ML19207C280
| ML19207C280 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/30/1979 |
| From: | RADIATION MANAGEMENT CORP. (RMC) |
| To: | |
| Shared Package | |
| ML18031A256 | List: |
| References | |
| RMC-TR-79-01, RMC-TR-79-1, NUDOCS 7909100671 | |
| Download: ML19207C280 (84) | |
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SUSQUEHANNA STEAM ELECTRIC STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGPAM I
I 1978 ANNUAL REPORT I
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Prepared for I Pennsylvania Power and Light Company I
- Radiation Management Corporation APRIL 1979 6 I
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TABLE OF CONTENTS PAGE SUFNARY ----------------------------------------- 1 INTRODUCTION ----------------------------------------- 2 PROGRAM --------------------------------.-------- 2 Sample Col 1ection ----------------------------------------- 3 Data Interpretation ----------------------------------------- 3 RESULTS AND DISCUSSION ----------------------------------------- 4 Aquatic Environment ----------------------------------------- 4 Atmospheric Environment ----------------------------------------- 5 1
Terrestrial Environment ----------------------------------------- 6 Direct Radiation ----------------------------------------- 7 9
h CONCLUSIONS -----------------------------------------
REFERENCES ----------------------------------------- 11 LIST OF TABLES ----------------------------------------- ii LIST OF FIGURES ----------------------------------------- ii LIST OF APPENDICES ----------------------------------------- ii I
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LIST OF TABLES g
NO. PAGE
- 1. Synepsis of the Susquehanna SES Radiological Environmental Monitoring Program-1978 --------------------------------- 13 g
I LIST OF FIGURES N0.
Average Concentrations of Tritium in Surface Water in PAGE l
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the Vicinity of Susquehanna SES,1973 through 1978 ------- 15 g
- 2. Gross Beta Activity in Air Particulates in the Vicinity of Susquehanna SES Site, 1978 --------------------------- 16 g
- 3. Average Ambient Radiation Levels in the Vicinity of Susquehanna SES, 1973 through 1978 ---------------------- 17 g
LIST OF APPENDICES Appendix A -
Environmental Radiological Monitoring Program g Annual Summary ---------------------------------- 19 Appendix B -
S amp l e Des i g na ti o n ------------------------------ 25 Appendix C -
Data Tables ------------------------------------- 33 Appendix D - Synopsi s of Analyti cal P rocedu res --------------- 53 Appendix E -
Results of Inter-Laboratory Comparison Program -- 67 Appendix F - Cow and Garden Survey --------------------------- 75 I
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SUMMARY
t During 1978 Radiation Management Corporation (RMC) conducted the radiological environmental monitoring program (REMP) for Pennsylvania Power and Light Company I (PP&L) for the Susquehanna Steam Electric Station (SES). This report presents the analytical results for samples taken during 1978. A total of 581 thermoluminescent dosimeter measurements and samples including surface water, fish, sediment, air I particulates, air iodine, well water, potable water, milk, food products, game and fodder crops were collected in 1978.
l A variety of radionuclides, both naturally-occurring and man-made, were detec-ted in the environs of the Susquehanna SES. In March, inmediately following the Peoples Republic of China's atmospheric nuclear weapon test, significant increases i in radionuclide concentrations in various media were observed. Annual seasonal variations tesulting from toe spring atmospheric inversion are also observed in the air particulate samples. The detection of these events shows that the Susque-I hanna SES REMP is sensitive to fluctuations in the radiological characteristics of the environment around Susquehanna SES. No other unusual radionuclide concentra-tions or ambient radiation levels were observed as part of the routine environmental I surveillance program.
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INTRODUCTION g
The Susquehanna SES will contain 2 BWR generating units, each with a capacity l of about 1050 MWe. Units #1 and #2 are scheduled for commercial operation in 1981 e and 1982, respectively. This site is located on a 1075 acre tract along the Susque-hanna River, five miles northeast of Berwick in Salem Township, Luzerne County, 3 Pennsylvania. W The area surrounding the site can be generally characterized as rural with l forest and agricultural lands predominating. More specific infomation on the dem- e ography, hydrology, meteorology and land use characteristics of the local area may be found in the Environmental Report (1), the Safety Analysis Report (2) and the j Environmental Statement - C.P. (3) for Susquehanna SES. W RMC :.s previously reported results for the radiological environmental g monitoring program (REMP) from 1972-1977 (4-9); the present document continues a the series with coverage for 1978. It presents in detail the type and number of samples analyzed, the analyses performed and the data generated. Data are g discussed and compared with those from previous years, s PROGRAM The investigational phase of the REMP began in 1972 and will continue until g 2 years prior to operation for Unit #1. At that time the preoperational phase of 5 the program will be initiated and will continue until initial criticality, when the operational phase of the program will be instituted and continue thereafter. The 3 preoperational and operational programs will be designed utilizing the guidance W in NUREG-0473, Draft Radiological Effluent Technical Specifications for BWR's (10).
The investigational phase of the program was designed:
- 1. To establish baseline radiological characteristics of the environs of Susquehanna SES for comparison with future data;
- 2. To assure that media sampled and analyzed are sensitive to fluctuations in the radiological characteristics of the Susquehanna SES environs; and 3 assure that the program will be responsive to station radioeffluent 5 discharge;
- 3. To establish potential critical pathways of station radioeffluent to man.
