Text

Artificial Island Radiological Environ Monitoring Program, Annual Radiological Rept for 1982
	ML20024A006
Person / Time
Site:	Salem
Issue date:	04/20/1983
From:	Liden E; Public Service Enterprise Group
To:	;
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ML18089A183	List: ML18089A182; ML20024A006;
References
	RMC-TR-83-03, RMC-TR-83-3, NUDOCS 8306150270
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{{#Wiki_filter:._ I I 4 i-RMC-TR-83-03 l L L ' ARTIFICIAL-ISLAND RADIOLOGICAL-ENVIRONMENTAL MONITORING PROGRAM l 1982 RADIOLOGICAL REPORT JANUARY 1 TO DECEMBER 31,1982 - I Prepared For -PUBLIC SERVICE ELECTRIC AND GAS COMPANY By RADIATION MANAGEMENT CORPORATION APRIL 1983 8306150270 830602 DR ACOCK 05000

a RMC-TR-83-03 1982 RADIOLOGICAL REPORT ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM January 1 to December 31, 1982 Prepared For Public Service Electric and Gas Compary by Radiation Management Corporation April 1983 1

TABLE OF CONTENTS F PAGE SLNMARY - 1 INTRODUCTION 2 THE PROGRAM 3 Objectives 3 Sample Collecticn 3 Data Interpretation 5 Ouality Assurance Program (RMC) 6 Program Changes 6 RESULTS AND DISCUSSION 7 Airborne 7 Direct 9 Water 12 Aquatic 16 Ingestion 17 CONCLUSIONS 21 REFEREN'CES 22 APPENDIX A - PROGRAM

SUMMARY

25 APPENDIX B - SAMPLE DESIGNATION & LOCATIONS 33 APPENDIX C - 1982 DATA TABLES 41 APPENDIX D SYN 0PSIS OF ANALYTICAL PROCEDURES (RMC) 97 APPENDIX D-2,- SYN 0PSIS OF ANALYTICAL PROCEDURES (PSE&G) 115 ' APPENDIX E - SUPNARY OF INTERLABORATORY COMPARIS0NS 133 APPENDIX F - SYt0PSIS OF DAIRY AND VEGETABLE GARDEN SURVEY 141 i

( --- LIST OF FIGURES NUMBER PAGE 1. Comparison of Average Concentrations of Beta Emitters in Precipitation and in Air Particulates,1973 through 1982........ 8 1 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 i i w ii 4

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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, will 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 favo'rably 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. t i 1

r 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 Decenber 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.- Artificial Island is actually a man-made peninsula in the Delaware River, created by the deposition of dredging spoils. It is located in Lower Alloways Township, Salem County, New Jersey. The environment around Artificial Island is 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). i l 2 I

m THE PROGRAM In the' operational phase of the REMP, the program was conducted in accordance with i Section 3.2 of the SNGS Environmental Technical Specifications (14). Radioanalytical data were collected and compared with results from the preoperational phase. 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 obligations of the Radiological Surveillance-Environmental sections of the Environmental Technical Specifications for SNGS. 2. To determine whether any significant increase occurs in the concentration of radionuclides in critical pathways. 3. To determine if SNGS has caused an increase in the radioactive inventory of long lived radionuclides. 4. To detect any change in ambient pamma 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 Environmental Technical Specifi-cations (ETS), summarizes the findings of the 1982 REMP. Results of the four year preoperational program have been summarized for purposes of comparison with subsequent operational reports (4). Sample Collection In order to meet the stated objectives, an appropriate operational REliP was developed by RMC in cooperation with Public Service Electric and Gas Company. Samples of various media were selected to obtain data for the evaluation of the radiation dose to man and other organisms. The selection of sample types was based on: (1) established critical pathways for the transfer of radionuclides through the environment to man, and (2) experience gained during the preoperational phase. Sampling locations were determined from site meteorology, Delaware 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; con-trol samples are collected at locations which are believed to be unaffected by station operations. Fluctuations in the levels of radionuclides and direct radiation at indi-cator stations are evaluated with respect to analogous fluctuations at control stations, which are 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 additional samples and analyses not specifically required by the Salem ETS. The summary tables in this report include these additional samples and analyses. 3

F 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 was 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 CaSO4 (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. 3 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 prior 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 Salem ETS, the entire operational program as perfomed 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 infomation on indivi-dual sampling locations, while naps B-1 and B-2 show the sampling locations. j i 4

Data Interpmtation Radiation fianagement 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 quality control, inter-laboratory cross-check analyses, and compre-hensive data review. The analytical methods utilized in this program are sunrnarized in Appendix D-1. The nethods utilized by the PSEaG 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 " Quale ity Control Data 1982 - Annual Report" (15). Several factors am important in the interpretation of the data. These factors are discussed here to avoid repetition in sections that follow. I Grab sampling is a useful and acceptable procedum 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 mpre-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 gra'o samles 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 mpresent 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 msults were calculated when applicable. The calculated standard deviations of grouped data found in Appendix C represent sanple 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 msult occurring at or below the lower limit of detection is considered to be at that limit. As a msult, averages obtained using this method are biased high. i 5

f~. 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-3G1 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 SWA-12C1 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 composite Sr-89 and -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 res~ults 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. / I l

a 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 proaram. It does not include the data from the quality assurance prog,am discussed previously. Airborne 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 pross alpha activity at two stations and for gross beta activity at eight stations. Guarterly 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 cgncentrations. The rance o gross' alpha acti-vity was from 0.0007 to 0.0048 pCi/m and averaged 0.0016 pCi/m 3 Weekly gross. beta analyses showed concentrations ranging from 0.00g to 0.060 pCi/m Fiaure 1 shows with the average for the eight sampling stations beina 0.027 pCi/m. the relation between gross beta activity in air and precipitation for the preopera-tional and the operational periods, showing the weapons-testina fluctuations. The Sr-89 analyses performed on the 32 quarterly composites jndicated no detectable in4ofthe32samplesrangedbetweeng.0003and0.0010pCi/m$.Sr-90 c activity. The MDLs ranged between <0.0003 and <0.0013 pCi/m 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 fa} lout 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 cartridaes was "TEDA" impregnated cha oal. 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/1. The LLDs ranged from <120 to <140 pCi/1. 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/1. The LLDs ranged from <0.6 to <1.1 pCi/1. Gross beta emitter concentrations were detected in nine samples and ranged from 2.4 to 16 pCi/1 with an average of 6.3 pCi/1. Quarterly composites of precipitation were analyzed for radiostrontium and ganma emi tters. The Sr-89 levels were below the MDL which ranged from <0.2 to <2.7 pCi/1. All results for Sr-90 were also below the MDL which ranged between <0.2 and <1.1 pCi/1. Results of gamma spectrometry showed two samples with detectable levels of K-40 (14 and 26 pCi/1.) Direct (Tables C-9, C-10, C-11) Direct radiation measurements were made at forty-one different locations, using CaS0 (Tm) thermoluminescent dosimeters. During 1982, 288 monthly,113 quarterly 3 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. When 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, 10S1 and 11S1, 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 (6.01 mrads/std. month). 9 l l

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r q l In order to better evaluate the variation between TLD results, a statistical model s, which is capable of separating a contribution by SNGS from the background component ' < has been developed. The statistical metbod-utilized is a linear rearession analysis which involves determining the functions which best describe the backaround component. by the least squares method. Six models were originally tested and arCdescribed in ' a separate publication (16). The equation 'which describes the model selected is: F (Y (CON jmi 3 im / COT ) (C0Tj / COT )) Y = j p where: f denotes a function of = Y,4 predicted value for station j, month m, and. year i = 3 preoperational mean for station j Y = j average of the control stations for month m and year i CON = im average of the control station for year i (a "p" in place COT = j of "i" represents the preoperational period) A computer program was developed for multiple repression analysis. The leasti squares fit (LSF) line based on all 1982 data was detennined 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 m 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 10S1 and twelve outliers at station 11S1 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 ir the river and the other is .in the Chesapeake and Delaware Canal. The station (12C1) 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. s 12 .s.

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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/1. 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/1. Four of the sixty samoles analyzed showed detectable gross alpha activity ranging from 0.3 to 0.8 pCi/1. 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/1. 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/1. K-40 is a naturally occurring radio-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/1) in all twenty quarterly composite samples. A detectable concentration of Sr-90 was found in one sample with a result of 0.5 pCi/1. The MDL values for the remaining samples ranged from <0.4 to <0.9 pCi/1. 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) Mcrthly well water samples were taken from two indicator wells and one control well. Ait well water samples were analyzed for tritium, gross alpha and gross beta acti-vity, and K-40 (by atomic absorption). 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/1. Gross alpha concentrations were generally below LLD which ranged from <0.8 to <3.6 pCi/1. Four of the samples analyzed showed detectable gross alpha activity ranging between 1.3 and 1.7 pCi/1. The concentrations of gross beta emitters averaged 12 pCi/l and ranged from 6.2 to 16 pCi/1. The potassium-40 activity as determined by atomic ab-sorption averaged 10 pCi/l and ranged between 7.1 and 14 pCi/1. This indicates that the gross beta activity observed in these samples is primarily the result of naturally occurring K-40, a beta emitter. 15

F . 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/1. All results for Sr-89 were below the MDL with a range of <0.5 to <0.8 pCi/1, All results for Sr-90 were also below the MDL with a range of <0.3 to <0.7 pCi/1. Potable Water (Tables C-21, C-22, C-23, C-24) Both raw and treated water samoles 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/1, 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/1. Gross beta and K-40 concentrations were lower than in the saline surface water, as exoected for fresh water. The average gross beta 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 emitters. Of the eight samples analyzed for Sr-89, three showed detectable concentrations ranging from 1.1 to 1.2 pCi/1. The MDL range for Sr-89 was <0.5 to <1.3 pCi/1. Sr-90 was observed in two of the eight samples with each having a concentration of 0.6 oCi/1. The MDL range for Sr-90 was <0.4 to <0.9 pCf /1. No nuclides were detected by ganma 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 inconsistencies 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 is within the MDL range (<0.02 to <12 pCi/g-l dry) of the other analyses. The MDL for radiostrontium as required by the Environ-1 1 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. l Sediment (Table C-26) Sediment was collected semiannually at four locations and analyzed for Sr-90 and gamma emitters. i Levels of Sr-90 were below MDL (<0.02 to <0.05 pCi/g-dry) in all eight samples analyzed. l 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; gansna 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 of 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/l for K-40 and 1.8 pCi/l 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/1. 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. Ganina spectrometry of these samples showed K-40 in all six sangles 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/1. 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 analyzed for the or-ganic fraction of tritium showed detectable activity ranging between 134 and 1800 pCi/1. One sample from the control station (12C1) and one sample from the indicator } station (7E1) showed results of 1740 and 1800 pCi/1, mspectively. 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 cit.sest indicator station (11A1) had no unusual levels.of tritium in the organic fraction. 17

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I 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 <0.1 pCi/g-dry. Three of four flesh sanples 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 comoarable 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 ganina 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 MCts 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) Two 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 sanples 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 fams and analyzed for gama emit-ters.. Gamma spectrometry of these -samples showed K-40, a naturally occurring nuclide, in all samples ranging between 2.7 and 18 pCi/g-dry. The average for these samples was 5.9 pCi/g-dry, i ( 20

l l 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-vi ronment. 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. " 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 - Preoperational 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. l (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) Public Service Electric and Gat Company. " Environmental Report, Operating License Stage - Salem Nuclear Generating Station Units 1 and 2". 1971. (12) United States Atomic Energy Commission. " 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. " Final Safety Analysis Report - Salem Nuclear Generating Station, Units 1 and 2". 1972. (14) Public Service Electric and Gas Company. " Environmental Technical Specifications - Salem Nuclear Generating Station Units 1 and 2". 1976. 22

REFERENCES (cont.) (15) Radiation Management Corporation. " Quality Control Data 1982 - Annual Report", 1983. (16) Radiation Management Corporation. " Artificial Island Radiological Environmental Monitoring Program - Statistical Interpretation of Results of the Thermoluminescent Dosimetry Program" RMC-TR-78-11, 1978. ) 23

APPENDIX A PROGRAM

SUMMARY

25

AR11FICIAL ISLAND RADIOLOGICAL EfNIP0t#1 ENTAL P10NITORING PROGRN1 Sutt1ARY SALD1 NUCLEAR GENERATING STATION DOCKET NO. 50-272 SALR1 COUNTY. NEW JERSEY JAffJARY 1,1982 TO DECD1BER 31,1982 i ANALYSIS AND LOWER MJMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST HEAN CONTR0l LOCATION NONRGJTINE SAMPLED OF ANALYSES DETECTION t1EAN** NNIE 11EAN ifEAN REPORTED (UNIT OF MEASUREMENT) PERF0FCiED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASURENENTS Air Particulates Alphs 104 0.6 1.7 (45/52) 16El 4.1 mi HNW 1.7 (45/52) 1.5(51/52) 0 3 (0.7-4.8) (0.7-4.8) (0.7-3.9) (10-3 pCi/m ) Beta 416 27(364/364) 252 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) O Sr-90 32 0.2 0.3f3/28) 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) 252 0.4 mi NNE 55(4/4) 49 (4/4) 0 ro (29-67) (44-67) (40-60) N 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 (1.4-2.2) (1.8-2.2 (1.5) Alr Iodine I-131 364 6.4 -(0/312) None Detected - (0/52) 0 (10~3 oCi/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 0.6 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 70(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 Gamma 4 K-40 7.8 20 (2/4) 2F2 8.7 mi NNE 20 (2/4) No Control 0 j (14-26) (14-26) Location

3 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROG 9AM SIMtARY SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 i~ SALEM COUNTY, NEW JERSEY JANUARY 1,1982 TO DECEMBER 31, 1982 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NtNBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN ' CONTROL-LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION. MEAN** NAME . MEAN MEAN REPORTED (UNITOFMEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE)- MEASUREMENTS l Gamma 288 5.70(240/240) 1151 0.09 mi SW 8.48(12/12) 6.01 (48/48) 0 Direct Radiation (mrad /std. month) Dose (monthly) (3.65-19.63 (5.41-19.63) (4.05-7.51) l Gama 113 5.11(94/94 1'151 0.09 mi SW 7.49(4/4) 5.30(19/19) 0 O-Dose (quarterly) (3.51-11.60 (5.72-11.60) (4.66-5.88) Gama - 34 4.83 (28/28) 16G1 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) t Surface Water H-3 60 120 208 (27/48) 11A1 0.2 mi SW 291 (7/12) 178(5/12) 0 (pC1/1) (120-470) (190-470) (160-200) Alpha 60 0.2 0.5 (3/48) 7El 4.5 mi SE 0.8(1/12) 0.4(1/12) 'O -(0.3-0.8) (0.8) (0.4) ,5(12/12) 36 (12/12) 0 Beta 60 3.4 45 (47/48) 7El 4.5 mi SE 6 (2.6-117) (18-117) (5.1-87) i N (D ^ Gama 60 K-40 7.8 58(35/48) 7El 4.5 mi SE 73(11/12) 48(10/12) 0 (12-150) (29-150) (9.7-83) t -(0/4) 0 l Sr-89 20 0.5 -(0/16) None Detected - 0.5 (1/16) IF2 7.1 mi N 0.5 (1/4) - (0/4) 0 Sr-90 20 0.4 (0.5) (0.5) Well Water H-3 36 120 - (0/24) .None Detected - (0/12) 0 (pti/1) Alpha 36 0.8 1.5(4/24) 451 Site Well #5 ENE 1.6(2/12) -(0/12) 0 (1.3-1.7) (1.4-1.7) 8 eta 36 13(24/24) SDI 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) 5D1 3.5 'mi E 11(12/12) 8.4 (12/12) 0 (9.2-14) (9.7-14) (7.1-9.3) ? Gamma 12 K-40 7.0 14 (2/8) FD1 3.5 mi E 17(1/4) - (0/4) 0 (11-17) (17) 1 .(0/4) O Sr-89 12 0.5 - (0/8) None Detected Sr-90 12 0.3 - (0 8) None Detected - (0/4) 0

