035 Quantity of strontium recovered = (28.9mg) x (.5935) = 17.2mg Corrected Chemical Recovery of Strontium= 17.2rng = .738 23.3mg 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/m3) = N*D =R (2.22)*(E)*(A)*(T)*(V) N = Net counts under photopeak D = Decay correction factor Atl*EXP(),t2) 1-EXP(-)..tl) tl = Acquisition live time t2 = Elapsed time from sample collection to start of acquisition
>.. = 0.693/nuclide half life E = Detector efficiency A = Gamma abundance factor (no. of photons per disintegration)
T = ~cquisition live time, mins. V = Sample volume, m3 2.22 = No. of dpm per pCi 2-sigma error (pCi/m3) = l.96*CGC+BC)l/2*R N GC = Gross counts BC = Background counts All other variables are as defined earlier. The LLD (pCi/m3) = (2.22)*(E)*(A)*(T)*(V) 144
SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE ANALYSIS OF AIR PARTICULATE FILTERS FOR GAMMA Air particulate filters are analyzed for gamma using a lithium-drifted germanium detector interfaced with a 2048 channel pulse height analyzer calibrated at 1.0 Kev per channel. Teledyne Isotopes employs one of three possible data acquisition and computation systems. The first, a. Data General 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 observed, then only the background is used (along with sample volume, collec-tion date and length of count) to determine the detection limit. The activity or MDL of each nuclide is computed on an IBM 360. This semi-automatic system is in contrast with the other two data acquisition and computation systems, namely, a Tracor Northern TN-11 and Nuclear Data 6620 which perform all the above computations automatically. All resultant spectra are stored on magnetic tape. 145
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE GAMMA ANALYSIS OF RAW MILK A well mixed 3.5-liter sample of raw milk is poured into a calibrated Marinelli beaker along with 20ml of 37% formaldehyde solution (used as a preservative). After stirring, the sample is allowed to reach ambient temperature and theµ counted o~ a gamma detector for 1000 minutes. Calculation of Gamma Activity: The following are the calculations performed for the gamma activity, 2-sigma error and LLD: Result (pCi/L) = N*D = R (2.22)*(E)*(A)*(T)*(V) N = Net counts under photopeak D = Decay correction factor Atl*EXP(At2) 1-EXP(-Atl) tl = Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition A = 0.693/nuclide half life E = Detector efficiency A = Gamma abundance factor (no. of photons per disintegration) T = Acquisition live time, mins. V = Sample volume, liters 2.22 = No. of dpm per pCi 2-sigma error (pCi/L) = l.96*(GC+BC)l/2*R N GC - Gross counts BC = Background counts All other variables are as defined earlier. The LLD (pCi/L) = (2.22)*(E)*(A}*(T)*(V) 146
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE GAMMA ANALYSIS OF WATER A 4-liter sample of wat~r 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 rubb.er. 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 for~eps and the water flpws 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 lOOml mark scribed on the inside of the can. After all the sampl~ has left the jug, any salts which have crept up the inside of the can, are pushed back into the sample by means of a rubber policeman. Also, the jug and glass tube are rinsed with distilled water and the rinsing added to the can. The water level i_s then adjusted back to the lOOml level by additional evaporation. The sample is finally left to cool to room temperature before sealing the can and then counting on a gamma detector for '1000 minutes. Calculation'of Gamma Activity: The following are the calculations .performed for the gamma activity, 2-sigma error and LLD: Result (pCi/L) = N*D =. R (2.22)*(E)*(A)*(T)*(V) N = Net counts under photopeak D = Decay correction factor J..tl *EXP C:\ t 2) 1-EXP(-).tl) tl = Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition
>.. = 0.693/nuclide half life E = Detector efficiency A = Gamma abundance factor (no. of photons per disintegration)
T = Acquisition live time, mins. V = Sample volume, liters 2.22 = No. of dpm per pCi 2~sigrna error (pCi/L) ~ l.96*CGC+Bc)l/2*R N GC_= Gross counts BC ~ Background counts All other variables are as defined earlier. The LLD (pCi/L) = 4.66*(GC)l/2*o (2.22)*(E)*(A)*{T)*(V) 147
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE GAMMA ANALYSIS OF SOLIDS Several methods are employed in preparing solids for gamma analysis, depending on the type of sample or sensitivity required. For high sensitivity analysis of vegetation, meat and seafood, the sample is first weighed, then oven-dried to a constant weight. A ratio of wet-to-dry weight is computed before the sample is ground and compressed to unit density (lg/cm3) *, whenever possible, in a tared aluminum can. The can is weighed and then hermetically sealed and counted on a gamma detector. When sample size or time is limited, a wet sample can be prepared (assuming sensitivity can be met) by using a food processor to puree it. The sample is then poured into a calibrated and tared clear plastic container until a standard volume is reached. The sample is weighed and then sealed with a screw cap before gamma counting. Soil and sediment samples are first oven dried until a constant weight is achieved and then pulverized. The sample is added to a tared aluminum can, compacted to a standard volume and weighed. It is hermetically sealed and _9amma counted. Benthic organisms are oven dried, followe~ by the physical removal of any obvious impurities (such as shells or twigs). The dried organisms are weighed and then wet-ashed with concentrated nitric acid. After all solids have been digested, the sample is evaporated to near dryness and the residual salts taken up with distilled water. The sample is filtered and the filtrate added to an aluminum can. The sample volume is brought up to the standard geometry with distilled water and the can hermetically sealed before gamma counting. calculation of Gamma Activity: The following are the calculations performed for the gamma activity, 2-sigma error and LLD: Result (pCi/kg) = N*D =R (2.22)*(E)*(A)*(T)*(V) N = Net counts under photopeak D = Decay correction factor
).tl*EXP().t2) 1-EXP(-).tl) tl = Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition
- \ = 0.693/nuclide half life E = Detector efficiency A = Gamma abundance fac*tor (no. of photons per disintegration)
T = Acquisition live time, mins. v = Sample volume, liters 2.22 = No. of dpm per pCi 148
2-sigma error (pCi/kg) = l.96*(GC+Bc)l/2*R N GC = Gross counts BC = Background counts All other variables are as defined earlier. The LLD (pCi/kg) = 4.66*(GC)l/2*o (2.22)*(E)*(A)*(T)*(V) 149
SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE ANALYSIS OF TELEDYNE ISOTOPES THERMOLUMINESCENT DOSIMETERS These devices are rectangular Teflon wafers impregnated with 25% easo 4 :Dy phosphor. They are first annealed in a 250°C oven prior to exposure in the field. Following field exposure (for a 1-month or 3-month period) four separate areas of the dosimeter ate read in a Teledyne Isotopes model 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 back-ground. The results are computed as follows: For any given area of the dosimeter, the dose in mR is calculated by the following formula: DOSE= R * (REDOSE/RR)-AVC R = Initial reading of the area RR = Second reading of the area (after re-irrad~ation) REDOSE = Re-irradiation dose, mR AVC = Average of control values, mR 4N where AVC = ~CDOSE/4N i=l N = Total number of control dosi-meters CDOSE = CR*(CREDOSE/CRR) CDOSE = Control area dose, rnR 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
APPENDIX E
SUMMARY
OF USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDIES PROGRAM RESULTS 151
SUMMARY
OF USEPA INTERCOMPARISON STUDIES PROGRAM Appendix E presents a summary of the analytical results for the 1984 USEPA Environmental Radioactivity Laboratory Intercornparison 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 .* . . . . . . . . . . . . . . . . . . . . . o ***** 155 E-3 Tri ti um in Water . . . . . . . . . . . . . . . . Cl *************** 157 E-4 Iodine in water and Milk . . . . . . . . . . . . . . * . . . . . . . . . 158 E-5 Strontium~89 and -90 in Air Particulates, Milk, water and Food Products . . . . . . . . * . . . . . . . . * . . . . . 159 E-6 Radium-226 a~d -228 in water .......*.......*.... 160 153
TABLE E-1 US EPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAL'-1 Gross Alpha and Gross Beta Analysis of Water (pCi/L) and Air Particulate (pCi/filter) PSE&G PSE&G EPA GRAND AVG DATE ENV ID NUMBER MEDIUM ANALYSIS Mean +/- s.d. Mean +/- s.d. Mean +/- s.d. 1/84 EPA-WAT-AB85 Water Alpha 33+/-3 10+/-5 10+/-3 84-116 Beta 11+/-1 12+/-5 13+/-3 3/84 EPA-WAT-AB91 Water Alpha 5+/-1 5+/-5 6+/-2 84-363 Beta 18+/-1 20+/-5 20+/-3 3/84 EPA-APT-GABS92 APT Alpha 18+/-1 15+/-5 16+/-3 84-364 Beta 69+/-2 51+/-5 56+/-6 5/84 EPA-BLD-P95 Water Alpha 35+/-4 (1) (1) 84-612 Beta 119+/-2 ' (1) (1) 5/84 EPA-WAT-AB97 Water Alpha 3+/-1 3+/-5 3+/-1' 84-740 Beta 5+/-1 6+/-5 7+/-2 7/84 EPA-WAT-AB102 Water Alpha 7+/-1 6+/-5 5+/-2 84-1007 Beta 12+/-1 13+/-5 13+/-3 8/84 EPA-APT-GABS106 APT Alpha 19+/-1 17+/-5 17+/-3 84-1144 Beta 58+/-2 51+/-5 52+/-6 9/84 EPA-WAT-AB113 Water Alpha 6+/-1 5+/-5 5+/-2 84-1368 Beta 13+/-1 16+/-6 15+/-3 11/84 EPA~WAT-AB122 Water Alpha 7+/-1 7+/-5 7+/-2 84-1680 Beta 18:1:1 20+/-5 21+/-3 11/84 EPA-WAT-Pll6 Water Alpha ll:tl 14+/-5 13+/-4 84-1542 Beta 22:1:1 64+/-5 60+/-7 11/84 EPA-APT-GABS123 APT Alpha 17+/-1 (1) (1) 84-1681 Beta 63+/-1 (1) (1) (1) Results not received from EPA. 154
TABLE E-2 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Gamma Analysis of Milk, Water. (pCi/L), Air Particulate (pCi/filter) and Food Products (Pei/kg) PSE&G PSE&G EPA GRAND AVG DATE ENV ID NUMBER MEDIUM NUCLIDE Mean +/- s.d. Mean +/- s.d. Mean +/- s.d. 2/84 EPA-WAT-G87 Water Cr-51 46+/-4 40+/-5 40+/-8 84-177 Co-60 11+/-1 10+/-5 11+/-2 Zn-65 53+/-3 50+/-5 50+/-8 Ru-106 65+/-10 61+/-5 55+/-9 Cs-134 30+/-3 31+/-5 29+/-3 Cs-137 16+/-2 16+/-5 16+/-3 3/84 EPA-0RG-GS86 Food I-131 19+/-2 20+/-6 20+/-4 84-117 Cs-137 21+/-2 20+/-5 21+/-3 K (*) 2510+/-80 2720+/-140 2665+/-250 3/84 EPA-APT-GABS92 APT Cs-137 10+/-1 10+/-5 12+/-3 84-364 5/84 EPA-WAT-P95 Water Co-60 29+/-2 (1) (1) 84-612 Cs-134 30+/-2 (1) (1) Cs-137 26+/-1 (1) ( 1) 6/84 EPA-MLK-GSlOl Milk I-131 43+/-1 43+/-6 43+/-4 84-819 . Cs-137 36+/-1 35+/-5 36+/-3 K (*) 1530+/-20 1496+/-75 1560+/-97 6/84 EPA-WAT-G98 Water Cr-51 73+/-12 66+/-5 64+/-13 84-741 Co=60 32+/-3 31+/-5 31+/-4 Zn-65 66+/-5 63+/-5 63+/-9 Ru-106 34+/-7 29+/-5 30+/-11 Cs-134 44+/-2* 47+/-5 44+/-6 Cs-137 37+/-1 37+/-5 37+/-4 7/84 EPA-ORG-GS103 Food I-131 39+/-2 39+/-6 39+/-5 84-985 Cs-137 25+/-2 25+/-5 27+/-3 K.(*) 2590+/-90 2605+/-130 2571+/-229 8/84 EPA-APT-GABS106 APT CS-137 14+/-1 15+/-5 17+/-4 84-1144 155
TABLE E-2 (cont'd) USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Gamma Analysis of Milk, Water (pCi/L), Air Particulate (pCi/filter) and Food Products (Pei/kg) PSE&G PSE&G EPA GRAND AVG DATE ENV ID NUMBER MEDIUM NUCLIDE Mean +/- s.d. Mean +/- s.d. Mean +/- s.d. 10/84 EPA-WAT-Gll4 Water Cr-51 50+/-9 40+/-5 38+/-8 84-1479 Co-60 20+/-1 20+/-5 20+/-3 Zn-65 14+/-1 147+/-7 149+/-12 Ru-106 40+/-1 47+/-5 45+/-9 Cs-134 30+/-1 31+/-5 29+/-3 Cs-137 25+/-1 24+/-5 25+/-3 10/84 EPA-MLK-GS117 Milk . I-131 62+/-22 42+/-6 40+/-5 84-1579 Cs-137 31+/-2 32+/-5 32+/-3 K(*) 1265+/-16 1517+/-76 1498+/-143 11/84 EPA-WAT-Pll6 Water Co-60 16+/-1 14+/-5 16+/-2 84-1542 Cs-134 2+/-1 2+/-5 3+/-2 Cs-137 15+/-2 14+/-5 16+/-2 11/84 EPA-APT-GABS123 APT Cs-137 10+/-1 (1) (1) 84-1681 (*) Reported as mg/L of Potassium (1) Results not received from EPA. 156
TABLE E-3 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAi."1 Tritium Analysis of Water (pCi/L) PSE&G PSE&G EPA GRAND AVG DATE ENV ID NUMBER MEDIUM NUCLIDE Mean +/- s.d. Mean +/- s.d. Mean +/- s.d. 2/84 EPA-WAT-H88 Water H-3 2370+/-80 2383+/-351 2366+/-247 84-178 4/84 EPA-WAT-H94 Water H-3 3360+/-100 3508+/-364 3461+/-288 84-472 6/84 EPA-WAT-H99 Water H-3 2920+/-40 3051+/-359 3039+/-235 84-785 8/84 EPA-WAT-H105 Water H-3 2780+/-20 2817+/-356 2842+/-251 84-1029 10/84 EPA-WAT-Hll5 Water H-3 2760+/-20 2810+/-356 2814+/-213 84-1480 12/84 EPA-WAT-Hl25 Water H-3 3280+/-70 3182+/-360 3206+/-236 84-1783 157
'.rABLE E-4 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Iodine Analysis of Water and Milk (pCi/L)
PSE&G PSE&G EPA GRAND AVG DATE ENV ID NUMBER MEDIUM NUCLIDE Mean +/- s.d. Mean +/- s.d. Mean +/- s.d. 3/84 EPA-MLK-I89(**) Milk I-131 6+/-1 6+/-1 6+/-1 84-265 4/84 EPA-WAT-I93 Water I-131 6+/-1 6+/-1 6+/-2 84-426 8/84 EPA-WAT-I104 Water I-131 36+/-1 34+/-6 36+/-5 84-1028 12/84 EPA-WAT-Il24 Water I-131 ,32+/-1 36+/-6 36+/-5 84-1688 (**) Special EPA/NRC low level study 158
TABLE E-5 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Strontium-89 and -90 Analysis of Air Particulates (pCi/filter), Milk, Water (pCi/L) and Food Products (pCi/kg) PSE&G PSE&G EPA GRAND AVG DATE ENV ID NUMBER MEDIUM NUCLIDE Mean +/- s.d. Mean +/- s.d. Mean +/- s.d. 1/84 EPA-WAT-S84 Water Sr-89 41+/-1 36+/-5 36+/-9 84-94 Sr-90 24+/-1 24+/-2 23+/-3 3/84 EPA-ORG-GS86 Food Sr-89 27+/-1 34+/-5 31+/-5 84-117 Sr-90 21+/-2 20+/-5 20+/-4 3/84 EPA-APT-GABS92 APT Sr-90 18+/-1 21+/-2 19+/-2 84-364 5/84 EPA-BLD-P95 Water Sr-89 22+/-1 ( 1) ( 1) 84-612 Sr-90 26+/-1 (1) (1) 5/84 EPA-WAT-S96 Water Sr-89 24+/-2 25+/-5 24+/-4 84-683 Sr-90 4+/-1 5+/-2 5+/-1 6/84 EPA-MLK-GSlOl Milk Sr-89 LT4 25+/-5 21+/-5 84-819 Sr-90 LT2 17+/-1. 5 15+/-2 7/84 EPA-ORG-GS103 Food Sr-89 (2) 84-985 Sr-90 (2) 8/84 EPA-WAT-GABS106 APT Sr-90 16+/-1 18+/-1. 5 17+/-2 84-1144 9/84 EPA-WAT-Sl07 Water Sr-89 32+/-2 34+/-5 30+/-8 84-1174 Sr-90 17+/-1 19+/-1.5 18+/-3 10/84 EPA-MLK-GS117 Milk Sr-89 18+/-3 22+/-5 19+/-4 84-1579 Sr-90 12::t:l 16+/-1. 5 15+/-2 11/84 EPA-WAT-Pll6 Water Sr-89 10+/-2 11+/-5 11+/-4 84-1542 sr~9o 11+/-1 12+/-1. 5 13+/-3 11/84 EPA-APT-GABS123 APT Sr-90 17+/-1 (1) (1) 84-1681 (1) Results not received from EPA. (2) No analysis results due to equipment failure. 159
TABLE E-6 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Radium-226 and -228 Analysis of Water (pCi/L) PSE&G PSE&G EPA GRAND AVG DATE ENV ID NUMBER MEDIUM NUCLIDE Mean +/- s.d. Mean +/- s.d. Mean +/- s.d. 3/84 EPA-WAT-R90 Water Ra-226 5.4+/-1 4.1+/-1 3.8+/-1 84-331 Ra-228 1. 7+/-1 2.0+/-1 2.4+/-1 5/84 EPA-BLD-P95 Water Ra-226 15+/-1 (1) (1) 84-612 Ra-228 9.8+/-0.6 (1) (1) 6/84 EPA-WAT-RlOO Water Ra-226 5.5+/-0.1 3.5+/-0.5 3.5+/-0.5 84-785 Ra-228 1. 8+/-0.4 2.0+/-0.3 2 .2+/-0. 9 9/84 EPA-WAT-Rll2 Water Ra-226 (2) 84-1367 Ra-228 (2) 12/84 EPA-WAT-Rl26 Water Ra-226 (2) 84-1784 Ra-228 (2) (1) Results not received from EPA. (2) Analysis cancelled by PSE&G. 160
APPENDIX F SYNOPSIS OF DAIRY AND VEGETABLE GARDEN SURVEY 161
APPENDIX F SYNOPSIS OF 1984 MILK ANIMAL AND VEGETABLE GARDEN SURVEYS MILK ANIMAL SURVEY A survey of dairy farms conducted out to a distance of five miles from the Salem Generating Station (SGS) was performed in May and September, 1984. The results of the May survey were as follows: One dairy farm, situated 4.9 miles West of SGS was located. The results of the September survey were as follows: No change from the May survey. VEGETABLE GARDEN SURVEY A survey of vegetable gardens conducted out to a distance of one mile of the SGS was performed in September 1984. No vegetable gardens were found within this area.
. 163
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RMC-TR-83-03 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1982 RADIOLOGICAL REPORT JANUARY 1 TO DECEMBER 31, 1982 Prepared For PUBLIC SERVICE ELECTRIC AND GAS COMPANY By RADIATION MANAGEMENT CORPORATION APRIL 1983
RMC-TR-83-03 1982 RADIOLOGICAL REPORT ARTIFICaAL ISLAND RADIO~OGICAL ENVIRONMENTAL MONITORING PROGRAM January 1 to December 31, 1982 Prepared For Public Service Electric and Gas Company by Radiation Management Corporation April 1983
TABLE OF CONTENTS PAGE
SUMMARY
1 INTRODUCTION 2 THE PROGRAM 3 Objectives 3 Sample Collection 3 Data Interpretation 5 Quality Assurance Program (RMC) 6 Program Changes 6 RESULTS AND DISCUSSION 7 Airborne 7 Direct 9 Water 12 Aquatic 16 Ingestion 17 CONCLUSIONS 21 REFERENCES 22 APPENDIX A - PROGRAM
SUMMARY
25 APPENDIX B - SAMPLE DESIGNATION &LOCATIONS 33 APPENDIX C - 1982 DATA TABLES 41 APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES {_RMC) 97 APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES (PSE&G) 115 APPENDIX E -
SUMMARY
OF INTERLABORATORY COMPARISONS 133 APPENDIX F - SYNOPSIS OF DAIRY AND VEGETABLE GARDEN SURVEY 141
LIST OF FIGURES NUMBER PAGE
- 1. Comparison of Average Concentrations of Beta Emitters in Precipitation and in Air Particulates, 1973 through 1982 8
- 2. Average Ambient Radiation Levels from Monthly TLDs in the Vicinity of Artificial Island, 1973 through 1982 ................ 10 2a. Comparison of Ambient Radiation Levels of Off-Site Indicator Stations vs. Control Stations, 1982 .. ......... ..... ......... ... . 11
- 3. Average Concentrations of Tritium in the Delaware River in the Vicinity of Artificial Island, 1973 through 1982 ............ 13
- 4. Average Concentrations of Beta Emitters and Potassium-40 in the Delaware River in the Vicinity of Artificial Island, 1973 through 1982 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14
- 5. Average Concentrations of Iodine-131 in Milk in the Vicinity of Artificial Island, May 1974 through December 1982 ............ 18 ii
SUMMARY
During the period January 1 to December 31, 1982, Radiation Management Corporation (RMC) participated in the Operational Radiological Environmental Monitoring Program conducted by Public Service Electric and Gas Company (PSE&G) at Artificial Island, New Jersey. Salem Nuclear Generating Station (SNGS) Unit #1 became critical on December 11, 1976, thereby initiating the operational phase of the Radiological Environmental Monitoring Program (REMP). This program was designed to identify and quantify concentrations of radioactivity in various environmental media and to quan-tify ambient radiation levels in the environs of Artificial Island. Unit #2 achieved initial criticality on August 2, 1980. During the operational phase, the program will monitor the operations of SNGS Units #1 and #2, wi11 fulfill the requirements of the SNGS Environmental Technical Specifications, and will provide background data for the Hope Creek Generating Station. This report presents the results of thermo-luminescent dosimetry and radiochemical analyses of environmental samples collected during 1982. A total of 2571 analyses were performed* on 1551 environmental samples during the period covered by this report. Samples of air particulates, air iodine, surface, ground and drinking water, benthos, sediment, milk, fish, crabs, vegetables, game, fodder crops, meat and precipitation were collected. Thermoluminescent dosimeters were used to measure ambient radiation levels. A variety of radionuclides, both naturally occurring and man-made, were found in the above samples. These nuclides were detected at levels similar to those found during the preoperational phase of this program. In general, results at indicator stations compared favorably to control stations. It is concluded that the radiological charac-teristics of the environment around Artificial Island during 1982 were not affected by the operation of SNGS Units #1 and #2. 1
INTRODUCTION Radiation Management Corporation has participated in the Artificial Island Radio-logical Environmental Monitoring Program since January 1973. RMC has previously reported results for the preoperational phase of the REMP from 1973 to 1976 (1-4). On December 11, 1976, SNGS Unit #1 first achieved criticality thereby initiating the operational phase of the REMP. Continuing since then, RMC has reported results for the operational phase of the REMP from 1976 to 1981 (5-10). This report sum-marizes the operational period between January 1 and December 31, 1982. Artificial Island is the site of two nuclear power reactors which are part of the Salem Nuclear Generating Station. Units #1 and #2 are pressurized water reactors (PWR), with a capacity of 1090 MWe and 1115 MWE respectively. Both are presently operational. Artiffcial Island is actually a man-made peninsula in the Delaware River, created by the deposition of dredging spoils. It is located in Lower Alloways Township, Salem County, New Jersey. The environment around Artificial Island is character-ized mainly by the Delaware River and Bay, extensive tidal marshes, and grass lands. These land types make up approximately 85% of the land area within five miles of the site. Most of the remaining land is used for agricultural production (11). More specific information on the demography, hydrology, meteorology, and land use characteristics of the local area may be found in the Environmental Report (11), Environmental Statement (12), and the Final Safety Analyses Report (Units 1 and 2 for SNGS ( 13). 2
THE PROGRAM In the operational phase of the REMP, the program was conducted in accordance with Section 3.2 of the SNGS Environmental Technical Specifications (14). Radioanalytical data were collected and compared with results from the preoperati~n~l ~hase. Differences between these periods were examined statistically, where applicable, to determine whether any station operational effects existed. Objectives The objectives of the operational radiological environmental program are:
- 1. To fulfill the obl.igations of the Radiological Surveillance-Environmental sections of the Environmental Technical Specifications for SNGS.
- 2. To determine whether any significant increase occurs in the concentration of radionuclides in critical pathways.
- 3. To determine if SNGS has caused an increase in the radioactive inventory of long lived radionuclides.
- 4. To detect any change in ambient gamma radiation levels.
- 5. To verify that SNGS operations have no detri.mental effects on the health and safety of the public or on the environment.
This report, as required by Secti.on 5.6 of the Salem Environmental Techni.cal Specifi-cations (ETSl, summarizes the findings of the 19-82 REMP.. Results of the four year preoperational program have been summarized for purposes of comparison with subsequent operational reports C4). Sample Collection In order to meet the stated objectives, an appropriate operational R.EMP was developed by RMC in cooperation with Public Service Electric and Gas Company. Samples of various media were selected to obtain data for the evaluation of the radiation dose to man and other organisms. The selection of sample types was based on: (1) established critical pathways for the transfer of radionuclides through the environment to man, and (2) experience gafned during the preoperational phase. Sampling locations were determined from site meteorology, Delaware estuarine ftydrolo9y, local demography, and land uses. Sampling locations were divided ihto two classes--indicator and control. Indicator stations are those which are expected to manifest station effe~ts, if any exist; con-trol samples are collected at locations wftich are believed to be unaffected by station operatipns:- Fluctuations in the levels of*radionuclides and direct radiation at indi-cator stations are evaluated with respect to analogous fluctuations at control stations, whtch. a.re unaffected by station operation. Indicator and control station data are also evaluated relative to preoperational data. The REMP for the Artificial Island Site in-cludes addittonal samples and analyses not specifically requi'red by the Salem ETS. The summary tables i.n this report include these additional samples and analyses. 3
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 charcoal cartridges connected in series behind the air particulate filters. Air sample volumes were measured with calibrated dry-gas meters corrected to standard temperature and pressure. Precipitation was collected on a 95-square-inch rain gauge. Samples were collected monthly and transferred to new polyethylene bottles. The rain gauge v1as rinsed at collection with distilled water to include residual particulates in the precipita-tion samples. Tritium results were corrected for the tritium content of the dis-tilled water. Ambient radiation levels in the environs were measured with energy-compensated Caso 4 (Tm) thermoluminescent dosimeters (TLDs). Packets containing four TLDs each were placed on and around the Artificial Island Site at various distances and were exposed on a monthly, quarterly and semi-annual basis. Monthly well and potable water samples were taken in new two-gallon polyethylene bottles. Separate raw and treated potable water samples were composited daily by personnel of the Salem Water Company. Surface water samples were collected by Icthyological Associates and shipped to RMC for analysis in new polyethylene bottles. Sample containers were rinsed twice with .the sample medium pdor to collection. Edible fish and crabs were taken by net, sealed in a bag or jar and shipped frozen. Benthos and sediment were taken with a bottom grab sampler. Milk samples were taken in new polyethylene bottles and shipped fresh. Food products, fodder crops, game and bovine thyroid samples were taken and sealed in plastic bags or jars. Perishable samples were frozen at the time of sampling without any preservatives. Appendix A describes and summarizes, in the format of Table 5.6...,1 of the Sale*m ETS, the entire operational program as performed in 1982. Appendix B describes the RMC coding system, which specifies sample type and relative locations at a glance. Also in Appendix B, Table B-1 gives the pertinent information on indivi-dual sampling locations, while maps B-1 and B-2 show the sampling locations. 4
Data Interpretation Radiation Management Corporation has an extensive quality assurance program designed to maximize confidence in the analytical procedures used. Approximately 20% of the total analytical effort is spent on quality control, including process quality con-trol, instrument q.uality control, inter-laboratory cross-check analyses, and compre-hensive data review. The analytical methods utilized in this program are surrrrnarized in Appendix D-1. The methods utilized by the PSE&G Research and Testing Lab are summarized in Appendix D-2. Results of the EPA inter-laboratory comparison program appear in Appendix E. A full discussion of these results can be found in the 11 Qual-i ty Control Pata 1982 - An~ual Report 11 (15). Several factors are important in the interpretation of the data. These factors are discussed here to avoid repetition in sections that follow. Grab sampling is a useful and aGceptable 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 chara_cteristi cs of the medium. This method, however,_ is only repre-sentative of the sampled medium for that specific location and instant of time. As a result, variation in the radionuclide concentrations of the samples will normally occur. Since these variations will tend to counterbalance one another, the extraction of averages based upon repetitive grab samples is valid. Within the data tables (Appendix C) an approximate 95% (+/-2 sigma) confidence inter-val is supplied for those data points above the lower limit of detection (LLD). An exception to this is Sr-89 and -90 detection capabilities which are based on the minimum detectable limit (MDL). These intervals represent the range of values into which 95% of repeated analyses of the same sample should fall. Results for- each type of sample were grouped according to the analysis performed. Means and standard deviations of these results were calculated when applicable. The calculate_d*standard deviations of grouped data found in Appendix C represent sample and not analytical variability. When a group of data was composed of mainly (>50%) LLD values, averages were not calculated. It is characteristic of environmental monitoring data that many results occur at or below the lower limit of detection~ For reporting and calculation of averages, any result occurring at or below the lower limit of detection is considered to be at that limit. As a result, averages obtained using this method are biased_high. 5
Quality Assurance Program (RMC) Beginning on October 1, 1981, modifications were made to the portion of the Radio-logical Environmental Monitoring Program for the Salem Nuclear Generating Station performed by RMC. It should be noted that all analyses not performed by RMC are being analyzed by the PSE&G Research and Testing Laboratory, a wholly owned subsi-diary of PSE&G. In order to insure quality of the results obtained by their laboratory, PSE&G has instituted a quality assurance program in which a portion of those samples analyzed by PSE&G will also be analyzed by RMC. This program is discussed below.