Samples for the 1978 REMP were taken from the aquatic, atmospheric and terrestrial environments with emphasis on those media which would yield data for the evaluation of radiation dose to man. Sediment also was sampled and a analyzed as a potentially sensitive indicator of the buildup of environmental 5 radioactivity. Specific sampling locations were chosen on the basis of potential water use, site meteorology, local demography and land uses. '
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Environmental sampling locations were divided into two classes, indicator and I control. Indicator samples are those collected at locations which are expected to manifest futpre station effects, if any exist, and were selected on the basis of distance from the site, topography, hydrology, meteorology, demography, and drainage I characteristics. Control samples are collected at locations which it is believed will be unaffected by station operation. These provide a basis by which to evaluate fluctuations in radioactivity at indicator locations in relation to natural phenomena 8 and fallout after the station is operational.
Table I summarizes the Susquehanna REMP for 1978. Appendix A describes and I summarizes the entire investigational program as performed in 1978. Appendix B des-cribes the RMC coding system, which specifies sample type and locations. Also in Appendix B, Table B-1 gives the pertinent information on individual sampling locations, I while maps B-1 and B-2 show the sampling locations. This report provides information to Pennsylvania Power and. Light Company, regulatory agencies, and the general public toward the stated objectives.
Sample Collection The aquatic environment around Susquehanna SES was examined by analyzing samples of surface water, fish and sediment. Surface water samples were collected in new unuse two gallon containers at four locations monthly. Sample containers were rinsed three I times with the sample medium prior to collection. Fish samples were collected in spring and in late sumer at both the control and the indicator locations. These samples were prepared by fillet, and frozen for shipment to RMC. Susquehanna River I sediment was sampled at three locations; near the planned outfall area, a few miles downstream in the Hess Island area and upstream near Gould Island. The biological consultants to PP&L, collected the samples and performed the species identification.
The atmospheric environment was examined by analyzing air particulates and air iodine. Air particulates were collected weekly at five locations on Gelman type-A/E, I glass fiber filters with low-volume air samplers. Air sample volumes were measured with temperature-compensated dry-gas meters. Air iodine was collected on a one inch deep Mine Safety Appliance charcoal cartridges connected in series behind the particu-I late filter at the Berwick Hospital (12E1) and the PP&L roof (7H1) locations.
The terrestrial environment was examined by analyzing samples of well water, I potable water, milk, pasture grass, game and locally grown food products. Well water and potable water samples were collected in new polyethylene containers which had been rinsed with the sample medium prior to collection. Milk and food products were pur-chased directly from local farmers. Game samples were obtained by hunting or from I' road killed animals.
l Data Interpretation The radioanalytical and ambient radiation data collected during 1978, together I with that collected previously, will be used as a baseline with which operational data may be compared. Several factors are important in the interpretation of the data. These factors are discussed here to avoid repetition in sections that follow.
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Within the data tables (Appendix C) a 95% ( 2 sigma) confidence interval is supplied for each result above the minimum detectable level (MDL). Numerically, h the MDL is equal to 3 times the square root of the dividend resulting from the background counts divided by the square of the background counting time. The a square root result is then divided by a dpq/ picocurie conversion factor, the g counting efficiency and the sample volume. The MDL is reported when the 2 sigma error exceeds 100% of the calculated activity. The 2 sigma intervals represent a the range of values into which 95% of repeated analyses of the same sample would 5 fall. The MDLs quoted for particular sample types (Table C-16) are nominal values.
The actual MDLs are calculated for each sample analyzed and will show variability a due to the amount of sample analyzcd, the length of time between sample collection g and counting, the length of time a particular sainple was counted and fluctuations in counting background.
It is characteristic of environmental monitoring data that many results occur I at or below the MDL. In this report, all results occurring at or below the relevant MDL were reported as being "less than" the MDL value.
Results for each type of sample were grouped according to the analysis performed.
Means and standard deviations of these results were calculated when applicable. The calculated standard deviations of grouped data (by location or over time) represent l sample rather than analytical variability. For these calculations any values below MDL were considered to be at the MDL. Thus, these averages were biased high and the corresponding standard deviations were biased low. Averages were not calculated l when a group of data was composed of many (>50%) MDL values.
RESULTS AND DISCUSSION I
All environmental samples and TLDs were analyzed by standard RMC procedures (11).
A synopsis of the analytical procedures used appears in Appendix D. Since the precision l and accuracy of the analytical results is of paramount importance, RMC devotes a fraction (usually 15-20%) of all analyses to quality control (QC). The results of RMC's QC program for 1978 are included in a separate RMC report (12). One important aspect in maintaining l laboratory quality control is RMC's participation in the USEPA inter-laboratory comparison program. This data appears in RMC's annual QC report and is also presented as Appendix E to this report. l The analytical results of the 1978 REMP have been divided into four categories:
aquatic, atmospheric, terrestrial and direct radiation. The individual samples and analyses within each category display the unique radiological characteristics of that l
type of environment. The analytical results for the 1978 program are summarized in Appendix A, lhe data for individual samples are presented in tabular form in Appendix C. l Aquatic Environment l
The radiological characteristics of the aquatic environs of Susquehanna SES were studied by analyzing samples of surface water, fish and sediment.
l Surface Water Susquehanna River water was sampled at three locations. Daily grab samples were I collected at 12H1 (Merck Company) then composited into a monthly sample. A monthly sample was also composited from weekly grabs at station 6S1 (near planned outfall area).
A monthly gr8 safnpl'e was collected at location 12F1 (Berwick Bridge). One additional l monthly grab surface water sample was collected at the Glen Brook Reservoir (13E1).