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SUtttARY SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 SALEM COUNTY, NEW JERSEY JANUARY 1,1982 TO DECEMBER 31, 1982 N'JMBER OF ANALYSIS AND LOWER 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 (6 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 Controi 0 Raw-Treated (130-170) (130-170) Location Alpha 24 0.5 1.2 (13/24) 2F3 8.0 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 24 2 2 (24/24) 2F3 8.0 mi NNE 2.2 (24/24) No Control 0 0.1-3.2) (1.1-3.2) Location S r-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 l 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) 7El 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) Gama 8 K-40 12(6/6) 12C1 2.5 mi WSW 13 (2/2) 13(2/2) 0 1 I (9.1-14) (12-14) (12-14) 16F1 6.9 mi NNW 13 (2/2) (12-14) Co-60 0.03 0.07 (1/6) 11A1 0.2 mi SW 0.07(1/2) - (0/2) 0 (0.07) (0.07) Cs-137 0.03 0.11 (5/6) 11A1 0.2 mi SW 0.14 (2/2) - (0/2) 0 (0.05-0.17) (0.11-0.17) 16F1 6.9 mi NNW 0.14(1/2) (0.14) Ra-226 0.53(6/6) 12C1 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) 16F1 6.9 mi NNW 0.98 (2/2) 0.87 (2/2) 0 (0.54-1.3) (0.65-1.3) (0.80-0.94) J t _ _ _

~ - _ _. ' ARTIFICIAL ISLAND nAD!0 LOGICAL ENVIRONMENTAL MONITORING PROGRAM SUPNARf 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 - 0F ANALYSES 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/1) 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) 572 7.0 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 r.i NNE 3.4 (4/12) 1.6 (4/12) 0 (1.4-8.7) (1.5-8.7) (1.4-1.9) f o Edible Fish H-3 6 112 81(1/4) 11A1 0.2 mi SW 81 (1/2) -(0/2) 0 (pC1/1) (aqueous) (81) (81) H-3 6 214 701(3/4) 12C1 2.5 mi WSW 1740(1/2) 1740(1/2) 0 (organic) (134-1800) (1740) (1740) i (pC1/g-dry) Sr-89 6 0.02 - (0/4) None Detected - (0/2) 0 (bones) Sr-90 6 0.03 -0.09 (2/4) 12C1 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) Gansna 6 K-40 3.0 (4/4) 12C1 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) 12C1 2.5 mi WSW 0.2 (1/2) 0.2 (1/2) 0 (0.2) -(0.2) (pCi/g-dry) (shells) - Sr-90 5 0.25 (3/3) 11A1 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) 1 (pC1/1) H-3 . 4 112 230 (1/2) 11A1 0.2 mi SW 230 (1/2) 157(12) 0 (flesh) (230 ) ~ .(230) (157 (pCi/g-wet) Sr-89 4 0.006 - (0/2) None Detected - (0/2 0 4 (flesh) Sr-90 4 0.006 0.006 (1/2) 11A1 0.2 mi SW 0.01(2/2) 0.01 (2/2) 0 (flesh) (0.006) (0.005-0.014) (0.005-0.014) Gansna 4 K a0 2.05 (2/2) 11A1 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) 12C1 2.5 mi WSW 2.05 (2/2) (2.0-2.1) f a ,m

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM StNMARY SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 SALEM COUNTY NEW JERSEY JANUARY 1,1982 TO DECEMBER 31, 1982 NUMBER OF ANALYSIS AND LOWER MEDIUM OR PATHWAY TOTAL NLFiBER LIMIT OF ALL INDICATOP 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 (pCf/g-wet) 0.03 (3/4) 0.01(7/9) 0 S r-90 23 0.002 0.02(9/14) SDI 3.5 mi E l (0.002-0.08) (0.006-0.08) (0.003-0.02) 1 i Gama 23 l K-40 2.8 (14/14) SD1 3.5 mi E 4.5 (4/4) 2.1 (9/9) 0 (1.2-12) (1.8-12) (0.94-3.4) l l Game S r-89 2 0.03 0.07 (1/1) 3E1 4.1 mi NE 0.07(1/1) - (0/1) 0 (pci/g-dry) (bones) (0.07) (0.07) l w Sr-90 2 0.09 (1/1) 3E1 4.1 mi NC 0.09 (1/1) 0.08 (1/1) 0 l (bones) (0.09) (0.09) (0.08) +-= l (pC1/g-wet) Gamma 2 i (flesh) l K-40 2.3(1/1) 3E1 4.1 mi NE 2.3(1/1) 2.0 (1/1) 0 1 (2.3) (2.3) (2.0) Beef Gamma 2 (pCi/g-wet) K-40 1.1 (1/1) 14F1 5.5 mi WNW 2.2 (1/1) 2.2 (1/1) 0 (1.1) (2.2) (2.2) Bovine Thyroid Gama 2 (pCi/g-wet) K-40 0.6 - (0/1) 14F1 5.5 mi WNW 2.3(1/1) 2.3(I/1) 0 (2.3) (2.3) Fodder Crops Gama 10 (pCi/g wet) K-40 5.0 (7/7) 3G1 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 t.LD or MDL only. Fraction of measurements above LLD or MDL are in parentheses.

l APPEliDIX B SN1PLE DESIGilATI0ll MID LOCATI0flS 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 "SA". The next three letters are for the media sampled. Air Iodine GAM Game AIO = = Immersion Dose (TLD) Air Particulates IDM APT = = Milk Hard Shell Blue Crab MLK ECH = = Potable Water (Raw) Benthos PWR ESB = = Potable Water (Treated) Edible Fish PUT ESF = = Sedinent RWA Rain Water ESS = = Beef SWA Surface Water FPB = = Bovine Thyroid Food Products, Various THB FPV = = Fodder Crops; Vegetation Grains VGT FPG = = Green Leafy Vegetables WWA Well Water FPL = = 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: 4-5 miles off-site On-site location E S = = 5-10 miles off-site 0-1 miles off-site F A = = 10-20 miles off-site 1-2 miles off-site G B = = >20 miles off-site 2-3 miles off-site H C = = 3-4 miles off-site D = The last number is the station numerical designation within each sector and zone; e.g.,1,2,3,... For example, the designation SA-WWA-5D1 would indicate a sample in the 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 1F1 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 1G1 13 mi. N of vent; local farm FPB,FPV 1G3 19 mi. N of vent; Wilmington, Delaware IDM 2S2 0.4 mi. NNE of vent APT,AIO,IDM 2E1 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 Comoany 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 2H1 34 mi. NNE of vent; RMC, Phila. IDM 3E1 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 IOM 3G1 17 mi. NE of vent; local farm IDM,MLK,FPG,VGT 3H1 32 mi. NE of vent; National Park, N.J. IDM c 3H3 110 mi. NE of vent; Maplewood Laboratories APT,AIO,IDM 3H4 88 mi. NE of vent; local farm FPV,FPG,FPL f 4S1 1400 ft. ENE of vent; site well #5 WWA 4D2 3.7 mi. ENE of vent; Alloway Creek Neck Road IDM 4 36

TABLE B-1 (CONT.) STATION STATION SAMPLE CODE LOCATION TYPES 551 1.0 mi. E of vent; site access road APT,AIO,IDM SD1 3.5 mi. E of vent; local farm APT,AIO,IDM,WWA, FPV,FPG,VGT 5F1 8.0 mi. E of vent IDM,FPV SF2 7.0 mi. E of vent; local farm MLK,VGT 6S2 0.2 mi. ESE of vent; observation bldg. IDM 6F1 6.4 mi. ESE of vent; Stow 'i;.ck Road IDM 751 0.12 mi. SE of vent; station personnel gate IDM 7El 4.5 mi. SE of vent; I mi. W of 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 10S1 0.14 mi. SSW of vent; site shoreline IDM 10Di 3.9 mi. SSW of vent; Taylor's Bridge Spur APT,AIO,IDM 10F2 5.8 mi. SSW of vent IDM 10G1 12 mi. SSW of vent; Smyrna, Delaware IDM 11S1 0.09 mi. SW of vent; site shoreline IDM 11A1 0.2 mi. SW of vent; outfall area SWA,ESB,ESS,ESF, ECH 11D1 3.5 mi SW of vent GAM 11E2 5.0 mi. SW of vent IDM 11F1 5.2 mi. SW of vent; Taylor's Bridge, Delaware IDM 12C1 2.5 mi. WSW of vent; west bank of Delaware River SWA,ESF,ECH,ESB, ESS 12E1 4.4 mi. WSW of vent; Thomas Landing IDM 12F1 9.4 mi. WSW of vent; Tcwnsend Elementary School IDM 13E1 4.2 mi. W of vent; Diehl House Lab IDM 37

TABLE B-1 (CONT.) STATION STATION SAMPLE CODE LOCATION TYPES 13E3 4.9 mi. W of vent; local farm MLK 13F1 9.8 mi. W of vent; Middletown, Delaware IDM i 13F2 6.5 mi. W of vent; Odessa, Delaware IDM 13F3 9.3 mi.-W of vent; Redding Middle School, Middletown, DE IDM 14D1 3.4 mi. WNW of vent; Bay View, Dalaware IDM 14F1 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 15F1 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 16F1-6.9 mi. NNW of vent; C & D Canal SWA,ESB,ESS 16F2 8.1 mi. NNW of vent; Delaware City Public School IDM 16G1-15 mi. NNW of vent; Greater Wilmington' Airport IDM ( 38

~ ~ ' ~ ~ _ - - _ _ _ _ _ _ ? I MAP 3 3 G LOC ATIONS AR FIClA Y %5 t V '/ i d~ i ,A -, j / ) LO. ER 2 \\ /_, ,3., .I. 2S2 Gil I u g I4 F" ( m,, 41 4Si es 7 i t 3 k ~ 13 1 7 SSI L s 1 I 6s2 S1 12 6 \\ 11 7 N IO 8 9 N \\N s f u O i SC Lt og _4, g g g 39

MAP B-2 0FF SITE SAMPLING LOCATIONS ARTIFICIAL ISLAND +K_ ' sci PEN LE .- x~ / act

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~ ? 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 Composi tes of Ai r Parti cul ates......................... 48 C-4 Concentrations of Iodine-131 in Fil tered Ai r..................... 52 C-5 Sampl i ng Dates for Ai r S ampl es................................... 54 C-6 Concentrations of Tri ti um i n Precipitation....................... 59 C-7 Concentrations of Gross Alpha and Gross Beta Emitters in P rec i p i ta ti o n.................................................... 60 C-8 Concentrations of Strontium-89 and -90 and Gamma Emitters in Quarterly Composites of Precipitation............................ 61 C-9 Di rect Radiation Measurements - Monthly TLD Results.............. 62 C-10 Direct Radiation Measurements - Quarterly TLD Results............ 63 C-11 Direct Radiation Measurements - Semi-Annual TLD Resul ts.......... 64 C-12 Concentrations of Tri ti um 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 -90 in Surface Water.......... 70 C-17 Concentrations of Triti um i n Well Water.......................... 72 C-18 Concentrations of Gross Alpha and Gross Beta Bnitters, and Potas s i um-40 i n Wel l Wa ter....................................... 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 Potable Water.................................................. 78 C-24 Concentrations of Strontium-89 and -90, and Gamma Emitters in Quarterly Composites of Potable Water............................. 79 C-25 Concentrati ons of Stronti um-89 and -90 in Benthos................. 80 C-26 Concentrations of Strontium-90 and Gamma Emitters in Sediment..... 81 C-27 Concentrations of Iodi ne-131 i n Mil k.............................. 82 C-28 Concentrations of Gamma Dnitters and Strontium-89 and -90 in Milk.. 83 C-29 Concentrations of Strontium-89 and -90 in Mil k.................... 85 C-30 Sampl i ng Da tes for Mil k Sampl es................................... 86 C-31 Concentrati ons 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 e vi -90 and Gamma Emitters in Food P ro d u c t s......................................................... 92 C-36 Concentrations of Strontium-89 and -90 and Gamma Emitters :in 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 E11TTERS Ill AIR PARTICULATES Results in Units of 10'3 pCi/m 2 2 signa 3

(All Results by PSEr.G Research Corporation) / 1 STATION NO. J #tuARY* FEBf0ARY FIARCH APRIL ttAY JUNE S A-APT-16El 0.ste.3 1.5 0.7 1.0 0.6 0.910.5 <0.8 1.4t0.7 1.4 0.6 1.710.6 1.410.7 2.0t0.7 <0.9 1.710.7

2. 0t0. 8

<1.1 0.710.4 4.411.1 (0.9 1.921.0 1.6tG.7 2.110.7 2.3t0.7 2.110.7 0.'? 0.5 2.0t0.7 1.210.6 1.4 0.7 SA-AFT-3H3 1.623.6 1.3 0.6 1.120.6 2.010.7 0.910.6 1.110.6 l (Control) 'i.220.( 2.2 0.7 1.5t0.7 2.410.7 <0.9 0.9t0.6 l 2.221.0 0.710.4 3.710.9 1.2 0.6 1.210.7. 1.710.6. ! _ t.7e;3 1.9r0.7 1.9 0.7 1.4 0.6 0.9io.5

2. 810.9 M

lu.720.4 2.0t0.8 e [ STATION NO. JULY AUGUST SEPTDtBER OCTOBER NOVEMSER DECDiBER AVERAGE SA-APT-16El 2.010.7 1.310. 8 4.811.1 1.0 0.6 1.2 0.6 1.210.7 4.511.1 1.010.7 <2.3 2.5 0.8 2.It0.7 1.310.5 2.911.0 2.5 0.8 2.0 0.7 1.010.6 1.410.7 <1.1 1.6!0.7 1.at0.7 1.410.6 <0.6 0.710.4 0.920.5 2 310.8 1.6t0.8 1.721.8 SA-APT-3H3 1.510.6 1.110.8 1.410.6 0.810.5 1.110.6 1.310.6 (Control) 2.5t LO 1.3+0.8 1.110.8 2.410.7 0.8 0.6 0.710.5 3.9tl.C 1.320.6 2.410.7 1.310.7 1.113.6 1.310.8 1.3tu.7 1.4 0.6 1.010.6 1.5t0.7 1.2 0.5 1.010.6 1.9 0.7 1.710.8 1.521.4 Samling dates can be foInd on Table C-5. ~ / i s ~ ,s l , 4 / f / "/ /, s /

FZ- 's ,i O ' ^ s' c ./ c-3 >( /, 3; e, 4..- p ,hs sh' l,,

~

z o 7%* 1 J t i..