- 1. Milk - Station MLK-3Gl will be analyzed for Sr-89 and -90 on a monthly basis by RMC. Each month one additional station will be chosen by Public Service Electric & Gas Company to receive Sr-89 and -90 analyses.
- 2. Surface Water - Station S~JA-12Cl will be analyzed for tritium on a monthly basis, and for Sr-89 and -90 on a quarterly composite basis by RMC. In addition, one other station will be chosen by PSE&G to receive monthly tritium analyses and quarterly comp6site Sr-89 ~nd -90 analyses.
- 3. Potable Water - Monthly tritium analyses and quarterly composite analyses for Sr-89 and -90 will be performed for station PWT-2F3 by RMC.
All results for the samples included in the quality assurance program appear on the data tables in Appendix C. This data is not included in the Results and Discussion portion of the text or in Appendix A. Program Changes The sampling frequency for the semi-annual TLDs was changed to quarterly collections. 6
RESULTS AND DISCUSSION The analytical results of the 1982 REMP samples are divided into categories based on exposure pathways: airborne, direct, water, aquatic and ingestion. The analytical results for the 1982 REMP samples are summarized in Appendix A. The data for indi-vidual samples are presented in Appendix C. This section discusses the data collected for the REMP program. It does not include the data from the quality assurance program discussed previously. Airborne Air Particulates (Tables C-1, C-2, C-3) Air particulate samples were analyzed for alpha and beta ~mitters, Sr-89 and -90, and gamma emitters. The weekly air particulate samples were analyzed for gross alpha activity at two stations and for gross beta activity at eight stations. Quarterly composites were prepared using the weekly samples from each station and analyzed for Sr-89, Sr-90 and specific gamma emitters. Of the 104 weekly air particulate samples (two stations) analyzed for gross alpha emitters, 96 were above detectable c§ncentrations. The range of gross alpha acti~ vity was from 0.0007 to 0~0048 pCi/m and averaged 0.0016 pCi/m3. Weekly gross beta analyses showed concentrations ranging from 0.00~ to 0.060 pCi/m3 with the av~rage for the eight sampling stations being 0.027 pCi/m . Figure 1 shows the relation between gross beta activity in air and precipitation for the preopera-tional and the operational periods, showing the weapons-testing fluctuations. The_S~-89 analyses performed on the 32 quarterly composit~s ~ndicated no detecta~le act1v1ty. The MDLs ranged between <0.0003 and <0.0013 pCl/m . Sr-90 concentrations in 4 of the 32 samples ranged between ~.0003 and 0.0010 pCi/m3. The MDLs for Sr-90 ranged between 0.0002 and 0.0009 pCi/m . Results of gamma spectrometry showed detectable levels of several radionuclides, both naturally occurring and man-made (Be-7, Cs-137 and Ce~144). The presence of Be-7 throughout the year can be attributed to cosmic ray activity. Cs-137 and Ce-144
- activities are due to fa1lout from previous atmospheric testing. The highest activity detected was 0.067 pCi/m of Be-7 in the second quarter composite for station APT-2S2.
Air Iodine (Table C-4) Iodine cartridges were connected in series behind each of the air particulate filters for adsorption of air iodine. The adsorption media used in these cartridges was 11 TEDA impregnated cha3coal. All results for I-131 were below the LLD and ranged from <0.0064 to <0.060 pCi/m . 7
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Precipitation (Tables C-6, C-7, C-8) Although not specifically required by the Salem ETS, precipitation was sampled con-tinuously and collected monthly at the Salem substation sampling location. The precipitation was analyzed for tritium, gross alpha and gross beta emitters on a monthly basis. Tritium activity was detected in three samples and ranged from 140 to 160 pCi/l. The LLDs ranged from <120 to <140 pCi/l. Of the eleven monthly rain water samples analyzed for gross alpha emitters, five showed detectable concentra-tions. The range of gross alpha activity was from 0.5 to 2.0 pCi/l. The LLDs ranged from <0.6 to <1.1 pCi/l. Gross beta emitter concentrations were detected in nine samples and ranged from 2.4 to 16 pCi/l with an average of 6.3 pCi/l. Quarterly composites of precipitation were analyzed for radiostrontium and gamma emitters. The Sr-89 levels were below the MDL which ranged from <0.2 to <2.7 pCi/l. All results for Sr-90 were also below the MDL which ranged between <0.2 and <1.1 pCi/l. Results of gamma spectrometry showed two samples with detectable levels of K-40 (14 and 26 pCi/l.) Direct (Tables C-9, C-10, C-11) Direct radiation measurements were mQde at forty-one different locations, using CaS0 4 (Tm) thermoluminescent dosimeters. During 1982, 288 monthly, 113 quarterly and 34 semi-annual TLD packets were collected. Each packet included four dosimeters for a total of 1740 analyses. These analyses resulted in an average dose rate of 5.76 mrads/standard month for monthly TLDs, 5.14 mrads/standard month for quarterly TLDs and 4.93 mrads/standard month for semi-annual TLDs. All TLD results presented in this report have been normalized to a standard month (30.4 days) to eliminate the apparent differences caused by variations in exposure periods. ~~hen the monthly data is plotted as in Figure 2, a slight peak is observed after June 1979, while from March 1981 to May 1981 a sharp reduction in the average is noted. This peak is attributed to the elevated readings from two on-site TLD stations. Since the two stations, 1051 and 1151, are on-site, they do not represent any environmental dose to the public. During the year a general increase in the ambient radiation levels were noted at all locations. The monthly TLD results (Table C-9) in the last quarter of 1982 were above the levels obtained earlier in the year. Ambient radiation levels tend to fluctuate during the year due to natural varia-tions in terrestrial and airborne radiation components, due primarily to the evolution of naturally radioactive radon daughter products from the soil and the shielding affects from the moisture content of the soil (NCRP-45). The quarterly TLD measurements (Table C-10) tend to fluctuate less than the monthly TLD measure-ments due to the fact that the variation in the natural radiation components mentioned above are less pronounced when averaged over a calendar quarter. The quarterly TLD results (Table C-10) were slightly lower than some of the levels obtained earlier in the year, nevertheless, the average of the monthly and quar-terly results fall within each others error bands and are consistent. The average of all monthly TLD results and the average of only the control stations are plotted in Figure 2, to indicate that the general increase in ambient radiation levels noted occurred concurrently at indicator and control stations. A comparison of the direct radiation data for 1982 shows a similarity between the average monthly dose for both indicator stations (5.70 mrads/std. month) and control stations (6.IDl mrads/std. month). 9
FIGURE 2 AVERAGE AMBIENT RADIATION LEVELS FROM MONTHLY TLDs IN THE VICINITY OF ARTIFICIAL ISLAND, 1973 THROUGH 1982
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- Sept. 17, 1977 March 14, 1978 March 28, 1979 Oct. 15, 1960 SNGS Unit #1 initial criticality SNGS Unit #2 initial criticality Dec. 11, 1976 Aug. 2, 1980
FIGURE 2A COMPARISON OF AMBIENT RADIATIONS LEVELS OF OFF-SITE INDICATOR STATIONS VS. CONTROL STATIONS 15 ::
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In order to better evaluate the variation between TLD results, a statistical model which is capable of separating a contribution by SNGS from the backaround component has been developed. The statistical method utilized is a linear regression analysis which involves determining the functions which best describe the back9round component by the least squares method. Six models were originally tested and are described in a separate publication (16). The equation which describes the model selected is: where: f = denotes a function of y .. Jml
= predicted value for station j, month m, and year i x.J = preoperational mean for station j CONim = average of the control stations for month m and year i COT., = average of the control station for year i (a p in place of i 11 11 represents the preoperational period) 11 11 A computer program was developed for multiple regression analysis. The least squares fit (LSF) line based on all 1982 data was determined along with the statistics for this line. The data for 1982 was tested against predicted values and prediction limits determined from the model period line. Differences between predicted and observed values are termed residuals. Residuals outside the pre-diction limits of the predicted value are identified as outliers. For 1982, thirty-five outliers were predicted from a possible 288.
Eleven outliers at station lOSl and twelve outliers at station llSl can be attri-buted to the refueling of Unit #1. These stations are located in the vicinity of the Refueling Water Storage Tank. Since these locations are on-site they do not represent a dose to the public. Water Surface Water (Tables C-12, C-13, C-14~ C-15, C-16) Monthly surface water samples were taken at five locations in the Delaware estuary. One is downstream from the outfall area, one is in the outfall area, and another is directly west of the outfall area at the mouth of the Appoquinimink River. Two other stations are located upstream--one station is in the river and the other is in the Chesapeake and Delaware Canal. The station (12Cl) located at the mouth of the Appoquinimink River serves as the operational control. Surface water samples were analyzed for tritium, gross alpha, gross beta and gamma emitters, and strontium-89 and -90. 12
FIGURE 3 AVERAGE CONCENTRATIONS OF TRITIUM IN THE DELAWARE RIVER IN THE VICINITY OF ARTIFICIAL ISLAND, 1973 THROUGH 1982 1000 100
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Analysis of surface water for tritium yielded an average concentration of 167 pCi/l and ranged from 120 to 470 pCi/l. These levels are similar to those measured in the preoperational program as shown in Figure 3. A gradual decrease in tritium activity from 1973 to 1982 can be attributed to general reduction in the world-wide tritium inventory with the cessation of routine atmospheric testing. Gross alpha concentrations were generally below LLD, which ranged from <0.2 to <1.0 pCi/l. Four of the sixty samples analyzed showed detectable gross alpha activity ranging from 0.3 to 0.8 pCi/l. Gross alpha activity may be expected in suspended solids from naturally occurring radionuclides especially during periods of high surface runoff.
- Gross beta concentrations found in fifty-nine of the sixty samoles ranged from 2.6 to 117 pCi/1 and averaged 43 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 gross beta and K-40 concentrations in the Delaware River. Due to the flow rate variations and the tidal nature of the estuarine environment, large varia-tions in the gross beta concentrations*were observed throughout the year. Much of this variation can be attributed to the tidal stage at the time of sampling.
Gamma spectrometric analysis of surface water samples showed detectable concentra-tions of K-40 in forty-five of sixty samples. The average K-40 concentration was 44 pCi/l and ranged from 9.7 to 150 pCi/l. K-40 is a naturally occurring raaio-nuclide which is expected to be found in salt and brackish waters. Levels of Sr-89 were below MDL (<0.5 to <1.2 pCi/l) in all twenty quarterly composite samples. A detectable concentration of Sr-90 was found in one sample with a result of 0.5 pCi/l. "The MDL values for the remaining samples ranged from <0.4 to <0.9 pCi/l. The.maximum level of Sr-90 detected in the preoperational program was 1.6 pCi/l (4). Well Water (Tables C-17, C-18, C-19, C-20) Monthly well water samples were taken from two indicator wells and one control well. All well water samples were analyzed for tritium, gross alpha and gross beta acti-vity, and K-40 (by atomic absorptionL Quarterly composites were analyzed for gamma emitters, and Sr-89 and Sr-90. No detectable concentrations of tritium were observed in any of the thirty-six well water samples analyzed. The LLDs ranged from <120 pCi/l to <140 pCi/h Gross alpha concentrations were generally below LLD whith ranged from <0.8 to <3.6 pCi/l. Four of the samples analyzed showed detectable gross alpha activity ranging between 1.3 and 1.7 pCi/l. The concentrations of gross beta emitters averaged 12 pCi/l and ranged from 6.2 to 16 pCi/l. The potassium-40 activity as determined by atomic ab-sorption averaged 10 pCi/l and ranged between 7.1 and 14 pCi/l. This indicates that the gross beta activity observed in these samples is primarily the result of naturally occurring K-40, a beta emitter. 15
Quarterly composites of well water samples were analyzed for gamma emitters and Sr-89 and -90. K-40 was detected by gamma spectrometry in two of the samples with results of 11 and 17 pCi/l. All results for Sr-89 were below the MDL with a range of <0.5 to <0.8 pCi/l. All results for Sr-90 were also below the MDL with a range of <0.3 to <0.7 pCi/l. Potable Water (Tables C-21, C-22, C-23, C-24) Both raw and treated water samples were taken at the Salem Water Company, the only drinking water processing plant.in the vicinity of Artificial Island. The raw water source for this plant is Laurel Lake (a tributary of the Delaware River) and several adjacent wells. Potable water samples were analyzed monthly for tritium, gross alpha and gross beta activity, and K-40 (by atomic absorption); Sr-89 and -90, and gamma emitters were analyzed on a quarterly basis. Detectable concentrations of tritium were observed in five of the twenty-four sam-ples ranging from 130 to 170 pCi/l, with no significant differences occurring be-tween the raw and treated samples.* Detectable gross alpha activity was observed in thirteen of twenty-four samples ranging between 0.6 pCi/l and 3.1 pCi/l with an average of 1.2 pCi/l. Gross beta and K-40 concentrations*were lower than in the saline surface water, as exoected for fresh*water. The average grossbeta concentrations were 3.1 pCi/l (raw) and 2.6 pCi/l (treated). The average K-40 results were 2.2 pCi/l (raw) and 2.1 pCi/l (.treated). Quarterly composites of raw and treated water samples were analyzed for Sr-89 and -90 and gamma .emii*tters. Of the. eight samples analyzed for Sr-89, three showed detectable concentrations ranging from 1.1 to 1.2 pCi/l. The MDL range for Sr-89 was <0.5 to <1.3 pCi/l. *sr-90. was observed in two of the eight samples with each having a concentration of 0.6 oCi/l. *The MDL range for Sr-90 was <0.4 to <0.9 pCi/l. No nuclides were detected by garrma spectrometry in any of the samples. Aquatic Benthos (Table C-25) Benthic organisms were collected at four locations and analyzed for Sr-89 and Sr-90. Levels of Sr-89 were below MDL (<0.02. to <24 pCi/g-dry) for all seven analyses. The wide fluctuations in MDL values were due to inconsist~ncies in sample size (0.05 to 25 grams dry). Sr-90 was found-in one* sample with a concentration of 0.03 pCi/g-dry. The detectable activity of this sample *;s within the MDL range (.<0.02 to <12 pCi/g-dry) of the other analyses. The MDL for radiostrontium as required by the Environ-mental Technical Specifications* for benthic organisms was not met in all of the samples due to the impracticality of obtaining a sufficiently large sample size of benthic organisms. Sediment (Table C-26) Sediment was collected semiannually at four locations and analyzed for Sr-90 and gamma emitters. Levels of Sr-90 were below MDL (<0.02 to <0.05 pCi/g~dry) in all eight samples analyzed. 16
-----~--*-*--*-*-*--------- --
Results of gamma spectrometry showed detectable levels of a variety of naturally occurring radionuclides as well as man-made radionuclides. Ingestion Milk (Tables C-27, C-28, C-29) Milk samples were taken twice a month from six local farms during 1982 and analyzed for I-131; gamma emitters, Sr-89 and Sr-90 were analyzed monthly. I*131 was not observed in any milk samples during 1982. Figure 5 shows the average I-131 concen-trations in milk samples resulting from atmospheric nuclear weapons tests by the Peoples Republic Qf China (June 1974, March 1978, and October 1980) and the Three Mile Island incident in 1979. Gamma spectrometry showed detectable concentrations of K-40 in all samples and Cs-137 in twenty-five of the seventy-two samples analyzed. The annual average concentrations were 1500 pCi/1 for K-40 and 1.8 pCi/1 for Cs-137. These levels were not significantly different between control and indicator stations. Strontium-89 was detected in one of the seventy-two samples analyzed with a result of 6.9 pCi/1. The range of MDL values for Sr-89 was <1.3 pCi/l to <2.7 pCi/1. The concentrations of Sr-90 were positive in sixty-nine of the seventy-two samples analyzed and averaged 2.9 pCi/l. The MDL range was <1.4 pCi/l to <1.8 pCi/1. Sr-90 concentra-tions were similar at indicator and control stations, indicating no contribution from SNGS. Due to the twenty-eight year half-life and biological assimilatiOn, Sr-90 can be expected to remain long after routine atmospheric testing has ceased .. Fish (Tables C-31, C-32) Edible fish samples (American Eel, White Perch, Channel Catfish~ Spot, etc.) were collected at three locations and analyzed for tritium and gamma emitters . . Fish bones were collected for Sr-89 and Sr-90. Gamma spectrometry of these samples showed K-40 in all six samples analyzed at an average concentration of 3.1 pCi/g-wet with a range of 2.9 to 3.7 pCi/g-wet. All six bone samples analyzed for Sr-89 were below the MDL (<0.02 to <0.3 pCi/g-dry). Four of the six samples analyzed for Sr-90 had detectable concentrations ranging from 0.05 to 0.21 pCi/g-dry with an average of 0.12 pCi/g-dry. The maximum level detected during the preoperational period was 0.94 pCi/g-dry. Tritium analyses were performed on both aqueous and organic fractions of the flesh portions of these samples. Only one sample had detectable concentrations of tritium for the aqueous fraction with a result of 81 pCi/l. Of the six samples analyzed for the aqueous fraction of tritium, all results are essentially, the same as those found* in surface water for the same period. Four of the six samples analyze'd for the or-ganic fraction of tritium showed detectable activity ranging between 134 and 1800 pCi/l. One sample from the control station (12Cl) and one sample from the indicator station (7El) showed results of 1740 and 1800 pCi/l ~ respectively. The high results could be due to chemiluminescence in the samples; however, due to the small sample sizes, the results could not be confirmed by reanalysis. These results probably cannot be attributed to plant operation since the closest indicator station (llAl) had no unusual levels of tritium in the organic fraction. 17
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Blue Crab (Tables C-33, C-34) Blue crab samples were collected at two locations and the flesh was analyzed for gamma emitters, Sr-89 and -90, and tritium in the aqueous fraction. The shells were also analyzed for Sr-89 and Sr-90. K-40 was the only gamma emitter detected with an average of 2.1 pCi/g-wet. All results for Sr-89 in flesh were below MDL with a range of <0.006 to <0.02 pCi/g-wet. Detectable concentration of Sr-89 was found in one of the shell samples, with a result of 0.2 pCi/g-dry. The MDL range for Sr-89 in shells was <0.04 to <O.l pCi/g-dry. Three of four flesh samples showed detectable activity with concentrations of 0.005 to 0.014 pCi/g-wet of Sr-90. The MDL value was <0.006 pCi/g-wet. All of the shells had detectable activity of Sr-90. The range of activities was 0.09 to 0.31 pCi/g-dry. Two samples showed detectable concentrations of tritium. The results were comparable to tritium values found in surface water for this same period. Food Products (Table C-35) A wide variety of other human food products was sampled and analyzed for Sr-89 and -90 and gamma emitters. These included cucumbers; asparagus, peppers, cabbage, corn, soybeans and tomatoes. Sr-89 concentrations were all below MDL, which ranged from <0.003 to <0.2 pCi/g-wet. Sixteen of the twenty-three samples analyzed showed detec-table Sr-90 activity ranging from 0.002 to 0.08 pCi/g-wet. The MDLs ranged from <0.002 to <0.007 pCi/g-wet. All samples contained K-40 at concentrations of 0.9 to 12 pCi/g-wet. No other gamma emitters were detected in these* food products. Game (Table C-36) Wwo samples of muskrat were taken during this period. Bones from both samples were analyzed for Sr-89 and -90 while muskrat flesh was analyzed for gamma emitters. One sample showed a detectable concentration of Sr-89 in muskrat bones with a result of 0.07 pCi/g-dry. Detectable Sr-90 concentrations averaging 0.085 pCi/g-dry were observed in both samples. Only naturally occurring K-40 was detected in the flesh samples with results of 2.0 to 2.3 pCi/g-wet. Beef (Table C-36) Two beef samples were collected and analyzed for gamma emitters. Only naturally occurring K-40 was detected in these samples at concentrations of 1.1 and 2.2 pCi/g-wet. 19
Beef Thyroid (Table C-36) Two beef thyroids were taken during this period and analyzed for gamma emitters. One sample showed a detectable concentration of naturally occurring K-40 at a con-centration of 2.3 pCi/g-wet. The other sample had an LLD for K-40 of <0.6 pCi/g-wet. No detectable concentrations of I-131 were detected in the samples. Fodder Crops (Table C-37) Ten fodder crop samples were taken at six local farms and analyzed for gamma emit-ters. Gamma spectrometry of these* samples showed K-40, a naturally occurring nuclide, 1n all samples ranging between 2.7 and 18 pCi/g~dry. The average for these samples was 5.9 pCi/g-dry. 20
CONCLUSIONS The Radiological Environmental Monitoring Program for Salem Nuclear Generating Station at Artificial Island was conducted during 1982 in accordance with the SNGS Environmental Technical Specifications. The objectives of the program were met during this period. The data collected assists. in demonstrating that SNGS Units #1 and #2 were operated in compliance with Environmental Technical Specifications. From the results obtained, it can be concluded that the levels and fluctuations of radioactivity in environmental samples were as expected for an estuarine en-vironment. With the possible exception of the organic fraction of tritium in fish flesh, no increases were observed in either radionuclide concentrations in critical pathways or with respect to radionuclide build up. The elevated levels of tritium in the organic fraction of fish flesh can probably be attri-buted to chemiluminescence rather than plant operation. Ambient radiation levels were relatively low, averaging about 5.76 mrad/std. month. No other unusual radiological characteristics were observed in the environs of Artificial Island. The operation of SNGS Units #1 and #2 had no discernable effect on the radiological characteristics of the environs of Artificial Island. 21
REFERENCES (1) Radiation Management Corporation. 11 Salem Nuclear Generating Station - Radiological Environmental Monitoring Program - 1973 11
- RMC-TR-74-09, 1974.
(2) Radiation Management Corporation. 11 Artificial Island Radiological Environmental Monitoring Program - 1974 Annual Report 11 , RMC-TR-75-04, 1975. (3) Radiation Management Corporation. 11 Artificial Island Radiological Environmental Monitoring Program - 1975 Annual Report 11
- RMC-TR-76-04, 1976.
(4) Radiation Management Corporation. 11 Artificial Island Radiological Environmental Monitoring Program - Preoperational Summary - 1973 through 1976 11
- RMC-TR-77-03, 1978.
(5) Radiation Management Corporation. 11 Artificial Island Radiological Environmental Monitoring Program - December 11 to December 31, 1976 11
- RMC-TR-77-02, 1977.
(6) Radiation Management Corporation. 11 Artificial Island Radiological Environmental Monitoring Program - 1977 Annual Report 11
- RMC-TR-78-04A, 1978.
(7) Radiation Management Corporation. 11 Artificial Island Radiological Environmental Monitoring Program - 1978 Annual Report 11
- RMC-TR-79-03, 1979.
(8) Radiation Management Corporation. 11 Artificial Island Radiological Environmental Monitoring Program - 1979 Annual Report 11
- RMC-TR-80-03, 1980.
(9) Radiation Management Corporation. 11 Artificial Island Radiological Environmental Monitoring Program - 1980 Annual Report 11
- RMC-TR-81-03, 1981.
(10) Radiation Management Corporation. 11 Artificial Island Radiological Environmental Monitoring Program - 1981 Annual Report 11
- RMC-TR-82-01, 1982.
(11) Public Service Electric and Gas Company. 11 Environmental Report, Operating Licensa Stage - Salem Nuclear Generating Station Units 1 and 2 11
- 197.1.
(12) United States Atomic Energy Commission. 11 Final Environmental Statement - Salem Nuclear Generating Station, Units 1 and 2. Docket No. 50-272 and 50-311, 1973. (13) Public Service Electric and Gas Company. 11 Final Safety Analysis Report - Salem Nuclear Generating Station, Units 1 and 2 11
- 1972.
'(14) Public Service Electric and Gas Company. 11 Environmental Technical Specifications - Salem Nuclear Generating Station Units 1 and 2 11
- 1976.