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Each monthly surface water sample was analyzed for beta emitters. Quarterly composites l for each location were analyzed for gamma emitters and H-3.
Concentrations of beta emitters in untreated surface water samples ranged from 1.3 l to 15 pCi/1, with 26 of 48 samples showing detectable activity. Tritium concentrations ranged between <66 and 125 pCi/1 and averaged 88 pCi/1. The gross beta results were essentially the same as those obtained in 1972 to 1977 (4-9). The average tritium' concentrations in surface water samples shows a gradual decline for this same period.
h This is likely the result of a reduction in atmospheric nuclear detonations. Average H-3 concentrations for all locations since 1973 were graphed in figure 1. A least l squares exponential curve, fit to this data, yielded a negative slope (ind :ating decay or decline) with a corralation coefficient of - 0.79. This is reasonably good correlation for environmental data. No gamma emitters were observed in any of the surface water l samples.
Fish E Various species of fish were sampled during 1978 at two locations. The species included were: brown bullhead, walleye, white sucker and channel catfish. Strontium-89 l and Sr-90 analyses were performed on the flesh portions of these samples. Strontium-89 was not detected in any of the 12 samples. Strontium-90 was detected in 4 of the 12 samples ranging between <0.004 and 0.008 pCi/g(wet).
I Gamma spectrometry of the flesh portions of all fish samples detected concentrations of two nuclides above MDL; K-40 and Cs-137. Naturally occurring K-40 was detected l in all samples and averaged 2.8 pCi/g(wet). Cesium-137 was detected in 5 of the 12 samples, ranging from <0.004 to 0.014 pCi/g(wet). All fish results were consistent with those previously found. Since the station is not in operation, and there are no other major nuclear power installations in the area, the man-made nuclides observed were attributed to nuclear weapons testing fallout.
l Sediment Sediment samples were taken from three locations in the Susquehanna River. Samples l were taken in the proposed outfall area (6A1), downstream near Hess Island (11C1) and upstream near Gould Island (2B1). All samples were analyzed by Ge(Li) gamma spectrometry.
Naturally-occurring K-40, Ra-226, and Th-232 were detected in all samples. Natu rally-l occurring Be-7 was also observed in three of the five samples analyzed. The man-made nuclides detected included Cs-137, Mn-54, Ru-106, 50-125, Ce-141 and Ce-144. Of these nuclides only Cs-137 was detected in all the samples. These nuclides have been observed l periodically throughout the investigational phase of the program. Since the station is not in operation, and there are no other major power nuclear installations in the area, the man-made nuclides observed were attributed to nuclear weapons testing fallout.
I Atmospheric Environment The atmospheric environment in the vicinity of Susquehanna SES was examined by analyzing filtered air for I-131 and samples of air particulates for beta and gamma emitters. Samples of air particulates were collected continuously on filter paper and l exchanged weekly at five stations; the biological laboratory (5S3), WSW of the site (12E1), the Mocanaqua Substation (101) near Pond Hill NE of the site (3D1), and the PP&L roof in Allentown (7H1). Air iodine was collected on Mine Safety Appliance char-l coal cartridges in series with the air particulate filter at station 12E1 (WSW of site) and analyzed for I-131. Beginning in May, airborne iodine was also collecteti on char-5
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coal cartridges at the Allentown station, 7Hl.
The gross beta concentration of each weekly sample was determined. These con- I centrations ranged from 0.018 to 0.908 pCi/ cubic meter for the on-site (SS3) samples; from 0.018 to 1.170 pCi/ cubic meter for Berwick (12E1) samples; from 0.018 to 1.930 pCi/ cubic meter for the Mocanaqua (101) samples; from 0.022 to 1.140 pCi/ cubic meter - l for Pond Hill (3D1) samples; and from 0.017 to 1.060 pCi/ cubic meter for the Allentown (7H1) samples. The annual average value was 0.094 pCi/ cubic meter for all indicator locations. The gross beta results for the Susquehanna SES site vicinity (plotted in l figure 2) show a gradual increasing trend with the approach of spring. This trend is the result of the atmospheric inversion which occurs annually during the spring season in the northern hemisphere (13) and has been observed in many recent years at l the site. The significant increase observed in March can be attributed to fallout from the Peoples Republic of China's atmospheric nuclear weapon test of March 14,.
1978. Similar increases were observed over the northeastern portion of the United l States during this period.
Quarterly composites of air particulate filters from each location were analyzed by gamma spectrometry. Naturally occurring Be-7 was detected in all 19 samples. Fall-out nuclides including Nb-95, Zr-95, Ru-103, Ru-106, Sb-125, I-131, I-132, Te-132, Cs-137, Bala-140, Ce-141 and Ce-144 were detected in many of the composites following the nuclear l weapons test which occurred in March 1978. The concentrations observed during 1978 were similar to those of 1977(9) and showed the same trends as the gross beta values of the previous years. l Of the 82 air iodine samples analyzed, only one showed detectable concentrations of I-131. When the peak of the Chinese fallout occurred during the third week of March, l iodine-131 was detected at a concentration of 0.055 and 0.070 pCi/ cubic meter.
Terrestrial Environment The terrestrial environment in the vicinity of Susquehanna SES was examined.by analyzing samples of well water, potable water, milk, food products, pasture, grass l and game.