6/3 rec. 2/11/83 I

6 TABLE C-2. e CONCENTRAT10nS'0F' GROSS BETA EMITTET.S 'IN dIR PARTICULATES p' )- 1 .e ~ ke /' e '/ Rasults in 0 nits of 10-3 pC1/m3 1 2 stoma /- / ,j# j; , (M1 bults by PSE&G R dbrpforporadion) ~ f ; y \\ e s ,g MONTH, 'SA W T-254 ' - i STATIfM NO. i g

.'l

/ e f, t, f ~SA-APT-SSI SA-APT-5D1 SA4PT-1001' SA-APT-leEl SA-APT-1F1 SA-APT-2F2 SAlAPT-3H3 AVERAGE i '. Gontrol) j -l JANUARY

20'S 2717 2717 2016 2016 25t6 2316 2316 e

2326 j' l f. I< r 3526 3617 4217 3816 43t7 38t7 3516 3717 M16 3 ,38t6 3817 4417 4017 48 8 41t7 4717 3816 4218 l ~47t6 51 8 40 7 3716 4317 4517 3316 3016 40113 2915 3016 3316 3116 31t7 3026 3226 35 6 3124 ) 4 FEBRUARY 2415 27 6 3016 2616 3016 3016 2716 28t6 2814 A' 3015 3816 40!6 3716 3516 37 6 3115 4316 36t9 20t6 2617 1916 20 6 2016 17t6 1215 6019 24130 33t7 2916 26 6 2515 26t6 3126 2916 3116 2916 MARCH 2526 2626 2816 29i6 2016 2616 2716 2716 2615 3217 3426 3317 1716 35t7 35t7 33 6 3317 34t3 13t6 1416 1716 14 6 14 6 1215 1315 1615 14t3 3016 26 6 31i6 3115 3416 2616 2725 2525 29t6 APRIL 33t6 3016 3116 29 6 3127 2816 3016 3016 3023 4517 35t6 4617 3325 3316 3816 3616 45 7 39111 3917 3326 34t6 3426 33 6 33 6 3416 3816 3515 3216 31 6 38t7 2925 32i6 3216 32 6 3416 3315 31i6 27 6 3216 3517 3217 2916 2916 3117 31t5 MAY 30t7 2517 2716 26 6 2716 2916 2616 3016 2814 23t6 25t6 1715 1615 2116 2115 1915 1716 2016 2016 1415 1415 1415 1515 1615 1815 2615 1718 16t5 1415 14t4 9.214.1 13 5 8.514.3 1515 1124 1315 JUNE 20t7 10 5 1115 8.4i5.1 8.715.5 9.715.0 1115 1215 1117 2517 1916 1515 2115 1915 1515 1815 1815 1916 1 2416 2816 20t6 18!6 2316 2115 2015 20t5 2216 3217 2717 2316 2115 2216 1615 1915 2516 23110 a

I N TABLE C-2 (cont.) CONCENTRATIONS OF GROSS BETA EMITTERS IN AIR PARTICULATES Results in Units of 10-3 pCi/n3 2 2 sigma (All Results by PSE?.G Research Corporation) STATION 140. MONTH S A-MT-252 S A-APT-551 S A-MT-531 SA MT-10D1 SleAPT-16El S A-@T-1F1 SA-APT-2F2 S A-APT-3H3 AVERAGE (Cc'f rol) t JULY 19t6 1716 26t6 2516 23 7 22 6 25t6 2226 2216 2518 16t7 17!6 26 6 34t7 2317 2217 27 8 24t12 26t7 2216 20t6 2226 25t7 23t6 2516 2617 24t4 ,J 36t7 24t7 26t8 36t7 32!7 23t6 32t7 2717 30210 35t7 33!7 28r7 29 6 31 7 34t7 2317 28t7 3126 AUGUST 3Jt7 25t7 29 6 2916 30 7 2826 ?SJo 2716 2814 22t7 2317 20 6 25t6 27 7 26 6 29t7 2117 24t6 33t7 30t7 25t6 28!6 4218 29 6 ?617 29t6 32t11 l 2723 26t3 25t3 24 3 2123 2723 24t3 2323 2514 SEPTEMBER 28t3 21 2 24t2 24i2 27 3 2713 25t3 1912 2416 fj 3518 3718 27.+7 27 7 20t12 3518 36 8 4218 32t14 33t1 36 7 36t6 31 6 4217 41+7 4017 2617 38t7 2112 2112 20 2 23 2 1912 2113 19t2 23t2 21t3 DCTOBER 21 6 21!6 1725 21!6 24t6 2126 97 6 16t5 2117 53!4 4413 4413 46 3 4313 45t3 4713 4313 4617 26t3 20t3 22 ? 21 3 2313 2113 25t3 2713 23t5 22 3 15 2 16?2 17t2 16t2 19t3 17t2 1712 1714 47t4 36t3 38 3 39t3 3923 45t3 38 3 43t3 4118 NOVEMBER 21t3 15!3 19 2 22t3 22t3 22 3 2413 23t3 2116 31t3 2923 31t3 29 3 28t3 2823 2Rt3 29t3 29t2 21!3 23t3 20 3 19t3 19t3 21t3 2223 25 3 2114 21t2 19t3 19t2 2112 18 2 1912 20t2 2213 20t3 DECEMBER lai2 14 2 1312 20t3 14 3 1412 14!3 18 3 1625 l 24t2 26t3 22t3 23t2 2412 23!2 23-3 26t3 24t3 l 24t3 22t3 20 3 "0t3 19 3 22t3 21t3 2223 2113 23 6 28t7 18!5 2315 22t5 2115 2626 2116 2327 l AVERAGE 28!16 26t17 26 13 26t16 27:18 26t18 26t16 28t19 Grand Average 27217 Sampling dates can be found on Table C-5. J

.g. ~ TABLE C-3 CONCENTRATIONS OF STRONTIl#1-89* AND -90 AND G#ttA E!11TTERS** Ill QUARTERLY C0ffPOSITES OF AIR PtRTICULATES Results in Units of 10-3 pC1/m 2 sigma 3 (All Results by PSEsG Research Corporation) STATION NUMBER AND DATE S r-89 S r-90 Bc-7 Cs-137 Ce-144 SA-APT-252 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 s 0 6-28-82 to <0.3 <0.2 5615 <0.5 <2.5 9-27-82 9-27-82 <2.3 to <0.8 <0.6 44 4 <0.4 12-27-82 SA-APT-551 12-28-81 to <0.4 <0.3 4924 <0.6 1.Sto.8 3-29-82 3-29-82 to <0.5 <0.3 55t6 <0.7 <3.5 6-28-82 6-28-82 to <0.4 <0.2 3615 <0.6 <2.4 9-27-82 9-27-82 to <0.9 <0.7 3915 <0.7 <2.4 12-27-82 a

i TABLE C-3 (cont.) CONCENTRATIONS OF STRONTIUM-89* Ato -90 MD GNitA EMITTERS ** IN QUARTERLY C0r1POSITES OF AIR PARTICULATES -3 3 Results in Units of 10 pCi/n 2 signa (All Results by PSEAr Research Corporation) STATION NUMBER AND DATE Sr-89 S r-90 B e-7 Cs-137 Ce-144 S A-APT-501 12-28-81 to <0.5 0.4t0.1 46!4 (0.6 1.420.7 3-29-8E 3-29-82 to <0.6 <0.4 49t4 <0.5 1.610.8 6-28-82 4 u3 6-28-82 to <0.3 <0.2 33t4 <0.8 <z.8 9-27-82 9-27-R? to <0.4 <0.3 33 4 <0.4 <1.6 12-27-82 SA-APT-1001 12-29-81 to <0.4 (0.3 40 5 <0.7 <3.? 3 82 3-30-82 to <0.6 <0.4 4324 (0.4 <2.' l 6-29-82 l 6-29-82 to <0.3 <0.2 29t4 <0.7 <2.2 l 9-28-82 9-28-82 to <0.8 <0.5 30t3 <0.5 <1.6 12-28-82

l i TABLE C-3 (cont.) CONCENTRATIONS OF STRONTIU!!-89* Ata -90 A.'O Gaff 1A EMITTERS ** IN QUARTERLY C01POSITES OF AIR PARTICULATES 3 Results in Units of 10-3 pC1/n 1 2 sigsta (All Results by PSE&G Research Corporation) STATION NUMBER AND DATE Sr-89 sSr-90 Be-7 Cs-137 Ce-144 SA-APT-16El 12-29-81 to <0.7 <0.4 4315 <0.7 <3.5 3-30-82 3-30-82 to <0.4 <0.3 53t5 0.7 0.3 <3.5 6-29-J2 en C' 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 3524 <0.5 <2.1 12-28-82 SA-APT-1F1 12-28-81 to <0.4 <0.3 4914 (0.4 <2.3 3-29-82 3-29-82 to <0.6 <0.4 51t4 <0.5 4.2.1 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 <G.5 32 3 <0.4 <2.2 12-27-82 ~ m

i TABLE C-3 (cont.) CONCENTRATIONS OF STRONTIUM-89* AND -90 A*O GAffiA EMITTERS ** IN QUARTERLY C0f tP0 SITES OF AIR PARTICULATES 3 Results in Units of 10-3 pCi/n 2 sigma (All Results by PSEAG 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 4424 <0.6 1.811.0 3-29-82 3-29-82 to <0.4 <0.3 64!6 0.S t0.3 2.221.1 6-28-82 6-28-82 to <0.4 <0.2 42 4 <0.4 <2.3 on 9-27-82 ra 9-27-82 to <1.3 <0.9 37 4 <0.6 <2.3 12-27-82 SA-APT-3H3 (Control) 12-28-81 to <1.1 1.0t0.3 48t4 <0.5 1.5 0.8 3-29-82 3-29-82 to <0.7 <0.5 60t6 <0.8 <3.3 6-28-82 6-28-82 to (0.3 <0.2 49t4 <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 sanple stop date. All other ganma emitters searched for were <LLD; typical LLDs are given in Table C-38. l

TABLE C-4 CONCEfiTRATIONS 0F 10 DINE-131* IN FILTERED AIR 3 Results in Units of 10-3 pC1/m STATION fl0. MONTH SA-AID-252 SA-AID-551 SA-AID-SDI SA-AIO-1001 SA-AID-16El SA-AID-2F2 SA-AIO-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 <9.3 <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 on <18 <16 <16 <15 <15 <15 <16 PO <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 <1l <9.8 <10 <9.1 <10 <10 <11 (12 (12 <11 <12 <12 <!2 <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 <!3 <14 <11 <10 <9.7 <9.4 <9.3 <10 <12 l l 1 l l \\ +

TABLE C-4 (cont.) CONCE'ITRATI0fiS OF 10 DINE-131* IN FILTERED AI't Results in Units of 10-3 pCi/n3 STATION H0. MONTH Sk AIC-252 S A-AIO-551 S A AIO-SD1 S A-A10-10D1 SA.AIO-16El S A-AIO-2F2 SA-AIO-3H3 (Control) JULY (44 (1 <32 <29 <31 ) <32 <30 (33 <60 <28 < 44 i <48 <55 <57 <60{1 < 33 g 1 < 45 <37 <46 ll <52 <42 (48 <18 <18 <21 <16 <15 <17 <23 <14 <17 <16 <16 <19 <19 <20 AUGUST <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 m SEPTEMBE R <10 <12 <13 <12 (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 <*2 <13 NOVEM*ER <9.9 <15 <9.1 <9.8 <11 <10 <11 < 7. 5 <P.8 < 8. 3 <7.1 (6.8 <8.6 <9.0 l <7.7 < 8. 0 <7.5 < 8. 6 <9.8 < 8. 3 <8.9 j < 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 sanple stop date. Actual s anpling dates can be found on Table C-5. (1) riigh LLD due to delay in counting resulting from equipment malfunction.

r TA8LE C-5 SAttPLING DATES FOR AIR SN!PLES STATION NO. MONTH 252 551 501 1001 16El IF1 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 l 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 IS 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 P-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 2-16-62 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 2-01-82 3 82 3-01-82 3-02-82 3-J2-82 3-01-82 3-01-82 J-01-82 I 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 3-03-82 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

TA8LE C-5 (cont.) SAMPLING DATES FOR AIR SAMPLES STATION NO. MONTH 2S2 551 5D1 1001 16El IF1 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 3-22-32 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 3-29-8 2 3-29-82 3-29-82 to to to to to to to to 4-05-82 4-05-82 4-05-82 4-05-82 4-05-82 4 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 Ln 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 I 5-10-82 5-10-82 5 82 6-11-82 5-11-82 5-10-82 5-10-82 5-10-82 l l 5-10-82 6-10-82 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 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.) SN1PLIiG DATES FOR AIR SMiPLES STATION NO, MONTH 252 SS1 SDI 1001 16El .1F1 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 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 6-28-62 cn 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 Ch 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 7-19-8 2 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 7-26-32 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 0-02-82 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 B-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 B-17-82 8-16-82 8-16-82 8-16-82 m

l TA8LE C-5 (cont.) SN1PLItG DATES FOR AIR S#1PLES STATION 180. MONTH 252 551 SDI 1001 16El IF1 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 82 to to ta 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 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 B-30-82 8-30-82 SEPTEM8ER 8-30-82 8-30-82 8-30-82 8-31-82 8 -3 1-82 8-30-82 8-30-82 8-30-82 to to to to to to to to 9-07-82 9-07-82 9-07-82 9-03-82 9-0 7-82 9-07-82 9-07-82 9-07-82 9-07-82 9-07-82 9 82 9-G B-82 9-07-92 9 82 9-07-82 9-07-82 to to to to to to to to 9-13-82 9-13-82 9 82 9-14-82 9-14-82 9-13-82 9-13-82 9-13-82 kS 9-13-82 9-13-82 9 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 82 9-20-82 9-20-82 9 82 9-20-82 9-20-82 9-20-82 9 82 9-20-82 9-20-82 9 82 9 82 9 82 9-20-82 9-20-82 to to to to to to to to 9-27-82 9 82 9-27-82 9-2 8-82 9-28-82 9 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 82 to to to to to to to to 10-04-82 10-04-82 10-04-82 10-04-82 10-04-R2 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-E2 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 l 1

'l TABLE C-5 (cont.) SN1PLING DATES FOR AIR SAMPLES STATION NO. MONTH 252 551 501 1001 16El IF1 2F2 3H3 N0VDtBER 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 11-10-82 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 to to to 11-22-82 11-22-82 11-22-82 11-22-82 11-22-82 11-22-82 11-22-82 11-22-82 en 00 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 12-23-82 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 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 u ^

I TABLE C-6 CONCENTRATIONS OF TRITIUM IN PRECIPITATION STATION SA-RWA-2F2 Results in Units of pCi/1 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 03 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 E!!ITTERS IN PRECIPITATION STATION SA-RWA-2 F2 Results in Units of pCi/1 2 sigma i 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 ES 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 2.01.0 1213 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 6.318.5 Average (1) Entire sample used for strontium analyses, et,

~ ~. - l l l l l l TABLE C-8 CONCENTRATIONS OF STR0llTIU !-89* #10 -90 AfD GNElA EllITTERS*= Ill f)1ARTERLY C0llP0 SITES OF PRECIPITATIO:1 STATION: S A-m1A-2F2 Results in Units of pCi/l 2 si9ma 12-29-81 3-29-82 6 82 9-27-82 to to to to NUCLIDE 3-29-82 6 82 9-27-82 12-28-82 O 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 26t3 l Sr-39 results are corrected for decay to sa@le stop date. All other gama emitters searched for were <LLD; typical LLDs are given in Table C-38.

b TABLE C-9 DIRECT RADIATION HEASURD1DITS - HONTHLY TLD RESULTS mrad /stendard month

STATION NUMBER JANUARY FEBRJARY MARCH APRIL MAY JUNE SA-IDH-252 5.26t0.55 5.06 0.10 4.4720.55 5.12 0.65 4.88 0.28 5.46 0.40 SA-1 5 551 4.45 0.44 4.26t0.30 4.04t0.17 4.7210.27 4.53 0.31 4.6910.52 SA-IDM-652 5.3610.68 4.9120.52 4.6010.44 5.49t0.55 4.9720.18 6.5610.75 SA-IDM-751 6.68t0.72 5.89t0.44 5.55 0.46 6.1010.76 6.05t0.38 6.1810.52 SA-l % 10S1 6.2710.26 6.04 tl.08 6.06to.52 6.6510.74 6.15 0.42 6.94 0.82 SA-IDM-1151 5.4110.62 6.5020.72 6.6910.48 8.8410.51 6.2220.41 5.7410.50 SA-!DM-501 4.6320.59 5.1010.40 4.6210.11 5.0310.08 4.82 0.25 6.0010.31 SA-IDM-1001 5.03:0.57 5.47t0.21 4.85t0.43 5.72t0.73 5.4710.70 6.1010.32 SA-! % 1401 5.5810.21 5.6410.20 5.2310.20 6.1120.31 5.49t0.18 6.12 0.22 Skl % 2E1 4.7710.32 4.85t0.33 4.6710.29 5.48t0.44 5.2410.42 5.28to.17 SkIDM-3E1 4.74 0.59 4.83!0.87 4.54t0.59 5.61 0.68 5.4620.27 5.66 0.75 SA IW13E1 4.8910.25 5.04r0.93 5.56 0.73 5.49 0.25 4.87 0.74 5.71 0.50 SA-IDM-16El 5.0910.80 5.2510.52 4.6710.62 5.87 0.75 5.5810.49 5.85 0.72 S AIDM-1F1 5.33t0.97 5.26 0.28 4.42 0.75 5.9210.19 5.74 0.87 5.9710.68 S k!DM-2F2 4.5610.83 4.0120.22 3.87 0.70 4.55 0.33 4.15 0.33 5.06 0.19 SAIDM-5F1 4.8320.53 4.87t0.74 4.6910.34 5.53 0.51 5.01 0.39 5.7610.50