22
--------------------~- - - -- -----
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REFERENCES (cont.) (15) Radiation Management Corporation. 11 Quality Control Data 1982 - Annual Report 11 , 1983. {16) Radiation Management Corporation. 11 Artificial Island Radiological Environmental Monitoring Program - Statistical Interpretation of Results of the Thermoluminescent Dosimetry Program 11 RMC-TR-78-11, 1978. 23
APPENDIX A PROGRAM
SUMMARY
25
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONttENTAL MONITORING PROGRJIJ'1
SUMMARY
SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 SALEM COUNTY, NEW JERSEY JANUARY 1, 1982 TO DECEMBER 31, 1982 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOT AL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORi\1ED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Air Particulates Alpha 104 0.6 1.7 (45/52) 16El 4.1 mi NNW 1. 7 ( 45/52) 1.5 (51/52) 0 (0.7-4.8) (0.7-4.8) (10- 3 pCi/m3 ) (0.7-3.9) Beta 416 27 (364/364) 2S2 0.4 mi NNE 28 (52/52) 28 (52/52) 0 (8.4-53) (13-53) (11-60) Sr-89 32 0.3 - (0/28) None Detected - (0/4) 0 Sr-90 32 0.2 0.3 (3/28) 3H3 110 mi NE 1.0 (1/4) 1.0 (1/4) 0 (0.28-0. 4) (1.0) (1. 0) Gamma 32 Be-7 44 (28/28) 2S2 0.4 mi NNE 55 (4/4) 49 (4/4) 0 N -.....i (29-67) ( 44-67) ( 40-60~ Cs-137 0.4 0.6 (2/28} 16El 4.1 mi NNW 0.7 (1/4) - (0/4 0 (0.5-0.7) (0. 7) Ce-144 1.6 1. 7 (5/28) 2F2 8.7 mi NNE 2.0 (2/4) 1.5 (1/4) 0 (I.4-2.2) (1.8-2.2) (1. 5) Air Iodine I-131 364 6.4 - (0/312) None Detected - (0/52) 0 (10- 3 pCi/m 3 ) Precipitation H-3 12 120 147 (3/12) 2F2 8.7 mi NNE 147 (3/12) No Control 0 (pCi /l) (140-160) (140-160) Location Alpha 11 o.6 1.1 (5/11) 2F2 8.7 mi NNE 1.1 (5/11) No Control 0 (0.5-2.0) (0.5-2.0) Location Beta 11 2.2 7.0 (9/11) 2F2 8.7 mi NNE 7.0 (9/11) No Control 0 (2.4-16) (2.4-16) Location Sr-89 4 0.2 - (0/4) None Detected No Control 0 Location Sr-90 4 0.2 - (0/4) None Detected No Control 0 Location Gemma 4 K.:..40 7.8 20 (2/4) 2F2 8.7 mi NNE 20 .(2/4) No Control 0 (14-26) (14-26) Location
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 SALEM COUNTY, NEW JERSEY JANUARY 1, 1982 TO DECEMBER 31, 1982 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST* MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Direct Radiation Gamma 288 5.70 (240/240) llSl 0.09 mi SW 8.48 (12/12) 6.01 (48/48) 0 (mrad/std. month) Dose (monthly) (3.65-19.63) (5.41-19.63) (4.05-7.51) Ganrna 113 5.11 (94/94) llSl 0.09 mi SW 7.49 (4/4) 5.30 (19/19) 0 Dose (quarterly) ( 3.51-11.60) (5. 72-11.60) (4.66-5.88) Ganuna 34 4.83 (28/28) 16Gl 15 mi NNW 5.63 (2/2) 5.38 (6/6) 0 Dose (semi-annual) (4.08-5.75) (5.60-5.65) (5.04-5.65) Surface Water H-3 60 120 208 (27/48) llAl 0.2 mi SW 291 (7/12) 178 (5/12) 0 {pCi/l) (120-470) (190-470) (160-200) Alpha 60 0.2 0.5 (3/48) ?El 4.5 mi SE 0.8 (1/12) 0.4 (1/12) 0 (0.3-0.8) (0.8) (0.4) Beta 60 3.4 45 (47/48) ?El 4.5 mi SE 65 ( 12/12) 36 (12/12) 0 N (2.6-117) (18-117) ( 5. l-87) co Ganuna 60 K-40 7.8 58 (35/48) ?El 4.5 mi SE 73 ( 11/12) 48 ( 10/12) 0 (12-150) (29-150) (9.7-83) Sr-89 20 0.5 - (0/16) None Detected - (0/4) 0 Sr-90 20 0.4 0.5 (1/16) 1F2 7.1 mi N 0 .5 ( 1/4) - (0/4) 0 (0.5) (0.5) Well Water H-3 36 120 - (0/24) None Detected - (0/12) 0 (pCi/l) Alpha 36 0.8 1.5 (4/24) 4Sl Site Well #5 ENE 1. 6 (2/12) - (0/12) 0 (L3-1.7) (1.4-1. 7) Beta 36 13 (24/24) 5Dl 3.5 mi E 13 (12/12) 9.0 (12/12) 0 (9. 3-16) (10-16) (6.2-11) K-40 36 11 (24/24) 5Dl 3.5 mi E 11 (12/12) 8.4 (12/12) 0 (9.2-14) (9.7-14) (7.1-9.3) Ganuna 12 K-40 7.0 14 ( 2/8) 5Dl 3.5 mi E 17 (J/4) - (0/4) 0 ( 11-17) (17) Sr-89 12 0.5 - (0/8) None Detected - (0/4) 0 Sr-90 12 0.3 - (0/8) None Detected - (0/4) 0
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 SALEM COUNTY, NEW JERSEY JANUARY 1, 1982 TO DECEMBER 31, 1982 ii ANALVS IS AND Lm/ER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER .LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Potable Water H-3 24 120 144 (5/24) 2F3 8.0 mi NNE 144 (5/24) No Control 0 Raw-Treated (130-170) (130-170) Location Alpha 24 0.5 1.2 (13/24) 2F3 8 .O mi NNE 1.2 (13/24) No Control 0 (0.6-3.1) (0.6-3.1) Location Beta 24 2. 9 (24/24) 2F3 8.0 mi NNE 2.9 (24/24) No Control 0 (1.7-4".4) (1.7-4 .4) Location K-40 211 1*2 (24/24) 2F3 8.0 mi NNE 2. 2 (_24/24) No Control 0
.1.1-3.2) (1.1-3.2) Location Sr-89 8 0.5 1.17 (3/8) 2F3 8.0 mi NNE 1.17 (3/8) No Control 0 (1.1-1.2) (1.1-1.2) Location Sr-90 8 0.4 0.6 (2/8) 2F3 8.0 mi NNE 0.6 (2/8) No Control 0 (0.6) (0.6) Location N
ID Gamma 8 - (0/8) None Detected - (0/8) No Control 0 Location Benthos Sr-89 7 0.02 - (0/5) None Detected - (0/2) 0 (pCi/g-dry) - Sr-90 7 0.02 0.03 (1/5) ?El 4.5 mi SE 0.03 (1/2) - (0/2) 0 (0.03) (0.03) Sediment Sr-90 8 0.02 - (0/6) None Detected - (0/2) 0 (pCi /g-dry) Gamma 8 K-40 12 (6/6) 12Cl 2.5 mi WSW 13 (2/2) 13 (2/2) 0 (9.1-14) (12-14) (12-14) 16Fl 6.9 mi NNW 13 (2/2) (12-14) Co-60 0.03 0.07 (1/6) 11Al 0.2 mi SW 0.07 (1/2) - (0/2) 0 (0.07) (0 .07) Cs-137 0.03 0.11 (5/6) llAl 0.2 mi SW 0.14 (2/2) - (0/2) 0 (0 .05-0 .17) (0.11-0.17) 16Fl 6.9 mi NNW 0.14 (1/2) (0 .14) Ra-226 0.53 (6/6) 12Cl 2.5 mi WSW 0.79 (2/2) 0.79 (2/2) 0 (0.45-0.72) (0.73-0.84) (0.73-0.84) Th-232 0.75 (6/6) 16Fl 6.9 mi NNW 0.98 (2/2) 0.87 (212) 0 (0.54-1.3) (0.65-1.3) (0.80-0.94)
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 SALEM COUNTY, NEW JERSEY JANUARY 1, 1982 TO DECEMBER 31, 1982 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYS6S DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Milk I-131 139 0.03 - (0/116) None Detected - (0/23) 0 ( pCi /l) Sr-89 72 1.3 6.9 {1/60) 13E3 4.9 mi W 6. 9 (1/12) - (0/12) 0 (6.9) (6.9) Sr-90 72 1.4 2.7 (57/60) OF2 7.lJ mi E 4 .2 ( 12/12) 3.8 (12/12) 0 (1.1-5.4) (3 .4-5 .4) (2.7-4.6) Gamma 72 K-40 1479 (60/60) 2F4 6.3 mi NNE 1583 ( 12/ 12) 1381 (12/12) 0 (900-2700) ( 1100-2700) (770-1800) Cs-137 1.1 2.9 (21/60) 2F4 6.3 mi NNE 3.4 (4/12) 1.6 (4/12) 0 ( 1.4-8. 7) (1.5..:8. 7) (1.4-1.9) w Edible Fish H-3 6 112 81 (1/4) llAl 0.2 mi SW 81 (1/2) - (0/2) 0 0 (pCi/l) (aqueous) (81) (81) H-3 6 214 701 (3/4) 12Cl 2.5 mi WSW 1740 (1/2) 1740 (1/2) 0 (organic) (134-1800) (1740) (1740) (pCi/g-dry) Sr-89 6 0.02 - (0/4) None Detected - (0/2) 0 (bones) Sr-90 6 0.03 0.09 (2/4) 12Cl 2.5 mi WSW 0.16 (2/2) 0.16 (2/2) 0 (bones) (0.05-0.13) (0 .10-0. 21) (0.10-0.21) (pCi/g-wet) Gamma 6 K-40 3.0 (4/4) 12Cl 2.5 mi WSW 3.4 (2/2) 3.4 (2/2) 0 (2.9-3.1) (3.1-3. 7) (3.1-3.7) Blue Crab Sr-89 5 0.04 - (0/3) 12Cl 2.5 mi WSW 0.2 (1/2) 0.2 (1/2) 0 (pCi/g-dry) (shells) (0.2) (0.2) Sr-90 5 0.25 (3/3) llAl 0.2 mi SW 0.25 (3/3) 0.14 (2/2) 0 (shells) (0.14-0.31) (0 .14-0. 31) (0.09-0.19) (pCi/l) H-3 4 112 230 (1/2) llAl 0.2 mi SW 230 (1/2) 157 (1/2) 0 (flesh) (230) (230) (157) (pCi/g-wet) Sr-89 4 0.006 - (0/2) None Detected - (0/2) 0 (flesh) Sr-90 4 0.006 0.006 (1/2) llAl 0.2 mi SW 0.01 (2/2) 0.01 (2/2) 0 (flesh) (0.006) (0.005-0.014) (0.005-0.014) Gallilla 4 K-40 2.05 (2/2) llAl 0.2 mi SW 2.05 (2/2) 2.05 (2/2) 0 (2.0-2.1) (2.0-2.1) (2.0-2.1) 12Cl 2.5 mi WSW 2.05 (2/2) (2.0-2.1)
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 SALEM COUNTY, NEW JERSEY JANUARY 1, 1982 TO DECEMBER 31, 1982 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION*WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Fruits &Vegetables Sr-89 23 0.003 - (0/14) None Detected - (0/9) 0 (pCi/g-wet) Sr-90 23 0.002 0.02 (9/14) 5Dl 3.5 mi E 0.03 (3/4) 0.01 (7/9) 0 (0 .002-0 .08) (0.006-0.08) (0.003-0.02) Gamma 23 K-40 2.8 {14/14) 5Dl 3.5 mi E 4.5 (4/4) 2.1 (9/9) 0 (1.2-12) (1.8-Fl (0.94-3.4) Game Sr-89 2 0.03 0.07 {1/1) 3El 4.1 mi NE 0.07 {1/1) - (0/1) 0 (pCi/g-dry) (bones) (0.07) (0 .07) Sr-90 2 0.09 {1/1) 3El 4.1 mi NE 0.09 {1/1) 0.08 (1/1) 0 (bones) (0.09) (0.09) (0.08) {pCi/g-wet) Gamma 2 (flesh) K-40 2.3 {1/1) 3El 4.1 mi NE 2. 3 ( 1/1) 2.0 ( 1/1) 0 (2.3) (2.3) (2.0) Beef Gamma 2 (pCi/g-wet) K-40 1.1 {1/1) 14Fl 5.5 mi WNW 2.2 {1/1) 2. 2 ( 1/1) 0 ( 1.1) (2.2) (2.2) Bovine Thyroid Gamma 2 (pCi/g-wet) K-40 0.6 - (0/1) 14Fl 5.5 mi WNW 2.3 (1/1) 2. 3 ( 1/1) 0 (2.3) (2.3) Fodder Crops Gamma 10 (pCi/g-~1et) K-40 5.0 (7/7) 3Gl 17 mi NE 8.1 (3/3) 8.1 (3/3) 0 (2.9-14) (2.7-18) (2.7-'18)
- LLD listed is the lowest calculated LLD during reporting period. Strontium-89 and -90 detection levels are Minimum Detectable Levels (MDLs).
- Mean calculated using values above LLD or MDL only. Fraction of measurements above LLD or MDL are in parentheses.
JIPPENDIX B SAMPLE DESIGNATION MID LOCATIONS 33
APPENDIX B Sample Designation RMC identifies samples by a three part code. The first two letters are the power station identification code, in this case nsAn. The next three letters are for the media sampled. AIO = Air Iodine GAM = Game APT = Air Particulates IDM = Immersion Dose (TLD) ECH = Hard Shel*l Blue Crab MLK = Mi 1k ESB = Benthos PWR = Potable Water (Raw) ESF = Edible Fish PWT = Potable Water (Treated) ESS = Sediment RWA = Rain Water FPB = Beef SWA = Surface Water FPV = Food Products, Various THB = Bovine Thyroid FPG = Grains VGT = Fodder Crops; Vegetation FPL = Green Leafy Vegetables WWA = Well Water The last four symbols are a location code based on direction and distance from the site. Of these, the first two represent each of the sixteen angular sectors of 22.5 degrees centered about the reactor site. Sector one is divided evenly by the north axis and other sectors are numbered in a clockwise direction; i.e., 2=NNE, 3=NE, 4=ENE, etc. The next digit is a letter which represents the radial distance from the plant: s = On-site location E = 4-5 miles off-site A = 0-1 miles off-site F = 5-10 miles off-site B = 1-2 miles off-site G = 10-20 mi 1es off-site c 2-3 miles off-site H = >20 miles off-site D = 3-4 miles off-site The last number is the station numerical designation within each sector and zone; e.g., 1,2,3, ... For example, the designation SA-WWA-5Dl would indicate a sample in the SNGS program SA, consisting of well water (WWA), which had been collected in the 22.5 degree sector centered on each axis (5), at a distance of 3 to 4 miles off-site (D). The number 1 indicates that this is sampling station
- 1 in the designated area.
35
Sampling Locations All sampling locations and specific information about the individual locations are given in Table B-1. Maps B-1 and B-2 show the locations of sampling stations with respect to the site. TABLE B-1 STATION STATION SAMPLE CODE TYPES lFl 5.8 mi. N of vent; Fort Elfsborg 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 lGl 13 mi. N of vent; local farm FPB, Fl?V 1G3 19 mi. N of vent; Wilmington, Delaware IOM 2S2 0.4 mi. NNE of vent APT ,AIO, IDM 2El 4.4 mi. NNE of vent; local farm IDM, FPV 2F2 8.7 mi. NNE of vent; Salem Substation APT ,AIO,RWA, IDM 2F3 8.0 mi. NNE of vent; Salem Water Company PWR,PWT 2F4 6.3 mi. NNE of vent; local farm MLK,VGT,FPG,FPL 2F5 7.4 mi. NNE of vent; Salem High School IDM 2Hl 34 mi. NNE of vent; RMC, Phi 1a. IDM 3El 4.1 mi. NE of vent; local farm IDM,WWA,THB,GAM,FPB 3F2 5.1 mi. NE of vent; Hancocks Bridge Municipal Bldg. IDM 3F3 8.6 mi. NE of vent; Quinton Township School IDM 3Gl 17 mi. NE of vent; local farm IDM,MLK,FPG,VGT 3Hl 32 mi. NE of vent; National Park, N.J. IDM 3H3 110 mi. NE of vent; Maplewood Laboratories APT ,AIO, IDM 3H4 88 mi. NE of vent; 1oca1 farm FPV,FPG,FPL 4Sl 1400 ft. ENE of vent; site well #5 WWA 4D2 3.7 mi. ENE of vent; Alloway Creek Neck Road IDM 36
TABLE B-1 (CONT.) STATION STATION SAMPLE CODE LOCATION TYPES 5Sl 1.0 mi. E of vent; site access road APT ,AIO, IDM 5Dl 3.5 mi. E of vent; local farm APT ,AIO, ID~, WWA, FPV,FPG,VGT 5Fl 8.0 mi. E of vent IDM, FPV 5F2 7.0 mi. E of vent; local farm MLK,VGT 6S2 0.2 mi. ESE of vent; observation bldg. IDM 6Fl 6.4 mi. ESE of vent; Stow Neck Road IDM 7Sl 0.12 mi. SE of vent; station personnel gate IDM 7El 4.5 mi. SE of vent; 1 mi. Wof Mad Horse Creek SWA,ESB,ESS,ESF 7F2 9.1 mi. SE of vent; Bayside, New Jersey IDM 9El 4.2 mi. S of vent IDM lOSl 0.14 mi. SSW of vent; site shoreline IDM lODl 3.9 mi. SSW of vent; Taylor's Bridge Spur APT ,AIO, I DM 10F2 5.8 mi. SSW of vent IDM lOGl 12 mi. SSW of vent; Smyrna, Delaware IDM llSl 0.09 mi. SW of vent; site shoreline IDM llAl 0.2 mi. SW of vent; outfall area SWA,ESB,ESS,ESF, ECH llDl 3.5 mi. SW of vent GAM 11E2 5.0 mi. SW of vent IDM llFl 5.2 mi. SW of vent; Taylor's Bridge, Delaware IDM 12Cl 2.5 mi. WSW of vent; west bank of Delaware River SWA,ESF,ECH,ESB, ESS 12El 4.4 mi. WSW of vent; Thomas Landing IDM 12Fl 9.4 mi. WSW of vent; Townsend Elementary School IDM 13El 4.2 mi. Wof vent; Diehl House Lab IDM 37
TABLE B-1 (CONT.) STATION STATION SAMPLE CODE LOCATION TYPES 13E3 4.9 mi. Wof vent; local farm MLK 13Fl 9.8 mi. Wof vent; Middletown, Delaware IDM 13F2 6.5 mi. Wof vent; Odessa, Delaware IDM 13F3 9.3 mi. Wof vent; Redding Middle School, Middletown, DE IDM 14Dl 3.4 mi. WNW of vent; Bay View, Delaware IDM 14Fl 5.5 mi. WNW of vent; local farm MLK,FPB,THB,VGT 14F2 6.6 mi. WNW of vent; Boyds Corner IDM 14F3 5.0 mi. WNW of vent; local farm FPV,FPG,FPL 15Fl 5.2 mi. NW of vent; local farm MLK,FPG,VGT 15F3 5.4 mi. NW of vent IDM 16El 4.1 mi. NNW of vent; Port Penn APT , AIO , IDM 16Fl 6.9 mi. NNW of vent; C & D Canal SWA,ESB,ESS 16F2 8.1 mi. NN\~ of vent; Delaware City Public School IDM 16Gl 15 mi. NNW of vent; Greater Wilmington Airport IDM 38
MAP B-1 ON SITE SAMPLING LOCATIONS ARTIFICIAL
- ISLAND 0
SCALE Of MILES 39
MAP B-2 OFF SITE SAMPLING LOCATIONS ARTIFICIAL ISLAND
!OF2 0 1 2
- 3 4 H-H I SCALI Of MILES 1061 40
APPENDIX C 1982 DATA TABLES 41
DATA TABLES Appendix C presents the analytical results of the 1982 Artificial Island Radiological Environmental Monitoring Program for the period of January 1 to December 31. TABLE TABLE TITLE PAGE NUMBER C-1 Concentrations of Gross Alpha Emitters in Air Particulates ....... 45 C-2 Concentrations of Gross Beta Emitters in Air Particulates 46 C-3 Concentrations of Strontium-89 and -90 and Gamma Emitters in Quarterly Composites of Air Particulates ........................ . 48 C-4 Concentrations of Iodine-131 in Filtered Air .................... . 52 C-5 Sampling Dates for Air Samples .................................. . 54 C-6 Concentrations of Tritium in Precipitation ...................... . 59 C-7 Concentrations of Gross Alpha and Gross Beta Emitters in Precipi ta ti on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 60 C-8 Concentrations of Strontium-89 and -90 and Gamma Emitters in Quarterly Composites of Precipitation ........................... . 61 C-9 Direct Radiation Measurements - Monthly TLD Results ............. . 62 C-10 Direct Radiation Measurements - Quarterly TLD Results ........... . 63 C-11 Direct Radiation Measurements - Semi-Annual TLD Results ......... . 64 C-12 Concentrations of Tritium in Surface Water .*..................... 65 C-13 Concentrations of Gross Alpha Emitters in Surface Water ......... . 67 C-14 Concentrations of Gross Beta Emitters in Surface Water .......... . 68 C-15 Concentrations of Gamma Emitters in Surface Water ............... . 69 C-16 Concentrations of Strontium-89 and ~go in Surfa~e Water ......... . 70 C-17 Concentrations of Tritium in Wel 1 Water ......................... . 72 C-18 Concentrations of Gross Alpha and Gross Beta Emitters, and Potas s i um-40 in We 11 Water ...................................... . 73 C-19 Concentrations of Gamma Emitters in Quarterly Composites of Well Water . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 74 C-20 Concentrations of Strontium-89 and -90 in Quarterly Composites of Well Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 75 43
DATA TABLES (cont.) TABLE TABLE TITLE PAGE NUMBER C-21 Concentrations of Tritium in Raw and Treated Potable Water 76 C-22 Concentrations of Tritium, Gross Alpha and Gross Beta Emitters, and Potassium-40 in Raw and Treated Potable Water ................. 77 C-23 Concentrations of Strontium-89 and -90 in Quarterly Composites of Pot ab 1e Water . . . . . . . . . . . . . . . . * . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 78 C-24 Concentrations of Strontium-89 and -90, and Gamma Emitters in Quarterly Composites of Potable Water . . . . . . * . . . . . . . . . . . . . . . . . . . . . . 79 C-25 Concentrations of Strontium-89 and -90 in Benthos 80 C-26 Concentrations of Strontium-90 and Gamma Emitters in Sediment..... 81 C-27 Concentrations of Iodine-131 in Milk .............................. 82 C-28 Concentrations of Gamma Emitters and Strontium-89 and -90 in Milk.. 83 C-29 Concentrations of Strontium-89 and -90 in Milk.................... 85 C-30 Sampling Dates for Milk Samples .................................... 86 C-31 Concentrations of Gamma Emitters in Edible Fish................... 88 C-32 Concentrations of Strontium-89 and -90, and Tritium in Edible Fish Samples . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 89 C-33 Concentrations of Gamma Emitters in Blue Crab Samples ............ . 90 C-34 Concentrations of Strontium-89 and -90, and Tritium in Blue Crab Samples . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 91 C-35 Concentrations of Strontium-89 and -90 and Gamma Emitters in Food Products . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 92 C-36 Concentrations of Strontium-89 and -90 and Garruna Emitters lin Game, Meat and Bovine Thyroid ............*........................ 93 C-37 Concentrations of Gamma Emitters in Fodder Crop Samples .......... . 94 C-38 LLDs for Gamma Spectrometry ...................................... . 95 44
- 4/4 rec. 3/01/83 TABLE C-1 CONCENTRATIONS OF GROSS ALPHA ErlITTERS m AIR PARTICULATES 3
Results in Units of 10- pCi/m 3 +/- 2 si!Jlla (All Results by PSE&G Research Corporation) STATION NO. JJINUARY* FEB RU MY MMCH APRIL MAY JUNE SA-APT-16El 0.9+/-0.5 1.5+/-0. 7 1.0+/-0.6 0.9+/-0.5 <0.8 1.4+/-0.7 1.4+/-0.6 1. 7+/-0. 6 1.4+/-0. 7 2.0+/-0.7 <0.9 1. 7+/-0. 7 2.0+/-0. 8 <1.1 0.7+/-0.4 4.4+/-1.1 <0.9 1.9+/-1.0 1.6+/-0.7 2.1+/-0.7 2.3+/-0.7 2.1+/-0.7 0.8+/-0.5 2.0+/-0.7
- 1. 2+/-0. 6 1.4+/-0.7 SA-APT-3H3 1. 6+/-0. 6 1.3+/-0.6 1.1+/-0.6 2.0+/-0.7 0.9+/-0.6 1.1+/-0. 6 (Control:) 1. 2+/-0. 6 2.2+/-0.7 1. 5+/-0. 7 2.4+/-0.7 <0.9 0.9+/-0.6 1.7+/-0.6 2.2+/-1.0 0.7+/-0.4 3.7+/-0.9 1.2+/-0.6 1.2+/-0.7 2.2+/-0.8 1. 9+/-0. 7 1.9+/-0.7 1. 4+/-0. 6 0.9+/-0.5 2.8+/-0.9 0.7+/-0.4 2.0+/-0.8 STATION NO. JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE SA-APT-16El 2.0+/-0.7 1. 3+/-0. 8 4.8+/-1. l 1.0+/-0.6 1.2+/-0. 6 1.2+/-0.7 4.5+/-1.1 1.0+/-0.7 <2.3 2.5+/-0.8 2.1+/-0.7 1.3+/-0.5 2.9+/-1.0 2.5+/-0.8 2.0+/-0.7 1.0+/-0.6 1.4+/-0. 7 <1.1 1.6+/-0.7 1.8+/-0.7 1.4+/-0.6 <0.6 .0.7+/-0.4 0.9+/-0.5 2.3+/-0.8 1.6+/-0.8 1. 7+/-1.8 SA-APT-3H3 1.5+/-0.6 1.1+/-0 .8 1.4+/-0.6 0.8+/-0.5 1.1+/-0.6 1.3+/-0.ti (Control) 2. 5+/-1. 0 1.3+/-0.8 1.1+/-0.8 2.4+/-0.7 0.8+/-0.6 0.7+/-0.5 3.9+/-1.0 1.3+/-0.6 2. 4+/-0. 7 1.3+/-0.7 1.1+/-0.6 1.3+/-0.8 1.3+/-0.7 1.4+/-0.6 1.0+/-0.6 1.5+/-0.7 1.2+/-0.6 1.0+/-0.6
- 1. 9+/-0. 7 1.7+/-0.8 1. 5+/-1.4
- Sampling dates can be found on Table C-5.
#6/3 rec. 2/11/83 TABLE C-2 CONCENTRATIONS OF GROSS BETA EMITTERS IN. AIR PARIICULAfES Results in Units of 10-3 pCi/m3 +/- 2 sigma (All Results by PSE&G Research .Corporation)
STATION NO. MONTH SA-APT-2S2 SA-APT-5Sl SA-APT-501 SA-APT-1001 SA-APT-16El SA-APT-lFl SA-APT-2F2 SA-APT-3H3 AVERAGE (Control) JANUARY* 20+/-5 27+/-7 27+/-7 20+/-6 20+/-6 25+/-6 23+/-6 23+/-6 23+/-6 35+/-6 36+/-7 42+/-7 38+/-6 43+/-7 38+/-7 35+/-6 37+/-7 38+/-6 38+/-6 38+/-7 44+/-7 40+/-7 48+/-8 41+/-7 47+/-7 38+/-6 42+/-8 42+/-6 51+/-8 40+/-7 37+/-6 43+/-7 45+/-7 33+/-6 30+/-6 40+/-13 29+/-5 30+/-6 33+/-6 31+/-6 31+/-7 30+/-6 32+/-6 35+/-6 31+/-4 FEBRUARY 24+/-5 27+/-6 30+/-6 26+/-6 30+/-6 30+/-6 27+/-6 28+/-6 28+/-4 ..j::::. 30+/-5 38+/-6 40+/-6 37+/-6 35+/-6 37+/-6 31+/-5 43+/-6 36+/-9 O"I 20+/-6 26+/-7 19+/-6 20+/-6 20+/-6 17+/-6 12+/-5 60+/-9 24+/-30 33+/-7 29+/-6 26+/-6 25+/-5 26+/-6 31+/-6 29+/-6 31+/-6 29+/-6 MARCH 25+/-6 26+/-6 28+/-6 29+/-6 20+/-6 26+/-6 27+/-6 27+/-6 26+/-5 32+/-7 34+/-6 33+/-7 37+/-6 35+/-7 35+/-7 33+/-6 33+/-7 34+/-3 13+/-6 14+/-6 17+/-6 14+/-6 14+/-6 12+/-5 13+/-5 16+/-5 14+/-3 30+/-6 26+/-6 31+/-6 31+/-5 34+/-6 26+/-6 27+/-5 25+/-5 29+/-6 APRIL 33+/-6 30+/-6 31+/-6 29+/-6 31+/-7 28+/-6 30+/-6 30+/-6 30+/-3 45+/-7 35+/-6 46+/-7 33+/-5 33+/-6 38+/-6 36+/-6 45+/-7 39+/-11 39+/-7 33+/-6 34+/-6 34+/-6 33+/-6 33+/-6 34+/-6 38+/-6 35+/-5 32+/-6 31+/-6 38+/-7 29+/-5 32+/-6 32+/-6 32+/-6 34+/-6 33+/-5 31+/-6 27+/-6 32+/-6 35+/-7 32+/-7 29+/-6 29+/-6 31+/-7 31+/-5 MAY 30+/-7 25+/-7 27+/-6 26+/-6 27+/-6 29+/-6 26+/-6 30+/-6 28+/-4 23+/-6 25+/-6 17+/-5 16+/-5 21+/-6 21+/-5 19+/-5 17+/-6 20+/-6 20+/-6 14+/-5 14+/-5 14+/-5 15+/-5 16+/-5 18+/-5 26+/-5 17+/-8 16+/-5 14+/-5 14+/-4 9.2+/-4.1 13+/-5 8.5+/-4.3 15+/-5 11+/-4 13+/-5 JUNE 20+/-7 10+/-5 11+/-5 8.4+/-5.1 8.7+/-5.5 9.7+/-5.0 11+/-5 12+/-5 11+/-7 25+/-7 19+/-6 15+/-5 21+/-5 19+/-5 15+/-5 18+/-5 18+/-5 19+/-6 24+/-6 28+/-6 20+/-6 18+/-6 23+/-6 21+/-5 20+/-5 20+/-5 22+/-6 32+/-7 27+/-7 23+/-6 21+/-5 22+/-6 16+/-5 19+/-5 25+/-6 23+/-10
TABLE C-2 (cont.) CONCENTRATIONS OF GROSS BETA EMITTERS IN AIR PARTICULATES Results in Units of 10-3 pCi/m3 +/- 2 sigma (All Results by PSE&G Research Corporation) STATION rm. MONTH SA-APT-2S2 SA-APT-5Sl SA-APT-5Dl SA-APT-1001 SA-APT-16El SA-APT-lFl SA-APT-2F2 SA-APT-3H3 AVERAGE (Control) JULY 19+/-6 17+/-6 26+/-6 25+/-6 23+/-7 22+/-6 25+/-6 22+/-6 22+/-6 25+/-8 16+/-7 17+/-6 26+/-6 34+/-7 23+/-7 22+/-7 27+/-8 24+/-12 26+/-7 22+/-6 20+/-6 22+/-6 25+/-7 23+/-6 25+/-6 26+/-7 24+/-4 36+/-7 24+/-7 26+/-8 36+/-7 32+/-7 23+/-6 32+/-7 27+/-7 30+/-10 35+/-7 33+/-7 28+/-7 29+/-6 31+/-7 34+/-7 28+/-7 28+/-7 31+/-6 Pl.JGUST 30+/-7 25+/-7 29+/-6 29+/-6 30+/-7 28+/-6 25+/-6 27+/-6 28+/-4 22+/-7 23+/-7 20+/-6 25+/-6 27+/-7 26+/-6 29+/-7 21+/-7 24+/-6 33+/-7 30+/-7 25+/-6 28+/-6 42+/-8 29+/-6 36+/-7 29+/-6 32+/-11 27+/-3 26+/-3 25+/-3 24+/-3 21+/-3 27+/-3 24+/-3 23+/-3 25+/-4 SEPTEMBER 28+/-3 21+/-2 24+/-2 24+/-2 27+/-3 27+/-3 25+/-3 19+/-2 24+/-6 ~ 35+/-8 37+/-8 27+/-7 -.....i 27+/-7 20+/-12 35+/-8 36+/-8 42+/-8 32+/-14 38+/-7 36+/-7 36+/-6 31+/-6 42+/-7 41+/-7 40+/-7 36+/-7 38+/-7 21+/-2 21+/-2 20+/-2 23+/-2 19+/-2 21+/-3 19+/-2 23+/-2 21+/-3 OCTOBER 21+/-6 21+/-6 17+/-5 21+/-6 24+/-6 21+/-6 27+/-6 16+/-5 21+/-7 53+/-4 44+/-3 44+/-3 46+/-3 43+/-3 45+/-3 47+/-3 43+/-3 46+/-7
. 26+/-3 20+/-3 21+/-3 21+/-3 23+/-3 21+/-3 25+/-3 27+/-3 23+/-5 22+/-3 15+/-2 16+/-2 17+/-2 16+/-2 19+/-3 17+/-2 17+/-2 17+/-4 47+/-4 36+/-3 38+/-3 39+/-3 39+/-3 45+/-3 38+/-3 43:!.:3 41+/-8 NOVEMBER 23+/-3 15+/-3 19+/-2 22+/-3 22+/-3 22+/-3 24+/-3 23+/-3 21+/-6 31+/-3 29+/-3 31+/-3 29+/-3 28+/-3 28+/-3 28+/-3 29+/-3 29+/-2 21+/-3 23+/-3 20+/-3 19+/-3 19+/-3 21+/-3 22+/-3 25+/-3 21+/-4 21+/-2 19+/-3 19+/-2 21+/-2 18+/-2 19+/-2 20+/-2 22+/-3 20+/-3 DECEMBER 18+/-2 14+/-2 13+/-2 20+/-3 14+/-3 14+/-2 14+/-3 18+/-3 16+/-5 24+/-2 26+/-3 22+/-3 23+/-2 24+/-2 23+/-2 23+/-3 26+/-3 24+/-3 24+/-3 22+/-3 20+/-3 20+/-3 19+/-3 22+/-3 21+/-3 22+/-3 21+/-3 28+/-6 28+/-7 18+/-5 23+/-5 22+/-5 21+/-5 26+/-6 21+/-6 23+/-7 AVERAGE 28+/-16 26+/-17 26+/-18 26+/-16 27+/-18 26+/-18 26+/-16 28+/-19 Grand Average 27+/-17
- Sampling dates can be found on Table C-5.