Well Water I The two wells (the biological laboratory, 5S2; and Berwick,12F1) were sampled quarterly for tritium. Tritium levels were consistent with those observed in previous years and ranged between <69 and 138 pCi/l for the eight samples analyzed.
l Potable Water Composite samples of treated potable water samples were taken quarterly a~t 'the 3erwick and Danville Water Companies and analyzed for tritium, beta emitters, Sr-89 and l Sr-90. Tritium concentrations ranged between 75 and 152 pCi/1. This range is similar to that observed in Susquehanna River water samples (76 to 125 pCi/1). Gross beta con-centrations averaged 2.6 pCi/1. Strontium-89 activity (0.4 and 0.9 pCi/l) was detected in two of the eight samples with the MDL of the other samples ranging from 0.6 to 0.9 l
pCi/1. One sample had Sr-90 activity (0.3 pCi/1) with the MDLs ranging between 0.4 and 0.8 pCi/1. l Milk E
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I Sr-89, Sr-90 and gamma emitters. The 12 quarterly milk samples showed results which I were consistent with previous years. Iodine-131 was detected in two samples taken in March with a concentratun of 0.15 and 4.7 pCi/1. Strontium-89 was detected in 5 of the 12 samples and ranged from <1.2 to 3.5 pCi/1. Strontium-90 was detected f in all of the samples ranging between 1.1 and 12 pCi/1. The ga ma emitters K-40 (900 to 1600 pCi/1) and Cs-137 (1.9 to 7.9 pCi/l) were detected at expected environ-mental levels in all the sarples. Both the I-131 and Cs-137 activities noted are 8 the results of atmospheric nuclear weapons testing.
Food Products E A variety of food pro' ducts were sampled and analyzed for gamma emitters.
These included apples, cabbage, corn, beef', chicken and eggs. Natural K-40 I was detected in all samples at normal environmental levels and ranged betwecn 0.5 and 5.4 pCi/g(wet). All other gamma emitting nuclides were below their respective MDLs.
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i Fodder Crops During the thiki quarter of 1978 pasture grass was added to the investigational phase of the REMP. The samples collected from a local farm (1LA2) was obtained quar-terly and analyzed by gamma spectrometry. Naturally-occurring Ba-7 and K-40 were I the only nuclides observed with Be-7 ranging between 1.5 and 9.1 pCi/g-dry while the K-40 activity ranged between 3.4 and 13 pCi/g-dry.
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g Three gace samples (two squirrel and one deer) were taken and analyzed for gamma g emitters. Nacurally-occurring K-40 was detected in all samples as expected, ranging from 2.1 to 2.8 pCi/ gram (wet). Cesium-137 was also detected in all game samples at concentrations of 0.29 pCi/ gram (wet) for the deer sample and 0.57 and 2.3 pCi/g(wet)
I for the two squirrel samples. These results are similar to results obtained in pre-vious years for these sample types. This phenomenon in squirrel:. was the subject of a more detailed investigational study presented in the 1975 annual report (7).
A statis*ical analysis of the K-40 and the Cs-137 concentrations in food products versus game was performed utilizing the ganma spectrome'ty data on thme samples. The I statistical test used was the Mann-Whitney Test (the nonparametric cotsterpart of the t-test) which utilizes a system of ranking to determine whe$har two random groups of a 3 samples are from different distributions (14). At the 99% cqnfidence level, no significant 5 difference in K-40 was observed in game versus food products. At this same confidence level, Cs-137 concentrations were significantly higher in the game samples.
l Direct Radiation Direct radiation measurements were made on a quarterly basis at 9 locations I using CaSO4 (Tm) thermoluminescent dosimeters. A total of 36 auarterly TLD packets were collected and analyzed. These analyses yielded an averacy2 dose rate of 6.02 mrads/ standard month. All TLD results presented in this report I have been normalized to a standard month (30.4 days) 3.c eliminate the apparent differences in data caused by the variations in exposure periods.
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1 The projected annual dose from direct radiation computed from these results is about 72 nrads, or 72 mrems assuming a quality factor of 1. The EPA terrestrial h and cosmic radiation dose rate calculated for the Wilkes-Barre area is 82 mrem / year, neglecting any neutron contribution (15). This compares with the average TLD measured dose rate of 72 mrem / year. This difference is not unexpected since the EPA values are gross general averages for an area and do not take into consideration l
specific terrestrial variations. Although the total annual dose appears to be a increasing from 1974 to the present (67 to 72 mrads), the increase is probably 5 attributed to normal environmental variability due to the terrestrial component of the total dose and also to program TLD station changes. The TLO's agree with the Shonka measurements taken in 1978 which indicate a slight increase in dose l from 1973 (16). The monthly average dose rates for all monitoring locations sir.ce 1973 are plotted in Figure 3. The differences observed between locations or between sampling periods were similar to those found previously (4-9). l I
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CONCLUSIONS The Radiological Environmental Monitoring Program for Susquehanna SES was conducted during 1978 as a continuation of the program initiated in 1972. The I data collected during 1978 further develops a baseline for comparison with future operational data.
From the results obtained and the analysis performed on the data it can be concluded that the levels and fluctuations of radioactivity in environmental samples were as expected for this environment. Aquatic samples consisting of I surface water, aquatic organisms, and sediment were chosen and reflect the normal background radiation found in this environment. Charcoal cartridges used to de-tect the presence of airborne iodine along with airborne particulate matter were I also analyzed. Airborne radiciodine was observed in one sample and was attributed to the atmospheric nuclear test on March 14, 1978. The particulate matter was sim-ilar to that observed throughout the Northeast portion of the country. In addition I milk, well water, drinking water, game and various food products, including green leafy vegetables were sampled. The results obtained from the analyses of these
,a samples were similar to the expected values of radioactivity usually associated y with the samples. Radioiodine was observed in two milk samples that were collected and analyzed immediately following the atmospheric nuclear test of March 14, 1978.