. Skl%6F1 4.5310.51 4.3810.49 3.6510.54 4.6310.64 4.55 0.25 5.03t0.60 S A-IDM-7F2 4.07*0.51 3.79 0.65 3.78 0.62 3.9410.68 4.15t0.06 4.6710.43 SAIDM-11F1 5.5210.46 5.87 0.23 5.3520.81 5.9410.85 5.7220.49 6.3510.29 SAIDM-13F1 4.9120.27 5.3221.20 4.6320.44 5.37r0.38 5.2910.06 6.2720.46 SA-I % 3G1 5.5710.94 5.1910.64 5.26 0.56 6.11t0.47 5.95t0.09 6.41t0.66 SA-I % 2H1 6.2310.70 4.05 0.57 4.67 0.43 5.5110.27 5.7220.58 7.5110.10 SA-I % 3H1 5.34t0.79 5.81 1.04 4.85 1.06 6.18 0.52 6.02t0.59 6.1210.85 SA-IDM-3H3 5.3710.56 5.4310.12 5.16 0.71 5.96tl.01 5.56t0.87 6.4110.58 AVERAGE 5.18t1.23 5.1221.36 4.8321.41 5.66 1.83 5.3221.21 5.91*1.34 STATION MAGER JULY AUGUST SEPTC1BER OCTOBER NOVDEER DECEMBER AVERAGE SA-I % 252 5.49t0.55 5.4920.51 4.44t0.44 5.81 0.69 5.4910.37 9.26 2.02 5.5222.50 S A IDM-551 5.13 0.77 5.28!0.24 4.3210.19 5.44 0.22 5.27 0.54 6.3810.55 4.8821.31 SA-I % 6S2 6.2910.73 5.52 0.50 5.04ia.48 6.31i0.64 6.14:0,18 7.70 1.26 5.7411.77 S AI W 751 7.09t0.49 7.0210.48 6.08 0.67 6.69tl.03 7.06 0.86 7.76 1.24 6.51 1.28 SA-IDM-10S1 6.72t0.24 8.09 0.61 8.3110.63 7.4110.73 6.86 0.62 7.7220.76 6.94t1.58 SA-IDM-11S1, 6.93 0.39 11.5020.41 19.53tl.74 8.58 0.63 6.19t0.45 9.5612.00 8.48!7.90 Sk!DM-501 5.4610.71 5.92 0.52 4.68t0.54 5.71 0.58 5.5010.52 8.32 0.92 5.4822.04 S A-IDM-10D1 6.5210.44 6.12t0.71 5.56t0.21 6.7510.30 6.8310.76 6.4410.51 5.91tl.31 $4IDM-14D1 6.75 0.41 6.8220.20 5.67 0.69 6.6310.54 6.3710.83 6.2910.65 S.06tl.06 SA-IDM-2E1 6.24+0.29 6.2110.07 5.35t1.04 6.3410.34 5.79 0.62 5.93 0.21 5.5121.18 SA-IDM-3E1 5.85 0.29 5.6C 0.45 5.3910.48 5.9310.65 6.1710.04 8.25i0.46 5.68 1.90 S klDM-13E1 5.4711.07 5.9310.49 4.9110.79 5.76 0.40 5.61 0.26 5.7310.15 5.41 0.76 SA-IDW 16El 6.4210.66 5.56!O.69 5.43 0.74 6.31t0.88 6.64t0.53 5.93t0.89 5.7221.15 SA-IDM-1F1 6.50t0.20 6.5710.62 5.4511.12 7.0210.69 6.52 0.29 5.8410.40 5.8611.40 SA-IDH-2F2 5.2120.59 4.58 0.40 4.00 0.20 5.6510.37 5.0210.07 4.47 0.37 4.59t1.10 S kIDM-5F1 6.13t0.36 5.1610.48 5.1010.73 5.84 0.98 5.80f0.55 5.52 0.26 5.35 0.94 SA-I % 6F1 5.23 0.26 4.52t0.51 3.93 0.64 4.88 0.23 5.26 0.50 4.79 0.29 4.62 0.96 SkIDM-7F2 4.0210.56 4.0210.11 3.91 0.44 4.50i0.34 4.38 0.49 4.4310.50 4.2110.69 SA-! % 11F1 6.5710.74 5.90t0.67 5.8110.85 6.82 0.73 6.4610.26 6.55to.52 6.0710.93 SA-IDH-13F1 6.1210.33 5.40 0.54 5.23t0.88 6.11 0.61 6.39 0.80 5.7220.68 5.56 1.12 SA-I W 3G1 7.1510.33 6.17tl.09 6.10 0.31 6.85 0.83 6.5210.38 6.36 0.68 6.14tl.18 SA-IDM 2H1 5.1710.33 6.20to.52 5.3310.27 7.00 0.47 5.3311.26 5.9120.40 5.7211.90 S AIDH-3H1 6.7910.21 6.9510.30 5.31!0.12 6.83t0.52 6.64to.81 6.42 0.37 6.1121.35 s) SA-IDM-3H3 6.6921.11 6.27 0.53 5.7020.31 6.6510.78 6.96 0.42 6.7220.25 6.0711.24 V AVERAGE 6.1121.40 6.12t2.89 5.81 6.14 6.33tl.70 6.0521.40 6.5812.73 5.7612.62 The standard month = 30.4 days. 62

TA8LE C-10 DIRECT RADIATION MEASUREMENTS - QUARTERLY TLD RESULTS mrad / standard nonth* JANUARY APRIL JULY OCTOBER to to to to AVERAGE STATION NUMER MARCH JUNE SEPTEfEER DECEMBER SA-IDH-252 4.23 0.19 5.33*0.30 3.98 0.57 4.48 0.56 4.5111.17 S A-I DM-SSI 3.7720.16 4.5810.31 4.32 0.44 4.85 0.29 4.38 0.92 S SIDM-652 4.6120.89 5.3220.29 4.6920.26 4.64 0.39 4.82!0.68 SA-IDM-7S1 5.73 0.34 5.79 0.23 6.08 0.61 6.26 0.78 5.97 0.50 SA-IDM 1051 5.52 0.39 6.0710.23 6.51io.12 6.45t0.62 6.1410.91 SA-IDH-1151 5.7210.63 6.1310.10 11.60 0.12 6.4910.50 7.49 5.52 SA-IDH-5DI 4.26io.44 5.13t0.24 5.87 0.09 4.66t0.90 4.98 1.58 SA-IDM-1001 5.2710.32 5.84 0.11 5.80 0.13 5.25 0.89 5.54r0.65 S A-IDM-14D1 5.11 0.24 5.42 0.30 5.80 0.18 5.45t1.11 5.4510.56 SA-IDM-2E1 4.97 0.28 5.41!O.25 5.17 0.10 5.71 0.53 5.32 0.64 S A-IDM-3E1 4.65 0.45 5.01 0.14 5.63:0.14 5.5211.11 5.20 0.91 S A-IDM 13E1

4. 60 !0. 35 5.3310.17 4.25 0.09 4.6110.66 4.70!0.91 SA-IDM-16El 4.83 0.54 5.16t0.21 5.78 0.24 5.3320.24 5.28 0.79 SA-IDM-1F1 4.9910.71 5.20 0.25 5.3210.30 4.90 0.91 5.10 0.38 S A-IDM-2F2 3.75 0.29 4.72 0.17 4.03 0.39 3.61 0.24 4.03 0.99 SA-IDSSF1 4.2810.37 5.0110.21 4.61 0.14 4.78:0.65 4.67 0.61 S A-IDH-6F1 3.75 0.39 4.55 0.27 4.43 0.21 3.69!O.19 4.1110.90 S A-IDH-7F2 3.51 0.23 3.9420.38 3.29 0.15 3.56 0.56 3.73 0.44 SA-IDM-11F1 5.30t0.37 5.82 0.21 5.8010.20 5.0310.16 5.50 0.73 S A-IDM-13F1 4.68 0.93 5.0710.36 5.33 0.25 4.70 0.75 4.95 0.63 SA-IDM-3G1 5.18i0.63 5.50!0.98 5.88 0.21 4.6610.25 5.3121.03 SA-IDM-2H1 5.1410.51 5.79 0.09 5.27 0.15 4.8120.06 5.25t0.81 SA-IDM-3H1 4.7720.36 5.5610.36 5.49 0.25 5.4110.95 5.31 0.73 S A-!DM-3H3 5.02!0.55 5.47 0.20 5.29 0.12 5.3511.06 5.28 0.38 SA-IDM-402 (1)

(1) (1) 5.33 0.88 5.33 SA-IDH-9El 5.9911.12 5.99 SA-! DM-11E2 5.8921.16 5.89 S A-IDM-12E l 5.55t0.36 5.55 SA-IDM-2F5 4.7210.13 4.72 S A-IDS 3F2 5.05 0.34 5.05 SA-IDM-3F3 4.64 0.88 4.64 SA-IDM-10F2 4.95 0.22 4.95 SA-IDS 12F1 5.48 0.25 5.48 S A-IDM-13F2 4.84 0.21 4.84 SA-IDM-13F3 5.2010.80 5.23 SA-IDM-14F2 4.97!0.76 4.97 SA-!D* 15F3 5.16 0.28 5.16 SA-IDM-16F2 5.16t0.31 5.16 SA-IDM-1G3 5.70 0.98 5.70 SA-I DM-10G1 5.07!0.22 5.07 SA-ID* 16G1 5.43 0.88 5.43 AVERAGE 4.7421.25 5.3011.02

5. 45 t 3.01 5.11 1.30 5.1411.80

.The standard month = 30.4 days. (1) Beginning in October 1982, semi-annual collections of TLDs were chan9ed to quarterly collections. 63

TABLE C-11 DIRECT RADIATI0fl11EASUREl1ENTS - SEMI-AtlNUAL TLD RESULTS mrad / standard month

SEPTEMBER APRIL STATION N0.

TO TO AVERAGE MARCH SEPTEl1BER S A-I DM-4D2 4.52 0.08 4.88i0.2 1 4.70 0.51 SA-IDH-9El 4.87 0.61 5.37 0.36 5.12 0.71 S A-IDM-11E2 .5.11 0.20 5.75 0.53 5.43 0.91 S A-IDM-12E 1 5.30 0.39 5.23 0.26 5.27 0.10 S A-IDPL2F5 4.38 0.86 4.52 0.02 4.45 0.20 22 SA-IDM-3F2 4.08 0.38 4.15 0.06 4.12 0.10 S A-IDM-3F3 4.22 0.69 4.22 0.22 4.22 SA-IDM-10F2 5.07 0.86 5.29 0.19 5.18 0.31-S A-IDM-12F1 5.10 0.75 4.77 0.19 4.94 0.47-SA-IDM-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-IDM-16F2 4.54 0.20 4.94 0.56 4.74 0.57 SA-IDH-1G3 5.46 0.40 5.31 0.17 5.39 0.21 S A-I DM-10G1 5.0410.37 5.21 0.39 5.13 0.24 SA-IDM-16G1 5.65 0.65 5.60 0.29 5.63 0.07 AVERAGE 4.88 0.85 4.97 0.92 4.93 0.83 The standard month = 30.4 days. L a.

x

TABLE C-12 CONCENTRATIONS OF TRITIU4 IN SURFACE WATER Results in Units of DC1/1 12 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-11A1 330i80 <120 <120 <120 230t80 <130 SA-SWA-12C1 <i20 <120 <120 <120 <130 <120 SA-SWA-7El <120 <130 <130 130 70 140 70 <130 SA-SWA-1F2 120170 <120 <120 <120 170 70 <130 ES SA-SWA-16F1 <130 <120 160130 160t70 <130 (120 Average 160!85 l STATION NO. 7-07-82 8-02-82 9-07-82 10-06-82 11-08-82 12-09-82 AVERAGE ShSWA-11A1 470t90 190 80 320180 280 80 <140 220t90 223t220 SA-SWA-12C1 170 80 180180 200 80 160 80 <140 180180 SA-SWA-7El 180180 210180 220 ISO 140 80 190 80 180 80 158271 SA-SWA-IF2 <120 290t80 220i80 170130 140180 (1 30 154 105 SA-SWA-16F1 < 130 190!80 230 80 150180 180t90 <130 153!67 Average 214 291 212 90 238294 180t114 158t50 168t77 167 129

TABLE C-12 (cont.) CONCENTRATIDNS OF TRITIUM IN SURFACE WATER Results in Units of pC1/12 2 sigma STATION NO.* 1-07-82 2-16-82 3-11-80 4-05-82 5-03-82 6-08-82 SA-SWA-11A1 SA-SWA-12C1 <110 <103 <106 (104 86173 <110 SA-SWA-7El <104 83 73 <110 SA-SWA-IF2 <110 <103 <106 Average 8514 cS STATION NO. 7-07-82 8-02-82 9-07-82 10-06-82 11-08-82 12-09-82 AVERAGE SA-SWA-11A1 343177 198t75 103271 101 75 115160 <110 1621192 SA-SWA-12C1 <120 124274 <115 237276 105160 <110 SA-SWA-7El SA-SWA-1F2 Average 232t315 161t105 109217 1692192 110114 For quality assurance purposes, station SWA-12C1 is to be analyzed for tritium on a monthly basis hy RMC: in addition, one station a quarter is seiected by PSE&G to receive a monthly tritium analysis. ....A

TreLE C-13 CONCENTRATIONS OF GROSS ALPHA E!!1TTERS IN SURFACE WATER Results in Units of pCi/1 2 sigma STATION NO. 1-07-82 2-16-82 3-11-82 4-05-82 5-03-82 6-08-82 j SA-SWA-11A1 <0.5 <0.3 <0.3 <0.5 <0.3 <0.2 SA-SWA-12C1 <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-IF2 <0.2 <0.3 <0.3 <0.3 <0.3 0.320.3 SA-SWA-16F1 <0.2 <0.3 <0.3 <0.4 <0.4 <0.4 C STATION NO. 7-07-82 8-02-82 9-07-82 10-06-82 11 'J8-P2 12 09-82 l S A-SWA-11 A1 <0.2 <0.4 <0.2 (0.4 <0.4 <0.3 SA-SWA-12C1 <0.2 <0.4 <0.2 <0.4 <0.5 0.4!O.2 SA-SWA-7El <0.3 <0.4 <0.2 <0.3 <0.5 <0.3 SA-SWA-IF2 <0.3 <0.3 <0.2 <0.1 <1.0 (1) <0.2 SA-SWA-16F1 <0.2 <0.3 <0.3 <0.4 0.40.4 <0.3 (1) Elevated LLD due to small sample size.

TABLE C-14 CONCENTRATIONS CF GROSS BETA EMITTERS IN SURFACE WATER Results in Units of pC1/112 sigma STATION NO. 1-07-82 2-16-82 3-11-82 4-05-82 5-03-82 6-0 8-82 SA-SWA-11A1 56t6 24t2 4525 6.122.2 1413 6727 SA-SWA-12C1 3314 1422 2924 7.612.3 5.122.5 3113 SA-SWA-7El 73t7 2613 6416 18 3 33t5 6627 SA-SW A-1F2 2524 6.911.4 14t3 5.0 t2.1 2.612.3 1913 cn SA-SWA-16F1 2614 1112 3014 4.112.0 <3.4 2423 00 Average 43142 16117 36t38 8ill 12226 41147 STATION NO. 7-07-82 8-02-82 9-07-82 10-06-82 11-08-82 12 B2 AVERAGE SA-SWA-11A1 35t5 6717 6017 106111 9019 7418 54160 SA-SWA-12Cl 21t4 4615 53 6 6527 8719 45t5 36248 SA-SWA-7El 34t5 7227 8619 117212 112111 8218 65265 SA-SWA-1F2 1123 2914 2915 4716 6727 4115 25139 SA-SWA-16F1 16t3 31t4 5016 7228 8619 4615 33252 Averaqe 23121 49240 56 41 81258 88132 58138 43160 e

l l l TABLE C-15 CONCENTRATIONS OF GM1A D1ITTERS* IN SURFACE WATER Results in Units of pCi/l 2 2 sigma STATION NO. NUCLIDE 1 82 2-16-82 3-11-82 4-05-82 5-03-82 6-08-82 SA-SWA-11A1 K-40 54t9 15t8 46t12 <7.8 <11 53t8 SA-SWA-12C1 K-40 54132 9.7 6.9 38 8 <11 <9.3 29t8 SA-SWA-7El K-40 64t15 35 8 68110 (9.3 3728 73t10 S A-SWA-IF2 K-40 1428 (9.3 12!9 < 9. 3 <7.8 <11 SA-SWA-16F1 K-40 <9.3 <9.3 2918 < 7. 8 <9.3 16 7 g Average 39 51 16 22 39141 36 52 STATION NO. NUCLIDE 7-07-82 8-02-82 9-07-82 10-06-82 11-08-82 12-09-82 Average S A-SWA-11 A1 K-40 43 10 76 8 70211 120 12 70 9 7628 53t65 S ArSWA-12C1 K-40 2218 5029 62 9 74t9 83t9 5917 42151 SA-SWA-7El K-40 29t8 80 10 65t9 120t12 150115 83 8 68t78 SA-SWA-1F2 K-40 <11 30t9 32 8 27!9 92112 58 6 26151 SA-SWA-16F1 K-40 <9.3 2a 8 55 9 73t10 8119 50t5 31153 Average 23t28 53 49 57 30 83r78 95 63 65 27 44t66 By gama spectrometry, all other gama emitters searched for were <LLD; typical LLDs are given in Table C-38.