TABLE C-3 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND GAMMA EMITTERS** Hl QUARTERLY COMPOSITES OF AIR PARTICULATES Results in Units of 10-3 pCi/m3 +/- 2 sigma (All Results by PSE&G Research Corporation) STATION NUMBER AND DATE Sr-89 Sr-90 Be-7 Cs-137 Ce-144 SA-APT-2S2 12-28-81 to <0.3 0.28+/-0.09 51+/-5 <0.6 <3.0 3-29-82 3-29-82 to <0.4 <0.3 67+/-5 <0.6 <2.4 6-28-82 .+::> 00 6-28-82 to <0.3 <0.2 56+/-5 <0.5 <2.5 9-27-82 9-27-82 to <0.8 <0.6 44+/-4 <0.4 <2.3 12-27-82 SA-APT-5Sl 12-28-81 to <0.4 <0.3 49+/-4 <0.6 1.5+/-0.8 3-29-82 3-29-82 to <0.5 <0.3 55+/-6 <0.7 <3.5 6-28-82 6-28-82 to <0.4 <0.2 36+/-5 <0.6 <2.4 9-27-82 9-27-82 to <0.9 <0.7 39+/-5 <0.7 <2.4 12-27-82
TABLE C-3 (cont.) CONCENTRATIONS OF STRONTIUM-89* AND -90 AND GAMMA EMITTERS** IN QUARTERLY COMPOSITES OF AI.R PARTICULATES Results in Units of 10-3 pCi/rn3 +/- 2 sigma (All Results by PSE&G Research Corporation) STATION NUMBER AND DATE Sr-89 Sr-90 Be-7 Cs-137 Ce-144 SA-APT-5Dl 12-28-81 to <0.5 0.4+/-0.1 46+/-4 <0.6 1.4+/-0.7 3-29-82 3-29-82 to <0.6 <0.4 49+/-4 <0.5 1. 6+/-0 .8 6-28-82 +::> l.O 6-28-82 to <0.3 <0.2 33+/-4 <0.8 <2.8 9-27-82 9-27-82 to <0.4 <0.3 33+/-4 <0.4 <1.6 12-27-82 SA-APT-lODl 12-29-81 to <0.4 <0.3 40+/-5 <0.7 <3.2 3-30-82 3-30-82 to <0.6 <0.4 43+/-4 <0.4 <2.1 6-29-82 6-29-82 to <0.3 <0.2 29+/-4 <0.7 <2.2 9-28-82 9-28-82 to <0.8 <0.5 30+/-3 <0.5 <1.6 12-28-82
TABLE C-3 (cont.) 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 (All Results by PSE&G Research Corporation) STATION NUMBER AND DATE Sr-89 Sr-90 Be-7 Cs-137 Ce-144 SA-APT-16El 12-29-81 to <0.7 <0.4 43+/-5 <0.7 <3.5 3-30-82 3-30-82 to <0.4 <0.3 53+/-5 0.7+/-0.3 <3.5 6-29-82 (Jl 0 6-29-82 to <0.3 <0.2 33+/-4 <1.1 <3.5 9-28-82 9-28-82 to <0.8 <0.6 35+/-4 <0.5 <2.1 12-28-82 SA-APT-lFl 12-28-81 to <0.4 <0.3 49+/-4 <0.4 <2.3 3-29-82 3-29-82 to <0.6 <0.4 51+/-4 <0.5 <2.1 6-28-82 6-28-82 to <0.3 <0.2 42+/-4 <0.8 <3.2 9-27-82 9-27-82 to <0.6 <0.5 32+/-3 <0.4 <2.2 12-27-82
I
' . Ii'l TABLE C-3 leant.)
CONCENTRATIONS OF STRONTIUM-89* AND -90 AND GAMMA EMITTERS** IN QUARTERLY COMPOS !TES OF AIR PARTICULATES Results in Units of io- 3 pCi/m3 +/- 2 sigma (All Results by PSE&G Research Corporation) STATION NUMBER AND DATE Sr-89 Sr-90 Be-7 Cs-137 Ce-144 SA-APT-2F2 12-28-81 to <0.4 0.3+/-0.1 44+/-4 <0.6 1.8+/-1. 0 3-29-82 3-29-82 to <0.4 <0.3 64+/-6 0.5+/-0.3 2.2+/-1.1 6-28-82 6-28-82 to <0.4 <0.2 42+/-4 <0.4 <2.3 (.J1 9-27-82 I-' 9-27-82 to <1.3 <0.9 37+/-4 <0.6 <2.3 12-27-82 SA-APT-3H3 (Contra 1) 12-28-81 to <1.1 1.0+/-0.3 48+/-4 <0.5 1.5+/-0.8 3-29-82 3-29-82 to <0.7 <0.5 60+/-6 <0.8 <3.3 6-28-82 6-28-82 to <0.3 <0.2 49+/-4 <1.0 <2.3 9-27-82 9-27-82 to <0.8 <0.6 40+/-4 <0.4 <1.7 12-27-82
- Strontium-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-38.
TABLE C~4 CONCENTRATIOl~S OF IOOINE-131* IN FILTERED AIR Results in Units of io-3 pCi/m3 STATION NO. MONTH SA-AI0-2S2 SA-AI0-551 SA-AI0-501 SA-AI0-1001 SA-AI0-16El SA-AI0-2F2 SA-AI0-3H3 (Control) JANUARY** <13 <18 <16 <16 <18 <15 <16
<9.6 <15 <11 <9.6 <11 <11 <13
<10 <16 <11 <13. <15 <11 <13
<9.1 <14 <10 <9.6 <10 <9.6 <11
<9.8 <13 <11 <11 <12 <10 <12 FEBRUARY <11 <16 <12 <13 <14 <12 <13
<8.6 <10 <9.0 <9.6 <10 <8.9 <9.8 CJ1 <18 <16 <16 <15 <15 <15 <16 N <13 <11 <13 <10 <10 <11 <12 MARCH <14 <13 <13 <13 <15 <14 <13
<13 <9.9 <13 <9.4 <10 <11 <11
<9.7 <14 <13 <15 <14 <13 <13
<10 <8.8 <9.7 <8.3 <8.9 <9.5 <10 APRIL <12 <12 <12 <13. <13 <13 <13
<11 <9.8 <10 <9 .1 <10 <10 <11
<12 <12 <11 <12 <12 <12 <13
<10 <9.1 <10 <8.6 <9.2 <9.7 <11
<9.0 <8.6 <9.9 <11 <12 <11 <14 MAY <14 <12 <11 <10 <10 <11 <11
<11 <10 <10 <13 <13 <11 <14
<12 <8.8 <9.3 <11. <11 <8.8 <9.8
<9.1 <8.6 <7.9 <9.1 <9.2 <10 <9.5 JUNE <14 <13 <11 <14 <16 <13 <14
<15 <13 <13 <11 <11 <12 <13
<14 <12 <14 <14 <15 <13 <14
<11 <10 <9.7 <9.4 <9.3 <10 <12
TABLE C-4 (cont.) CONCEtlTRATIONS OF IODINE-131* IN FILTERED AIR Results in Units of 10-3 pCi/m3 i I; STATION rm. MONTH SA-AI0-252 SA-AI0-5S 1 SA-AI0-501 SA-AI0-1001 SA-AI0-16El SA-AI0-2F2 SA-AI0-3H3 (Control)
<31 (1)
~1)
JULY <44 ( 1) <32 (1) <29 (1) <32 (1)
<60
<33 (1 (ll <60 (1)
<45 (1)
<28 ~ 1)
<37 1)
<44 (1)
<46 (1)
<48
<52 1 Pl
<30
<55
<42 B
<33 (1)
<57 (1)
<48 (1)
<18 <18 <21 <16 <15 <17 <20
<14 <17 <16 <16 <19 <19 <20 JU GUST <18 <16 <16 <16 <16 <18 <18
<13 <11 <11 <11 <12 <12 <14
< 17 <16 <15 <15 <17 <15 <17
<13 <10 <12 <13 <13 <15 <13 U"1 SEPTEMBER <10 <12 <13 <12 w <17 <14 <14
<14 <11 <11 <12 <26 <13 <13
<9.3 <11 <11 <12 <13 <12 <12
<16 <14 <15 <14 <14 <18 <19 OCTOBER <12 <12 <12 <14 <13 <13 <12
<13 <9.4 <9.2 <11 <9.8 <10 <9.8
<14 <12 <10 <12 <12 <13 <13
<14 <11 <9.3 <10 <10 <12 <11
<9.8 <11 <10 <11 <12 <12 <13 NOVEMBER <9.9 <15 <9.1 <9.8 <11 <10 <11
<7.5 <9.8 <8.3 <7.1 <6.8 <8.6 <9.0
<7.7 <8.0 <7.5 <8.6 <9.8 <8.3 <8.9
<7.2 <7.9 <7.0 <6.4 <6.9 <7 .5 <8.6 DECEMBER <8. 2 <8.5 <8.3 <9.8 <11 <9.6 <9.8
<12 <13 <13 <11 <11 <14 <14
<9.6 <10 <9.4 <12 <13 <10 <12
<47 ( 1) <53 (1) <48 (1) <41 (1) <22 (1) <26 (1) <31 (1)
- I-131 results are corrected for decay to sample stop date.
** Actual sampling dates can be found on Table C-5.
(1) High LLD due to delay in counting resulting fran equipment malfunction.
TABLE C-5 SAMPLING DATES .FOR AIR.S.AJllPLES. STATION NO. MONTH 2S2 5Sl 501 1001 16El lfl 2F2 3H3 JANUARY 12-28-81 12-28-81 12-28-81 12-29-81 12-29-81 12-28-81 12-28-81 12-28-81 to to to to to to to to 1-04-82 1-04-82 1-04-82 1-04-82 1-04-82 1-04-82 1-04-82 1-04-82 1-04-82 1-04-82 1-04-82 1-04-82 1-04-82 1-04-82 1-04-82 1-04-82 to to to to to to to to 1-11-82 1-11-82 1-11-82 1-12-82 1-12-82 1-11-82 1-11-82 1-11-82 1-11-82 1-11-82 1-11-82 1-12-82 1-12-82 1-11-82 1-11-82 1-11-82 to to to to to to to to 1-18-82 1-18-82 1-18-82 1-18-82 1-18-82 1-18-82 1-18-82 1-18-82 1-18-82 1-18-82 1-18-82 1-18-82 1-18-82 1-18-82 1-18-82 1-18-82 to to to to to to to to 1-25-82 1-25-82 1-25-82 1-26-82 1-26-82 1-25-82 1-25-82 1-25-82 (J1 .+:> 1-25-82 1-25-82 1-25-82 1-26-82 1-26-82 1-25-82 1-25-82 1-25-82 to to to to to to to to 2-01-82 2-01-82 2-01-82 2-02-82 2-02-82 2-01-82 2-01-82 2-01-82 FEBRUARY 2-01-82 2-01-82 2-01-82 2-02-82 2-02-82 2-01-82 2-01-82 2-01-82 to to to to to to to to 2-08-82 2-08-82 2-08-82 2-08-82 2-08-82 2-08-82 2-08-82 2-08-82 2-08-82 2-08-82 2-08-82 2-08-'82 2-08-82 2-08-82 2-08-82 2-08-82 to to to to to to to to 2-16-82 2-16-82 2-16-82 2-16-82 2-16-82 2-16-82 2-16-82 2-16-82 2-16-82 2-16-82 2-16-82 2-16-82 2-16-82 2-16-82 2-16-82 2-16.:82 to to to to to to to to 2-22-82 2-22-82 2-22-82 2-22-82 2-22-82 2-22-82 2-22-82 2-22-82 2-22-82 2-22-82 2-22-82 2-22-82 2-22-82 2-22-82 2-22-82 2-22-82 to to to to to to to to 3-01-82 3-01-82 3-01-~2 3-02-82 3-02-82 3-01-82 3-01-82 3-01-82 MARCH 3-01-82 3-01-82 3-01-82 3-02-82 3-02-82 3-01-82 3-01-82 3-01-82 to to to to to to to to 3-08-82 3-08-82 3-08-82 3-08-82 3-08-82 3-08-82 3-08-82 3-08-82 3-08-82 3-08-82 3-08-82 3-08-82 3-08-82 3-08-82 3-08-82 3-08-82 to to to to to to to to 3-15-82 3-15-82 3-15-82 3-16-82 3-16-82 3-15-82 3-15-82 3-15-82
TABLE C*-5 (cont.) SAMPLING DATES FOR AIR SAMPLES STATION NO. MONTH 2S2 5Sl 501 1001 16El lfl 2F2 3H3 MARCH 3-15-82 3-15-82 3-15-82 3-16-82 3-16-82 3-15-82 3-15-82 3-15-82 to to to to to to to to 3-22-82 3-22-82 3-22-82 3-22-82 3-22-82 3-22-82 3-22-82 3-22-82 3-22-82 3-22-82 3-22-82 3-22-82 3-22-82 3-22-82 3-22-82 3-22-82 to to to to to to to to 3-29-82 3-29-82 3-29-82 3-30-82 3-30-82 3-29-82 3-29-82 3-29-82 APRIL 3-29-82 3-29-82 3-29-82 3-30-82 3-30-82 3-29-82 3-29-82 3-29-82 to to to to to to to to 4-05-82 I 4-05-82 4-05-82 4-05-82 4-05-82 4-05-82 4-05-82 4-05-82 4-05-82 4-05-82 4-05-82 4-05-82 4-05-82 4-05-82 4-05-82 4-05-82 to to to to to to to to 4-12-82 4-12-82 4-12-82 4-13-82 4-13-82 4-12-82 4-12-82 4-12-82 (J1 (J1 4-12-82 4-12-82 4-12-82 4-13-82 4-13-82 4-12-82 4-12-82 4-12-82 . to to to to to to to to 4-19-82 4-19-82 4-19-82 4-19-82 4-19-82 4-19-82 4-19-82 4-19-82 4-19-82 4-19-82 4-19-82 4-19-82 4-19-82 4-19-82 4-19-82 4-19-82 to to to to to to to to 4-26-82 4-26-82 4-26-82 4-27-82 4-27-82 4-26-82 4-26-82 4-26-82 4-26-82 4-26-82 4-26-82 4-27-82 4-27-82 4-26-82 4-26-82 4-26-82 to to to to to to to to 5-04-82 5-04-82 5-03-82 5-03-82 5-03-82 5-03-82 5-03-82 5-02-82 MAY 5-04-82 5-04-82 5-03-82 5-03-82 5-03-82 5-03-82 5-03-82 5-02-82 to to to to to to to to 5-10-82 5-10-82 5-10-82 5-11-82 5-11-82 5-10-82 5-10-82 5-10-82 5-10-82 5-10-82 5-10-82 5-11-82 5-11-82 5-10-82 5-10-82 5-10-82 to to to to to to to to 5-17-82 5-17-72 5-17-82 5-17-82 5-17-82 5-17-82 5-17-82 5-16-82 5-17-82 5-17-82 5-17-82 5-17-82 5-17-82 5-17-82 5-17-82 5-16-82 to to to to to to to to 5-25-82 5-25-82 5-25-82 5-24-82 5-24-82 5-25-82 5-25-82 5-24-82 5-25-82 5-25-82 5-25-82 5-24-82 5-24-82 5-25-82 5-25-82 5-24-82 to to to to to to to to 6-02-82 6-02-82 6-02-82 6-01-82 6-01-82 6-01-82 6-01-82 6-01-82
TABLE C-5 (cont.) SAMPLING DATES FOR AIR SAMPLES STATION NO. MONTH 2S2 5Sl 501 1001 16El lFl 2F2 3H3 JUNE 6-02-82 6-02-82 6-02-82 6-01-82 6-01-82 6-01-82 6-01-82 6-01-82 to to to to to to to to 6-08-82 6-08-82 6-08-82 6-07-82 6-07-82 6-07-82 6-07-82 6-07-82 6-08-82 6-08-82 6-08-82 6-07-82 6-07-82 6-07-82 6-07-82 6-07-82 to to to to to to to to 6-14-82 6-14-82 6-14-82 6-15-82 6-15-82 6-14-82 6-14-82 6-14-82 6-14-82 6-14-82 6-14-82 6-15-82 6-15-82 6-14-82 6-14-82 6-14-82 to to to to to to to to 6-21-82 6-21-82 6-21-82 6-21-82 6-21-82 6-21-82 6-21-82 6-21-82 6-21-82 6-21-82 6-21'-82 6-21-82 6-21-82 6-21-82 6-21-82 6-21-82 to to to to to to to to 6-28-82 6-28-82 6-28-82 6-29-82 6-29-82 6-28-82 6-28-82 6-28-82 CJ1 JULY 6-28-82 6-28-82 6-28-82 6-29-82 6-29-82 6-28-82 6-28-82 6-28-82 O'I to to to to to to to to 7-06-82 7-06-82 7-06-82 7-06-82 7-06-82 7-06-82 7-06-82 7-06-82 7-06-82 7-06-82 7-06-82 7-06-82 7-06-82 7-06-82 7-06-82 7-06-82 to to to to to to to to 7-12-82 7-12-82 7-12-82 7-13-82 7-13-82 7-12-82 7-12-82 7-12-82 7-12-82 7-12-82 7-12-82 7-13-82 7-13-82 7-12-82 7-12-82 7-12-82 to to to to to to to to 7-19-82 7-19-82 7-19-82 7-19-82 7-19-82 7-19-82 7-19-82 7-19-82 7-19-82 7-19-82 7-19-82 7-19-82 7-19-82 7-19-82 7-19-82 7-19-82 to to to to to to to to 7-26-82 7-26-82 7-26-82 7-27-82 7-27-82 7-26-82 7-26-82 7-26-82 7-26-82 7-26-82 7-26-82 7-27-82 7-27-82 7-26-82 7-26-82 7-26-82 to to to to to to to to 8-02-82 8-02-82 8-02-82 8-03-82 8-03-82 8-02-82 8-02-82 8-02-82 AUGUST 8-02-82 8-02-82 8-02-82 8-03-82 8-03-82 8-02-82 8-02-82 8-02-82 to to to to to to to to 8-09-82 8-09-82 8-09-82 8-10-82 8-10-82 8-09-82 8-09-82 8-09-82 8-09-82 8-09-82 8-09-82 8-10-82 8-10-82 8-09-82 8-09-82 8-09-82 to to to to to to to to 8-16-82 8-16-82 8-16-82 8-17-82 8-17-82 8-16-82 8-16-82 8-16-82
TABLE C-5 (cont.) SAMPLING DATES FOR AIR SAMPLES STATION tlO. MONTH 2S2 5Sl 501 1001 16El lFl 2F2 3H3 AUGUST 8-16-82 8-16-82 8-16-82 8-17-82 8-17-82 8-16-82 8-16-82 8-16-82 to to to to to to to to 8-23-82 8-23-82 8-23-82 8-24-82 8-24-82 8-23-82 8-24-82 8-23-82 8-23-82 8-23-82 8-23-82 8-24-82 8-24-82 8-23-82 8-24-82 8-23-82 to to to to to to to to 8-30-82 8-30-82 8-30-82 8-31-82 8-31-82 8-30-82 8-30-82 8-30-82 SEPTEMBER 8-30-82 8-30-82 8-30-82 8-31-82 8-31-82 8-30-82 8-30-82 8-30-82 to to to to to to to to 9-07-82 9-o"7-82 9-07-82 9-08-82 9-07-82 9-07-82 9-07-82 9-07-82 9-07-82 9-07-82 9-07-82 9-0B-82 9-07-82 9-07-82 9-07-82 9-07-82 to to to to to to to to 9-13-82 9-13-82 9-13-82 9-14-82 9-14-82 9-13-82 9-13-82 9-13-82 U1 "'-J 9-13-82 9-13-82 9-13-82 9-14-82 9-14-82 9-13-82 9-13-82 9-13-82 to to to to to to to to 9-20-82 9-20-82 9-20-82 9-20-82 9-20-82 9-20-82 9-20-82 9-20-82 9-20-82 9-20-82 9-20-82 9-20-82 9-20-82 9-20-82 9-20-82 9-20-82 to to to* to to to to to 9-27-82 9-27-82 9-27-82 9-28-82 9-28-82 9-27-82 9-27-82 9-27-82 OCTOBER 9-27-82 9-27-82 9-27-82 9-28-82 9-28-82 9-27-82 9-27-82 9-27-82 to to to to to to to to 10-04-82 10-04-82 10-04-82 10-04-82 10-04-82 10-04-82 10-04-82 10-04-82 10-04-82 10-04-82 10-04-82 10-04-82 10-04-82 10-04-82 10-04~82 10-04-82 to to to to to to to to 10-12-82 10-12-82 10-12-82 10-12-82 10-12.,-82 10-12-82 10-12-82 10-12-82 10...;12-82 10-12-82 10-12-82 10-12-82 10-12-82 10-12-82 10-12-82 10-12-82 to to to to to to to to 10-18-82 10-18-82 10-18-82 10-18-82 10-18-82 10-18-82 10-18-82 10-18-82. 10-18-82 10-18-82 10-18-82 10-18-82 10-18-82 10-18-82 10-18-82 10-18-82 to to to to to to to to 10-25-82 10-25-82 10-25-82 10-26-82 10-26-82 10-25-82 10-25-82 10-25-82 10-25-82 10-25-82 10-25-82 10-26-82 10-26-82 10-25-82 10-25-82 10-25-82 to to to to to to to to 11-01-82 11-01-82 11-01-82 11-01-82 11-01-82 11-01-82 11-01-82 11-01-82
TABLE C-5 (cont.) SAMPLING DATES FOR AIR SAMPLES STATION NO. MONTH 2S2 5Sl 5Dl lODl 16El lFl 2F2 3H3 NOVEMBER 11-01-82 11-01-82 11-01-82 11-01-82 11-01-82 11-01-82 11-01-82 11-01-82 to to to to to to to to 11-08-82 11-09-82 11-08-82 11-08-82 11-08-82 11-08-82 11-08-82 11-08-82 11-08-82 11-09-82 11-08-82 11-08-82 11-08-82 11-08-82 11-08-82 11-08-82 to to to to to to to to 11-15-82 11-15-82 11-15-82 11-16-82 11-16-82 11-15-82 11-15-82 11-15-82 11-15-82 11-15-82 11-15-82 11-16-82 11-16-82 11-15-82 11-15-82 11-15-82 to to to to to t<J to to Ul 11-22-82 11-22-82 11-22-82 11-22-82 11-22-82 11-22-82 11-22-82 11-22-82 co 11-22-82 11-22-82 11-22-82 11-22-82 11-22-82 11-22-82 11-22-82 11-22-82 to to to to to to to to 11-29-82 11-29-82 11-29-82 11-30-82 11-30-82 11-29-82 11-29-82 11-29-82 DECEMBER 11-29-82 11-29-82 11-29-82 11-30-82 11-30-82 11-29-82 11-29-82 11-29-82 to to to to to to to to 12-06-82 12-06-82 12-06-82 12-06-82 12-06-82 12-06-82 12-06-82 12-06-82 12-06-82 12-06-82 12-06-82 12-06-82 12-06-82 12-06-82 12-06-82 12-06-82 to to to to to to to to 12-13-82 12-13-82 12-13-82 12-14-82 12-14-82 12-13-82 12-13-82 12-13-82 12-13-82 12-13-82 12-13-82 12-14-82 12-14-82 12-13-82 12-13-82 12-13-82 to to to to to to to to 12-20-82 12-20-82 12-20-82 12-20-82 12~20-82 12-20-82 12-20-82 12-20-82 12-20-82 12-20-82 12-20-82 12-20-82 12-20-82 12-20-82 12-20-82 12-20-8*2 to to to to to to to to 12-27-82 12-27-82 12-27-82 12-28-82 12-28-82 12-27-82 12-27-82 12-27-82
TABLE C-6 CONCENTRATIONS OF TRITIUM IN PRECIPITATION STATION SA-RWA-2F2 Results in Units of pCi/l +/- 2 sigma (All Results by PSE&G Research Corporation) COLLECTION PERIOD H-3 12-29-81 to 2-01-82 <130 2-01-82 to 3-02-82 <130 CJ1 <..O 3-02-82 to 3-29-82 140+/-70 3-29-82 to 4-27-82 <130 4-27-82 to 6-01-82 <120 6-01-82 to 6-29-82 <120 6-29-82 to 7-26-82 160+/-80 7-26-82 to 8-31-82 140+/-80 8-31-82 to 9-27-82 <130 9-27-82 to 11-01-82 <130 11-01-82 to 11-30-82 <130 11-30-82 to 12-28-82 <140
TABLE C-7 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS IN PRECIPITATION STATION SA-RWA-2F2 Results in Units of pCi/l +/- 2 sigma COLLECTION PERIOD ALPHA BETA 12-29-81 to 2-01-82 0.5+/-0.4 4. 4+/-1. 7 2-01-82 to 3-02-83 0.8+/-0.6 5.4+/-1.4 3-02-82 to 3-29-82 0.5+/-0.4 5 .1+/-2. 4 3-29-82 to 4-27-82 <0.7 5.1+/-2.2 O"I 0 4-27-82 to 6-01-82 <0.6 8. 3+/-1. 8 6-01-82 to 6-29-82 <1.0 4.1+/-2.0 6-29-82 to 7-26-82 2.0+/-1.0 12+/-3 7-26-82 to 8-31-82 1. 5+/-0. 9 16+/-3 8-31-82 to 9-27-82 (1) (1) 9-27-82 to 11-01-82 <1.1 2.4+/-1.6 11-01-82 to 11-30-82 <1.1 <2.2 11-30-82 to 12-28-82 <1.1 <3.7 Average 6.3+/-8.5 (1) Entire sample used for strontium analyses.
TABLE C-8 CONCENTRATIONS OF STRONTILJr1-89* /lJ'm -90 Nm GAM11A EMITTERS** IN QUARTERLY COMPOSITES OF PRECIPITATION STATION: SA-RWA-2F2 Results in Units of pCi /1 +/- 2 sigma 12-29-81 3-29-82 6-29-82 9-27-82 to to to to NUCLIDE 3-29-82 6-29-82 9-27-82 12-28-82 0) I-"' Sr-89 <0.2 <0.3 <2.7 <0.5 Sr-90 <0.2 <0.3 <1.1 <0.4 K-40 <16 14+/-7 <7.8 26+/-3
- Sr-89 results are corrected for decay to sample stop date.