The activity detected was attributed to that test. Direct radiation levels were 8 relatively low and approximately the same at all locations. Based on the analyses of these samples it can be concluded that no unusual radiological characteristics were observed in the environs of the Susquehanna Steam Electric Station.
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I I REFERENCES E (1) Pennsylvania Power and Light Company, "Susquehanna Steam Electric Station Applicant's Environmental Report," Operating License l Stage, May 1978.
Pennsylvania Power and Light Company, "Susquehanna Steam Electric (2)
Station, Final Safety Analysis Report," 1978.
l (3) United States Atomic Energy Commission, Directorate of Licensing, l " Final Environmental Statement Related to the Construction of Susquehanna Steam Electric Station Units 1 and 2," Docket-Nos.
50-387 and 50-388, June 1973.
(4) Radiation Management Corporation, "Susquehanna Steam Electric Station, Radiological Environmental Monitoring Program, Report l #1 (April - December 1972)" RMC-TR-73-14, July 1973.
Radiation Management Corporation, "Susquehanna Steam Electric (5)
Station, Preoperational Radiological Environmental Monitoring l Program 1973," RMC-TR-74-07, May 1974.
(6) Radiation Management Corporation, "Susquehanna Steam Electric l Station, Preoperational Radiological Environmental Monitoring Program,1974 Annual Report," RMC-TR-75-07, April 1975.
(7) Radiation Management Corporation, "Susquehanna Steam Electric Station, Radiological Environmental Monitoring Program,1975 g Annual Report," RMC-TR-76-05, May 1976.
(8) Radiation Management Corporation, "Susquehanna Steam Electric Station, Radiological Environmental Monitoring Program,1976 1 Annual Report," RMC-TR-77-04, March 1977.
I (9) Radiation Management Corporation, "Susquehanna Steam Electric Station, Radiological Environmental Monitoring Program,1977 Annual Report," RMC-TR-78-01, May 1978.
(10) United States Nuclear Regulatory Commission, NUREG-0473, Draft Radiological Effluent Technical Specifications for BWR's Revision g 1, October 1978.
(11) Radiation Management Corporation, " Analytical and Quality Control Program," RMC-TM-75-3, 1975.
(12) Radiation Management Corporation, " Quality Control Data - 1978 Annual Repart", February 1979.
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REFERENCES (cont.)
(13) United Nations Scientific Committee on the Effects of Atomic Radiation, Ionizing Radiation: Levels and Effects, Volume 1:
I Levels, United Nations Publication, New York,1972.
l (14) Conover, W. J., Practical Nonparametic Statistics, John Wiley
& Sons Inc. , New York,1971.
l (15) Oakley, Donald T., Natural Radiation Exposure in the United States, ORP/SID 72-1, United States Environmenial Protection Agency, June 1972.
(16) Radiation Management Corporation " Environmental Dose Rate Measurements in the Vicinity of Susquehanna Steam Electric Station," RMC-TR-78-07, May 1978.
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I I TABLE 1 SYNOPSIS OF THE SUSQUEHANNA SES RADIOLOGICAL ENVIkONMENTAL MONITORING PROGRAM 1978 i SAMPLE SAMPLING NUMBER ANALYSIS NUMBER TYPE FREQUENCY LOCATION COLLECTED TYPE FREQUENCY PERFORMED AQUATIC ENVIRONMENT Surface Water M 4 48 Gross Beta M 48 H-3 QC 16 Gama QC 16 Fish SA 2 12 Gama SA 12 (Flesh) Sr-89 SA 12 Sr-90 SA 12 Sediment SA 3 5 Gama SA 5 ATMOSPHERIC ENVIRONMENT Air Particulates W 5 249 Gross Beta W 249 Gamma QC 20 Air Iodine W 2 82 1-131 W 82 TEkRESTRIAL ENVIRONMENT Well Water Q 2 8 H-3 ) 8 Drinking Wat'er Q 2 8 H-3 0 8 Gross Beta Q 8 Sr-89 Q 8 Sr-90 Q 8 Milk 3 12 1-131 0 12 i Q Sr-89 Q 12 Sr-90 Q 12 Gama Q 12 Fodder Crops Q 1 2 Gama Q 2 I Food Products A 4 5 Gama A 5 Game A 2 J Gama A 3 Beef and Poultry SA 2 4 Gama SA 4 DIRECT RADIATION Dosimeters (TLDs) Q 9 144 Gama dose rate Q 144 I