TABLE C-16 CONCENTRA110NS OF STRONTIUM-89* ANO -90 IN SURFACE WATER Results in Units of PC1/1 1 2 sigma (All Results by PSE&G Research 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 S r-90 S r-89 S r-90 S r-89 S r-90 c$ SA-SWA-11A1 <1.1 <0.9 <0.8 <0.6 <0.9 <0.7 <0.7 <0.5 SA-SWA-12C1 <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-IF2 <1.0 <0.8 (0.6 <0.4 <0.6 0.St0.2 <0.8 <0.6 SA-SWA-16F1 <0.7 <0.6 <0.8 <0.6 <0.8 <0.6 <0.5 <0.5 Stror. tium-89 results are corrected for decay to sample stop date.

1 l l TABLEC-16(cont.) CONCENTRATIONS OF STR0'iTIUtt-89* AND -90 IN SURFACE WATEP, Results in Units of pCi/l 2 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 S r-89 Sr-90 S r-89 S r-90 S r-69 Sr-90 S r-89 Sr-90 [j SA-SWA-11A1 <1.6 <0.3 <0.4 <0.3 S ArSWA-12C1 <0.4 0.410.2 <0.3 <0.3 <1.1 <0.2 <0.4 0.310.2 l SA-SWA-7El <0.6 0.Si0.4 S A-SW A-IF2 <0.4 0.5 0.3 Sr-39 results are corrected for decay to sample stop date. For quality assurance purposes, station 12C1 is analyzed for Sr-89 and -90 on a quarterly basis by RMC; in addition, one station a quarter is selected by PSEAG to receive a quarterly compnsite Sr-89 and -90 analysis. g

T/BLE C-17 C0flCENTRATIONS OF TRITIt!!! Ill WELL UATER Results in Units of pCi/l .2 sityia ( All Results by PSEAG Research Corporation) STATION NO. RADI0 ACTIVITY 1-11-82 2-16-8?. 3 82 4-12-82 5-10-82 6-14-82 SA-WWA-451 <120 <120 <120 <120 (1) <120 <120 SA-WWA-501 <120 <120 <120 <120 <120 <120 SA-WWA-3E1 <120 <120 <120 <120 <120 <120 M STATION N0. RADI0 ACTIVITY 7-12-82 8-09-82 9-13-82 10-12-82 11-15-82 12-13-82 S A-WWA-451 <140 <120 <130(2) <130 <130 <140 S A-WWA-531 <130 <120 <120 <130 <130 <140 S A-WW A-3E1 <130 <120 <120 <130 <130 <140 l (1) Station WWA-4S1 was collected on 4-19-82. l (2) Station WWA-4S1 was collected on 9-14-82 l l I ~

l ~ g, 1 pl (^ \\N TA8LE C-la - s CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS AND POTASSIl#1-40 IN WELL WATER Results in JJnits of pC1/1 12 sigma N T STATION NO. RA010 ACTIVITY 1-11-82 ' 2-16-c? 3-15-82 4-12-82 s 5-10-E2 6-14-82 SA-WWA-451 Alpha '2.4 1.hfl.5 1.4tl.3 <0.9(1) <2.5' <3.6 Beta 1413-12t2 1312 1313 12 34 1412 - K 43 13r1 13t1 12t1 13 1 1111-1111 s SA-WWA-5D1 ,A Alphe <2.0 ' 1.St'. 2 <1.1 <2.0 <1.7 <2.7 N' Beta 13t3 1312 14 2 1513 12t3 12t2,' A-40 1221 1421 13t1 13t1 9.911.0 11!1 s SA-WWA GE1 f-?pha <2.1 <1.2 <1.2 <2.1 <1.9 <3.0 , I Beta 10t2 9.0t1.5 9.3t1.5 8.3 2.3 8.0t2.5 9.3t2.1 ~ K-40 8.5t0.9 8.5t0.9 9.320.9 7.5 0.8 8.7!0.9 9.0 0.9 ; a v ~- STATION NO. RADIOACTIVITY 7-12-82 8-09-82 9-13-82 10-12-82 11-15-82 12-13-82 SA-Wl-451 ~ Alpha <2.2 <1.4 <2.3 (2)' <2.7 <2.6 <1.1 ^ Beta 1423 9.3i3.2 1313 h 11!3 15 3 12+2 + ' s, 12ff~ v. - ^ K-40 1011 9.5t1.0 9.5t1.0 9.210.9 9.721.0 SA-WWA-501 Alpha <1.5 1.3 1.1 <1.7 i <2.2 <1.9 <0.8 , 12!3 16t3 15 3 14i3 Beta 1213 10'3 K-40 11 1 9.721.0 < 1111, 1111 10t1 12 1 SA-WWA-3E1 Alpha <1.8 <0.9 <1.8 <?.3 < 2.0 (0.9 Beta 9.512.8 6.223.0 2.613.0 8.6 2.8 1013 11t3 K-40

8. 110.8 7.8 0.8

,A.4t0.8 9.2i0.9 7. 110.7

8. 2 t0. 8 s

t ) (1) Station WWA-451 was collected on 4-19-82. (2) Station WWA-451 was collected on 9-14-82. o T s

of

+ k 73 i ,s

'y . _sr - V s(. j i

p :._,

4 3

)- J

~ f ~s .- 5 ^ ) I ';' R ?}f._ f,),n,' f, I/j(& 0'l f s e - \\

P

\\ ( y j\\')'\\,. f , h-s?'l (lf [$ l,s,y. / d 5 }w,' - TABLE

IN QUARTERLkf.JitPd, C.S. OF w}iLL'WA.TER.

!p

3. yj,

.) t;- y t.~ .J CONCEllTRATI0fd5 If f *I1A EFITTE93* g4 >.f ' f-N

'd' Results'N[ Units of pCi/Liksigna d k

^ hg/} *j. ; d' f,. f .I' g pj %f p)# d ' '.9' t. ;I 4 3 v _y g

f

[,.. ;, 8

a

/ j- - 102%d2 A.'. *. 4-12-82 j 7-12-82 10-12-82 STATION NIKiBER to n. to ~ to to 'I RN)I0 ACTIVITY 3-15-32 N 6-14-82 9-13-32 ' 12-13-32 -p ), r q.. ]$f '[ ) /f/ *[' SAbMA-451 [<9.3-(1) N,.* V7.3'(f) J- ' p,f, r - 11 3 ' K-40 <7.8 -), i t Others <LLD /,g f eLLD f., Q 3 'fiLD '<LLD ,,e f.9,5 0, ? '/,"li ] ,, 2 ) SA-WkA,501 (",q -- [) ,f *" s i I f.,c f I, /lr

l '. rf,.'.k Y

( ,1 ,e ,\\ s , / 'y,<9.3 -;./ ? -c ~ t (?!3 ' 4 ' <9M 17 4 ~ K-40 // <LLQ 'f . LLD ' <LLD Others / 7e * '/ <LLD .. r, 1- ? , i SA-WWA-3E1 ,e r K-40 <11 <11 <9.3 <7.0 Others <LLD <LLD <LLD <LLD l l All gama emitters searched for were <LLD; typical LLDs are given in Table C-38. (1) Start date for station IMA-4S1 was 4-19-32. (2) Stop date for station WWA-4S1 was 9-14-82. I ~

~ l TABLE C-20 C0tiCEllTRATIO!15 0F STRONTIUT1-89* AtlD -90 Ill QUARTERLY C0f1POSITES OF WELL WATER nesults in Units of pCi/1 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 RADI0 ACTIVITY 3-15-82 6-14-82 9-13-82 12-13-82 SA-WWA-451 Sr-89 <0.6 <0.5 (1) <0.5 (2) <0.5 Sr-90 <0.5 <0.4' <0.4 <0.4 ym 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-3E1 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. (1) Start date for station WWA-4S1 was 4-19-82. (2) Stop date for station WWA-4S1 was 9-14-82. L ___

T ~ l TABLE C CONCENTRATIONS OF TRITIUM IR RAW A'I) TREATED POTABLE WATER Results in Units of pC1/1 i 2 signa (All Results by PSESG Research Corporation) STATION RADI0 ACTIVITY JNIUARY FEBRUARY MARCH APRIL MAY -JUNE l SA-PWR-2F3 i (Raw) <140

<120

<130 130 80 <120- <130 N* SA-PWT-2F3 (Treated) 170190 <120 <130 <120 <120 <130 l I STATION RADI0 ACTIVITY JULY AUGUST SEPTEMBER OCTOBER NOVE!*.3ER DECEMBER S A-PWR-2F3 (Raw) 150180 <130 140180 <130 <140 <140 SA-PWT-2F3 (Treated) <130 <130 130i80 (130 <130 (140 il 4 ? Wl'- u a-u

1 TABLE C-22 CONCENTRATIONS OF TRITIUM, GROSS ALPHA AND GROSS BETA EMITTERS, AND POTASSILfi-40 IN RAW AND TREATED POTABLE WATER STATION SA-PWA-2F3 Results in Units of pCi/l i 2 sigma RADI0 ACTIVITY JANUARY FEBRUARY MARCH APRIL MAY JUNE H-3* (Treated) <118 <101 < 104 93 74 <112 <122 Alpha Raw) 1.1 0.6 0.84 5 0.7 0.5 1.1 0.6 1.3t0.7 2.9!1.0 Treated) 0.710.6 0.6t0.5 0.6i0.5 0.9t0.7 <1.0 3.Itl.3 Beta Raw) 4.410.6 3.9!0.5 2.9 0.4 3.9io.5 4.210.(, 2.7!0.4 Treated) 3.8t0.5 2.6i0.5 2.7 0.4 3.0 0.5 3.910.5 2.5 0.4 ' 220.3 2.4 0.2 1.9t0.2 2.0t0.2 1.5 0.2 2.320.2 K-40 (Raw) + D (Treated) . 9i0.3 2.710.3

2. 4 +0. 2 1.6 0.2 2.5t0.3 2.5t0.3 RADI0 ACTIVITY JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE H-3*

(Treated) <119 <121 <121 <108 <109 <110 Aloha Raw) <1.0 <0.8 1.0 0.5 <0.6 <0.7 0.8 0.5 1.1+'. 2 Treated) <1.3 <0.9 <0.5 <0.8 <0.8 d.9 Beta Raw) 2.6t0.5 2.7t0.6 2.710.4 2.010.4 3.3t0.5 2.6 0.4 3.121.5 Treated) 2.4 0.5 1.7!0.4 2.0t0.4 2.0 0.4 2.4t0.5 2.4*0.4 2.6il.3 K-40 (Raw) 2.2 0.2 2.010.2 2.1 0.2 2.Ito.2 2.30.2 2.3to.2 2.2!0.8 (Treated) 2.3t0.2 1.1 +0.1 1.30.1 2.1 0.2 1.8!0.2 2.4t0.2 2.121.1 For quality assurance purposes, treated potable water samles are analyzed for tritium on a monthly basis.

TABLE C-23 CONCENTRATIONS OF STRONTIUM-89* AllD -90 Ill QJARTERLY COMPOSITES OF P0 TABLE WATER Results in Units of pCi/1 2 sigma-(A11'Results by PSE&G Research Corporation) 1-01-82 4-01-82 7-01-82 10-01-82 STATION to to to to RADI0 ACTIVITY 3-31-82 6-30-82 9-30-82 12-31-82 SA-PWR-2F3 Bi (R aw) Sr-89 <1.3 1.2 0.4 1.2 0.5 <0.5 Sr-90 <0.9 <0.7 <0.7 <0.4 l S A-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 sample stop date. l l l l 7

TABLE C-24 CONCENTRATIONS OF STRONTIUit-89* AND -90, NID GNEtA B1ITTERS** IU QUARTERLY COMPOSITES OF POTABLE WATER STATION SA-Pila-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 82 9-30-82 12-31-82 Raw Gamna yu) Emitte rs <LLD <LLD <LLD <LLD Trea ted* ** S r-89 <0.3 <0.3 <0.4 <0.4 Sr-90 0.6 0.3 <0.3 <0.3 <0.3 G amna Baitters < LLD <LLD < LLD < L LD Sr-89 results are corrected for decay to sample stop date. All gamna enitters 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 BENTH0S Results in Units of pCi/g(dry) 2 sigma STATION NUMBER DATE Sr-89 Sr-90 SA-ESB-11A1 6-08-82 <0.02 <0.02 10-05-82 <3.4 <1.6 I SA-ESB-12C1 6-08-82 <0.03 <0.03 8 10-05-82 <5.6 <2.8 SA-ESB-7El 6-08-82 <0.03 0.03 0.02 10-05-82 <1.5 <0.8 S A-ESB-16F1 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 ?!DL due to small sample size. ~-

l l r TABLE C-26 1 00NCENTRATIONS OF STRONTIUM-90 AND GAMMA

EMITTERS IN SEDIMENT **

Result in Units of pCi/g(dry) 2 sigma STATION NO. SA-ESS-11A1 SA-ESS-12C1 SA-ESS-7El SA-ESS-16F1 OATE 6-08-82 10-05-82 6-08-82 10-05-82 6-08-82 10-05-32 6-08-82 10-05-82 Sr-90 <0.03 <0.04 <0.02 <0.05 <0.03 <0.04 <0.05 <0.05 co K-40 13 1 1111 1421 1211 1211 9.1!0.9 1411 1211 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'O.02 0.05 0.02 <0.03 0.1410.02 l Ra-226 0.52 0.05 0.56t0.06 0.84 0.08 0.73 0.07 0.4710.05 0.4510.05 0.7210.07 0.48t0.05 Th-232 0.7410.07 0.72 0.07 0,9410.09 0.80 0.08 0.54r0.07

0. 54 t0.06 1.3!0.1 0.6510.07 All other gamma emitters <LLD; typical LLDs are given in Table C-38.

Sediment samples included associated benthic organisms, d

TABLE C-27 CONCENTRATIONS OF 10 DINE-131 IN MILK Results* in Units of PC1/1 STATION NO. JANUARY ** FEBRUARY MARCH APRIL HAY JUNE SA-MLK-13E3 <0.07 <0.09 <0.06 <0.1 <0.07 <0.08 <0.07 <0.07 <0.09 <0.08 <0.1 (0.08 SA-MLK-2F4 <0.06 <0.1 <0.08 <0.1 <0.09 <0.08 <0.0 7 <0.06 <0.1 <0.08 <0.1 (0.09 SA-MLK-5F2 <0.07 <0.1 <0.08 <0.1 <0.09 <0.1 <0.07 <0.08 <0.1 <0.08 <0.1 <0.1 SA-MLK-14F1 <0.07 <0.1 <0.07 <0.1 <0.1 <0.1 <0.08 <0.08 <0.09 <0.09 <0.1 <0.1 SA-MLK-15F1 <0.08 <0.1 <0.09 <0.1- <0.1 <0.09 <0.08 <0.08 <0.1 <0.09 <0.1 <0.1 SA-MLK-3G1 <0.1 <0.1 <0.07 <0.1 <0.03 <0.1 (0.08 <0.09 <0.08 <0.08 <0.09 <0.1 STATION NO. JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMPER SA-MLK-13E3 <0.3 <0.1 <0.2 <0.% <0.09 <0.08 <0.2 <0.1 <0.1 <0.1 <0.1 <0.07 SA-MLK-2F4 <0.3 <0.1 <0.1 <0.1 <0.08 <0.08 <0.2 <0.09 <0.1 <0.1 <0.1 <0.07 SA-MLK-5F2 (1) <0.1 <0.2 <0.1 <0.1 (1) <0.2 <0.09 (0.2 <0.1 <0.1 <0.09 SA-MLK-14F1 <0.3 <0.1 <0.1 <0.08 <0.1 <0.08 <0.2 <0.1 <0.2 <0.1 <0.1 (1) SA MLK-15F1 <0.3 <0.1 <0.1 <0.08 <0.1 <0.08 <0.2 (0.1 <0.2 (0.1 <0.1 (1) SA-MLK-3G1 <0.2 <0.1 <0.1 <0.09 <0.2 <0.1 <0.2 <0.1 <0.2 <0.1 <0.1 (1) I-131 results decay corrected to saple 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 S A-MLK-13E 3 K-40 14001140 12001120 11001110 1600 160 1500t150 1500t150 Cs-137 <1.4 <1.4 <1.1 4.0tl.2 1.8 1.1 <1.2 <2.2 Sr-89 Sr-90 4.911.6 SA-MLK-2F4 K-40 1400t140 11001110 1800 180 2700t270 1700t170 20001200 Cs-137 <1.4 1.6tl.1 1.511.0 8.7tl.4 1.911.2 <1.2 Sr-89 <7.8 (1) Sr-90 1015 S A-ML K-5F2 K-40 2000t200 1300t130 1100t110 1700t170 1300t130 1400t140 Cs-137 1.9tl.2 <1.2 <1.2 2.211.1 2.0 1.1 6.911.2 Sr-89 <4.7 <1.5 00 5.5tl.1 to S r-90 6.711.1 STATION N0. NUCLIDE JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER SA-MLK-13E3 K-40 15001150 1700 170 920 92 1300tl30 15001150 15001150 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 1400t140 1500t150 1100!110 13001130 1500il50 15001150 Cs-137 <1.2 <1.2 <1.2 <1.1 <1.2 <1.6 Sr-89 <2.4 l Sr-90 3.020.7 i SA-MLK-5F2 K-40 10001100 14002140 1100t110 1800t180 13002130 1400t140 Cs-137 1.9t0.8 3.6t1.3 <1.2 <1.2 <1.2 1.8t0.7 S r-89 <1.7 Sr-90 3.911.0

1 i ~ TABLE C-28 (cont.) l . CONCENTRATIONS OF GAf9tA EMITTERS

AND STRONTIUM-.89** AND -90 IN MILK.