** All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-38.
TABLE C-9 DIRECT RADIATION MEASUREMENTS - MONTHLY TLD RESULTS mrad/standard month* STATION NUMBER JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-IDM-2S2 5.26+/-0.55 5.06+/-0.18 4.47+/-0.55 5.12+/-0.65 4.88+/-0.28 5.46+/-0.40 SA-IDM-5Sl 4.45+/-0.44 4.26+/-0.30 4.04+/-0.17 4.72+/-0.27 4.53+/-0.31 4.69+/-0.52 SA'-IDM-6S2 5.36+/-0.68 4.91+/-0.52 4.60+/-0.44 5.49+/-0.55 4.97+/-0.18 6.56+/-0.75 SA-IDM-7Sl 6.68+/-0.72 5.89+/-0.44 5.55+/-0.46 6.10+/-0.76 6.05+/-0.38 6.18+/-0.52 SA- I DM- lOS 1 6.27+/-0.26 6.04+/-1.08 6.06+/-0.52 6.65+/-0.74 6.15+/-0.42 6.94+/-0.82 SA- IDM- llS 1 5.41+/-0.62 6.50+/-0.72 6.69+/-0.48 8.84+/-0.51 6.22+/-0.41 5.74+/-0.50 SA-IDM-5Dl 4.63+/-0.59 5.10+/-0.40 4. 62+/-0 .11 5.03+/-0.08 4.82+/-0.25 6.00+/-0.31 SA-IDM-lODl 5.03+/-0.57 5.47+/-0.21 4.85+/-0.43 5.72+/-0.73 5.47+/-0.70 6.10+/-0.32 SA- IDM-14Dl 5.58+/-0.21 5.64+/-0.20 5.23+/-0.20 6.11+/-0.31 5.49+/-0.18 6.12+/-0.22 SA-IDM-2El 4.77+/-0.32 4.85+/-0.33 4.67+/-0.29 5.48+/-0.44 5.24+/-0.42 5.28+/-0.17 SA-IDM-3El 4. 74+/-0. 59 4.83+/-0.87 4.54+/-0.59 5.61+/-0.68 5.46+/-0.27 5.66+/-0.75 SA-IDM-13El 4.89+/-0.25 5.04+/-0.93 5.56+/-0.73 5.49+/-0.25 4.87+/-0.74 5. 71+/-0. 50 SA-IDM-16El 5.09+/-0. 80 5.25+/-0.52 4.67+/-0.62 5.87+/-0.75 5.58+/-0.49 5.85+/-0.72 SA-IDM-lFl 5.33+/-0.97 5.26+/-0.28 4.42+/-0.75 5.92+/-0.19 5. 74+/-0. 87 5.97+/-0.68 SA-IDM-2F2 4.56+/-0.83 4.01+/-0.22 3.87+/-0.70 4.55+/-0.33 4.15+/-0.33 5.06+/-0.19 SA-IDM-5Fl 4.83+/-0.53 4.87+/-0.74 4.69+/-0.34 5.53+/-0.51 5.01+/-0.39 5.76+/-0.50 SA-IDM-6Fl 4.53+/-0.51 4.38+/-0.49 3.65+/-0.54 4.63+/-0.64 4:55+/-0.25 5.03+/-0.60 SA-IDM-7F2 4.07+/-0.51 3.79+/-0.65 3.78+/-0.62 3.94+/-0.68 4.15+/-0.06 4.67+/-0.43 SA-IDM-llFl 5.52+/-0.46 5.87+/-0.23 5.35+/-0. 81 5.94+/-0.85 5.72+/-0.49 6.35+/-0.29 SA-IDM-13Fl 4.91+/-0.27 5.32+/-1. 20 4.63+/-0.44 5.37+/-0.38 5.29+/-0.06 6.27+/-0.46 SA-IDM-3Gl 5.57+/-0.94 5.19+/-0.64 5.26+/-0.56 6.11+/-0. 47 5.95+/-0.09 6.41+/-0.66 SA-IDM-2Hl 6.23+/-0.70 4.05+/-0.57 4.67+/-0.43 5.51+/-0.27 5. 72+/-0 .58 7.51+/-0.10 SA-IDM-3Hl 5.34+/-0.79 5.81+/-1.04 4.85+/-1.06 6.18+/-0.52 6.02+/-0.59 6.12+/-0.85 SA-IDM-3H3 5.37+/-0.56 5.43+/-0.12 5.16+/-0.71 5. 96+/-1.01 5.56+/-0.87 6.41+/-0.58 AVERAGE 5.18+/-1.23 5.12+/-1.36 4.83+/-1.41 5.66+/-1.83 5.32+/-1.21 5.91+/-1.34 STATION NUMBER JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE SA-IDM-2S2 5.49+/-0.55 5.49+/-0.51 4.44+/-0.44 5.81+/-0.69 5.49+/-0.37 9.26+/-2.02 5.52+/-2.50 SA-IDM-5Sl 5.13+/-0.77 5.28+/-0.24 4.32+/-0.19 5.44+/-0.22 5.27+/-0.54 6.38+/-0.55 4.88+/-1.31 SA-IDM-6S2 6.29+/-0.73 5.52+/-0.50 5.04+/-0.48 6.31+/-0.64 6.14+/-0.18 7. 70+/-1. 26 5. 74+/-1. 77 SA-IDM-7Sl 7.09+/-0.49 7.02+/-0.48 6.08+/-0. 67 6. 69+/-1.03 7.06+/-0.86 7.76+/-1.24 6.51+/-1.28 SA-IDM-lOSl 6.72+/-0.24 8.09+/-0.61 8.31+/-0. 63 7.41+/-0.73 6.86+/-0.62 7.72+/-0.76 6.94+/-1.58 SA-IDM-llSl 6.93+/-0.39 11.50+/-0.41 19.63+/-1.74 8.58+/-0.63 6.19+/-0.45 9.56+/-2.00 8.48+/-7.90 SA-IDM-5Dl 5.46+/-0.71 5.92+/-0.52 4.68+/-0.54 5.71+/-0.58 5.50+/-0.52 8.32+/-0.92 5.48+/-2.04 SA- IDM-lODl 6.52+/-0.44 6.12+/-0.71 5.56+/-0.21 6.75+/-0.30 6.83+/-0.76 6.44+/-0.51 5.91+/-1.31 SA-IDM-14Dl 6.75+/-0.41 6.82+/-0.20 5.67+/-0.69 6.63+/-0.54 6.37+/-0.83 6.29+/-0.65 6.06+/-1.06 SA-IDM-2El 6.24+/-0.29 6.21+/-0.07 5.35+/-1.04 6.34+/-0.34 5.79+/-0.62 5.93+/-0.21 5.51+/-1.18 SA-IDM-3El 5.85+/-0.29 5.68+/-0.45 5.39+/-0.48 5.93+/-0.65 6.17+/-0.04 8.25+/-0.46 5.68+/-1.90 SA-IDM-13El 5.47+/-1.07 5.93+/-0.49 4.91+/-0.79 5.76+/-0.40 5.61+/-0.26 5.73+/-0.15 5.41+/-0.76 SA-IDM-16El 6.42+/-0.66 5.56+/-0.69 5.43+/-0.74 6.31+/-0.88 6.64+/-0.53 5.93+/-0 .89 5. 72+/-1.15 SA-IDM-lFl 6.30+/-0.20 6.57+/-0.62 5.45+/-1.12 7.02+/-0.69 6.52+/-0.29 5.84+/-0.40 5 .86+/-1.40 SA-IDM-2F2 5.21+/-0.59 4.58+/-0.40 4.00+/-0.20 5.65+/-0.37 5.02+/-0.07 4.47+/-0.37 4.59+/-1.10 SA-IDM-5Fl 6.13+/-0.36 5.16+/-0.48 5.10+/-0. 73 5.84+/-0.98 5.80+/-0.55 5.52+/-0.26 5.35+/-0.94 SA-IDM-6Fl 5.23+/-0.26 4.52+/-0.51 3.93+/-0.64 4.88+/-0.23 5.26+/-0.50 4.79+/-0.29 4.62+/-0.96 SA-IDM-7F2 4.82+/-0.56 4.02+/-0.11 3.91+/-0.44 4.50+/-0.34 4.38+/-0.49 4.43+/-0.50 4.21+/-0.69 SA-IDM-llFl 6.57+/-0.74 5.90+/-0.67 5.81+/-0.85 6.82+/-0.73 6.46+/-0.26 6.55+/-0.52 6.07+/-0.93 SA- IDM-13Fl 6.12+/-0.33 5.40+/-0.54 5.23+/-0.88 6.11+/-0. 61 6.39+/-0.80 5.72+/-0.68 5. 56+/-1.12 SA-IDM-3Gl 7 .15+/-0 .33 6.17+/-1.09 6.10+/-0.31 6.85+/-0.83 6.52+/-0.38 6.36+/-0.68 6 .14+/-1.18 SA-IDM-2Hl 5.17+/-0.33 6.20+/-0.52 5.33+/-0.27 7.00+/-0.47 5.33+/-1. 26 5.91+/-0.40 5.72+/-1.90 SA-IDM-3Hl 6.79+/-0.21 6.95+/-0.30 5.31+/-0.12 6.83+/-0.52 6.64+/-0.81 6.42+/-0.37 6.11+/-1.35 SA-IDM-3H3 6. 69+/-1.11 6.27+/-0.53 5.70+/-0.31 6.65+/-0.78 6.96+/-0.42 6.72+/-0.25 6.07+/-1.24 AVERAGE 6.11+/-1.40 6.12+/-2.89 5.86+/-6.14 6.33+/-1.70 6.05+/-1.40 6.58+/-2.73 5.76+/-2.62
- The standard month = 30.4 days.
62
TABLE C-10 DIRECT RADIATION MEASUREMENTS - QUARTERLY TLD RESULTS mrad/standard month* JANUARY APRIL JULY OCTOBER to to to to AVERAGE STATION NUMBER MARCH JUNE SEPTEMBER DECEMBER SA-IDM-2S2 4.23+/-0.19 5. 33+/-0. 30 3.98+/-0.57 4.48+/-0.56 4.51+/-1.17 SA-IDM-5Sl 3. 77+/-0.16 4.58+/-0.31 4.32+/-0.44 4.85+/-0.29 4.38+/-0.92 SA-IDM-6S2 4. 61+/-0. 89 5.32+/-0.29 4.69+/-0.26 4.64+/-0.39 4.82+/-0.68 SA-IDM-7Sl 5.73+/-0.34 5. 79+/-0.23 6.08+/-0.61 6.26+/-0.78 5.97+/-0.50 SA- IDM- lOS 1 5.52+/-0. 39 6.07+/-0.23 6.51+/-0.12 6.45+/-0.62 6.14+/-0.91 SA- IDM- llS 1 5.72+/-0.63 6.13+/-0.10 11.60+/-0.12 6.49+/-0.50 7.49+/-5.52 SA-IDM-501 4.26+/-0.44 5.13+/-0.24 5.87+/-0.09 4.66+/-0.90 4. 98+/-1. 38 SA-IDM-1001 5.27+/-0.32 5.84+/-0.11 5.80+/-0.13 5.25+/-0.89 5.54+/-0.65 SA-IDM-1401 5.11+/-0.24 5.42+/-0.30 5.80+/-0.18 5.45+/-1.11 5.45+/-0.56 SA-IDM-2El 4.97+/-0.28 5.41+/-0~25 5.17+/-0.10 5. 71+/-0.53 5.32+/-0.64 SA-IDM-3El 4.65+/-0.45 5.01+/-0.14 5.63+/-0.14 5.52+/-1.11 5.20+/-0.91 SA-IDM-13El 4.60+/-0.35 5.33+/-0.17 4.25+/-0.09 4.61+/-0.66 4.70+/-0.91 SA- IDM-16E 1 4.83+/-0.54 5.16+/-0.21 5. 78+/-0.24 5.33+/-0.24 5.28+/-0.79 SA-IDM-lFl 4.99+/-0. 71 5.20+/-0.25 5.32+/-0.30 4.90+/-0.91 5 .10+/-0. 38 SA-IDM-2F2 3. 75+/-0.29 4. 72+/-0.17 4.03+/-0.34 3.61+/-0.24 4.03+/-0.99 SA-IDM-5Fl 4.28+/-0.37 5.01+/-0.21 4.61+/-0.14 4.78+/-0.65 4.67+/-0.61 SA-IDM-6Fl 3.75+/-0.39 4.55+/-0.27 4.43+/-0.21 3.69+/-0.19 4.11+/-0.90 SA-IDM-7F2 3.51+/-0.23 3.94+/-0.38 3.89+/-0.15 3.56+/-0 .56 3.73+/-0.44 SA-IDM-llFl 5. 30+/-0. 37 5.82+/-0.21 5.80+/-0.20 5.09+/-0.16 5.50+/-0.73 SA-IDM-13Fl 4.68+/-0.93 5.07+/-0.36 5.33+/-0.25 4. 70+/-0. 75 4.95+/-0.63 SA-IDM-3Gl 5.18+/-0 .63 5.50+/-0.98 5. 88+/-0.21 4.66+/-0.25 5.* 31+/-1. 03 SA-IDM-2H 1 5.14+/-0.51 5.79+/-0.09 5.27+/-0.15 4.81+/-0.06 5.25+/-0.81 SA-IDM-3Hl 4. 77+/-0. 36 5.56+/-0.36 5.49+/-0.25 5.41+/-0.95 5.31+/-0.73 SA-IDM-3H3 5.02+/-0.55 5.47+/-0.20 5.29+/-0.12 5. 35+/-1.06 5.28+/-0.38 SA-IDM-402 ( 1) (1) ( 1) 5.33+/-0.88 5.33 SA-IDM-9El 5.99+/-1.12 5.99 SA-IDM-11E2 5.89+/-1.16 5.89 SA-IDM-12E 1 5.55+/-0.36 5.55 SA-IDM-2F5 4. 72+/-0.13 4.72 SA-IDM-3F2 5.05+/-0.34 5.05 SA-IDM-3F3 4.64+/-0.88 4.64 SA-IDM-1DF2 4.95+/-0.22 4.95 SA-IDM-12Fl 5.48+/-0.25 5.48 SA-IDM-13F2 4.84+/-0.21 4.84 SA-I DM-13F3 5.20+/-0.80 5.20 SA- I DM-14F2 4.97+/-0.76 4.97 SA-IDM-15F3 5.16+/-0.28 5.16 SA- IDM-16F2 5.16+/-0.31 5.16 SA-IDM-163 5.70+/-0.98 5.70 SA-IDM-lOGl 5.07+/-0.22 5.07 SA-IDM-1661 5.43+/-0.88 5.43 AVERAGE 4.74+/-1.25 5. 30+/-1.02 5.45+/-3.01 5.11+/-1. 30 5.14+/-1.80
- *The standard month = 30.4 days.
(1) Beginning in October 1982, semi-annual collections of TLDs were changed to quarterly collections. 63
TABLE C-11 DIRECT RADIATION MEASUREMENTS - SEMI-ANNUAL TLD RESULTS mrad/standard month* SEPTEMBER APRIL STATION NO. TO TO AVERAGE MARCH SEPTEMBER SA-IDM-4D2 4.52+/-0.08 4. 88+/-0.21 4.70+/-0.51 SA-IDM-9El 4.87+/-0.61 5.37+/-0.36 5.12+/-0. 71 SA-IDM-11E2 5.11+/-0. 20 5.75+/-0.53 5.43+/-0.91 SA- I DM-12E 1 5. 30+/-0. 39 5.23+/-0.26 5.27+/-0.10 SA-IDM-2F5 4.38+/-0.86 4.52+/-0.02 4.45+/-0.20 O'l +::> SA-IDM-3F2 4.08+/-0.38 4.15+/-0.06 4.12+/-0 .10 SA-IDM-3F3 4.22+/-0.69 4.22+/-0.22 4.22 SA- I DM-10 F2 5.07+/-0.86 5.29+/-0.19 5.18+/-0.31 SA-I DM-12Fl 5.10+/-0. 75 4. 77+/-0.19 4.94+/-0.47 SA-I DM-13F2 5 .10+/-0. 49 4.56+/-0.48 4. 83+/-0. 76 SA-IDM-13F3 4.87+/-0.17 4. 72+/-0.19 4.80+/-0.21 SA- IDM-14F2 4. 76+/-0. 75 4.68+/-0.20 4.72+/-0.11 SA-IDM-15F3 4.95+/-0.56 5.26+/-0.10 5 .11+/-0. 44 SA- I DM-16F2 4.54+/-0.20 4.94+/-0.56 4.74+/-0.57 SA-IDM-1G3 5.46+/-0.40 5.31+/-0.17 5.39+/-0.21 SA-IDM- lOGl 5.04+/-0.37 5 .21+/-0. 39 5.13+/-0.24 SA-IDM-16Gl 5.65+/-0.65 5.60+/-0.29 5.63+/-0.07 AVERAGE 4.88+/-0.85 4. 97+/-0. 92 4. 93+/-0. 88
- The standard month = 30.4 days.
TABLE C-12 CONCENTRATIONS OF TRITIUM IN SURFACE WATER Results in Units of pCi/l +/- 2 sigma (All Results by PSE&G Research Corporation) STATION NO. 1-07-82 2-16-82 3-11-82 4-05-82 5-03-82 6-08-82 SA-SWA-llAl 330+/-80 <120 <120 <120 230+/-80 <130 SA-SWA-12Cl <120 <120 <120 <120 <130 <120 SA-SWA-7El <120 <130 <130 130+/-70 140+/-70 <130 SA-SWA-1F2 120+/-70 <120 <120 <120 170+/-70 <130 °' CJ1 SA-SWA-16Fl <130 <120 160+/-80 160+/-70 <130 <120 Average 160+/-85 STATION NO. 7-07-82 8-02-82 9-07-82 10-06-82 11-08-82 12-09-82 AVERAGE SA-SWA- llAl 470+/-90 190+/-80 320+/-80 280+/-80 <140 220+/-90 223+/-220 SA-SWA-12Cl 170+/-80 180+/-80 200+/-80 160+/-80 <140 180+/-80 SA-SWA-7El 180+/-80 210+/-80 220+/-80 140+/-80 190+/-80 180+/-80 158+/-71 SA-SWA-1F2 <120 290+/-80 220+/-80 170+/-80 140+/-80 <130 154+/-105 SA-SWA-16Fl <130 190+/-80 230+/-80 150+/-80 180+/-90 <130 153+/-67 Average 214+/-291 212+/-90 238+/-94 180+/-114 158+/-50 168+/-77 167+/-129
TABLE C-12 (cont.) CONCENTRATIONS OF TRITIUM IN SURFACE WATER Results in Units of pCi/l +/- 2 sigma STATION NO.* 1-07-82 2-16-82 3-11-82 4-05-82 5-03-82 6-08-82 SA-SWA-llAl SA-SWA-12Cl <110 <103 <106 <104 86+/-7'3 <110 SA-SWA-7El <104 83+/-73 <110 SA-SWA-1F2 <110 <103 <106 Average 85+/-4 O'l O'l STATION NO. 7-07-82 8-02-82 9-07-82 10-06-82 11-08-82 12-09-82 AVERAGE SA-SWA-11Al 343+/-77 198+/-75 103+/-71 101+/-75 115+/-60 <110 162+/-192 SA-SWA-12Cl <120 124+/-74 <115 237+/-76 105+/-60 <110 SA-SWA-7El SA-SWA-1F2 Average 232+/-315 161+/-105 109+/-17 169+/-192 110+/-14
- For quality assurance purposes, station SWA-12Cl is to be analyzed for tritium on a monthly basis by RMC; in addition, one station a quarter is seiected by PSE&G to receive a monthly tritium analysis.
TABLE C-13 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN SURFACE WATER Results in Units of pCi/l +/- 2 sigma STATION NO. 1-07-82 2-16-82 3-11-82 4-05-82 5-03-82 6-08-82 sA:..swA-11A1 <0.5 <0.3 <0.3 <0.5 <0.3 <0.2 SA-SWA-12Cl <0.3 <0.3 <0.3 <0.3 <0.3 <0.2 SA-SWA-7El <0.4 0.8+/-0.3 <0.3' <0.3 <0.4 <0.3 SA-SWA-1F2 <0.2 <0.3 <0.3 <0.3 <0.3 0.3+/-0.3 SA-SWA-16Fl <0.2 <0.3 <0.3 <0.4 <0.4 <0.4 0) '..J STATION NO. 7-07-82 8-02-82 9-07-82 10-06-82 11-08-82 12-09-82 SA-SWA-llAl <0.2 <0.4 <0.2 <0.4 <0.4 <0.3 SA-SWA-12Cl <0.2 <0.4 <0.2 <0.4 <0.5 0.4+/-0.2 SA-SWA-7El <0.3 <0.4 <0.2 <0.3 <0.5 <0.3 SA-SWA-1F2 <0.3 <0.3 <0.2 <0.3 <1.0 (1) <0.2 SA-SWA-16FJ. <0.2 <0.3 <0.3 <0.4 0.4+/-0.4 <0.3 (1) *Elevated LLD due to small sample size.
TABLE C-14 CONCENTRATIONS OF GROSS BETA EMITTERS IN SURFACE WATER Results in Units of pCi/l +/- 2 sigma STATION NO. 1-07-82 2-16-82 3-11-82 4-05-82 5-03-82 6-08-82 SA-SWA-llAl 56+/-6 24+/-2 45+/-5 6 .1+/-2.2 14+/-3 67+/-7 SA-SWA-12Cl 33+/-4 14+/-2 29+/-4 7.6+/-2.3 5.1+/-2.5 31+/-3 SA-SWA- ?El 73+/-7 26+/-3 64+/-6 18+/-3 33+/-5 66+/-7 SA-SWA-1F2 25+/-4 6.9+/-1.4 14+/-3 5.0+/-2.1 2.6+/-2.3 19+/-3 CJ) SA-SWA-16Fl 26+/-4 11+/-2 30+/-4 4.1+/-2.0 <3.4 24+/-3 00 Average 43+/-42 16+/-17 36+/-38 8+/-11 12+/-26 41+/-47 STATION NO. 7-07-82 8-02-82 9-07-82 10-06-82 11-08-82 12-09-82 AVERAGE SA-SWA- llAl 35+/-5 67+/-7 60+/-7 106+/-11 go+/-9 74+/-8 54+/-60 SA-SWA-12Cl 21+/-4 46+/-5 53+/-6 65+/-7 87+/-9 45+/-5 36+/-48 SA-SWA-7El 34+/-5 72+/-7 86+/-9 117+/-12 112+/-11 82+/-8 65+/-65 SA-SWA-1F2 11+/-3 29+/-4 29+/-5 47+/-6 67+/-7 41+/-5 25+/-39 SA-SWA-16 Fl 16+/-3 31+/-4 50+/-6 72+/-8 86+/-9 46+/-5 33+/-52 Average 23+/-21 49+/-40 56+/-41 81+/-58 88+/-32 58+/-38 43+/-60
TABLE C-15 CONCENTRATIONS OF Glt1MA EMITTERS* rn SURF ACE l~ATER Results in Units of pCi/l +/- 2 sigma STATION NO. NUCLIDE 1-07-82 2-16-82 3-11-82 4-05-82 5-03-82 6-08-82 11, I SA-SWA-llAl K-40 54+/-9 15+/-8 46+/-12 <7.8 <11 53+/-8 I 1 I j I SA-SWA-12Cl K-40 54+/-32 9.7+/-6.9 38+/-8 <11 <9.3 29+/-8 SA-SWA-7El K-40 64+/-15 35+/-8 68+/-10 <9.3 37+/-8 73+/-10 SA-SWA-1F2 K-40 14+/-8 <9.3 12+/-9 <9.3 <7.8 <11 SA-SWA-16Fl K-40 <9.3 <9.3 29+/-8 <7.8 <9.3 16+/-7 O'I Average 39+/-51 16+/-22 39+/-41 36+/-52 l..D STATION NO. NUCLIDE 7-07-82 8-02-82 9-07-82 10-06-82 11-08-82 12-09-82 Average SA-SWA-llAl K-40 43+/-10 76+/-8 70+/-11 120+/-12 70+/-9 76+/-8 53+/-65 SA-SWA-12Cl K-40 22+/-8 50+/-9 62+/-9 74+/-9 83+/-9 59+/-7 42+/-51 SA-SWA-7El K-40 29+/-8 80+/-10 65+/-9 120+/-12 150+/-15 83+/-8 68+/-78 SA-SWA-1F2 K-40 <11 30+/-9 32+/-8 27+/-9 92+/-12 58+/-6 26+/-51 SA-SWA-16Fl K-40 <9.3 28+/-8 55+/-9 73+/-10 81+/-9 50+/-5 31+/-53 Average 23+/-28 53+/-49 57+/-30 83+/-78 95+/-63 65+/-27 44+/-66
- By gamma spectrometry, all other gamma emitters searched for were <LLD; typical LLDs are given in Table C-38.
TABLE C-16 CONCENTRATIONS OF STRONTIUM-89* AND -90 IN SURFACE WATER Resu1ts in Units of pCi/1 +/- 2 sigma (A11 Resu1ts by PSE&G Researcrr Corporation) 1-07-82 4-05-82 7-07-82 10-06-82 STATION to to to to NUMBER 3-11-82 6-08-82 9-07-82 12-09-82 Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 SA-SWA-11Al <1.1 <0.9 <0.8 <0.6 <0.9 <0.7 <0.7 <0.5 SA-SWA-12Cl <0.8 <0.6 <1.0 <0.7 <0.6 <0.5 <0.6 <0.5 SA-SWA-7El <1.2 <0.9 <1.0 <0.7 <0.9 <0.6 <0.6 <0.5 SA-SWA-1F2 <1.0 <0.8 <0.6 <0.4 <0.6 0.5+/-0.2 <0.8 <0.6 SA-SWA-16Fl <0.7 <0.6 <0.8 <0.6 <0.8 <0.6 <0.5 <0.5
- Strontium-89 resu1ts are corrected for decay to samp1e stop date.
TABLE C-16 (cont.) CONCENTRATIONS OF STRONTIUM-89* AND -90 IN SURFACE WATER Results in Units of pCi/l +/- 2 sigma 1-07-82 4-05-82 7-07-82 10-06-82 STATION** to to to to NUMBER 3-11-82 6-08-82 9-07-82 12-09-82 Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 -.....J I-' SA-SWA- llAl <1.6 <0.3 <0.4 <0.3 SA-SWA-12Cl <0.4 0.4+/-0.2 <0.3 <0.3 <1.1 <0.2 <0.4 0.3+/-0.2 SA-SWA-7El <0.6 0.5+/-0.4 SA-SWA-1F2 <0.4 0.5+/-0.3
- Sr-89 results are corrected for decay to sample stop date.
** For quality assurance purposes. station 12Cl is analyzed for Sr-89 *and -90 on a quarterly basis by RMC; in addition, one station a quarter is selected by PSE&G to receive a quarterly composite Sr-89 and -90 analysis.
TABLE C-17 CONCENTRATIONS OF TRITIUM IN WELL WATER Results in Units of pCi/l +/- 2 sigma (All Results by PSE&G Research Corporation) STATION NO. RADIOACTIVITY 1-11-82 2-16-82 3-15-82 4-12-82 5-10-82 6-14-82 SA-WWA-4Sl <120 <120 <120 <120 (1) <120 <120 SA-WWA-501 <120 <120 <120 <120 <120 <120 SA-WWA-3El <120 <120 <120 <120 <120 <120 -.....J N STATIOI~ NO. RAD IOACTI VITV 7-12-82 8-09-82 9-13-82 10-12-82 11-15-82 12-13-82 SA-WWA-4Sl <140 <120 <130 (2) <130 <130 <140 SA-WWA-5Dl <130 <120 <J.20 <130 <130 <140 SA-WWA-3El <130 <J.20 <120 <130 <130 <140 (1) Station WWA-4Sl was collected on 4-19-82. (2) Station W\'IA-4SI vwas collected on 9-14-82
TABLE C-18 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, AND POTASSIUM-40 IN WELL WATER Results in Units of pCi/l +/- 2 sigma STATION NO. RADIOACTIVITY 1-11-82 a-16:..82 3-15-82 4-12-82 5-10-82 6-14-82 SA-WWA-4Sl Alpha <2.4 1. 7+/-1.5 1.4+/-1.3 <0.9 (1) <2.5 <3.6 Beta 14+/-3 12+/-2 13+/-2 13+/-3 12+/-3 14+/-2 K-40 13+/-1 13+/-1 12+/-1 13+/-1 11+/-1 11+/-1 SA-WWA-5Dl Alpha <2.0 1.5+/-1. 2 <1.1 <2.0 <1. 7 <2.7 Beta 13+/-3 13+/-2 14+/-2 15+/-3 12+/-3 12+/-2 K-40 12+/-1 14+/-1 13+/-1 13+/-1 9.9+/-1.0 11+/-1 SA-WWA-3El Alpha <2.1 <1.2 <1.2 <2.1 <1.9 <3.0 Beta 10+/-2 9 .0+/-1.5 9 .3+/-1.5 8.3+/-2.3 8.0+/-2.5 9.3+/-2.1 K-40 8.5+/-0.9 8.5+/-0.9 9.3+/-0.9 7.5+/-0.8 8.7+/-0.9 9.0+/-0.9 STATION NO. RADIOACTIVITY 7-12-82 8-09-82 9-13-82 10-12-82 11-15-82 12-13-82 SA-WWA-4Sl Alpha <2.2 <1.4 <2.3 (2) <2.7 <2.6 <1.1 Beta 14+/-3 9.3+/-3.2 13+/-3 11+/-3 15+/-3 12+/-3 K-40 10+/-1 9.5+/-I.O 9.5+/-1.0 9.2+/-0.9 9.7+/-1.0 12+/-1 SA-WWA-501 Alpha <1.5 1. 3+/-1.1 <1. 7 <2.2 <1. 9 <0.8 Beta 12+/-3 10+/-3 12+/-3 16+/-3 15+/-3 14+/-3 K-40 11+/-1 9.7+/-1.0 11+/-1 11+/-1 10+/-1 12+/-1 SA-WWA-3El Alpha <1.8 <0.9 <1.8 <2.3 <2.0 <0.9 Beta 9.5+/-2.8 6.2+/-3.0 8.6+/-3.0 8.6+/-2.8 10+/-3 11+/-3 K-40 8.1+/-0.8 7.8+/-0.8 8.4+/-0.8 9.2+/-0.9 7.1+/-0.7 8.2+/-0.8 (1) Station WWA-4Sl was collected on 4-19-82. (2) Station WWA-4Sl was collected on 9-14-82. 73
TABLE C-19 CONCEfffRATIONS OF GA'1~1A EMITTERS* IN QUARTERLY COfWOSITES OF \~ELL WATER Results in Units of pCi/l +/- 2 sigma 1-11-82 4-12-82 7-12-82 10-12-82 STATION NUMBER to to to to RAD IOACTIV ITV 3-15-82 6-14-82 9-13-82 12-13-82 SA-WWA-4Sl K-40 <7.8 <9.3 (l} <7.8 (2) 11+/-3 Others <LLD <LLD <LLD <LLD -.....J +'=> SA-WWA-5Dl K-40 <9.3 <9.3 <9.3 17+/-4 Others <LLD <LLD <LLD <LLD SA-WWA-3El K-40 <11 <11 <9.3 <7.0 Others <LLD <LLD <LLD <LLD
*(1) All gamma emitters searched for were <LLD; typical LLDs are given in Table C-38.
Start date for station l'J\~A-451 was 4-19-82. (2) Stop date for station \~WA-451 was 9-14-82.
TABLE C-20 CONCENTRATIONS OF STRONTIUM-89* AND -90 IN QUARTERLY COMPOSITES OF WELL ~~ATER Results in Units of pCi/l +/- 2 sigma (All Results by PSE&G Research Corporation) 1-11-82 4-12-82 7-12-82 10-12-82 STATION -NUMBER to to to to RAD IOACTI VITV 3-15-82 6-14-82 9-13-82 12-13-82 SA-WWA-4Sl Sr-89 <0.6 <0.5 (1) <0.5 (2) <0.5 --.J Sr-90 <0.5 <0.4' <0.4 <0.4 tn SA-WWA-501 Sr-89 <0.8 <0.5 <0.5 <0.5 Sr-90 <0.7 <0.4 <0.4 <0.4 SA-WWA-3El Sr-89 <0.7 <0.5 <0.5 <0.5 Sr-90 <0.6 <0.3 <0.4 <0.4
- Sr-89 results are corrected for decay to sample stop date.
(i) Start date for station WWA-4Sl was 4-19-82. ( 2) Stop date for station WWA-4Sl was 9-14-82.