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I APPENDIX A ENVIPONMENTAL RADIOLOGICAL MONITORING PROGRAM I ANNUAL
SUMMARY
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WWWM MM M M MM M M M M M M M M M M MM APPENDIX A ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL SLFtiARY Susquehanna SES Docket No.: 50-387 & 50-388 y Luzerne, Pa. January 1 to December 31, 1978 TYPE AND MINIMUM NUMBER OF KDIUM OR PATHWAY TOTAL NUMBER DETECTABLE ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES LEVEL MEAN (2) NAME MEAN (2) MEAN (2) REPORTED (UNIT OF MEASUREMENT) PERFORMED (MDL) (1) RANGE DISTANCE & DIRECTION RANGE RANGE MEASUREMENTS e
Surface Water Gross Beta 48 1.3 4.0 (26/48) 12F1 5.2 mi WSW 4.8 (8/12) N/A 0 (pC1/1) (2.5-15) (2.6-15)
H-3 16 77 101 (7/16) 12F1 5.2 mi WSW 125 (2/4) 0 (76-125) (125)
Gamma 16 None Detected N/A Well Water H-3 8 69 106 (6/8) 12F2 5.2 mi WSW 112 (4/4) N/A 0 y (pCi/1) (78-138) (78-138)
Drinking Water H-3 8 79 101 (5/8) 12F2 5.2 mi WSW 127 (3/4) N/A 0 (pC1/1) (75-152) (106-152)
Gross Beta 8 1.7 3.1 (5/8) 12H2 20 mi WSW 3.3 (3/4) 0 (2.2-4.5) (2.2-4.5)
S r-89 8 0.0 0.7 (2/8) 12H2 20 mi WSW 0.7 (2/4) 0 (0.4-0.9) (0. 4-0.9 )
Sr-90 8 0.4 - (0/8) N/A 0 Fish Sr-89 12 0.01 - (0/12) N/A 0 (pCi/g-wet) -
" r-90
, 12 0.004 0.007 (1/6) IND 0.9 mi ESE 0.007 (1/6) 0.005(3/6) 0 (0.007) (0.007) (0.004-0.008)
.a Ganma 12 2.7 (6/6) IND 0.9 mi ESE 2.7 (6/6) 2.8(6/6) 0 1b8f K-40 -
- - (2.3-3.3) (2.3-3.3) (1.6-4.0)
C;s Q Cs-137 0.005 0.010 (2/6) IND 0.9 mi ESE 0.010 (2/6) 0.012 (3/6) O
- p. (0.007-0.013) (0.007-0.019) (0.008-0.014) 2 a
APPENDIX A ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL
SUMMARY
Susquehanna SES Docket. 50-387 & 50-388 g Luzerne, Pa. January 1, to Decent >er 31, 1978 TYPE AND MINIMUM NUMBER OF MEDIUM.0R PATHWAY TOTAL NUMBER DETECTABLE ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LCCATIONS NONROUTINE SAMPLED OF ANALYSES LEVEL MEAN (2) NAME MEAN (2) MEAN (2) REPORTED (UNITOFMEASUREMENT) PERFORMED (MDL) (1) RANGE DISTANCE & DIRECTION RANGE RANGE KASUREMENTS Sediment Gamma 5 (pCi/g(dry) Be-7 0.2 0.5 (2/4) 6A2 0.8 mi ESE 0.5(2/2) 0.4 (1/1) 0 (0.4-0.6) (0.4-0.6) (0.4)
K-40 -
10.4 (4/4) 6A2 0.8 mi ESE 11.6 (2/2) 11 (1/1) 0 (9.1-14) (9.1-14) (11)
Mn-54 0.02 0.02 (2/4) 6A2 0.8 mi ESE 0.2 (1/2) - (0/1) 0 (0.02) (0.2) -
Ru-106 0.2 0.4 (1/4) 6A2 0.8 mi ESE 0.4 (1/2) 0.3 (1/1) 0 (0.4) (0.4) (0.3)
Sb-125 0.05 0.06 (1/4) 6A2 0.8 mi ESE 0.06 (1/2) - (0/1) 0 (0.06) (0.06) -
Cs-137 -
0.15(4/4) 6A2 0.8 mi ESE 0.17 (2/2) 0.21(1/1) 0 N" (0.06-0.25) (0.09-0.25) (0.21)
Ce-141 0.03 - (0.4) 281 1.6 mi NNE 0.03(1/1) 0.03 (1/1) 0 (0.03) (0.03)
Ce- 144 0.02 0.5 (1/4) 6A2 0.8 mi ESE 0.5 (1/2) 0.4 (1/1) 0 (0.5) (0,5) (0.4)
Ra-226 -
0.74 (4/4) 6A2 0.8 mi ESE 0.80 (2/2) 0.78 (1/1) 0 (0.66-0.92) (0.68-0.92) (0.78)
Th-232 -
0.85 (4/4) 6A2 0.8 mi ESE 0.9 (2/2) 0.84 (1/1) 0 (0.78-1.0) (0.8-1.0) (0.84)
Air Iodine I-131 82 2.5 55 (1/52) 12E15.1 mi WSW 55(1/52) - (0/30) 0 (10-3pCi/m 3) (55) (55) -
Air Particulates Gmss Beta 249 5 97 (249/249) 1D1 3.7 mi N 114 (41/41) 102 (52/52) 0 (10-3 pC1/m3 ) (17-1930) (18-1930) (17-1060)
Garuna 19 Be-7 -
69 (15/15) 3D1 3.2 mi NE 79 (4/4) 59 (4/4) 0 (54-105) (63-106) (40-70)
Zr-95 1.0 2.4 (5/15) 553 0.7 mi E 4.9 (1/4) 2.3 (2/4) 0 Q (1.2-4.9) (4.9) (1.6-2.9)
Q Nb-95 0.6 2.9 (7/15) 12E1 5.1 mi WSW 3.4 (2/4) 2.2 (2/4) 0 X (2.2-4.5) (2.2-4.5) (1.7-2.7)
Ru-103 0.6 ) 12E1 5.1 mi WSW 1/4) 1/4) 0 C
se es m me em m es se m We e as m es es e se en m eE' *<
WW WWW M W m MM M M M M M M M M M M MM APPENDIX A ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL SLNMARY Susquehanna SES Docket No.- 50-387 & 50-388 Luzerne, Pa. January 1 to Decerter 31, 1978
'g.