Results'.in Units of pC1/1 i 2 sigma STATION NO.*** NUCLIDE JANUARY **** FEBRUARY MARCH APRIL MAY JUNE SA-MLK-14F1 K-40 1600t160 1700t170 2500t250 16002160 18001180. 16001160 Cs-137 <1.2 <1.2 2.821.1 1.721.0 2.011.1 <1.4 Sr-89 <1.0 Sr-90 2.5t0.9 SA-MLK-15F1 K-40 15001150-14002140 13001130 ' 1500t150 16001160 1500t150-Cs-137 . <1.4 3.121.1 <1.4 4.0 1.3 2.321.2 3.311.3-Sr-89 <2.8 Sr-90 3.711.3 SA-MLK-3G1-K-40 14001140 14002140 770t77 13002130 14002140 '1400t140 Cs-137 1.7tl.1 - <1.4 1.421.1 <1.2 <1.2 1.921.1 Sr-89 <46 1 . <3.9 <1.1 <1.0 <1.9 <13 (1)- Sr-90 <56 1 5.421.8 1.411.0 1.511.0 5.4tl.4 7.514.8 co su I' STATION NO. NUCLIDE JULY' AUGUST SEPTEMBER OCTOBER NOVEMER DECEMBER I SA-MLK-14F1 K-40 14002140 12002120 900190 -1400t140 14001140 1300t130 Cs-137 <1.2 <1.2 <1.1 <1.2 < 1. 2 - <1.4 Sr-89 <3.3 Sr-90 3.612.4 SA-MLK-15F1 K-40 15001150-15001150 17001170 1400t140 1600t160 i3001130 Cs-137 < 1.4 <1.4 <1.2 <1.2 <1.2 1.4t0.7 l-Sr.<1.0 3.822.3 Sr-90 3.4 0.6 0.820.7 SA-MLK-3G1' K-40 18002180 16002160 14002140 1300i130 13001130 1500t150 Cs-137 <1.2 < 1.4 - 1.5i0.9 <1.2 <1.1 <1.2 Sr-89 <1.3 <2.6 4.4t4.3 <1.2 <1.6 <1.2 Sr-90 3.30.8 5.9tl.7 2.4t1.8 ' 3.8t0.7 4.720.9 4.110.8 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 M.K-3G1 is analyzed for Sr-89 and -90 on a monthly basis by RMC; in addition, one station I 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. k

l TABLE C-29 CONCENTRATIONS OF STRONTIUM-89* AND -90 IN MILK i Results in Units of pCi/1 i 2 sigma ( All Results by PSE&G Research Corporation) STATION NO.** NUCLIDE JAf0ARY FEBRUARY T1 ARCH APRIL NAY JUNE SA-MLK-13E3 Sr-89 6.911.0 <1.8 <1.9 <2.1 <2.0 (1.9 Sr-90 <1.8 2.7t0.7 2.410.7 2.7 0.8 2.1!0.7 2.210.6 SA-f1LK-2F4 Sr-89 <1.9 <1.8 <1.9 <2.2 <2.0 <1.9 Sr-90 2.0t0.6 2.410.6 2.4t0.7 2.6io.8 <1.5 1.4 0.6 SA-MLK-SF2 Sr-89 <2.0 <2.4 <2.1 <2.4 <1.9 <2.2 Sr-90 4.1 0.7 4.2 0.9 3.710.8 4.0 0.9 3.5t0.7 5.210.8 SA-MLK-14F1 Sr-89 <2.0 <1.8 <1.7 <1.7 <1.7 <2.0 Sr-90 2.4!0.7 2.4 0.7 2.5t0.7 2.7 0.6 1.9 0.6 2.920.7 SA4tLK-15F1 Sr-89 <2.0 <2.1 <2.0 <2.1 <1.8 <2.7 S r-90 2.6to.7 2.7 0.7 2.8!0.8 2.7 0.8 <1.4 2.6 0.9 CD SA-ffLK-3G1 Sr-89 <2.2 <2.2 <2.2 <2.3 <1.8 <2.1 Sr-90 4.3 0.8 3.6t0.8 3.4 0.8 3.8 0.8 2.710.6 4.0t0.7 STATION NO. ** f0;LIDE JULY MIGUST SEPTEMBER OCTOBER N0VDiBER DECENSER SA-!fLK-13E3 Sr-89 <1.6 <1.7 <1.9 <1.7 <1.6 <1.5 S r-90 2.0t0.6 2.4 0.6 3.2!0.7 2.8 0.6 2.9 0.6 2.2 0.6 S A-MLK-2F4 S r-89 <1.4 <1.3 <1.6 <1.6 <1.5 <1.5 S r-90 1.5t0.5 1.110.5 1.6t0.6 1.3t0.6 2.0t0.5 1.610.6 SA-MLK-5F2 Sr-89 <2.2 <1.8 <1.9 <1.9 <1.8 <1.7 S r-90 5.4 0.8 3.4t0.7 4.8!0.7 4.3to.7 3.910.7 3.410.6 S A-MLK-14F1 Sr-89 <1.6 <1.7 <1.6 <1.6 <1.6 <1.5 Sr-90 2.0t0.6 2.It0.6 1.8 0.6 2.910.6 3.210.6 2.6 0.6 SA-MLK-ISF1 S r-89 <2.1 <1.6 <1.8 <1.6 <1.6 <1.7 Sr-90 3.3t0.8 a.6t0.6 2.8 0.6 2.3t0.6 2.1 0.6 2.810.7 S A-MLK-3G1 S r-39 <2.0 (2.0 <2.2 <1.9 <1.8 <1.8 Sr-90 4.0r0.7 3.8 0.8 4.5 0.8 4.6 0.7 4.0t0.7 2.7t0.6 Sr-89 results are corrected for decay to sample stop date. Sampling dates can be found on Table C-30.

.9 TABLE C-30 S#iPLING DATES FOR M:G 3st;".ES MONTH 13E3 2F4 SF2 14F1 15F1 3G1 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 2-07-22 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 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 1 to to to to to to l 3-09-82 3-08-82 3-08-82 3-09-82 3-08-82 3-09-82 f 3-22-82 3-21-82 3-21-82 3-22-82 3-21-82 3-22-82 to to to to to to j 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 4-05-62 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 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 5-16-92 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-L2 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 6-07-62 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 6-22-02 6-21-82 6-22-82 6-21-82

TABLE C-30 (cont.) SAMPLING DATES FOR HILK SAMPLES MONTH 13E3 2F4 SF2 14F1 15F1 3G1 JULY 7-06-82 7-05-82 7-05-82 7-06-82 7-05-82 7-05-82 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 SEPTEMBER 9-06-82 9-07-82 9-07-82 9-06-82 9-07-82 9-06-82 to to to to to to 9-08-82 9-08-82 9-08-82 9-07-82 9-08-82 9-07-82 9 82 9-19-82 9-19-82 9-20-82 9-19-82 9-20-82 to to to to to tc 1 9-21-82 9-20-82 9-20-82 9-21-82 9-20-82 9-21-82 l l OCTOBER 10 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-b2 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 11-23-8? 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

i TABLE C-31 CONCENTRATIONS OF GAf1MA EftITTERS* Ill EDIBLE FISH Results in Units of pCi/g(wet) '2 sigma STATION SAMPLIllG K-40 t0MBER DATE 1 SA-ESF-11A1 5-03-82 to 3.110.3 ) 7-30-82 l 9-16-82 i to 2.9 0.3 10-08-82 SA-ESF-12C1 5-03-82 to 3.7 0.4 7-30-82 9-16-82 to 3.10.4 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. l l ~ ~.

I TABLE C-32 C0HCENTPATIOlis OF STRONTilEl-89* AftD -90, NID TRITIU:1 I!4 EDIBLE FISH SN1PLES Bones Flesh Aqueous Fraction Organic Fraction (pCi/g(dry) 2 signa) (pCi/1 2 sigma) (pC1/1 2 sigma) STATION DATE S r-89 Sr-90 H-3 H-3 SA-ESF-11A1 5 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 co SA-ESF-12C1 5 82 "3 to <0.5 0.10 0.06 <112 <641 (1) 7 82 9-16-82 to <0.1 0.21 0.05 <116 17401170 (2) 10-08-82 SA-ESF-7El 5-03-82 I to <0.3 <0.03 <112 134t99 7-30-82 9 82 to <0.3 <0.2 <369 (1) 1800t180 (2) 10-08-82 Sr-89 results are corrected for decay to sanple stop date. (1) High LLD due to small sample size. (2) Chemiluminescence suspected; insufficient sample for reanalysis.

TABLE C-33 C0liCENTRATIONS OF G#EIA D1ITTERS* IN BLUE CRAB SN1PLES Results in Units of pCi/g(wet) i 2 sigma STATION llu!1BER DATE SNIPLE TYPE K-40 SA-ECH-11A1 5-03-82 to Flesh 2.0 0.3 7-30-82 10-26-82 to Flesh 2.10.2 10-26-82 SA-ECH-12C1 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. r

I TABLE C-34 CONCENTRATIONS OF STRONTIU!1-89* AND -90 AND TRITIUt1 IN BLUE CRAB SAMPLES STATION Sr-89 Sr-90 H-3 (Edible Portion) NUMBER DATE SAMPLE DCi/g 2 sigma pCi/g 2 sigma pCi/1 2 2 sigma SA-ECH-11A1 5-03-82 Flesh <0.01 <0. 006 <112 to 7-30-82 Shell <0.1 0.14!0.04 9-16-82 Flesh (1) (1) 230174 to 10-08-82 Shell <0.04 0.29 0.03 10-26-82 Flesh <0.006 0.00610.004 ua Shell <0.04 0.3110.03 SA-ECH-12C1 5-03-82 Flesh <0.02 0.014t0.005 (112 to 7-30-82 Shell 0.2!0.1 0.09t0.05 i i 9-16-82 Flesh <0.02 0.005!0.004 157 73 to 10-08-82 Shell <0.05 0.19t0.02 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) i 2 sigma STATION NO. DATE SAMPLE TYPE Sr-89 Sr-90 K-40 SA-FPV-2E1 5-11-82 Asparagus <0.008 <0.007 2.1t0.2 SA-FPV-5D1 7 82 Corn <0.004 <0.004 2.510.3 SA-FPL-IF3 7-26-82 Cabbage <0.2 0.0210.01 2.1r0.3 SA-FPL-2F4 7 82 Cabbage <0.008 0.01210.005 2.8t0.3 SA-FPG-2F4 7-26-82 Corn <0.01 0.002 0.001 2.9t0.3 SA-FPV-14F3 7-26-82 Tomatoes <0.04 <0.003 1.3i0.1 SA-FPG-1G1 7 82 Corn <0.004 <0.004 2.lto.2 SA-FPV-1G1 7-26-82 Peppers <0.03 0.01010.003 2.4t0.2 SA-FPV-1G1 7-26-82 Tomatoes <0.004 0.003t0.003 0.9420.09 SA-FPV-1G1 7 82 Cucumbers <0.01 0.020 t0.008 2.0f0.2 SA-FPV-1F3 8-02-82 Peppers <0.008 <0.006 1.8 0.2 SA-FPV-IF3 8 82 Tomatoes <0.006 0.008r0.003 1.410.1 SA-FPV-5F1 8-02-82 Tomatoes <0.05 0.006t0.004 2.510.3 SA-FPL-14F3 8 82 Cabbage <0.005 0.005 t0.003 1.2i0.2 SA-FPG-14F3 8-02-82 Corn <0.04 <0. 005 3.110.3 SA FPL-3H4 8-02-82 Cabbage <0.01 0.009t0.007 3.4t0.3 SA-FPG-3H4 8 82 Corn <0,103 <0.002 2.610.3 SA-FPV-3H4 8-02-82 Cucumbers <0.02 0.003t0.002 1.4 0.1 SA-FPV-3H4 8-02-82 Peppers (0.02 0.0210.01 2.3 0.2 SA-FPV-3H4 S-02-82 Tomatoes <0.004 0.004!0.004 1.410.1 SA-FPV-5D1 8-03-82 Peppers <0.004 0.006:0.005 1.810.2 SA-FPV-5DI 8-03-82 Tomatoes <0.03 0.006t0.002 1.8 0.2 SA-FPG-501 10-12-82 Soybeans <3.0 3 0.08 0.01 1211 Sr-89 results are cot rected for decay to sagte stop date.

- All other gamma emitters searched for were (LLD; typical LLDs are given in Table C-38.