TABLE C-21 CONCENTRATIONS OF TRITIUM W RAW AND TREATED POTABLE WATER Results in Units of pCi/l +/- 2 sigma (All Results by PSE&G Research Corporation) STATION RADIOACTIVITY Ji\NUARY FEBRUARY MARCH APRIL MAY JUNE SA-PWR-2F3 (Raw) <140 <120 <130 130+/-80 <120 <130 -....J Ol SA-PWT-'2F3 (Treated) 170+/-90 <120 <130 <120 <120 <130 STATION RADIOACTIVITY JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER SA-PWR-2F3 (Raw) 150+/-80 <130 140+/-80 <130 <140 <140 SA-PWT-2F3 (Treated) <130 <130 130+/-80 <130 <130 <140
TABLE C-22 CONCENTRATIONS OF TRITIUM, GROSS ALPHA AND GROSS BETA EMITTERS, AND POTASSIUM-40 IN RAW AND TREATED POTABLE WATER STATION SA-PWA-2F3 Results in Units of pCi/l +/- 2 sigma RADIOACTIVITY JANUARY FEBRUARY MARCH APRIL MAY JUNE H-3* {Jrea:ted) <118 <101 <104 93+/-74 <112 <122 Alpha (Raw) 1.1+/-0.6 0 .8+/-0 .5 0.7+/-0.5 1.1+/-0 .6 L3+/-0.7 2 .9+/-1.0 (Treated) 0.7+/-0.6 0.6+/-0.5 0.6+/-0.5 0.9+/-0.7 <1.0 3.1+/-1.3 Beta (Raw) 4.4+/-0.6 3.9+/-0.5 2.9+/-0.4 3.9+/-0.5 4.2+/-0.6 2.7+/-0.4 (Treated) 3.8+/-0.5 2.6+/-0.5 2.7+/-0.4 3.0+/-0.5 3.9+/-0.5 2.5+/-0.4 K-40 (Raw) 3.2+/-0.3 2.4+/-0.2 1.9+/-0.2 2.0+/-0.2 1.5+/-0.2 2.3+/-0.2 "" (Treated) 2.9+/-0 .3 2.7+/-0.3 2.4+/-0.2 1. 6+/-0 .2 2.5+/-0.3 2.5+/-0.3 RADIOACTIV ITV JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE H-3* (Treated) <119 <121 <121 <108 <109 <110 Alpha (Raw) <l.O <0.8 1.0+/-0 .5 <0.6 <0.7 0 .8+/-0 .5 1.1+/-1. 2 (Treated) <1. 3 <0.9 <0.5 <0.8 <0.8 <0.9 Beta (Raw) 2.6+/-0.5 2.7+/-0.6 2.7+/-0.4 2.0+/-0.4 3.3+/-0.5 2.6+/-0.4 3.1+/-1.5 (Treated) 2.4+/-0.5 1. 7+/-0 .4 2.0+/-0.4 2.0+/-0.4 2.4+/-0.5 2.4+/-0.4 2.6+/-1.3 K-40 (Raw) 2.2+/-0.2 2.0+/-0.2 2.1+/-0.2 2.1+/-0.2 2.3+/-0.2 2.3+/-0.2 2.2+/-0.8 (Treated) 2.3+/-0.2 1.1+/-0 .1 1. 3+/-0 .1 2.1+/-0.2 1.8+/-0. 2 2.4+/-0.2 2.1+/-1.1
- For quality assurance purposes, treated potable water sam~les are analyzed for tritium on a monthly basis.
TABLE C-23 CONCENTRATIONS OF STRONTIUM-89* AND -90 IN QUARTERLY COMPOSITES OF POTABLE WATER Results in Units of pCi/l +/- 2 sigma (All Results by PSE&G Research Corporation) 1-01-82 4-01-82 7-01-82 10-01-82 STATION to to to to RAD I OACT IV ITV 3-31-82 6-30-82 9-30-82 12-31-82 SA-PWR-2F3 -....J co (Raw) Sr-89 <1.3 1.2+/-0 .4 1.2+/-0.5 <0.5 Sr-90 <0.9 <0.7 <0.7 <0.4 SA-PWT-2F3 (Treated) Sr-89 <0.9 <0.8 1.1+/-0. 3 <0.7 Sr-90 0.6+/-0.3 0.6+/-0.2 <0.5 <0.5
- Sr-89 results are corrected for decay to stvnple stop date.
TABLE C-24 CONCENTRATIONS OF STRONTIUM-89* AND -90, AND GAMMA EMITTERS** IN QUARTERLY COMPOSITES OF POTABLE l~ATER STATION SA-PWA-2F3 Results in Units of pCi/l +/- 2 sigma 1-01;..82 4-01-82 7-01-82 10-01-82 to to to to SAMPLE 3-31-82 6-30-82 9-30-82 12-31-82 Raw -....J Gamma l.C Emitters <LLD <LLD <LLD <LLD Treated*** Sr-89 <0.3 <0.3 <0.4 <0.4 Sr-90 0.6+/-0.3 <0.3 -<0.3 <0.3 Gemma Emitters <LLD <LLD <LLD <LLD
- 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-38.
*** For quality assurance purposes, treated potable water samples are analyzed for Sr-89 and Sr-90 on a quarterly basis.
TABLE C-25 CONCENTRATIONS OF Sr-89* AND -90 IN BENTHOS Results in Units of pCi/gldry} +/- 2 sigma STATION NUMBER DATE Sr-89 Sr-90 SA-ESB-llAl 6-08-82 <0.02 <0.02 10-05-82 <3.4 <1.6 SA-ESB-12Cl 6-08-82 <0.03 <0.03 co 10-05-82 <5.6 <2.8 0 SA-ESB-7El 6-08-82 <0.03 0.03+/-0.02 10-05-82 <1.5 <0.8 SA-ESB-16Fl 6-08-82 (1) (1) 10-05-82 <24 (2) <12 (2)
- Sr-89 results are decay corrected to sample stop date.
(1) Insufficient sample for analysis. (2) High MDL due to small sample size.
TABLE C-26 CONCENTRATIONS OF STRONTIUM-90 AND GAMMA* EMITTERS IN SEDIMENT** Results in Units of pCi/g(dry) +/- 2 sigma STATION NO. SA-ESS-llAl SA-ESS-12Cl SA-ESS-7El SA-ESS-16F 1 DATE 6-08-82 10-05-82 6-08-82 10-05-82 6-08-82 10-05-82 6-08-82 10-05-82 Sr-90 <0.03 <0.04 <0.02 <0.05 <0.03 <0.04 <0.05 <0.05 K-40 13+/-1 11+/-1 14+/-1 12+/-1 12+/-1 9.1+/-0.9 14+/-1 12+/-1 Co-60 0.07+/-0.03 <0.04 <0.03 <0.03 <0.04 <0.03 <0.03 <0.03 Cs-137 0.11+/-0.02 0.17+/-0.02 <0.03 <0.03 0.07+/-0.02 0.05+/-0.02 <0.03 0.14+/-0.02 Ra-226 0.52+/-0.05 0.56+/-0.06 0.84+/-0.08 0.73+/-0.07 0.47+/-0.05 0.45+/-0.05 o. 72+/-0.07 0.48+/-0.05 Th-232 0.74+/-0.07 0.72+/-0.07 0J94+/-0.09 0.80+/-0.08 0.54+/-0.07 0.54+/-0.06 1.3+/-0.1 0.65+/-0.07
- All other gamma emitters <LLD; typical LLDs are given in Table C-38.
- Sediment samples inc 1uded associated benth ic organisms.
TABLE C-27 CONCENTRATIONS OF IODINE-131 IN MILK Results* i.n Units of pCi/l JANUARY** FEBRUARY MARCH APRIL MAY JUNE STATION NO.
<0.07 <0.09 <0.06 <0.1 <0.07 <0.08 SA-MLK-13E3 <0.1 <0.08
<0.07 <0.07 <0.09 <0.08
<0.06 <0.1 <0.08 <0.1 <0.09 <0.08 SA-MLK-2F4 <O.l <0.09
<0.07 <0.06 <0.1 <0.08
<0.07 <0.1 <0.08 <0.1 <0.09 <0.1 SA-MLK-5F2 <0.08 <0.1 <0.1
<0.07 <0.08 <0.1
<0.07 <O.l <0.07 <0.1 <O.l <O.l SA-MLK-14Fl <0.09 <0.1 <O.l
<0.08 <0.08 <0.09
<0.08 <0.1 <0.09 <O. l <0.1 <0.09 SA-MLK-15 Fl <0.1 <0.1
<0.08 <0.08 <0.1 <0.09
<0.1 <0.1 <0.07 <0.1 <0.03 <0.1 SA-MLK-3Gl <0.09 <0.1 co <0.08 <0.09 <0.08 <0.08 N
JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER STATION NO.
<0.3 <O.l <0.2 <0.06 <0.09 <0.08 SA-MLK-13E3 <0 .1 <0.07
<0.2 <0.1 <0.1 <0.1
<0.3 <0.1 <0.1 <0.1 <0.08 <0.08 SA-MLK-2F4 <O.l <0.07
<0.2 <0.09 <0.1 <0.1 (1) <0.1 <0.2 <0.1 <0.1 (1)
SA-MLK-5F2 <0.09
<0.2 <0.09 <0.2 <0.1 <0.1
<0.3 <0.1 <0.1 <0.08 <O.l <0.08 SA-MLK-14Fl <0.1 (1)
<0.2 <0.1 <0.2 <0.1
<0.3 <0.1 <0.1 <0.08 <0.1 <0.08 SA-MLK-15Fl (1)
<0.2 <0.1 <0.2 <O.l <0.1
<0.2 <0:1 <0.1 <0.09 <0.2 <0.1 SA-MLK-3Gl <0.1 (1)
<0.2 <0.1 <0.2 <O.l
- I-131 results decay corrected to sample stop date.
** Sampling dates can be found on Table C-30.
(1) Data lost due to computer malfunction.
TABLE C-28 CONCENTRATIONS OF GAMMA EMITTERS* AND STRONTIUM-89** AND -90 IN MILK Results in Units of pCi/l +/- 2 sigma STATION NO.*** NUCLIDE JANUARY**** FEBRUARY MARCH APRIL MAY JUNE SA-MLK-13E3 K-40 1400+/-140 1200+/-120 1100+/-110 1600+/-160 1500+/-150 1500+/-150 Cs-137 <1.4 <1.4 <1.1 4.0+/-1.2 1. 8+/-1.1 <L2 Sr-89 <2.2 Sr-90 4.9+/-1.6 SA-MLK-2F4 K-40 1400+/-140 1100+/-110 1800+/-180 2700+/-270 1700+/-170 2000+/-200 Cs-137 <1.4 1.6+/-1.1 1. 5+/-1. 0 8. 7+/-1.4 1.9+/-1.2 <1.2 Sr-89 <7 .8 (1) Sr-90 10+/-5 SA-MLK-5F2 K-40 2000+/-200 1300+/-130 1100+/-110 1700+/-170 1300+/-130 1400+/-140 Cs-137 1. 9+/-1. 2 <1. 2 <1. 2 2 .2+/-1.1 2.0+/-1.1 6.9+/-1.2 co Sr-89 <4.7 <1.5 w Sr-90 6. 7+/-1.1 5.5+/-1.1 STATION NO. NUCLIDE JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER SA-MLK-13E3 K-40 1500+/-150 1700+/-170 920+/-92 1300+/-130 1500+/-150 1500+/-150 Cs-137 <1.4 <1.1 <1.1 <1.2 <1.4 <1.4 Sr-89 <26 (1) Sr-90 <5.0 SA-MLK-2F4 K-40 1400+/-140 1500+/-150 1100+/-110 1300+/-130 1500+/-150 1500+/-150 Cs-137 <1. 2 <1.2 <1.2 <1.1 <1.2 <1.6 Sr-89 <2.4 Sr-90 3.0+/-0.7 SA-MLK-5F2 K-40 1000+/-100 1400+/-140 1100+/-110 1800+/-180 1300+/-130 1400+/-140 Cs-137 1. 9+/-0.8 3.6+/-1.3 <1.2 <1.2 <l.2 1.8+/-0. 7 Sr-89 <1:.7 Sr-90 3.9+/-1.0
TABLE C-28 (cont.) CONCENTRATIONS OF GAMMA EMITTERS* AND STRONTIUM-89** AND -90 IN MILK Results in Units of pCi/l +/- 2 sigma STATION NO.*** NUCLIDE JANUARY**** FEBRUARY MARCH APRIL MAY JUNE SA-MLK- 14Fl K-40 1600+/-160 1700+/-170 2500+/-250 1600+/-160 1800+/-180 1600+/-160 Cs-137 <1.2 <1.2 2.8+/-1.1 1. 7+/-1.0 2 .0+/-1.1 <1.4 Sr-89 <1.0 Sr-90 2.5+/-0.9 SA-MLK-15Fl K-40 1500+/-150 1400+/-140 1300+/-130 1500+/-150 1600+/-160 1500+/-150 Cs-137 <1.4 3.1+/-1.1 <1. 4 4.0+/-1.3 2.3+/-1.2 3.3+/-1.3 Sr-89 <2.8 Sr-90 3. 7+/-1.3 SA-MLK-3Gl K-40 1400+/-140 1400+/-140 770+/-77 1300+/-130 1400+/-140 1400+/-140 Cs-137 1. 7+/-1.1 <1.4 1. 4+/-1.1 <1. 2 <1.2 1.9+/-1.1 Sr-89 <46 11) <3.9 <1.1 <1.0 <1.9 <13 (1) Sr-90 <56 1) 5 .4+/-1. 8 1.4+/-1.0 1.5+/-1.0 5 .4+/-1.4 7.5+/-4.8 00 +:> STATION NO. NUCLIDE JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER SA-MLK-14Fl K-40 1400+/-140 1200+/-120 900+/-90 1400+/-140 1400+/-140 1300+/-130 Cs-137 <1.2 <1. 2 <1.1 <1.2 <1.2 <1.4 Sr-89 <3.3 Sr-90 3.6+/-2.4 SA-MLK-15Fl K-40 1500+/-150 1500+/-150 1700+/-170 1400+/-140 1600+/-160 i300+/-130 Cs-137 <1.4 <1.4 <1. 2 <1. 2 <1. 2 1.4+/-0. 7 Sr-89 <1.0 3.8+/-2.3 Sr-90 3.4+/-0.6 0.8+/-0.7 SA-MLK-3Gl K-40 1800+/-180 1600+/-160 1400+/-140 1300+/-130 1300+/-130 1500+/-150 Cs-137 <1.2 <1.4 1.5+/-0.9 <1.2 <1.1 <1.2 Sr-89 <1.3 <2.6 4.4+/-4.3 <1.2 <1.6 <1.2 Sr-90 3.3+/-0.8 5 .9+/-1. 7 2.4+/-1.8 3.8+/-0.7 4.7+/-0,9 4.1+/-0.8
- All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-38.
** Sr-89 results are corrected for decay to sample stop date. *** For quality assurance purposes, station MLK-3Gl is analyzed for Sr-89 and -90 on a monthly basis by RMC; in addition, one station a month is selected by PSE&G to be analyzed for Sr-89 and -90. **** Sampling dates can be found on Table C-30.
(1) High MDL due to low chemical yield.
TABLE C-29 CONCENTRATIONS OF STRONTIUM-89* AND -90 IN MILK Results in Units of pCi/l +/- 2 sigma (All Results by PSE&G Research Corporation) STATION NO.** NUCLIDE JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-MLK-13E3 Sr-89 6.9+/-1.0 <1.8 <1.9 <2.1 <2.0 <1.9 Sr-90 <I.8 2.7+/-0.7 2.4+/-0.7 2.7+/-0.8 2.1+/-0.7 2.2+/-0.6 SA-MLK-2F4 Sr-89 <1.9 <1.8 <1.9 <2.2 <2.0 <1.9 Sr-90 2.0+/-0.6 2.4+/-0.6 2.4+/-0.7 2.6+/-0.8 <1.5 1.4+/-0.6 SA-MLK-5F2 Sr-89 <2.0 <2.4 <2.1 <2.4 <1.9 <2.2 Sr-90 4.1+/-0.7 4.2+/-0.9 3.7+/-0.8 4.0+/-0.9 3.5+/-0. 7 5.2+/-0.8 SA-MLK-14Fl Sr-89 <2.0 <1.8 <1~7 <1.7 <1.7 <2.0 Sr-90 2.4+/-0.7 2.4+/-0.7 2.5+/-0.7 2.7+/-0.6 1.9+/-0.6 2.9+/-0.7 SA-MLK-15Fl Sr-89 <2.0 <2.1 <2.0 <2.1 <1.8 <2.7 Sr-90 2.6+/-0.7 2.7+/-0.7 2.8+/-0.8 2.7+/-0.8 <1.4 2.6+/-0.9 co SA-MLK-3Gl Sr-89 <2.2 <2.2 <2.2 <2.3 <1.8 <2.1 c..n Sr-90 4.3+/-0.8 3.6+/-0.8 3.4+/-0.8 3.8+/-0.8 2.7+/-0.6 4.0+/-0.7 STATION NO. ** NUCLIDE JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER SA-MLK-13E3 Sr-89 <1.6 <1. 7 <1.9 <1. 7 <1.6 <1.5 Sr-90 2.0+/-0.6 2.4+/-0.6 3.2+/-0.7 2.8+/-0.6 2.9+/-0.6 2.2+/-0.6 SA-MLK-2F4 Sr-89 <1.4 <1.3 <1.6 <1.6 <1.5 <1.5 Sr-90 1.5+/-0.5 1.1+/-0. 5 1. 6+/-0. 6 1.3+/-0 .6 2.0+/-0.5 1.6+/-0 .6 SA-MLK-5F2 Sr-89 <2.2 <1.8 <1.9 <1.9 <1.8 <1.7 Sr-90 5.4+/-0.8 3 .4+/-0. 7 4.8+/-0.7 4.3+/-0.7 3.9+/-0.7 3.4+/-0.6 SA-MLK-14Fl Sr-89 <1.6 <1.7 <1.6 <1.6 <1.6 <1.5 Sr-90 2.0+/-0. 6 2.1+/-0.6 1.8+/-0. 6 2.9+/-0.6 3.2+/-0.6 2.6+/-0.6 SA-MLK-15Fl Sr-89 <2.1 <1.6 <1.8 <1.6 <1.6 <1.7 Sr-90 3.3+/-0.8 2.6+/-0.6 2.8+/-0.6 2.3+/-0.6 2.1+/-0.6 2.8+/-0.7 SA-MLK-3Gl Sr-39 <2.0 <2.0 <2.2 <1.9 <1.8 <1.8 Sr-90 4.0+/-0.7 3.8+/-0.8 4.5+/-0.8 4~6+/-0.7 4.0+/-0.7 2.7+/-0.6
- Sr-89 results are corrected for decay to sample stop date.
** Sampling dates can be found on Table C-30.
TABLE C-30 SAMPLING DATES FOR MILK SAMPLES MONTH 13E3 2F4 5F2 14Fl 15F1 3Gl JANUARY 1-04-82 1-04-82 1-04-82 1-04-82 1-04-82 1-03-82 to to to to to to 1-05-82 1-05-82 1-05-82 1-05-82 1-05-82 1-04-82 1-18-82 1-18-82 1-16-82 1-17-82 1-18-82 1-17-82 to to to to to to 1-19-82 1-19-82 1-18-82 1-18-82 1-19-82 1-18-82 FEBRUARY 2-08-82 2-07-82 2-07-82 2-08-82 2-07-82 2-08-82 to to to to to to 2-09-82 2-08-82 2-08-82 2-09-82 2-08-82 2-09-82 2-22-82 2-21-82 2-21-82 2-22-82 2-21-82 2-22-82 to to to to to to 2-23-82 2-22-82 2-22-82 2-23-82 2-22-82 2-23-82 MARCH 3-08-82 3-07-82 3-07-82 3-08-82 3-07-82 3-08-82 to to to to to to 3-09-82 3-08-82 3-08-82 3-09-82 3-08-82 3-09-82 co O'l 3.:.22-82 3-21-82 3-21-82 3-22-82 3-21-82 3-22-82 to to to to to to 3-23-82 3-22-82 3-22-82 3-23-82 3-22-82 3-23-82 APRIL 4-05-82 4-04-82 4-04-82 4-05-82 4-04-82 4-05-82 to to to to to to 4-06-82 4-05-82 4-05-82 4-06-82 4-05-82 4-06-82 4-19-82 4-18-82 4-18-82 4-19-82 4-18-82 4-19-82 to to . to to to to 4-20-82 4-19-82 4-19-82 4-20-82 4-19-82 4-20-82 MAY 5-03-82 5-02-82 5-02-82 5-03-82 5-02-82 5-03-82 to to to to to to 5-04-82 5-03-82 5-03-82 5-04-82 5-03-82 5-04-82 5-17-82 5-16-82 5-16-82 5-17-82 5-16-82 5-17-82 to to to to to to 5-18-82 5-17-82 5-17-82 5-18-82 5-17-82 5-18-82 JUNE 6-06-82 6-07-82 6-06-82 6-06-82 6-07-82 6-06-82 to to to to to to 6-07-82 6-08-82 6-07-82 6-07-82 6-08-82 6-07-82 6-20-82 6-21-82 6-21-82 6-20-82 6-21-82 6-20-82 to to to to to to 6-22-82 6-22-82 6-22-82 6-21-82 6-22-82 6-21-82
TABLE C-30 (cont.} SAMPLING DATES FOR MILK SAMPLES MONTH 13E3 2F4 5F2 14Fl 15Fl 3Gl JULY 7-06-82 7-05-82 7-05-82 7-06-82 7-05-82 7-06-82 to to to to to to 7-07-82 7-06-82 7-06-82 7-07-82 7-06-82 7-07-82 7-18-82 7-19-82 7-19-82 7-18-82 7-19-82 7-18-82 to to to to to to 7-20-82 7-20-82 7-20-82 7-19-82 7-20-82 7-19-82 AUGUST 8-01-82 8-02-82 8-02-82 8-01-82 8-02-82 8-01-82 to to to to to to 8-02-82 8-03-82 8-03-82 8-02-82 8-03-82 8-03-82 8-15-82 8-16-82 8-16-82 8-15-82 8-16-82 8-15-82 to to to to to to 8-16-82 8-17-82 8-17-82 8-16-82 8-17-82 8-16-82 I SEPTEMBER 9-06-82 9-07-82 9-07-82 9-06-82 9-07-82 9-06-82 'I to to to to to to co 9-08-82 9-08-82 9-08-82 9-07-82 9-08-82 9-07-82 -....J 9-20-82 9-19-82 9-19-82 9-20-82 9-19-82 9-20-82 to to to to to to 9-21-82 9-20-82 9-20-82 9-21-82 9-20-82 9-21-82 OCTOBER 10-04-82 10-03-82 10-03-82 10-04-82 10-03-82 10-04-82 to to to to to to 10-05-82 10-04-82 10-04-82 10-05-82 10-04-82 10-05-82 10-18-82 10-17-82 10-17-82 10-18-82 10-17-82 10-18-82 to to to to to to 10-19-82 10-18-82 10-18-82 10-19-82 10-18-82 10-19-82 NOVEMBER 11-07-82 11-08-82 11-08-82 11-07-82 11-08-82 11-07-82 to to to to to to 11-09-82 11-09-82 11-08-82 11-08-82 11-09-82 11-08-82 11-21-82 11-22-82 11-22-82 11-21-82 11-22-82 11-21-82 to to to to to to 11-23-82 11-23-82 11-22-82 11-22-82 11-23-82 11-22-82 DECEMBER 12-05-82 12-06-82 12-06-82 12-05-82 12-06-82 12-05-82 to to to to to to 12-06-82 12-07-82 12-07-82 12-06-82 12-07-82 12-06-82 12-19-82 12-20-82 12-20-82 12-19-82 12'.'"20-82 12-19-82 to to to to to to 12-20-82 12-21-82 12-21-82 12-20-82 12-21-82 12-20-82
TABLE C-31 CONCENTRATIONS OF GAMMA EMITTERS* IN EDIBLE FISH Results in Units of pCi/g(wet) +/- 2 sigma STATION SAMPLING K-40 NUMBER DATE SA-ESF-llAl 5-03-82 to 3.1+/-0.3 7-30-82 9-16-82 to 2.9+/-0.3 10-08-82 00 00 SA-ESF-12Cl 5-03-82 to 3.7+/-0.4 7-30-82 9-16-82 to 3.1+/-0 .4 10-08-82 SA-ESF-7El 5-03-82 to 3.0+/-0 .3 7-30-82 9-16-82 to 2.9+/-0.3 10-08-82
- All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-38.
TABLE C-32 COl'ICENTRATIONS OF STRONTIUM-89* AND -90 , AND TRITIUM rn EDIBLE FISH S/11'1PLES Bones Flesh Aqueous Fraction Organic Fraction (pCi /g( dry) +/- 2 sigma) (pCi/1 +/- 2 sigma) (pCi/1 +/- 2 sigma) STATION DATE Sr-89 Sr-90 H-3 H-3 SA-ESF-llAl 5-03-82 to <0.02 0.05+/-0.01 <112 <214 (1) 7-30-82 9-16-82 to <0.06 0.13+/-0.03 81+/-72 168+/-73 10-08-82 00 SA-ESF-12Cl 5-03-82 0..0 to <0.5 0.10+/-0.06 <112 <641 (1) 7-30-82 9-16-82 to <0.1 0.21+/-0.05 <116 1740+/-170 (2) 10-08-82 SA-ESF-7El 5-03-82 to <0.3 <0.03 <112 134+/-99 7-30-82 9-16-82 to <0.3 <0.2 <369 (1) 1800+/-180 (2) 10-08-82
- Sr-89 results are corrected for decay to SCITlple stop date.
(1) High LLD due ~o small sample size. (2) Chemiluminescence suspected; insufficient sample for reanalysis.
TABLE C-33 CONCENTRATIONS OF GM1MA EMITTERS* IN BLUE CRAB SAMPLES Results in Units of pCi/g(wet} +/- 2 sigma STATION NUMBER DATE SAMPLE TYPE K-40 SA-ECH- llAl 5-03-82 to Flesh 2.0+/-0.3 7-30-82 c.o 0 10-26-82 to Flesh 2.1+/-0.2 10-26-82 SA-ECH-12Cl 5-03-82 to Flesh 2.0+/-0.2 7-30-82 9-16-82 to Flesh 2.1+/-0 .3 10-08-82
- All other gamma emitters <LLD; typical LLDs are given in Table C-38.
TABLE C-34 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND TRITIUM IN BLUE CRAB SAMPLES STATION Sr-89 Sr-90 H-3 (Edible Portion) NUMBER DATE SAMPLE pCi/g +/- 2 sigma pCi/g +/- 2 sigma pCi/l +/- 2 sigma SA-ECH-llAl 5-03-82 Flesh <0.01 <O .006 <112 to 7-30-82 Shell <O .1 0.14+/-0.04 9-16-82 Flesh (1) (1) 230+/-74 to 10-08-82 Shell <0.04 0.29+/-0.03 10-26-82 Flesh <0.006 0.006+/-0.004 <..O I-' Shell <0.04 0 .31+/-0.03 SA-ECH-12Cl 5-03-82 Flesh <0.02 0.014+/-0.005 <112 to 7-30-82 Shell 0.2+/-0.1 0. 09+/-rl. 05 9-16-82 Flesh <0.02 0.005+/-0Jl04 157+/-73 to 10-08-82 Shell <0.05 0.19+/-0.02
- Sr-89 results are corrected for decay to sample stop date.
Indicates tritium analysis not performed on shells. (1) Entire amount of flesh sample used for tritium analysis. Recollected on 10-26-82.
TABLE C-35 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND GAMMA EMITTERS** IN FOOD PRODUCTS Results in Units of pCi/g(wet) +/- 2 sigma STATION NO. DATE SAMPLE TYPE Sr-89 Sr-90 K-40 SA-FPV-2El 5-11-82 Asparagus <0.008 <0.007 2.1+/-0.2 SA-FPV-5Dl 7-26-82 Corn <0.004 <0.004 2.5+/-0.3 SA-FPL-1F3 7-26-82 Cabbage <0.2 0.02+/-0.01 2.1+/-0.3 SA-FPL-2F4 7-26-82 Cabbage <0.008 0.012+/-0.005 2.8+/-0.3 SA-FPG-2F4 7-26-82 Corn <0.01 0.002+/-0.001 2.9+/-0.3 SA-FPV-14F3 7-26-82 Tomatoes <0.04 <0.003 1.3+/-0.1 SA-FPG-lGl 7-26-82 Corn <0.004 <0.004 2.1+/-0.2 SA-FPV-lGl 7-26-82 Peppers <0.03 0.010+/-0.003 2.4+/-0.2 SA-FPV-lGl 7-26-82 Tomatoes <0.004 0.003+/-0.003 0.94+/-0.09 l..O N SA-FPV-lGl 7-27-82 Cucumbers <0.01 0.020+/-0.008 2.0+/-0.2 SA-FPV-1F3 8-02-82 Peppers <0.008 <0.006 1.8+/-0.2 SA-FPV-1F3 8-02-82 Tomatoes <0.006 0. 008+/-0. 003 1.4+/-0 .1 SA-FPV-5Fl 8-02-82 Tomatoes <0.05 0.006+/-0.004 2.5+/-0.3 SA-FPL-14F3 8-02-82 Cabbage <0.005 0.005+/-0.003 1. 2+/-0.2 SA-FPG-14F3 8-02-82 Corn <0.04 <0.005 3.1+/-0.3 SA-FPL-3H4 8-02-82 Cabbage <0.01 0.009+/-0.007 3.4+/-0. 3 SA-FPG-3H4 8-02-82 Corn <0.003 <0.002 2.6+/-0.3 SA-FPV-3H4 8-02-82 Cucumbers <0.02 0.003+/-0.002 1.4+/-0.1 SA-FPV-3H4 8-02-82 Peppers <0.02 0.02+/-0.01 2.3+/-0.2 SA-FPV-3H4 8-02-82 Tomatoes <0.004 0.004+/-0.004 1.4+/-0. l SA-FPV-5Dl 8-03-82 Peppers <0.004 0.006+/-0.005 1.8+/-0. 2 SA-FPV-501 8-03-82 Tomatoes <0.03 0.006+/-0.002 1.8+/-0.2 SA-FPG-5Dl 10-12-82 Soybeans <0.03 0.08+/-0.01 12+/-1
- Sr-89 results are corrected for decay to samEl e stop date.