I TYPE AND MINIMUM NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER DETECTABLE ALL INDICATOR LOCATIONS LOCATION WITH' HIGHEST ANNUAL MEAN CONTROL LOCATIONS NONROUTINE SAMPLED OF ANALYSES LEVEL MEAN (2) NAME MEAN (2) MEAN (2) REPORTED PERFORMED (MDL) (1) RANGE DISTANCE & DIRECTION RANGE RANGE MEASUREMENTS (UNIT OF MEASUREMENT)
Air Particulates Ru-106 6.0 12 (7/15) 3D1 3.2 mi NE 13 (2/4) 10 (2/4) 0 (10-15) (11-15) (8-11)
-3 pCi/m3 ) 3.5 (1/4) 2.3 (1/4) 0 (10 Sb-125 1.0 3.2 (5/15) 12E1 5.1 mi WSW (2.3 4.1) (3.5) (2.3) 1-131 3.4 7.8 (3/15) 3D1 3.2 mi NE 8.7 (1/4) 9.6 (1/4) 0 (7.3-8.7) (8.7) (9.6)
I-132 0.5 0.8 (2/15) 12E1 5.1 mi WSW 0.9 (1/4) - (0/4) 0 (0.6-0.9) (0.9) -
Te-132 0.3 9.1 (2/15) 12E1 5.1 mi WSW 14 (1/4) - (0/4) 0 (4.2-14) (14) -
to Cs-137 0.8 2.1(12/15) 553 0.7 mi E 3.2 (3/4) 1.8(4/4) 0 W (1.0-4.8) (2.0-4.8) (1.2-2.5)
Bala-140 0.7 11 (3/15) 12E1 5.1 mi WSW 13 (1/4) 10 (1/4) 0 (8.1-13) (13) (10)
Ce-141 1.0 2.9 (7/15) 7H1 47 mi SW 5.5 (1/4) 5.5 (1/4) 0
( 0. 6- 5. 3) (5.5) (5.5)
Ce-144 4.0 29 (12/15) 3D1 3.2 mi NE 31 (2/4) 15 (4/4) 0 (4-42) (20-42) (5-21)
Milk S r-89 12 1.2 2.4 (5/8) 12B2 1.2 mi WSW 2.8 (2/4) - (0/4) 0
[3 7 (pCi/l)
S r-90 12 -
( 1. 5-3. 5) 5.3 (8/8) 1282 1.2 mi WSW (2.1-3.5) 8.3 (4/4) 4.7 (4/4) O C" (1.1-12) (4. 5-12 ) (2.8-8.2)
Cd I-131 12 0.04 2.4 (2/8) 1202 1.2 mi WSW 4.7 (1/4) - (0/4) 0 N ( 0.15-4. 7 ) (4.7) -
O Gama 12 K-40 -
1250 (8/8) 12B1 1.7 mi WSW 1325 (4/4) 1375 (4/4) 0 (900-1600) (1000-1600) (1000-1700)
Cs-137 -
5.2 (8/8) 1202 1.2 mi WSW 6.9 (4/4) 4.9 (4/4) 0 (1.9-7.9) (6.0-7.9) (1.9-9.8) 1 Fodder Crops Gama 2 (pCi/g-dry) B e- 7 -
5.3 (2/2) 15A2 0.8 mi NNW 5.3 (2/2) No Control 0 (1.5-9.1) (1.5-9.1) Location
,A K-40 -
8.2 (2/2) 15A2 0.8 mi NNW 8.2 (2/2) 0 (3.4-13) (3.4-13)
i APPENDIX A ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL SlJiMARY Susquehanna SES Docket No.: 50-387 & 50-383 Luzerne, Pa. January 1 to December 31, 1978 TYPE AND MINIMUM NUPEER OF MEDIUM OR PATHWAY TOTAL NtNBER DETECTABLE ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATIONS NONROUTINE SAMPLED OF ANALYSES LEVEL MEAN (2) NAME MEAN (2) MEAN (2) REPORTED (UNIT OF MEASUREMENT) PERFORMED (MDL) (1) RANGE DISTANCE & DIRECTION RANGE RANGE MEASUREMENTS Fruit & Vegetables Gansna 5 (pCi/g-dry) K-40 -
1.5 (4 4) ZH1 21 mi NNL 2.8 (1/1) 2.8 (1/1) 0 (0.5-2.5) (2.8) (2.8)
Game Ganina 3 N .(pCi/g-wet)
K-40 2.5 (3/3) - Site Vicinity 2.8 (1/1) N/A 0 (2.1-2.8) (2.8)
Cs-137 1.1 (3/3) Site Vicinity 2.3 (1/1) 0 (0.3-2.3) (2.3)
Meat & Poultry Gamma 4 (pCi/g-wet) K-40 2.4 (4/4) 12B2 1.2 mi WSW 5.4 (1/1) N/A 0 (1.0-5.4) (5.4) knbient Radiation TLD 36 0.1 6.3 (28/28) 12F1 5.2 mi WSW 7.39 (4/4) 4.99 (8/8) 0 (mrem) (', .46-7. 96 ) (7.22-7.55) (4.35-5.85)
- 1 (1) The MDLs quoted are the lowest actual MDLs obtained in the various media during the reporting period. A typical gamma MDL was determined for N each searched for nuclide as found on Table C-16. Where all nuclides were >MDL for a specific media no MDL was listed.