I TABLE C-36 CONCENTRATIONS OF STRONTIUM-89 AND -90* AND GAMMA EMITTEaS** IN GAME, MEAT AND B0 VINE THYROID Results in Units of pCi/g(wet) 2 sigma STATION NO. DATE SAMPLE TYPE Sr-89 Sr-90 K-40 pC1/9(dry)

2 sigma SA-GAM-3E1 2-07-82 Muskrat 0.07 0.05 0.09 0.03 2.3!0.2 SA-GAM-1101 2-15-82 Muskrat

<0.03 0.0810.03 2.0t0.2 e La SA-FPB-3E1 2-15-82 Beef 1.110.1 SA-THB-3E1 2-15-82 Bovine Thyroid <0.6 SA-FPB-14F1 11-12-82 Beef 2.2 0.2 SA-THB-14F1 11-12-82 Bovine Thyroid 2.3t0.6 Radiostrontium performed on muskrat only. 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. Indicates strontium analyses not performed. m_____________

' TABLE C-37 CONCENTRATIONS OF GAMMA EMITTERS 0 IN F0DDER CR0P SN1PLES-Results in Units of pCi/g(wet) 2' sigma STATION SM!PLE NUMBER DATE TYPE K-40 SA-VGT-3G1 8-16-82 Green Chop 3.510.4 f SA-VGT-2F4 9-01-82 to Sil age 3.6 0.4 9-07-82 SA-VGT-3G1 9-03-82 to Sil age 2.7 0.5 9-04-82 SA-VGT-15F1 9-07-82 Alfalf a 4.8 0.5 q g SA-VGT-5F2 9-07-82 to Silage 2.9 0.5 9-08-82 SA-VGT-5D1 9-13-82 Grass 3.3 0.4 SA-VGT-14F1 9-14-82 Corn Silage / Green Chop 3.610.6 SA-VGT-15F1 10-04-82 Silage 2.9 1.6 SA-FPG-3G1 11-21-82 Soybeans 18 2 I SA-FPG-15F1 11-22-82 Soybeans 14 1 t All other gansna emitters searched for were <LLD; typical LL0s are 9fven in Table C-38.

f TABLE C-38 LLDs FOR GAMMA SPECTROMETRY AIR SURFACE WELL/ POTABLE PARTICULATES PRECIPITATION WATER WATER SE0IMENT MILK NUCLIDES (10 pci/m ) (pCi/1) (pCi/1) (pCi/1) (pCi/g. dry) (oCi/1) -3 3 Be-7 8.1 5.2 6.3 0.3 7.6 1.0 Na-22 0.3 0.8 0.6 0.8 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 0.02 2.0 Co-57 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 20 Co-60 0.3 0.8 0.6 0.6 0.03 0.9 In-65 0.7 1.5 1.4 1.4 0.05 1.7 0.05 e

(n Zr-95 0.7 9.05 Nb-95 0.4 0.9 0.6 0.0 0.6 ZrNb-95 87 Mo-99 17 160 27 52 0.04 Ru-103 0.4 Ru-106 3.4 6.5 6.3 6.3 0.2 8.0 Ag-110m 0.3 0.7 0.6 0.6 0.02 1.0 C.06 Sb-125 0.7 Te-129m 3.4 17 11 13 1.5 19 1.9 I-131 0.6 3.5 1.1 1.4 0,.6 4,9 3.7 Te-132 1.3 11 2.1 1-133 Cs-134 0.3 0.6 0.6 0.6 0.02 1.0 Cs-136 0.5 2.3 1.4 1.6 0.2 2.6 Cs-137 0.4 0.8 0.6 0.6 0.03 1.1 0.8 Ba-140 1.5 0.2 La-140 0.7 1.7 2.4 1.0 1.3 3ala-140 0.05 Ce-141 0.5 Ce-144 1.6 3.3 1.6 1.6 0.1 3.2 1.6 Pa-226 1.0 1.2 1.1 1.2 3.1 Th-232 1.5 3.1 3.1 3.1

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M-APPENDIX D-1 SYNOPSIS OF ANALYTICAL PROCEDURES UTILIZED BY RMC 97 m

l GROSS ALPHA ANALYSIS OF SAMPLES Total Water (AO, A1) A 250 ml (AO) or one 1 (A1) 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-weighed. The planchet is counted in a low-background, gas flow proportional 3 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/1) = ((S/T) - (8/t)) / (2.22 V E TF) 2 sigma error (pCi/1) = 2 ((S/T ) + (B/t ))1/2 / (2.22 V E TF) 2 2 where: Gross counts of sample S = Counts of blank B = Fractional Pu-239 counting efficiency E = Number of minutes sample was counted T = Number of minutes blank was counted t = Sample aliquot size (liters) V = Transmission factor (based on net weight of sample TF = 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/1) = 4.66 (B1/2) / (2.22 V E TF t) where: Counts of blank B = Fractional Pu-239 counting efficiency E = Number of minutes blank was counted t = Sample aliquot size (liters) V = Transmission factor (based on net weight of sample TF = in counting planchet) 99

GROSS BETA ANALYSIS OF SAMPLES Total Water (B0, B1) A 250 ml (89) or one 1 (B1) 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-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 V E TF) 2 sigma error (pCi/1) = 2 ((S/T ) + (B/t ))1/2 / (2.22 V E TF) 2 2 where: c Gross counts of sample S = Counts of blank B = Fractional Sr-90-Y-90 counting efficiency E = Number of minutes sample was counted T = Number of minutes blank was counted t = Volume of aliquot (liters) V = Transmission factor (based on net weight of samp;e TF = 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 tne standard deviation of that background. LLD (pCi/1) = 4.66 (B1/2) / (2.22 V E TF t) where: Counts of blank B = Fractional Sr-90-Y-90 counting efficiency E = Number of minutes blank was counted t = Volume of aliquot (liters) V = Transmission factor (based on net weight of sample TF = in counting planchet) e 100

i ENVIRONMENTAL DOSIMETRY (DS, D1, 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 elemeni. energy compensation shield supplied by. Panasonic Corporation, manu-facturer of the TLD reader. The four dosimeters per station are sealed in a polyethylene bag to demonstrate integrity at time of measurement. Visible through the bag are the sample placement instructions. One set of TLDs is placed in a lead shield at RMC and represents a zero dose. The TLDs are then taken and placed in the field stations; one field TLD set is placed in a field lead shield at station 18 and is used in calculating the 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: (G-Z) R C 0.955 mrad / Roentgen T = SZ - (RZ DL / DR) I = T-I N = n ((sum N) / n) (30.4 / DL) Average = i=1 t (n-1) (SD / n /2) (30.4 / DL) l Error = where: Individual TLD reading corrected to standard instrument T = conditions Gross reading of dosimeter i G = Zero for dosimeter, i Z = Correction factor of reader (see Procedure T-6) R = Calibration factor dosimeter i C = I In-transit dose = Mean of n dosimeters in site lead shield SZ = Mean of n dosimeters in RMC lead shield RZ = Exposure period of location (days) DL = Exposure period of RMC0 (days) DR = 101 _____________________A

6 4 4 - =

A+

ENVIR0iiMENTAL D0SIMETRY (cont.) J Average Mean exposure per standard exposure period at a given = station N Net dose 'obtained during exposure' period in the field = Number of readings n- = 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 = 2 ( 102 ,_ ~- -. -,.,. -,_.. ~

l l 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 soectrochotometrically on a Perkin Elmer Model 373 atomic absorotion 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 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 (.1/S) K = where: Concentration of Standard (pg K/ml) Cs = Sample reading C = Standard reading S = Dilution factor D = Specific activity of K-40 per unit weight of potassium (.852 pCi/mg) K = 103 a

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 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/1) water is vacuum cistilled 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/1) ((S/T) - (B/t)) / (2.22 V E) = 2 2 2 ((S/T ) + (B/t ))1/2 / (2.22 V E) 2 sigma error (pCi/1) = where: Total gross counts of sample S = Counts of blank B = Fractional H-3 counting efficiency E = Number of minutes sample was counted T = Number of minutes blank was counted t = Aliquot volume (liters) V = 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 samole only are calculated using the following equa-tions: ((s-b)v) / G S = (c(G+H)) / V s = (d(H)) / V b = G V/(G+H) v = where: ( Gross counts of sample S = Volume of sample G = Volume of rinse H = Volume corrected gross counts of sample plus rinse s = Volume corrected gross counts of rinse b = Corrected aliquot volume v = Uncorrected gross counts of sample plus rinse c = Uncorrected gross counts of rinse d = 104 j

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. 4.66 (B1/2) / (2.22 V E t) LLD (pCi/1) = where: Counts of blank B = Fractional H-3 counting efficiency E = Number of minutes blank was counted t = Aliquot volume (liters) V = 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 samples are counted. b. Organic Bound H-3 in Food Products The dried residue is combusted in an RMC designed oxidizer. The collected water - organic fraction is measured and vacuum distilled to remove any impurities. Permanganate in K0H solution is added to remove impurities If less than eight (8) quot is counted in a liquid An eight (8) ml ali which may cause quenching. ml are collected, the entire scintillation counter. 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. Pe r-manganate in K0H 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 samole of deep well water is counted as a blank. Calculations am made utilizing the following equations: ((S/T) - (B/t)) / (2.22 V E) Result (pCi/1) = of distillate 2 ((S/T ) + (B/t ))1/2 / (2.22 V E) 2 2 2 sigma error (pCi/1) = 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(YF) = 2 sigma error (pCi/g or 1 of original sample) C(YF) = where: S Gross counts of sample = B Counts of blank = E Fractional H-3 counting efficiency = T Number of minutes sample was counted = Number of minutes blank was counted t = V_ Volume of distillate counted = YI Liters of water-organic recovered / g of freeze dried sample = Liters of water recovered / (1 or g) of sample aliquot counted YF = A Result in pCi/1 of distillate = C 2 sigma error in pCi/1 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. 4.66 (B1/2) / (2.22 V E t) LLD(pCi/1) = LLD (pCi/g of freeze dried sample) F (YI) = LLD (pCi/1 or g) F(YF) = of original sample r where: Counts of blank B = Fractional H-3 counting efficiency E = Number of minutes blank was counted t = V Volume of distillate counted = YI Liters of water-organic recovered /g of freeze dried sample = Liters of water recovered /(1 or g) of sample aliquot counted YF = F LLD in pCi/1 of distillate = F l 106

l ANALYSIS OF SAMPLES FOR 10 DINE-131 Milk or Wa9r (IO) 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 res,in. The iodide is eluted from the resin with sodium hypochlorite, and purified cy 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: (S-B) / (2.22 V E F Y T) Result = (pCi/1) 2 (S+B)1/2 / (2.22 V E,F Y) 2 sigma error = (pCi/l) 4.66 (B1/2) / (2.22 V E F Y T) LLD = (pCi/1) where: Gross counts of sample in channels containing I-131 peak S = Background counts in channels containing I-131 peak B = Number of minutes sample was counted T = Iodine-131 counting efficiency E = Sample aliquot size ~ V = Fractional gama abundance F = Chemical yield of iodine Y = Air Cartridges (II) An iodine adsorber composed of charcoal is emptied into an aluminum can (6 cms high by 8 cms 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. Calculations are made utilizing the following equations: Result 3= ((S/T) - (B/t)) / (2.22 V E F Y) (pCi/m ) 107

2 ((S/T ) +-(B/t ))1/2 / (2.22 V E F Y) 2 2 _2 sigmg) error = (pCi/m 4.66 (.63(Q1/2)b)1/2 / (2.22 V E F Y t) LLD = 3 (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 = Number of minutes background was counted t = E Iodine-131 counting efficiency = V Sample aliquot size = F Fractional gamma abundance = Y Chemical yield of iodine = 4 4 4 i + i j i i' 108 .-- m ., ~. - -w.,--- ,,,,,,,-e, w,.

GAMMA SPECTROMETRY OF SAMPLES Water (N1) Four liters of sample is reduced to 100 ml and sealed in a standard container and counted with a NaI(T1) 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, G8) A large quantity of the sample is dried at a low temperature, less than 100 C. A 100 gram aliquot (or the total sample if less than 100 grams) is taken, 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 ama, 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 conputer program is used for spectrum analysis. Calculations are made utilizing the following equations: ((S/T) - (B/t)) / (2.22 V E F) Result (pCi/l or g) = 2 sigma error (pCi/l or g) = 2 ((S/T ) + (B/t ))1/2 / (2.22 V E F) 2 2 where: Net area, in counts, of sample (Region of spectrum of. interest) S = Net area, in counts, of background (Region of spectrum of interest) B = Number of minutes sample was counted T = Number of minutes background was counted t = Detector efficiency for energy of interest E = Sample aliquot size V = Fractional ganna abundance (specific for each emitted nuclide) F = 109

Calculation of lower limit of detection (LLD) for G8 4.66 (6 S)1/2 / (2.22 V E F T) LLD (pCi/1 or g) = where: Net area, in counts, of sample (Region'of spectrum of interest) S = Number of minutes sample was counted T = Detector efficie~ncy for energy of interest E = V Sample aliquot size = F Fractional gatea abundance = Calculation of lower limit ot' 6'etection (LLD) for N1, N7, N8 and NA 4.66 (.63 (Q)1/2 3)1/2 / (2.22 V E F T) LLD (pCi/1 or g) = where: Net area, in counts, of sample (Region of spectrum of interest) S = Number of minutes sample was counted T = j E Detector efficiency for energy of interest = V Sample aliquot size- = F Fractional gansna abundance = Q Channel number = I ) 110

i ANALYSIS OF SAMPLES FOR STRONTIUM-89 AND -90 Total Water (SO, TO) 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 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 detennined 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 nineral 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 (SS, T5) A large quantity of the sample is dried, ashed and a 25 g portion is then dissolved in concentrated acid. Stable strontium carrier is added to the 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 r.t least two precipitations of strontium nitrate in concentrated nitric acid. Addi-tional iron / rare earth hydroxide precipitations and barium chromate separatior.s 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 detennined 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 (SS, 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 P riod of time. Sr-90 is then determined by counting yttrium oxalate after initi..., 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). t Result Sr-90 = (A/T1-B/T2) / (2.22 V E Y X exp(-0.693 t1/64.1)(1-exp(-0.693t2/64.1))) (pCi/l or g) 2 sigma error Sr-90 = 2(A/T1 +B/T2 )1/2 / (2.22 V E Y X exp(-0.693t1/64.1)(1-exp(-0.693 2 2 (pCi/1 or g) t2/64.1))) 1/2 MDL Sr-90 = 3 B / (2.22 T2 V E Y X exp(-0.693t1/64.1)(1-exp(-0.693t2/64.1))) (pCi/1 or g) where: A Gross Y-90 counts = Gross blank counts of yttrium B = Y-90 counting time T1 = T2 Blank counting time = V Sample aliquot size = E Y-90 counting efficiency = Yttrium chemical yield Y = X Strontium chemical yield = Time in hours from second separation of Y-90 until counting time t1 = of yttrium planchet plus one-half the counting time Time in hours between first and second separations of Y-90 ( t2 = (ingrowth time) Result Sr-89 = (C/T3 - D/T4 - G - H)/(2.22 V F X exp(-0.693t4/50.5)) (pC1/1 or g) I 2 sigma error Sr-89 = 2 (C/T32 + D/T42 + G/T3 + H/T3)1/2 / (2.22 V F X exp(-0.693t4/50.5)) (pCi/1 or g) 112 n_

MDL Sr-89 = 3(D+GT3+HT3)1/2 / (2.22 T4 V F X exp(-0.693t4/50.5)) (pCi/l or g) where: Gross strontium counts C = Gross blank counts of strontium D = Additional background from Sr-90 activity G = (Sr-90 activity of sample) (2.22 VXJ) = Additional background from Y-90 activity H = (Sr-90 activity of sample) (2.22 VXE) (1-exp(-0.693t5/64.1)) = Sample aliquot size V = Sr-90 counting efficiency J = Sr-89 counting efficiency F = Strontium chemical yield X = Time in days from sampling date to strontium count t4 = Strontium counting time T3 = Blank counting time T4 = Time in hours from second separation of Y-90 to counting of t5 = strontium planchet plus one-half the counting time 113

NN 1 l APPENDIX D-2 SYNOPSIS OF ANALYTICAL PROCEDURES UTILIZED BY THE RESEARCH AND TESTING LABORATORY 115

L GROSS ALPHA AllALYSIS OF AIR PARTICULATE SAf1PLES After allowing at least a three de (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-7)/29.92 P = Pressure correction factor B = Time-averaged barometric pressure during sampling V = period, "Hg Time-averaged vacuum during sampling period 29.92 = Standard atmospheric pressure at 32*F, "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) 3 V = Corrected air flow, m P = Pressure correction factor Using these corrected air flows, the gross alpha activity is computed as follows: 3 Result (pCi/m ) = (G-B)/T G = Sample gross count (2.22)*(E)*(V) B = Background counts (from blank filter) T = Count time of sample and blank, mins. E = Fractional Am-241 counting efficiency V = Cgrrected air flow of sample m 2.22 = fic, of dpm's per pCi 2 sigma error (pCi/m ) = (1.96*(G+B)1/2)*A A = Gross alpha activity, pC1/m 3 3 (G-B) 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. 3 1/2 LLD (pCi/m ) = 4.66

LB?

B = Background counts (from blank IZ.ZZ)*1;EJ*(V)*(T) filter) E = Fractional Am-241 countiac efficiency V = C rrected air flow of sainple. T = Count time of blank, mins. i 1 118

GROSS BETA AtlALYSIS 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 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 correction factor B = Time-averaged barometric pressum during sampling period, "Hg _V = Time-averaged vacuum during sampling period 29.92 = Standard atmospheric pressure at 32 F, "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) 3 V = Corrected air flow, m P = Pressure correction factor Using these corrected air flows, the gross beta activity is computed as follows: 3 Result (pCi/m ) = (G-B?/T G = Sample gross counts (2.22)*(E)*(V) B - Background counts (from blank filte r) T = Count time of sample and blank, mins. E = Fractional Sr-90 counting efficgency V = Corrected air flow of sanple, m 2.22 = flo. of dpm's per pCi 2 sigma error (pC1/m ) = (1.96*(G+B)1/2)*A 3 3 (G-B) A = Gross beta activity, pCi/m 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)= 4.66 * (B)1/2 B = Background counts (from blank 3 I2.22)*(E)*(V)*(T) filter) E = Fractional Sr-90 counting l efficiency V = Cgrrected air flow of sample m T = Count time of blank, mins. l 120

GAlifM Af1ALYSIS 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 florthern 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 full-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 photopeak. The following are the calculations perfonned for the gamma activity, 2 sigma error and LLD: 3 Result = (pCi/m ) = fl*D =R (2.22)*(E)*(A)*(T)*(V) fl = flet counts under photopeak D = Decay correction factor At1*EXP(At2) 1-EXP(-Ati) t1 = 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 = Acquisition liv 3 V = Sample volume, m 2.22 = lio, of dpm's per pCi 2 sigma error (pC1/m ) = 2 * (ok +os 2)1/2 3 ~ 1/2 ok = statistical error of the ok = 1 n 1

A (V)2 activity measurement.