**All other gamma emitters searched for were < LD; typical LLDs are given iri Table C-38.
TABLE C-36 CONCENTRATIONS OF STRONTIUM-89 AND -90* AND GAMMA EMITTERS** IN GAME, MEAT AND BOVINE THYROID Results in Units of pCi/g(wet) +/- 2 sigma STATION NO. DATE SAMPLE TYPE Sr-89 Sr-90 K-40 pCi/g(dry) +/- 2 sigma SA-GAM-3El 2-07-82 Muskrat 0.07+/-0.05 0.09+/-0.03 2.3+/-0.2 SA-GAM- llDl 2-15-82 Muskrat <0.03 0.08+/-0.03 2.0+/-0.2 \0 w SA-FPB-3El 2-15-82 Beef 1.1+/-0 .1 SA-THB-3El 2-15-82 Bovine Thyroid <0.6 SA-FPB-14Fl 11-12-82 Beef 2.2+/-0.2 SA-THB-14Fl 11-12-82 Bovine Thyroid 2.3+/-0.6
- Radiostronti um performed on muskrat only. Sr-89 results are corrected for decay to sample stop date.
** All other gamma emitters searched for were <tLD; typical LLDs are given in Table C-38.
Indicates strontium analyses not performed.
TABLE C-37 CONCENTRATIONS OF GAMMA EMITTERS* IN FODDER CROP SAMPLES Results in Units of pCi/g(_wet) +/- 2 sigma STATION S.AMPLE NUMBER DATE TYPE K-40 SA-VGT-3Gl 8-16.-82 Green Chop 3.5+/-0.4 SA-VGT-2F4 9-01-82 to Sil age 3.6+/-0.4 9-07-82 SA-VGT-3Gl 9-03-82 to Sil age 2.7+/-0.5 9-04-82 \.0 .+=> SA-VGT-15Fl 9-07-82 Alfalfa 4.8+/-0.5 SA-VGT-5F2 9-07-82 to Sil age 2. 9+/-0. 5 9-08-82 SA-VGT-501 9-13-82 Grass 3.3+/-0.4 SA-VGT-14Fl 9-14-82 Corn Silage/Green Chop 3.6+/-0.6 SA-VGT-15Fl 10-04-82 Silage 2.9+/-1.6 SA-FPG-3Gl 11-21-82 Soybeans 18+/-2 SA-FPG-15Fl 11-22-82 Soybeans 14+/-1
- All other gamma emitters searched for were <LLD; typical LLDs are given in Tab le C-38.
TABLE C-38 LL Os FOR GAMMA SPECTROMETRY AIR SURFACE WELL/POTABLE PARTICULATES PRECIPITATION WATER WATER SEDIMENT MILK NUCLIDES (lo- 3pCi/m 3) (pCi/l) ( pCi /l) (pCi /l) (pCi/g-dry) ( pCi /l) Be-7 8.1 5.2 6.3 0.3 7.5 Na-22 0.3 0.8 0.6 0.8
- 1.0 K-40 5.5 7.8 7.8 7.0 Cr-51 3.2 7.8 5.6 5.9 0.5 7.9 Mn-54 0.3 0.7 0.6 0.6 0.02 1.0 Co-57
- 2.0 *
- 0.02
- Co-58 0.4 0.8 0.7 0.7 0.03 1.1 Fe-59 0.7 1. 7 1.4 1.4 0.08 2.0 Co-60 0.3 0.8 0.6 0.6 0.03 0.9
<..C Zn-65 0.7 1. 5 1.4 1.4 0.05 1.7 U1 Zr-95 0.7 * *
- 0.05
- Nb-95 0.4 * *
- 0.05
- ZrNb-95
- 0.6 0.6 0.6
- 0.9 Mo-99 17 160 27 52
- 87 Ru-103 0.4 * *
- 0.04
- Ru-106 3.4 6.5 6.3 6.3 0.2 8.0 Ag-llOm 0.3 o.7 0.6 0.6 0.02 1.0 Sb-125 0.7 * *
- 0.06
- Te-129m 3.4 17 11 13 1. 5 19 I-131 0.6 3.5 1.1 1.4 0.6 1.9 3.7 4.9 Te-132 I-133 1.3 11
-If 2.1 Cs-134 0.3 0.6 0.6 0.6 0.02 1.0 Cs-136 0.5 2.3 l.4 1.6 0.2 2.6 Cs-137 0.4 0.8 0.6 0.6 0.03 1.1 Ba-140 1.5 * *
- 0.8
- La-140 0.7 * *
- 0.2
- BaLa-140
- 2.4 1.0 1.3
- i.. 7 Ce-141 0.5 * *
- 0.06
- Ce-1:44 1.6 3.3 1. 6 1.6 0.1 3.2 Ra-226 1.0 1. 2 1.1 1.2 1.6 Th-232 1.5 3.1 3.1 3.1 3.1
TABLE C-38 (cont.) LLDs FOR GAMMA SPECTROMETRY FOOD MEAT FODDER FISH SHELLFISH PRODUCTS AND CROPS GAME NUCLIDES (pCi/g-wet) (pCi/g-wet) (pCi/g-wet) (pCi/g-wet) (pCi/g-wet) Be-7 0.1 0.1 0.02 0.04 0.2 Na-22 0.01 0.02 0.003 0.006 0.02 K-40 0.6 Cr-51 0.1 0.1 0.02 0.06 0.2 Mn-54 0.01 0.01 0.003 0.006 0.02 Co-57 * * * *
- Co-58 0.01 0.02 0.002 0.007 0.02 Fe-59 0.02 0.04 0.007 0.008 0.07 Co-60 0.01 0.02 0.002 0.003 0.03 Zn-65 0.02 0.03 0.005 0.006 0.06 Zr-95 * * * *
- l..O Nb-95 * * * *
- O"I ZrNb-95 0.009 0.02 0.002 0.002 0.03 Mo-99 36 3.6 0.4 0.4 0.4 Ru-103 * * * *
- Ru-106 0.08 0.1 0.02 0.06 0.3 Ag-llOm 0.01 0.02 0.002 0.006 0.03 Sb-125 * * * *
- Te-129m 0.2 0.2 0.05 0.08 0.5 I-131 0.07 0.04 0.01 0.009 0.04 Te-132 1. 4 0.2 0.03 0.03 0.04 I-133 *
- 0.06 0.8 0.6 Cs-134 0.01 0.01 0.002 0.002 0.03 Cs-136 0.05 0.03 0.01 0.01 0.06 Cs-137 0.009 0.02 0.002 0.006 0.03 Ba-140 * * * *
- La-140 * * * *
- BaLa-140 0.04 0.03 0.006 0.01 0.04 Ce-141 * * * *
- Ce-144 0.03 0.05 0.007 0.02 0.09 Ra-226 0.02 0.03 0.003 0.003 0.05 Th-232 0.03 0.06 0.008 0.03 0.1 Indicates a positive concentration was measured in all samples analyzed.
- Indicates that no LLD was calculated for that nuclide in that media.
--- - ~--- APPENDIX D-1 SYNOPSIS OF ANALYTICAL PROCEDURES UTILIZED BY RMC 97
GROSS ALPHA ANALYSIS OF SAMPLES Total Water (A0, Al) A 250 ml (A0) or one 1 (Al) aliquot of the sample is evaporated to dryness on a hot plate in a preweighed, 211 X 1/4 11 ringed planchet, allowed to cool, and re-weighed. The planchet is counted in a low-background, gas flow proportional counter. Self-absorption corrections are made based on the measured sample weight and calculated thickness. The calibration standard used is Pu-239. A 250 ml or one 1 sample of distilled water is evaporated in the same manner and used as a blank. Total Salt Water (AA) Alpha emitters are concentrated initially from a liter aliquot of water sample by coprecipitation with magnesium hydroxide. The precipitate is then dissolved in hydrochloric acid and titanium trichloride is added to the solution. The alpha emitters are coprecipitated by adding barium chloride and sulfuric acid to pre-cipitate barium sulfate. The precipitate is transferred to a tared stainless steel planchet and dried. The planchet is reweighed and counted in a low back-ground gas-flow proportional counter. Self-absorption corrections are made on the basis of the weight of the precipitate. Calculations are made utilizing the following equations: Result (pCi/l) = ((S/T) - (B/t)) I (2.22 VE TF) 2 sigma error (pCi/l) = 2 ((S/T 2) + (B/t 2)) 1/ 2 / (2.22 VE TF) where: S = Gross counts of sample B = Counts of blank E = Fractional Pu-239 counting efficiency T = Number of minutes sample was counted t = Number of minutes blank ~as counted V = Sample aliquot size (liters) TF = Transmission factor (based on net weight of sample in counting planchet) Calculation of lower limit of detection (LLD) The detection limit is assumed to be exceeded when the counting result is different from the blank reading by at least 4.66 times the standard deviation of that back-ground. LLD (pCi/l) = 4.66 (sl/2) I (2.22 VE TF t) where: B = Counts of blank E = Fractional Pu-239 counting efficiency t = Number of minutes blank was counted V = Sample aliquot size (liters) TF = Transmission factor (based on net weight of sample in counting planchet) 99
GROSS BETA ANALYSIS OF SAMPLES Total Water (B0, Bl) A 250 ml (B0) or one 1 (Bl) aliquot is evaporated to dryness on a hot plate in a preweighed, 211 X 1/4 11 , ringed planchet and reweighed. The planchet is then counted in a low background gas-flow proportional counter. Self-absorption corrections are made based on the measured residue weight and calculated thickness. The calibration standard used is Sr Y-90. A 250 ml or one 1 sample of distilled water is evapo-rated in the same manner and used as a blank. Calculations are made utilizing the following equations: Result (pCi/l) = ((S/T) - (B/t)) / (2.22 VE TF) 2 sigma error (pCi/l) = 2 ((S/T 2) + (B/t 2)) 112 / (2.22 V E TF) where: s = Gross counts of sample B = Counts of blank E = Fractional Sr-90-Y-90 counting efficiency T = Number of minutes sample was counted t = Number of minutes blank was counted v = Volume of aliquot (liters) TF = Transmission factor (based on net weight of sample in counting planchet) Calculation of lower limit of detection (LLD) The detection limit is assumed to be exceeded when the counting result for the sample is different from the blank reading by at least 4.66 times the standard deviation of that background. LLD (pCi/l) = 4.66 (B 1/ 2) I (2.22 VE TF t) where: B = Counts of blank E = Fractional Sr-90-Y-90 counting efficiency t = Number of minutes blank was counted V = Volume of aliquot (liters) TF = Transmission factor (based on net weight of sample 1n counting planchet) 100
ENVIRONMENTAL DOSIMETRY (D0, Dl, D2) Measurement Techniques Each dosimeter utilized is a capillary tube containing calcium sulfate (Tm) powder as the thermoluminescent dosi*meter (TLD) material. This was chosen primarily for its high light output, minimal thermally induced signal loss (fading), and lack of self-dosing. The energy response curve has been flattened by a complex multi-ple element energy compensation shield supplied by Panasonic Corporation, manu-facturer of the TLD reader. The four dosimeters per station are sealed in a polyethy~ene bag to demonstrate integrity at time of measurement. Visible through the bag are the sample placement instructions. One set of TLDs is placed in a lead shield at RMC and represents a zero dose. The TLDs are then taken and placed in the field stations; one fi~ld TLD set is placed in a field lead shield at station 18 and is used in calculating the in-transit dose. Following the pre-designated exposure period the TLD is heated with hot gas and the luminescence measured with a TLD reader. Data are normalized to standard machine conditions by correcting machine settings to zero before readout. Data are corrected for in-transit dose using a set of TLDs which is kept in a lead shield in the field and only exposed during transit. Average dose per exposure period, and its error, are calculated. The basic calibration is in mR exposure to a standard Cs-137 source. This is converted to absorbed dose in tissue by the factor : 0.955 rad/Roentgen and to dose equivalent by using a quality factor of 1. Calculations are made utilizing the following equations: T = (G-Z) R C 0.955 mrad/ Roentgen I = SZ - (RZ DL I DR) N = T-I n Average = ((sum N) I n) (30.4 I DL) i=l Error = t (n-1) (SD I n1/ 2) (30.4 I DL) where: T = Individual TLD reading corrected to standard instrument conditions G = Gross reading of dosimeter i z = Zero for dosimeter, i R = Correction factor of reader (see Procedure T-6) c = Calibration factor dosimeter i I = In-transit dose sz = Mean of n dosimeters in site lead shield RZ = Mean of n dosimeters in RMC lead shield DL = Exposure period of location (days) DR = Exposure period of RMC~ (days) 101
ENVIRONMENTAL DOSIMETRY (cont.) Average = Mean exposure per standard exposure period at a given station N = Net dose obtained during exposure period in the field n = Number of readings 30.4 = Days in standard exposure period Error = The 95% confidence limit error of the average t(n-1) = t-distribution (student) factor for 95% CL SD = Standard deviation of n readings of sum N 102
ANALYSIS OF WATER SAMPLES FOR POTASSIUM-40 BY AA (E0) Sample Preparation An aliquot sample size of 100 ml is filtered. The concentration of potassium is determined soectrophotometrically on a Perkin Elmer Model 373 atomic absorption unit. The result obtained, in micrograms per milliliter, is multiplied by the specific activity of 0.12% for natural potassium to determine the amount of potassium-40 present in the sample. The error reported is 10% of the result. A sample of distilled water is processed as a blank. Calculations are made using the following equations: K-40 ( pCi /l) = Cs D (C/S) K LLD ( pCi /l) = Cs D ( .1/S) K where: Cs = Concentration of Standard ( µg K/ml) c = Sample reading s = Standard reading D = Dilution factor K = Specific activity of K-40 per unit weight of potassium (.852 pCi/mg) 103
ANALYSIS OF SAMPLES FOR TRITIUM Water (H2) A 15 ml aliquot of the sample is vacuum distilled to eliminate dissolved gases and non-volatile matter. The distillate is frozen in a trap cooled with a dry ice-isopropanol mixture. Eight (8) ml of the distillate are mixed with ten (10) ml of Insta-Gel liquid scintillation solution. The samole is then counted for tritium in a liquid scintillation counter. A sample of* low tritium (<50 pCi/l) water is vacuum distilled as a blank and is counted with each batch of samples. In the calculation of the result it is assumed that the condensated and original sample are of equivalent volumes. The volume change associated with the removal of dissolved gases and non-volatile matter is not significant compared to the other errors in the analysis. Calculations are made utilizing the following equations: Result (pCi/l) *= ((S/T) - (B/t)) I (2.22 V E) 2 sigma error (pCi/l) = 2 ((S/T 2 ) + (B/t 2)) 112 / (2.22 VE) where: s = Total gross counts of sample B = Counts of blank E = Fractional H-3 counting efficiency T = Number of minutes sample was counted t = Number of minutes blank was counted v = Aliquot volume (liters) Gross counts of sample may be corrected for the blank activity. If the collection container is rinsed with distilled water and the rinse* is added to the samole, the rinse plus sample and a separate aliquot of the distilled water are counted. The corrected gross counts for the sample only are calculated using the following equa-ti ans: s = ((s-b)v) I G s = (c(G+H)) IV b = (d(H)) I V v = G V/(G+H) .* where: s = Gross counts of sample G = Volume of sample H = Volume of rinse s = Volume corrected gross counts of sample pl us rinse b = Volume corrected gross counts of rinse v = Corrected aliquot volume c = Uncorrected gross counts of sample pl us rinse d = Uncorrected gross counts of rinse 104
Calculation of lower limit of detection (LLD) The detection limit is assumed to be exceeded when the counting result is different from the blank reading by at least 4.66 times the standard deviation of that background. LLD (pCi/l) = 4.66 (B 112) I (2.22 VE t) where: B = Counts of blank E = Fractional H-3 counting efficiency t = Number of minutes blank was counted V = Aliquot volume (liters) Aqueous and Organic Fraction of Milk or Organic Solids (H3, H4, H9) A carefully measured aliquot of a food product, such as milk or fish, is dried in a rotating vacuum flash evaporator. During the evaporation process, the evaporated water fraction is trapped out by a dry ice isopropanol mixture for counting as in (a) below. The dried residue is reserved for (b). The wet sample is analyzed as in (c).
- a. Aqueous H-3 in Food Products An eight (8) ml aliquot of the cold~trapped water is counted in a liquid scintillation counter in the same manner as surface water samoles are counted.
b, Organic Bound H-3 in Food Products The dried residue is combusted in an RMC designed oxidizer. The collected water - organic fraction is measured and vacuum distilled to remove any impurities. Permanganate in KOH solution is added to remove impurities which may cause quenching. An eight (8) ml aliquot is counted in a liquid scintillation counter. If less than eight (8) ml are collected, the entire portion collected is carefully measured with a 10 ml pipette and then counted. A sample of deep well water is counted as a blank.
- c. Aqueous and Organic Bound H-3 in Food Products A wet weight aliquot is combusted in an RMC designed oxidizer. The collected water fraction is measured and vacuum distilled to remove any impurities. Per-manganate in KOH solution is added to remove impurities which may cause quenching.
An eight (8) ml aliquot is counted in a liquid scintillation counter. If less than eight (8) ml are collected, the entire portion collected is carefully measured with a 10 ml pipette and then counted. A sample of deep well water is counted as a blank.
- Cal cul ati ons are made utilizing the following equations:
Result (pCi/l) = ((S/T) - (B/t)) I (2.22 VE) of distillate 2 sigma error (pCi/l) = 2 ((S/T 2) + (B/t 2)) 112 I (2.22 V E) of distillate 105
Result (pCi/g of freeze dried sample) = A (YI) 2 sigma error (pCi/g of freeze dried sample) = C (YI) Result (pCi/g or 1 of original sample) = A (VF) 2 sigma error (pCi/g or 1 of original sample) = C (VF) where: s = Gross counts of .sample B = Counts of blank E = Fractional H-3 counting efficiency T = Number of minutes sample was counted t = Number of minutes blank was counted v = Vo 1ume of dis ti 11 ate counted YI = Liters of water-organic recovered/ g of freeze dried sample VF = Liters of water recovered/ (1 or g) of sample aliquot counted A = Result in pCi/l of distillate c = 2 sigma error in pCi/l of distillate Calculation of lower limit of detection (LLD) The* detection limit is assumed to be exceeded when the counting res*u1t is different from the blank reading by at least 4.66 times the standard deviation of that back-ground. LLD (pCi/l) = 4.66 (B 112) I (2.22 V E t) LLD (pCi/g of freeze dried sample) = F (YI) LLD (pCi/l or g) = F (VF) of original sample where: B = Counts of blank E = Fractional H-3 counting efficiency t = Number of minutes blank was counted v = Volume of distillate counted YI = Liters of water-organic recovered/g of freeze dried sample VF = Liters of water recovered/{l or g) of sample aliquot counted F = LLD in pCi/l of distillate 106
ANALYSIS OF 'SAMPLES FOR IODINE-131 Milk or Water (I0) The initial stable iodide concentration in milk ts determined with an iodide ion specific electrode. Thirty milligrams of stable iodide carrier is then added to four (4) liters of milk. The iodide is removed from the milk by passage through ion-exchange resin. The iodide is eluted from the resin with sodium hypochlorite, and purified by a series of solvent extractions with the final extraction into a toluene phase. The toluene phase is mixed with a toluene-based liquid scintilla-tion solution. The sample is then counted in a beta-gated gamma coincidence de-tector, shielded by six inches of steel. Distilled water is used as a blank. The yield is calculated from stable iodine recovery based on the recovered volume. Calculations are made utilizing the following equations: Result = (S-B) I (2.22 V E F Y T) (pCi/l) 2 sigma error = 2 (S+B) 112 I (2.22 V E FY) ( pCi /1) LLD = 4.66 (8 112) I (2.22 V E F Y T) ( pCi/l) where: s = Gross counts of sample in channels containing I-131 peak B = Background counts in channels containing I-131 peak T = Number of minutes sample was counted E = Iodine-131 counting efficiency v = Sample aliquot size F Fractional gamma abundance y = Chemical yield of iodine Air Cartridges (Il). An iodine adsorber composed of charcoal is emptied into an aluminum can (6 ems high by B ems in diameter) and counted with a NaI(Tl) scintillation detector, coupled to a multi-channel puls~-height analyze~. Calculation of results and two sigma error Peaks are identified by changes in the slope of the spectrum. If peaks are identified, the spectrum obtained is smoothed to minimize the effects of random statistical fluctu-ations. The presence of iodine-131 is identified by the presence of a 364 Kev peak. The net area above the baseline is calculated. This area is converted to activity in curie units, making allowance for counting efficiency and gamma ray abundance. A PDP-11 computer program is used for spectrum analysis. Results are corrected for de-cay from the sampling time to the middle of the counting period, using a half-life value for I-131 of 8.06 days. Calculations are made utilizing the following equations: Result 3 = ((S/T) - (B/t)) I (2.22 V E FY) (pCi/m ) 107
2 sigm~ error = 2 ((S/T 2) + (B/t 2)) 112 I (2.22 V E FY) (pCi/m ) LLD = 4.66 (.63(Q 1/ 2)b) 1/ 2 I (2.22 VE FY t) (pCi/m 3) . where: s = Net area, in counts, of sample in I-131 peak B = Net area, in counts, of background in I-131 peak b = Counts in I-131 peak channel T = Number of minutes sample was counted t = Number of minutes background was counted E = Iodi ne-131 counting *efficiency v = Sample aliquot size F = Fractional gamma abundance y = Chemical yield of iodine 108
GAMMA SPECTROMETRY OF SAMPLES Water (Nl) Four liters of sample is reduced to 100 ml and sealed in a standard container and counted with a Nal(Tl) detector coupled to a multi-channel pulse-height analyzer. The counting time is 50,000 seconds. Milk (N7) A 4 liter aliquot is dried at 175°C, ashed at 500°C until no carbon residue is present, compressed and sealed in a standard container, and then counted with a Nal(Tl) detector, coupled to a multi-channel pulse-height analyzer. The counting time is 50,000 seconds. Dried Solids (N8, G8) A large quantity of the sample is dried at a low temperature, less than l00°C. A 100 gram aliquot (or the total sample if less than 100 grams) is taken, com-pressed to a known geometry, sealed in a standard container, and counted with a NaI(Tl) or Ge(Li) detector, coupled to a multi-channel pulse~height analyzer. The counting time is 50,000 seconds. Air Dried Solids (NA) A large quantity of sample is air dried. A 100 gram aliquot (or the total sample if less than 100 grams) is- taken, compressed to unit density, sealed in a stan-dard container and counted with a Nal(Tl) detector, coupled to a multi-channel pulse-height analyzer. The counting time is 50,000 seconds. Calculation of results and two sigma error The spectrum obtained is smoothed to minimize the effects of random statistical fluc-tuations. Peaks are identified by changes in the slope of the gross spectrum. The net area, 'in counts, above the baseline is calculated. This area is converted to activity in curie units, making allowance for counting efficiency and gamma ray abundance. A computer program is used for spectrum analysi:s. Calculations are made utilizing the following equations: Result (pCi/l or g) = ((S/T) - (B/t)) I (2.22 V E F) 2 sigma error (pCi/l or g) = 2 ((S/T 2) + (B/t 2)) 112 I (2.22 V E F) where: s = Net area, in counts, of sample (Region of spectrum of interest) B = Net area, in counts, of background (Region of spectrum of interest) T = Number of minutes sample was counted t = Number of minutes background was counted E = Detector efficiency for energy of interest v = Sample aliquot size F = Fractional gamma abundance (specific for each emitted nuclide) 109
Calculation of lower limit of detection (LLD) for G8 LLD (pCi/l or g) = 4.66 (6 S) 1/ 2 I (2.22 V E FT) where: s = Net area, in counts, of sample (Region of spectrum of interest) T = Number of minutes samole was counted E = Detector efficiency for energy of interest v = Sample aliquot size F = Fractional gamma abundance Calculation of lower limit of detection (LLD) for Nl, N7, N8 and NA LLD (pCi/l or g) = 4.66 (.63 (Q) 112 S) 112 I (2.22 VE FT) where: s = Net area, in counts, of sample (Region of spectrum of interest) T = Number of minutes sample was counted E = Detector efficiency for energy of interest v = Sample aliquot size F = Fractional gamma abundance Q = Channel number 110
ANALYSIS OF SAMPLES FOR STRONTIUM-89 AND -90 Total Water (S0, T0) A two liter aliquot of sample is used. Stable strontium carrier is added to the liquid to facilitate chemical separation of Sr-89 and -90, and to determine the strontium recovery. Strontium concentration and purification is ultimately real-ized by at least two precipitations of strontium nitrate in concentrcated nitric acid. Additional i'ron/rare earth hydroxide precipitations and barium chromate separations are performed to remove suspected interfering nuclides. After puri-fication, the Y-90 is allowed to ingrow for a known period of time. Sr-90 is then determined by counting yttrium oxalate after initially precipitating Y-90 as yttrium hydroxide. Sr-89 is determined by counting strontium carbonate and correcting the observed activity for the amount of Sr-90 and Y-90 on the plan-chet. A sample of distilled water is used as a blank. Milk (S4, T4) A one and half liter aliquot of milk is ashed to destroy organic material and then dissolved in concentrated mineral acid. Stable strontium is added to the eluted liquid or dissolved ash to facilitate chemical separation of Sr-89 and -90, and to determine the strontium recovery. Strontium concentrations and purification is ultimately realized by at least two precipitations of strontium nitrate in concen-trated nitric acid. Additional iron/rare earth hydroxide precipitations and barium chromate separations are performed to remove suspected interfering nuclides. After purification, the Y-90 is allowed to ingrow for a known period of time. Sr-90 is then determined by counting yttrium oxalate after initially precipitating Y-90 as yttrium hydroxide. Sr-89 is determined by counting strontium carbonate and correcting the observed activity for the amount of Sr-90 and Y-90 on the planchet. A sample of distilled water is used as a blank. Bones and Shells (S5, T5) A large quantity of the sample is dried, ashed aDd a 25 g portion is then dissolved in concentrated acid. Stable strontium carrier is addedto the dissolved sample to facilitate chemical separations ofSr-89 and*-90, and to determine the strontium recovery. Strontium concentration and purification is ultimately realized by at least two precipitations of strontium nitrate in concentrated nitric acid. Addi-tional iron/rare earth hydroxide precipitations andbarium chromate separations are performed to remove suspected interfering nuclides. After purification, the Y-90 is allowed to ingrow for a known period of time. Sr-90 is then determined by counting yttrium oxalate after initially precipitating Y-90 as yttrium hydroxide. Sr-89 is determined by counting strontium carbonate and correcting the observed activity for the amount of Sr-90 and Y-90 on the planchet~ A sample of distilled water is used as a blank. Soil and Sediment (S6, T6) A large quantity of sample is dried, and a 25 g portion is then leached with concen-trated HCl before drying. Stable strontium carrier is added to the sample to facili-tate isolation of the strontium and.to determine the strontium recovery. Strontium concentration and purification is ultimately realized by at least two precipitations of strontium nitrate in concentrated nitric acid. Additional iron/rare earth hydroxide precipitations and barium chromate separations are performed to remove suspected 111
interfering nuclides. After purification, the Y-90 is allowed to ingrow for a known period of time. Sr-90 is then determined by counting yttrium oxalate after initially precipitating Y-90 as yttrium hydroxide. Sr-89 is determined by counting strontium carbonate and correcting the observed activity for the amount of Sr-90 and Y-90 on the planchet. A sample of distilled water is used as a blank. Organic Solids (S8, T8) A 250 g portion of the sample is ashed and then dissolved in concentrated acid. Stable strontium carrier is added to the dissolved sample to facilitate chemical separation of Sr-89 and -90, and to determine the strontium recovery. Strontium concentration and purification is ultimately realized by at least two precipitations of strontium nitrate in concentrated nitric acid. Additional iron/rare earth hy-droxide precipitations and barium chromate separations are performed to remove suspected interfering nuclides. After purification, the Y-90 is allowed to ingrow for a known period of time. Sr-90 is then determined by counting yttrium oxalate after initially precipitating Y-90 as yttrium hydroxide. Sr-89 is determined by counting strontium carbonate and correcting the observed activity for the amount of Sr-90 and Y-90 on the planchet. A sample of distilled water is used as a blank. Calculations of the results, the two sigma errors and minimum detectable levels (MDL) for Sr-89, -90 are expressed in activity (pCi) per unit volume (liter) or mass (gram). Result Sr-90 = (A/Tl-B/T2) / (2.22 VEY X exp(-0.693 tl/64.1)(1-exp(-0.693t2/64.1))) (pCi/l or g) 2 sigma error Sr-90 = 2(A/Tl 2+B/T2 2) 112 / (2.22 VEY X exp(-0.693tl/64.1)(1-exp(-0.693 (pCi/l or g) t2/64.1))) MDL Sr-90 = 3 s112 I (2.22 T2 VEY X exp(-0.693tl/64.1)(1-exp(.;.0.693t2/64.l))) (pCi/l or g) where: A = Gross Y-90 counts B = Gross blank counts of yttrium Tl = Y-90 counting time T2 = Blank counting time v = Sample aliquot size E = Y-90 counting efficiency y = Yttrium chemical yield x = Strontium chemical yield tl = Time in hours from second separation of Y-90 until counting time of yttrium planchet plus one-half the counting time t2 = Time in hours between first and second separations of Y-90 (ingrowth time) Result Sr-89 = (C/T3 - D/T4 - G - H)/(2.22 V F X exp(-0.693t4/50.5)) (pCi /1 or g) 2 sigma error Sr-89 =2 (C/T3 2 + D/T4 2 + G/T3 + H/T3) 112 I (2.22 V F X exp(-0.693t4/50.5)) (pCi/l or g) 112
MDL Sr-89 = 3(D+GT3+HT3) 112 I (2.22 T4 V F X exp(-0.693t4/50.5)) (pCi /1 or g) where: c = Gross strontium counts D = Gross blarik counts of strontium G = Additional background from Sr-90 activity
= (Sr-90 activity of sample) (2 .. 22 VXJ)
H = Additional background from Y-90 activity
= (Sr-90 activity of sample) (2.22 VXE) (1-exp(-0.693t5/64.1))
v = Sample aliquot size J = Sr-90 counting efficiency F = Sr-89 counting efficiency x = Strontium chemical yield t4 = Time in days from sampling date to strontium count T3 = Strontium counting time T4 = Blank counting time t5 = Time in hours from second separation of Y-90 to counting of strontium planchet plus one~half the counting time 113
--1 APPENDIX D-2 SYNOPSIS OF ANALYTICAL PROCEDURES UTILIZED BY THE RESEARCH AND TESTING LABORATORY 115
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 then counted for gross alpha activity on a low background gas proportional counter. Along with a set of air particulate samples, a clean air filter is included as a blank with an Am-241 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 into account the air pressure correction due to the vacuum being drawn, the correction factor of the temperature - corrected gas meter as well as the gas meter efficiency itself. Calculation of Gross Alpha Activity: 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 29.92 = Standard atmospheric pressure at 32°F, 11 Hg V = F*P*0.946*0.0283 F = Uncorrected air flow, ft3 E 0.946 = Temperature correction factor from 60°F to 32°F 0.0283 = Cubic meters per cubic foot E = Gas meter efficiency (= % efficiency /100) V = Corrected air flow, m3 P = Pressure correction factor Using these corrected air flows, the gross alpha activity is computed as follows: Result (pCi/m 3) = (G-B~/T G = Sample gross count . (2 .;22)* E)*(V) B = Backgro~nd counts (from blank filter) T = Count time of sample and blank, mins. E = Fractional Am-241 counting efficiency V = C~rrected air flow of sample m 2.22 = No. of dpm's per pCi 2 sigma error (pCi/m3) A= Gross alpha activity, pCi/m3 G = Sample gross counts B = Background counts (from blank filter) 117
Calculation of lower limit of detection: A sample activity is assumed to be LLD if the sample net count is less than 4.66 times the standard deviation of the count on the blank. LLD (pCi/m3) = 4.66
- fB~l/ 2 B = Background counts (from blank T2.22)* E *(V)*(T) filter)
E = Fractional Am-241 counting efficiency V = C§rrected air flow of sample, m T = Count time of blank, mins. 118 J
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 oat, air particulate samples are then counted for gross beta activity on a low background gas proportional counter. Along with a set of air particulate samples, a clean air filter is included as a blank with an Sr-90-Y-90 air filter geometry beta counting standard. The specific 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 it-self. Calculation of Gross Beta Activity: Air flow is corrected first by using the following equations: P = (B-V)/29.92 P = Pressure correcti..on factor B = Time-averaged barometric pressure during sampling period, 11 Hg V = Time-averaged vacuum during sampling period 29.92 = Standard atmospheric pressure at 32°F, 11 Hg V = F*P*0.946*0.0283 F = Uncorrected air flow, ft3 E 0.946 = Temperature correction factor from 60°F to 32°F 0.0283 = Cubic meters per cubic foot E = Gas meter efficiency (= % efficiency I 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/m3) = (G-B~/T G = Sample gross counts (2.22)* E)*(V)
- B = Background counts (from b1ank filter)
T = Count time of sample and blank, mins. E = Fractional Sr-90 counting effic~ency V = Corrected air flow of sample, m 2.22 = No. of dpm's per pCi 2 sigma error (pCi/m3) = (1.96*fG+B~ 1 / 2 )*A G-B A= Gross beta activity, pCi/m3 G = Sample gross counts B = Background counts (from blank filter} 119
Calculation of lower limit of detection: A sample activity is assumed to be LLD if the sample net count is less than 4.66 times the standard deviation of the count on the blank. LLD (pCi/m 3) = 4.66 * ~B~l/ 2 B = Background counts (from blank
"("2.22)* E *(V)*(T) filter)
E = Fractional Sr-90 counting efficiency V = C§rrected air flow of sample m T = Count time of blank, mins. 120
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, active area facing down, 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 Ge(Li) detector for 500 minutes. Calculation of Gamma Activity A special program developed by Tracor Northern is run on a PDP-11 computer. Photo-peaks are located by passing a digital filter through the spectrum, channel-by-channel, with the effect that the background portion of the spectrum is greatly reduced, leaving the peaks intact. To compute the desired net count under any one of these: photopeaks, a background baseline is established extending from 1.5 times the fu11...:width-at-half-max above, to' the same distance below the centroid. The. counts under this baseline are then subtracted out from the total number of counts under the photo}!>eak~ The following are the calculations performed for the gamma activity, 2 sigma error and LLD: . Result = (pCi/m 3) = N*D =R 2=--.="'22,,. . .*).;,.;. .,*(.. :ET"':)*,. . .,. (A., . ,),-:-*"""'T,( ,. . .)*.,.....,(..,...,.V)
..,...,t N = Net counts under photopeak D = Decay correction factor Xtl*EXP Xt2 1-EXP -t..tl tl = Acqu1sition live time t2 = Elapsed time from sample collection to start of acquisition
= 0.693/nuclide half life E = Detector efficiency A = Gamma abundance factor (no. of photons per disintegration)
T = Acquisition live time, mins. V = Sample volume, m3 2.22 = No. of dpm's per pCi 2 sigma error (pCi/m3) = 2 * (crk 2+crs 2)1/2 crk = 1 1/2 crk = statistical error of the n 1
- A ("()~1 activity measurement. It is L a 2 determined from the accuracy i=l of the least squares evalu-ation performed on the peaks of a particul~r nuclide.