It is E o2 1 detennined from the accuracy i=1 of the least squares evalu-ation performed on the peaks ~ ~ of a particular nuclide, n = number of peaks in the nuclide of question ci = (GC+BC)1/2, where GC and BC are gross counts and background counts, respectively. 121

A (y) i = N*D =gpaabundancefactorforthe (E)*(R)*(2.22)*(T)*(V) -i peak under consideration, for a given nuclide os 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/m ) = 4.66*(GC)1/2*D 3 (2.22)*(E)*(A)*(T)*(V) Again, all other variables are as defined earlier. P 122

ANALYSIS OF AIR FILTERS FOR RADI0 STRONTIUM 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 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, 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: 3 Sr-90 Results (pCi/m ) N4/R = (2.22) * (E) * (0.7621) * (S6) * (V) * (U) = W2 where S6 = 1.4115 - 0.03409*M + 0.000443*M2 (This is normalized dr-90 efficiency regression equation for one particular gas proportional counter) 2 M = Thickness density of strontium carbonate precipitate, mg/cm 2 0.7621 = Ratio of Sr-90 efficiency at thickness value of 15 mg/cm to Sr-90 counting standard efficiency (This standard is run with each group of environmental strontium samples) E = Sr-90 counting standard efficiency 3 V = Sample quantity (lifers, m or kg) U = Chemical yield N4 = (N2 - Fl*N1)/W1 = net counts due to Sr-90 only W1 = ((1 + R1*I2) - (1 t R1*II)*F1) Il = 1 - EXP ((-0.693/2.667)*tl) I2 = 1 - EXP ((-0.693/2.667)*t2) t1 = 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

R1 = 1.242 +' 0.0179*H + 0.000151*M2 Y-90 eff'y/Sr-90 eff'y ratio). (This is regression equation for N2 = X - Y, whem X and Y am recount gross counts and background counts, respectively. N1 = X1 - Y1, where XI and Y1 are initial gross counts and background counts, respectively. 2.22 = No. of dpm's per pCi F1=EXP((-0.693/2.667)*t2) R = Count time of sample and blank 3 Using the same variable definitions as above, the 2 sigma error for Sr-90 (pCi/m ) = 2* (X+Y) + (X1+Y1) *F12 1/2 ,(W1*W2) W14 W14 (N2-Fl*N1) Again, keeping the same variable definitions, the, 3 2 1/2 LLD Sr-90 (pCi/m ) = 4.66* (X+Y) + (X1+Y1)*F1 W14 W14 Calculation of Sr-89 Activity: N6/R 3 Sr-89 Results (o01/m ) = (2.22) * (E) * (1.0922) * (S7) * (V) * (U) * (F9) = W3 S7 = 1.052 - 0.00272*M - 0.00005*M2 regression equation for one par (This is normalized Sr-89 efficiency ticular gas proportional counter) N6 = N1 - N7* (1 + R1*II) N7 = (N2 - Fl*N1)/W1 (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 sanples, this represents the i. 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. 2*(S8,39 )1/2*W3 2 2 3 The 2 sigma error for Sr-89 (pC1/m ) = (N1 - N7* (1+R1*II) 124

l l n S8 = + (X1 1)*F12 1/2 S9 = (X1+Y1)1/2 All other variables are as originally defined. Keeping the same variable definitions, the LLD Sr-89 (pCi/m ) = 4.66* (S8,39 )1/2 3 2 2 2 125

Af4ALYSIS OF RAW MILK FOR RAD 10STR0fiTIUM 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 pick up stron-tium, calcium, magnesium and other cations. These cations are then eluted off with a TRIS-buffered 4ft sodium chloride solution into a beaker and precipitated as carbonates upon heating. The carbonates are converted to nitrates with 6fl 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 performed 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 initial 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/1) f44/R = (2.22) * (E) * (0.7621) * (S6) * (V) * (U) = W2 1.4115 - 0.03409*M + 0.000443*f t2 (This is normalized Sr-90 efficiency where S6 = regression equation for one particular gas proportional counter) 2 Thickness density of strontium carbonate precipitate, mg/cm M = 2 Ratio of Sr-90 efficiency at thickness value of 15 mg/cm to Sr-90 0.7621 = counting standard efficiency (This standard is run with each group of environmental strontium samples) E Sr-90 counting standard efficiency = 3 Sample quantity (liters, m orkg) V = Chemical yield U = (fi2 - Fl*fil)/W1 = net counts due to Sr-90 only f14 = ((1 + R1*I2) - (1 + R1*II)*F1) { W1 = 1 - EXP ((-0.693/2.667)*tl) Il = 1 - EXP ((-0.693/2.667)*t2) { 12 = t1 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

1.242 + 0.0179*M + 0.000151*ll2 (This is regression equation for R1 = Y-90 eff'y/Sr-90 eff'y ratio) X - Y, where X and Y are recount gross counts and background 11 2 = counts, respectively XI - Y1, where X1 and Y1 are initial gross counts and background til = counts, respectively l10. of dpm's per pCi 2.22 = EXP((-0.693/2.667)*t2) F1 = Count time of sanple and blank R = Using the same variable definitions as above, the 2 sigma error for Sr-90 (pCi/1) = 2 1/2 (W1*W2) 2* ( X+Y), + (X1+Y1)*F1 W1' W1' (f42-Fl*fil) Again,keepingthesamevayiabledefinitions,tge-/2 LLD Sr-90 (pCi/1) = 4.66* ( X+Y), + (X1+Yl)*F1 W 1' W1' Calculation of Sr-89 Activity: Sr-89 Results (pCi/1) = fl6/R (2.22) * (E) * (1.0922) * (S7) * (V) * (U) * (F9) = W3 1.052 - 0.00272*M - 0.00005*M2 (This is nomalized Sr-89 efficiency S7 = regression equation for one particular gas proportional counter) lil - f17* (1 + R1*II) 14 6 = (ll2 - Fl*fil)/W1 (This represents counts due to Sr-90) 11 7 = 2 Ratio of Sr-89 efficiency at thickness value of 15 mg/cm to Sr-90 1.0922 = counting standard efficiency (This standard is run with each group of environmental strontium samples) EXP((-0.693/50.5)*t) F9 = Elapsed time from midpoint of collection period to time of recount t = for milk samples only. For all other samples, this mpresents the elapsed time from sample stop date to time of mcount. Half-life of Sr-89, days 50.5 = All other variables are as originally defined 127

I The 2-sigma error for Sr-89 (pCi/1) = 2* (S8 +S9 )1/2 *W3 2 2 (lil - f47* (1+R1*I1)) 2 1/2 S8.= + (X1+) )*F1 .(X1+Y1)1/2 S9 = All other variables are as. originally defined 2 2 Keeping the same variable definitions, the LLD Sr-89 (pCi/1) = 4.66* (S8 +39 )1/2 6 s e N 128

AftALYSIS OF WATER SAf1PLES FOR TRITIUf4 Approximately 50 ml of raw sample is mixed with sodium hydroxide and potassium permanganate and is distilleg 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: Activity A (pCi/1) = (G-B) A = Background count of sample 2.22(E) (V) (T) B = Gross count of sample G = Counting efficiency E = Aliquot volume (L) V = Count time (min) T = dpm/pCi 2.22 = Efficiency (E) is computed as follows: flet cpm of spiked sample E = (ll) (D) Il = Decay factor of spike A' D = A' dpm of spike = li is determined as follows: cpm of spiked sanple N = C-(G/T) C = Gross counts of sample G = Count time (min) T = The associated error is expressed at 95% confidence limit, as follows: 1.96(G/T +B/T )1/2 2 2 2.22 (V) (E) If collection container is rinsed with distilled water (e.g., rainwater), the sample is corrected for the blank as follows: Rainwater volume (R) (S2) S1 A (pCi/1) = (G) (SI) = Sample volume V V V = Rinsewater volume 2.22(V-S2) (E) (1000) S2 = Rinse counts R = flote: G and R are corrected for background counts Samples are designated LLD if the activity is less than the following value: l/2 (4.66) (B'l LLD = 2.22 (V) (E) (T) 129 l

RADIOSTRONTIUM IN WATER Stable strontium carrier is first introduced into a two liter water sample and 4 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 chemical recovery of strontium to its true val ue.' Calculation of Sr-90 Activity: Sr-90 Results (pCi/1) N4/R = (2.22) * (E) * (0.7621) * (S6) * (V) * (U) = W2 1.4115 - 0.03409*M + 0.000443*M2 (This is normalized Sr-90 where S6 = efficiency regression equation for one particular gas propor-tional counter) 2 Thickness density of strontium carbonate precipitate, mg/cm M = 2 Ratio of Sr-90 efficiency at thickness value of 15 mg/cm to 0.7621 = Sr-90 counting standard efficiency (This standard is run with each group of environmental strontium samples) Sr-90 counting standard efficiency E = 3 Sample quantity (liters, m or kg) V = Chemical yield U = (N2 - Fl*N1)/W1 = net counts due to Sr-90 only f N4 = ((1 + R1*I2) - (1 + R1*II)*F1) W1 = 5 1 - EXP ((-0.693/2.667)*tl) Il = 1 - EXP ((-0.693/2.667)*t2) 12 = Elapsed time from Y-90 strip to first count t1 = Elapsed time from Y-90 strip to second count t2 = 130

i Half-life of Y-90, days 2.667 = 1.242 + 0.0179*M + 0.000151*M2 (This is regression equation for R1 = Y-90 eff'y/Sr-90 eff'y ratio) X - Y, where X and Y are recount gross counts and background fl2 = counts, respectively X1 - Y1, where X1 and Y1 are initial gross counts and background N1 = counts, respectively flo. of dpm's per pCi 2.22 = EXP ((-0.693/2.667)*t2) F1 = Count time of sample and blank R = Using the same variable definitions as above, the 2 sigma error for Sr-90 (pCi/1) = 2 1/2 2* (X+X) + (X1+X1)*F1 ,LWi*W2) W1' W1' (ll2-Fl*fil) Again, keepi[1g the same variable definitions, the LLD Sr-90 (pCi/1) = 2 1/2 4.66* (X+X) + (X1+Yl)*F1 W1' W 1' Calculation of Sr-89 Activity: Sr-89 Results (pCi/1) = N6/R (2.22) * (E) * (1.0922) * (S7) * (V) * (U) * (F9) = W3 1.052 - 0.00272*M - 0.00005*M2 (This is nonnalized Sr-89 efficiency S7 = regression equation for one particular gas proportional counter) N1 - fl7*(1 + R1*II) N6 = (fl2 - Fl*N1)/W1 (This represents counts due to Sr-90) N7 = 2 Ratio of Sr-89 efficiency at thickness value of 15 mg/cm to Sr-90 1.0922 = counting standard efficiency (This standard is run with each group of environmental strontium samples) EXP ((-0.693/50.5)*t) F9 = Elapsed time from midpoint of collection period to time of recount t = 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 (S8,39 )1/2 *W3 2 2 'Tha 2 sigma error for Sr-89 (pCi/1) = 2* (fil - 147* (1+R1*II)) 2 1/2 = - + (X1 )*F1 58 (X1+Y1)1/2 ~ S9 = All other variables are as originally defined Ke: ping the same variable definitions, the LLD Sr-89 (pCi/1) = 4.66* (S8 +S9 )1/2 2 2 '4 4 w \\ '(,. "", _X } \\ v

7.,

, c. -Q \\ - 3 N. 4 4 \\ t y-w 4 x

1 APPENDIX E SUfEARY OF INTERLABORATORY C0!1 PARIS 0NS 133

TABLE E-1 INTER-LABORATORY COMPARIS0flS GROSS ALPHA N1D BETA Ill WATER (pCi/ liter) and AIR PARTICULATES (pCi/ filter) SA1PLE ITIC EPA All Participants DATE R:1C # TYPE NIALYSIS 11ENl s.d. t1EN1 s.d. l1EAll s.d. J an 67011 Water a 22 2 24 6 21 6 1982 S 29 1 32 5 31 6

1 arch 70043 Water a

15 1 19 5 18 4 1982 S 19 1 19 5 20 4 March 70631 APT a 24 3 27 7 26 4 1982 6 58 2 55 5 59 8 April 72020 Water a 50 3 85 21 75 16 1982 6 93 2 (a) 106 5 106 13 May 73330 Water a 22 1 28 7 25 7 1982 6 31 3 29 5 30 6 July 76747 Water a 11 2 16 5 16 5 1982 S 22 1 23 5 21 5 Sept 81226 Water a 20 1 29 7 26 6 1982 S 34 1 40 5 38 6 Sept 81457 APT a 27 3 32 8 28 6 1982 6 38 2 (b) 67 5 61 8 Oct 83052 Water a 48 2 55 14 47 14 1982 S 101 1 81 5 76 11 Nov 84691 Water a 17 2 19 5 17 4 1982 6 22 2 24 5 24 3 Nov 91763 APT a 28 1 27 7 29+4 1982 8 64 2 59 5 66 7 I (a) Insufficient sanple to reanalyze. Probable reasons for discrepancy are incomplete transfer of sample to planchet, incorrect pipetting of sample aliquot and nonhono-9eneity of sample. (b) Calculation was verified. Sample could not be reanalyzed because it was destroyed in the strontium analysis. Gross alpha, ganna and strontium-90 for that sample were in a9reement with the EPA. 135

f TABLE E-2 IllTER-LABORATORg0l1 PARIS 0!!S GNVIA SN1PLE Rf1C EPA All Participants DATE RMC # TYPE IS0 TOPE !!EAN s.d. IlEAll s.d. !!EAll s.d. Feb 68029 Water Cr-51 <56 0 59 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 !! ilk Co-60 30 2 30 5 31 4 1982 Cs-137 28 3 28 5 30 4 Ba-140 <147 0 57 K 1530 204 1500 75 1495 178 June 74569 Water Cr-51 <72 (b) 23 5 25 13 1982 Co-60 r 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 0 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.) IllTER-LABORATOR{1g0l1 PARIS 0!lS GA!!!A SAflPLE RitC EPA All Participants DATE Rf1C # TYPE ISOTOPE f1EAll s.d. flEAfl s.d. !!EAll s.d. Oct 83052 llater Co-60 <4 0 37 1982 Cs-134 <3 25 6 11 Cs-137 21 2 20 5 20 3 Oct 33535 !! ilk I-131 47 5 42 6 40 7 1982 Cs-137 35 4 34 5 35 3 Ba-140 <31 0 25 K 1682 68 1560 78 1528 196 tiov 84177 Food 1-131 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 ng/ liter for milk and ng/ 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 C r-51. 137

TABLE E-3 INTER-LABORATORY C0f1 PARIS 0NS TRITIUf1 IN WATER pCi/ liter SN1PLE RIC EPA All Participants DATE Rtic # TYPE ANALYSIS f1EAN s.d. IIEAll s.d. t1EAli 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 Jun2 74602 Water 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 Water H-3 2007 75 1990 345 2009 233 1982 \\ 138

l TABLE E-4 INTER-LABORATORY COMPARIS0NS 10 DINE-131 IN WATER pCi/ liter 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 5.410.8 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

i TABLE E-5 INTER-LABORATORY COMPARIS0NS ) STRONTIUM-89 AND STRONTIUM-90ll 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 33 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 seca-ration technique. 140

l l l l ^ APPENGIX F SYNOPSIS OF DAIRY & '.TGETABLE GARDEN SURVEY 141 m

APPENDIX F SYN 0PSIS 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 from April survey. Since dairy farms were located within 5 miles of the site, the vegetable garden survey was perfonned to a distance of one mile. No vegetable gardens were found in this area. 143 _ _ _}}

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