n = number of peaks in the nuclide of question cri = (GC+Bc)l/2, where GC and BC are gross counts and background counts, respectively. 121 I
A (y) i = N*D = g~wna abundance factor for the (E}*(R)*(2.22)*(T)*(V) i peak under consideration, for a given nuc1ide crs represents systematic errors (such as errors in detector efficiency) over and above the statistical error of the activity measurement. It is assigned a fixed value representing 5% of the computed activity and should be regarded as a minimum estimate of the activity error. All other variables are as defined earlier. The LLD (pCi/m3) = 4.66*~Gc)l/ 2 *~ (2.22)*(E *(A)*(T *(V) Again, all other variables are as defined earlier. 122
ANALYSIS OF AIR FILTERS FOR RADIOSTRONTIUM 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 a couple of fuming add leabhings are carried out to remove the radiostrontium from the filter media. Once this is done, the resultant nitrates are dissolved in distilled water and the filter residue is filtered out. Radioactive interferences are stripped out by coprecipitation on ferric hydroxide (yttrium strip) followed by a barium chromate strip. The strontium, now largely devoid of any radio-logical impurities, is converted to a carbonate form 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 Sr-90 and Sr-89 are both unknown quantities requiring two simultaneous equations to solve for them. Calculation of Sr-90 Activity: Sr-90 Results (pCi/m 3) N4/R
= (2.22) * (E) * (0.7621) * (S6) * (V) * (U)
= W2 where S6 = 1.4115 - 0.03409*M + 0.000443*M 2 (This is normalized Sr-90 efficiency regression equation for one particular gas proportional counter)
M = Thickness density of strontium carbonate precipitate, mg/cm 2 0.7621 =Ratio of Sr-90 efficiency at thickness value of 15 mg/cm 2 to Sr-90 counting standard efficiency (This standard is run with each group of environmental strontium samples) E = Sr-90 counting standard efficiency V = Sample quantity (liters, m3 or kg) U = Chemical yield N4 = (N2 - Fl*Nl)/Wl = net counts due to Sr-90 only Wl = ((1 + Rl*I2) - (1 ~ Rl*ll)*Fl) 11 = 1 - EXP ((-0.693/2.667)*tl) 12 = 1 - EXP ((-0.693/2.667)*t2) tl = Elapsed time from Y-90 strip to first count t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days 123
Rl = 1.242 + 0.0179*M + 0.000151*M2 (This is regression equation for Y-90 eff'y/Sr-90 eff 1 y ratio). N2 = X- Y, where X and Y are recount gross counts and background counts, respectively. Nl = Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively. 2.22 = No. of dpm*~ per pCi Fl~ 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 Sr-90 (pCi/m3) = 2* [ (X+Y) + (Xl+Yl) *F1 2] / w12 w12 1 2
* (Wl*W2)
(N2-Fl*Nl) Again, keeping tbe same variable definitions, the LLD Sr-90 (pCi/m 3 ) = 4.66* [(x+v~ + (Xl+Yl)*Fl 2l11 2 Ca lcul ati on of Sr-89 Ac ti vi ty: Wl w12 :I N6/R Sr-89 Results (pCi/m3) = (2.22) * (E) * (1.0922) * (s7) * (V) * (U) * (F9)
= W3 S? = 1.052 - 0.00272*M - 0.00005*M2 (This is normalized Sr-89 efficienc.v regression equation for one particular gas proportional counter)
N6 = Nl - N7* (1 + Rl*ll) N7 "' (N2 - Fl*Nl)/Wl (This represents counts due to Sr-90) 1.0922 = Ratio of Sr-89 efficiency at thickness value of 15 mg/cm2 to Sr-90 counting standard efficiency (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 =Half-life of Sr-89, days All other variables are as originally defined. The 2 sigma error for Sr-89 (pCi/m3) = 2*(S8 2+s9 2 ) 1/ 2*W3 (Nl - N7*(l+Rl*Il) 124
SS = l(x+p + (Xl+~l)*Fl2ll/2 LWl Wl J S9 = (Xl+Yl)l/ 2 All other variables are as originally defined. Keeping tbe same variable definitions, the LLD Sr-89 (pCi/m3) = 4.66* (S8~+s9 2 ) 1 / 2 125
ANALYSIS OF RAW MILK FOR RADIOSTRONTIUM A stable strontium carrier is first introduced into a one liter milk sample and into a distilled water sample of equal volume to be used as a blank. The sam-ple(s) and blank are passed through cation resin columns which pi ck up stron-tium, 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 upon heating. The carbonates are converted to nitrates with 6N nitric acid and, by acidifying further to an overall concentration of 70% ni-tric acid, strontium is forced out of solution somewhat ahead of calcium. Barium chromate precipitation is then perforl!Jed to remove any traces of radium and radio-barium. Strontium recrystallization is carried out to remove residual calcium which may have been coprecipitated with the foitial strontium precipitation. Another recrystallization removes ingrown Y-90, marking the time of the yttrium strip. The strontium is reconverted to the carbonate, filtered, dried and weighed to determine strontium recovery. 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 Sr-90 and Sr-89 are both unknown quanti-ties requiring two simultaneous equations to solve for them. Calculation of Sr-90 Activity: Sr-90 Results (pCi/l) = N4/R (2.22) * (E) * (0.7621) * (S6) * (V) * (U)
= W2 where S6 = 1.4115 - 0.03409*M + 0.000443*M2 (This is normalized Sr-90 efficiency regression equati-on for one particular gas proportional counter)
M = Thickness density of strontium carbonate precipitate, mg/cm2 0... 7621 = Ratio of Sr-90 efficiency at thickness value of 15 mg/cm2 to Sr-90 counting standard efficiency (This standard is run with each group of environmental strontium samples) E = Sr-90 counting standard efficiency V = Sample quantity (liters, m3 or kg) U = Chemical yield N4 = (N2 - Fl*Nl)/Wl = net counts due to Sr-90 only Wl = ((1 + Rl*I2) - (1 + Rl*Il)*Fl) Il = 1 - EXP ((-0.693/2.667)*tl) I2 = 1 - EXP ((-0.693/2.667)*t2) tl = Elapsed time from Y-90 strip to first count t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days 126
Rl = 1.242 + 0.0179*M + 0.00015l*M 2 (This is regression equation for Y-90 eff'y/Sr-90 eff 1 y ratio) N2 - X - Y, where X and Y are recount gross counts and background
*COUnts, respectively Nl = Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 = No. of dpm s per pCi 1
Fl = EXP ((-0.693/2.667)*t2) R = Count ti me of sample and b1ank Using the same variable definitions as above, the 2 sigma error for Sr-90 (pCi/l) = 2* [cx+v~ Wl
+ (Xl+~l)*F1 Wl 2J 1 1 2 Wl*W2 N2-Fl*Nl Again, keeping the same variable definitions, t~e 112 LLD Sr-90 (pCi /1) = 4.66*[ (X+Y~ + (Xl+Y2)*Fl L Wl Wl J
. Calculation of Sr-89 Activity: Sr-89 Results ( pCi /1) =
- N6/R
~C2-.-2..,...2)-*-.(-E).--*--.(...-1-.o,.;.:.9=-22-r:)'---*---.-(s--7......
) -*--.-(v..,....)_*.,___,..(u--)-*-.(~F9)
= W3 57 = 1.052 - 0.00272*M - 0.00005*M 2 (This is normalized Sr-89 efficiency regression equation for one particular gas proportional counter)
N6 = Nl - NY~ (1 + Rl*Il)
!U = (N2 - Fl*fH)/Wl (This represents counts due. to Sr-90) 1.0922 = Ratio of Sr-89 efficiency at thickness value of 15 mg/cm 2 to Sr-90 counting standard efficiency (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 mi 1k samp*les only. For al 1 other samples, this represents the elapsed time from sample stop date to time of recount. 50.5 = Half-life of Sr-89, days All other variables are as originally defined 127
The 2 sigma error for Sr-89 (pCi/1) = 2* (ss 2+s92) 1/ 2 *W3 (Nl - N7* (l+Rl*Il)) S8 = [cx+p + (Xl+Y~)*Fl2l 112 Wl Wl J S9 = (Xl+Y1) 112 All other variables are as originally defined Keeping tbe same variable definitions, the LLD Sr-89 (pCi/1)
ANALYSIS OF WATER SAMPLES FOR TRITIUM Approximately 50 ml of raw sample is mixed with sodium hydroxide and potassium permanganate and is distille~ under vacuum. Eight ml of distilled sample is mixed with 10 ml of Instagel liquid scintillation solution, and placed in the liquid scintillation spectrometer for counting. Prepared simultaneously for counting is the internal standard. This is done by mixing eight ml of sample, 10 ml of Instagel, and 0.1 ml of a standard with known activity. The efficiency is detennined from this. Also prepared is a blank consisting of eight ml of distilled low-tritiated water and 10 ml of Instagel, to be used for a background determination. This is done for each pair of samples to be counted. Activity is computed as follows: A ( pCi I 1) = 4-(G:; _-.=:. .B)~-.--.,--.--.- A = Activity
- 2. 22 ( E} (V) (T) B = Background count of sample G = Gross count of sample E = Counting efficiency v = Aliquot volume (L)
T = Count time (min) 2.22 = dpm/pCi Efficiency (E) is computed as follows: E = (N) ~D) N = Net cpm of spiked sample A 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 95% confidence limit, as follows: l.96(G/T 2+B/T 2) 112 2.22 (V) (E) If collection container is rinsed with distilled water (e.g., rainwater), the sample is corrected for the blank as follows:' A (pCi/l) = (G) (Sl) - (R) (S2) Sl = Rainwater volume v v V = Sample volume 2.22(V-S2) (E) (1000) S2 = Rinsewater volume R = Rinse counts Note: G and R are corrected for background counts Samples are designated LLD if the activity is less than the following value: 2 LLD = (4.66~ ~B~l/ 2.22VE) (T) 129
RADIOSTRONTIUM rn WATER Stable strontium carrier is first introduced into a two liter 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 pre-cipitating the carbonates. The carbonates are converted over to nitrates by fuming nitric acid recrystallization which acts to purify the sample of most of the calcium. Radioactive interferences are stripped out by coprecipitation on ferric hydroxide (yttrium strip) followed by a barium chromate strip. The stron-tium, now largely devoid of any chemical or radiological impurities, is converted back to a carbonate form 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 Sr-90 and Sr-89 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 via DC Argon Plasma Emission. These results are used in correcting the chemica*l recovery of strontium to its true value. Calculation of Sr-90 Activity: Sr-90 Results (pCi/l} N4/R
= (2.22) * (E) * (0.7621) * (S6) * (V) * (U)
= W2 where S6 = 1.4115 - 0.03409*M + 0.000443*M 2 (This is normalized Sr-90 efficiency regression equation for one particular gas propor-tional counter}
M = Thickness density of strontium carbonate precipitate, mg/cm 2 0.7621 = Ratio of Sr-90 efficiency at thickness value of 15 mg/cm2 to Sr-90 counting standard efficiency (This standard is run with each group of environmental strontium samples) E = Sr-90 counting standard efficiency V = Sample quantity (liters, m3 or kg) U = Chemical yield N4 = (N2 - Fl*Nl)/Wl = net* counts due to Sr-90 only Wl = ( (1 + Rl*I2) -. (1 + Rl*Il)*Fl) Il = 1 - EXP ((-0.693/2.667)*tl) I2 = 1 - EXP ((-0.693/2.667)*t2) tl = Elapsed time from Y-90 strip to first count t2 = Elapsed time from Y-90 strip to second courit 130
2.667 = Half-life of Y-90, days Rl = 1.242 + 0.0179*M + 0.000151*M 2 (This is regression equation for Y-90 eff'y/Sr-90 eff'y ratio) N2 = X - Y, where X and Y are recount gross counts and background counts, respectively Nl = Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 = No. of dpm's per pCi Fl = 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 Sr-90 (pCi/l) = 2* [wWl
+ (Xl+~l)*F1 l Wl 2 11 2
- Wl*W2 J N2-Fl*Nl Again, keeping the same variable definit'lons, the LLD Sr-90 (pCi/1) =
4.66* [w Wl
+ (Xl+Y~)*F12]1/ 2 Wl Calculation of Sr-89 Activity:
Sr-89 Results (pCi /l) = N6/R (2.22} * (E} * (1.0922) * (S7} * (V} * (U) * (F9}
= W3 57 = 1.052 - 0.00272*M - 0.00005*M 2 (This is normalized Sr-89 efficiency regression equation for one particular gas proportional counter)
N6 = Nl - N7*(1 + Rl*Il) N7 = (N2 - Fl*Nl)/Wl (This represents counts due to Sr-90) 1.0922 = Ratio of Sr-89 efficiency at thickness value of 15 mg/cm2 to Sr-90 counting standard efficiency (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 = Half-life of Sr-89, days 131
All other variables are as originally defined The 2 sigma error for Sr-89 (pCi/l) = 2* S8 2+s9 2 112 *W3 Nl - N7* l+Rl*Il S8 = lcx+2) + (Xl+Y~~~F1 2J 1 1 2 LWl Wl S9 = (Xl+Y1) 1/ 2 All other variables are as originally defined Keeping the same variable definitions, the LLD Sr-89 (pCi/l) = 4.66* (S8 2+s9 2) 1/ 2 132
APPENDIX E
SUMMARY
OF INTERLABORATORY COMPARISONS 133
TABLE E-1 INTER-LJlBORATORY cm1PAIUSONS GROSS ALPHA Al'JD BETA IN HATER (pCi/liter) and AIR PARTICULATES (pCi/filter) SJlMPLE Ri'IC EPA All Participants DATE R;-.tC # TYPE ANALYSIS i'1EAN+/-s.d. MEAN+/-s .d. MEA!J+/-s .d. Jan 67011 Water a 22+/-2 24+/-6 21+/-6 1982 B 29+/-1 32+/-5 31+/-6
- 1arch 70043 Hater a 15+/-1 19+/-5 18+/-4 1982 B 19+/-1 19+/-5 20+/-4 March 70631 APT a 24+/-3 27+/-7 26+/-4 1982 B 58+/-2 55+/-5 59+/-8 Apri 1 72020 Hater a 50+/-3 85+/-21 75+/-16 1982 B 93+/-2 (a) 106+/-5 106+/-13 May 73330 Water a 22+/-1 28+/-7 25+/-7 1982 B 31+/-3 29+/-5 30+/-6 July 76747 Water a 11+/-2 16+/-5 16+/-5 1982 B 22+/-1 23+/-5 21+/-5 Sept 81226 Water a 20+/-1 29+/-7 26+/-6 1982 B 34+/-1 40+/-5 38+/-6 Sept 81457 APT a 27+/-3 32+/-8 28+/-6 1982 B 38+/-2 (b) 67+/-5 61+/-8 Oct 83052 Water a 48+/-2 55+/-14 47+/-14 1982 B 101+/-1 81+/-5 76+/-11 Nov 84691 Water a 17+/-2 19+/-5 17+/-4 1982 B 22+/-2 24+/-5 24+/-3 Nov 91763 APT a 28+/-1 27+/-7 29+/-4 1982 B 64+/-2 59+/-5 66+/-7 (a) Insufficient sample to reanalyze. Probable reasons for discrepancy are incomplete transfer of sample to pl anchet, incorrect pi"petting of sample aliquot and nonhono-geneity of sample.
(b) Calculation was verified. Sample could not be reanalyzed becat1se it was destroyed in the strontium analysis. Gross alpha, gamma and strontium-90 for that sample were in agreement with the EPA. 135
TABLE E-2 ItffER-LABORATOR¥ CCl1PARISOUS GA~1r1A l 1J SAMPLE RMC EPA All Participants DATE RMC # TYPE ISOTOPE HEAN+/-s.d. MEAN+/-s.d. r*tEAH+/-s .d. Feb 68029 Water Cr-51 <56 0 5+/-9 1982 Co-60 22+/-4 20+/-5 20+/-5 Zn-65 16+/-3 15+/-5 15+/-4 Ru-106 <32 (a) 20+/-5 19+/-8 Cs-134 20+/-1 22+/-5 21+/-3 Cs-137 22+/-0 23+/-5 24+/-4 March 70631 APT Cs-137 32+/-1 23+/-5 27+/-6 1982 April 72020 Water Co-60 <3 0 5+/-10 1982 Cs-134 16+/-1 15+/-5 15+/-4 Cs-137 16+/-2 16+/-5 17+/-4 April 72074 i'1i 1k Co-60 30+/-2 30+/-5 31+/-4 1982 Cs-137 28+/-3 28+/-5 30+/-4 Ba-140 <147 0 5+/-7 K 1530+/-204 1500+/-75 1495+/-178 June 74569 Water Cr-51 <72 (b) 23+/-5 25+/-13 1982 Co-60 29+/-2 29+/-5 31+/-4 Zn-65 26+/-3 26+/-5 27+/-6" Ru-106 <30 0 10+/-11 Cs-134 34+/-1 35+/-5 34+/-4 Cs-137 24+/-2 25+/-5 27+/-4 July 76127 Food I-131 105+/-13 94+/-9 100+/-9 1982 Cs-137 27+/-4 20+/-5 26+/-4 Ba-140 <19 0 0 K 2660+/-244 2400+/-120 2645+/-244 Sept 81457 APT Cs-137 25+/-4 27+/-5 25+/-4 1982 Oct 82539 Water Cr-51 <93 (b) 51+/-5 51+/-15 1982 Co-60 21+/-4 20+/-5 20+/-3 Zn-65 21+/-6 24+/-5 24+/-4 Ru-106 41+/-6 30+/-5 31+/-8 Cs-134 16+/-2 19+/-5 18+/-3 Cs-137 17+/-3 20+/-5 21+/-3 136
TABLE E-2 (cont.) INTER-LABO:~~~( l y0!'1PARISOUS SAMPLE RMC EPA All Participants DATE RMC # TYPE ISOTOPE MEAN+/-s .d. MEAN+/-s.d. MEAN+/-s.d. Oct 83052 Uater Co-60 <4 0 3+/-7 1982 Cs-134 <3 2+/-5 6+/-11 Cs-137 21+/-2 20+/-5 20+/-3 Oct 83535 r1i 1 k I-131 47+/-5 42+/-6 40+/-7 1982 Cs-137 35+/-4 34+/-5 35+/-3 Ba-140 <31 0 2+/-5 K 1682+/-68 1560+/-78 1528+/-196 Nov 84177 Food I-131 30+/-6 25+/-6 25+/-5 1982 Cs-137 28+/-4 27+/-5 29+/-4 Ba-140 <32 0 0 K 2934+/-118 2780+/-140 2846+/-207 Nov 91763 APT Cs-137 31+/-2 27+/-5 30+/-5 1982 ( 1) Results reported in pCi/liter for milk and water, pCi/sample for air particulates, and pCi/kilograms for food products except K which is reported in mg/liter for milk and mg/kilogram for food products. (a) Positive activity was not detected due to the low sensitivity of the analysis for Ru-106. (b) Positive activity was not detected due to the low sensitivity of the analysis for Cr-51. 137
TABLE E-3 INTER-LABORATORY COMPARISONS TRITIUM IN WATER pCi/liter SAMPLE ~IC EPA All Participants DATE RMC # TYPE ANALYSIS MEAN+/-s .d. MEAN+/-s.d. MEAN+/-s .d. Feb 67807 Water H-3 1913+/-138 1820+/-342 1853+/-229 1982 Apr 71295 Water H-3 2800+/-89 2860+/-360 2812+/-242 1982 June 74602 ~~ater H-3 1867+/-590 1830+/-340 1765+/-229 1982 Aug 77486 Water H-3 3077+/-100 2890+/-360 2847+/-270 1982 Oct 82727 Water H-3 2473+/-58 2560+/-350 2517+/-250 1982 Dec 90744 ~Jater H-3 2007+/-75 1990+/-345 2009+/-233 1982 138
TABLE E-4 INTER-LABORATORY COMPARISONS IODINE-131 IN WATER pCi/l iter SAMPLE RMC EPA All Participants DATE RMC # TYPE ANALYSIS MEAN+/-s.d. MEAN+/-s.d. MEAN+/-s.d. Jan 67243 Water I-131 7.0+/-0.1 8.4+/-1.5 8. 3+/-1. 0 1982 Apr 70963 Water I-131 66+/-4 62+/-6 63+/-8 1982 June 75597 Water I-131 3. 9+/-0. 7 4.4+/-0.7 4. 5+/-1.1 1982 July 77316 Water I-131 5.5+/-0.3 5.4+/-0.8 5. 7+/-1.5 1982 Aug 78175 Water I-131 88+/-2 87+/-9 86+/-10 1982 Dec 90378 Water I-131 40+/-3 37+/-6 38+/-5 1982 139
TABLE E-5 INTER-LABORATORY COMPARISON£ STRONTIUM-89 AND STRONTIUM-9oll) SAMPLE RMC EPA All Participants DATE RMC # TYPE ANALYSIS MEAN+/-s.d. MEAN+/-s.d. MEAN+/-s.d. Jan 66079 Water Sr-89 15+/-1 21+/-5 20+/-4 1982 Sr-90 12+/-1 12+/-2 11+/-2 March 70631 APT Sr-90 28+/-6 (a) 16+/-1 16+/-2 1982 April 72020 Water Sr-89 14+/-8 (a) 24+/-5 24+/-4 1982 Sr-90 10+/-1 12+/-2 12+/-2 April 72074 Milk Sr-89 <23 25+/-5 22+/-5 1982 Sr-90 <26 16+/-2 14+/-3 May 73333 Water Sr-89 17+/-2 22+/-5 22+/-5 1982 Sr-90 13+/-2 13+/-2 12+/-2 July 76127 Food Sr-89 22+/-11 26+/-5 29+/-7 1982 Sr-90 18+/-8 20+/-5 23+/-2 Sept 80211 Water Sr-89 19+/-1 25+/-5 24+/-4 1982 Sr-90 15+/-1 15+/-2 14+/-2 Sept 81457 APT Sr-90 17+/-1 20+/-2 17+/-2 1982 Oct 83052 Water Sr-89 <5 0 13+/-20 1982 Sr-90 12+/-1 17+/-2 16+/-2 Oct 83535 Milk Sr-89 <5 0 3+/-3 1982 Sr-90 17+/-1 19+/-2 17+/-3 Nov 84177 Food Sr-89 16+/-2 0 7+/-13 1982 Sr-90 22+/-17 28+/-2 26+/-7 Nov 91763 APT Sr-90 16+/-1 16+/-2 16+/-2 1982 (1) Results reported in pCi/l for water and milk, pCi/filter for air particulates, and pCi/kg for food. (a) A new strontium procedure was introduced in March 1982. These intercomparison sam-ples were analyzed in the testing stage and showed the need for retraining in sepa-ration technique. 140
APPENDIX F SYNOPSIS OF DAIRY &VEGETABLE GARDEN SURVEY 141
APPENDIX F SYNOPSIS OF DAIRY &VEGETABLE GARDEN SURVEY A door-to-door survey of dairy farms within 5 miles of SNGS was performed in April and July. The results of the April survey were as follows: One dairy farm, situated 4.4 miles from SNGS in the NNE sector was located. One dairy farm, situated 4.9 miles from SNGS in the west sector was located. The results of the July survey were as follows: No change fr.om April survey. Since dairy farms were located within 5 miles of the site, the vegetable garden survey was ~erformed to a distance of one mile. No vegetable gardens were found in this ar.ea. 143}}