C Q (2) Mean and range based upon detectable measurements only. Fraction of detectable measurements is indicated in parentheses.
N P
m se me es as es se en es as am se sus as em se e es aus e es ans
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I APPEtlDIX B SAtiPLE DESIGilATI0tl I
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I APPENDIX B I Table B-1 lists the samoling locations and includes both the distance and direction from the Susquehanna SES and the media sampled at each location.
Maps B-1 and B-2 show the sampling locations with respect to the Susquehanna SES.
Samole Designation Samoles are identified by a three part code. The first two letters are the power station identification code, in this case "SS" for Susquehanna Steam Electric Station. The next three letters are for the media samoled.
AIO = Air Iodine FPP = Food Products, Poultry A0F = Fish GAD = Gane, Deer I AOS = Sedinent GAS = Gane, Squirrel APT = Air Particulates IDM =
Imersion Dose (TLD)
FPB = Food Products, Beef MLK = Milk E FPE = Food Products, Eggs PAS = Pasture Grass FPF = Food Products, Fruit PWT = Potable Water, Treated FPG = Food Products, Grain SWA = Surface Water FPL = Food Products, Leafy Vegetables WWA = Well Water I The last four synbols are a location code based on direction and distance from the site. Of these, the first two represent each of the 16 angular sectors of 22-1/2 degrees centered about the reactor site. Sector one is divided evenly I 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 station:
S = On-site location E = 4-5 miles off-site A = 0-1 miles off-si te F = 5-10 miles off-site B = 1-2 miles off-si te G = 10-20 miles off-site C = 2-3 miles off-si te H = >20 miles off-site D = 3-4 miles off-si te The last number is the station numerical designation within each sector and zone; e.g. 1, 2, 3, . . . .
Specific information about the individual sampling locations is given in I table B-1.
to the site.
Maps B-1 and B-2 show the locations of sampling stations with respect F<'0323 27 I
I TABLE B-1 SUSQUEHANNA SES RADIOLOGICAL ENVIRONMENTAL 00NITORING PROGRAM SAMPLIrlG LOCATIONS i
1978 LOCATION SAMPLE CODE DESCRIPTION
- TYPES I
IND** 0.8 mile , 0utfall Area AQF 2S1 0.7 mile NNE, Near Site Boundary GAS 3S1 0.8 mile NE, Off Route 11 0.8 mile ENE, Off Route 11 IDM, GAD IDM l
4S1 SS1 0.7 mile E, North ;f Biological Consultants ID; SS2 L 4 mile, E Site - Peach Stand 0.7 mile E, Site - Biological Consultants WWA APT l
SS3 651 0.1 mile ESE, Outfall Area SWA 7S1 0.3 mile SE, On 230 KV tower IDM g 1151 0.3 mile SW, On 230 KV tower IDM 6A2 0.8 mile ESE, Outfall Area AQS 15A2 0.8 mile NNW, Local Farm, At Site Boundary PAS 2B1 1.6 mile NNE, Gould Island AQS 7B1 1.5 mile SE, Heller Orchard FPF 12B1 1.7 mile WSW, Shultz Fara MLK, FPA, FPG 1282 1.2 mile WSW, Young Farm MLK, FPE, FPP 1283 1.4 mile WSW, Kisner Farm FPB 1101 2.0 mile SW, Hess Island AQS 101 3.7 mile N, Near Moquanaqua Substation IDM 3D1 3.2 mile NE, Pond Hill APT 11D1 4.3 mile SW, Vegetable Farm FPL gmu 28 I
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TABLE B-1 (cont.)
I SUSQUEHANNA SES RADIOLOGICAL ENVIRONMENTAL MONITORING PP,0GPAM SAMPLING LOCATIONS 1978 I LOCATION SAMPLE CODE DESCRIPTION
- TYPES I
12E1 5.1 mile WSW, Berwick Hospital APT, AIO 13E1 4.5 mile W, Glen Brook Reservoir SWA 12F1 5.2 mile WSW, Berwick ID'i, SWA 12F2 5.2 mile WSW, Berwick Water Co. WWA, PWT I 2G1 30 mile NNE, Near Falls, PA AQF 9G1 19 mile S, Davis Farm MLK 2H1 21 mile NNE, Vegetable Stand FPL I 7H1 47 mile SE, PP8L . roof, Allentown APT, AIO, IDM 7H2 40 mile SE, Crystal Springs Dairy MLK 8H1 92 mile SSE, RMC roof, Philadelphia ID I 12H1 26 mile WSW, Merck Co. SWA l 12H2 26 mile WSW, Danville Water Company PWT l
- All distances measured from vent.
No actual location is indicated since fish are sar. pled over an area which l extends through 3 sectors (5, 6 and 7) near the outfall area.
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MAP B -1 ON SITE EfWIRONMt.1TAL SAMPLIiG g
[ LOCATIONS - SUSQl;EHANilA SES
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APPENDIX C DATA TABLES I
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APPENDIX C DATA TABLES TABLE PAGE N0. TABLE TITLE Aquatic Environment C-1 Concentrations of Beta Emitters in Surface Water Samples in the vi ci ni ty of Susquehanna SES ----------------------------- 37 C-2 Concentrations of Gamma Emitters in Quarterly Composite l Samples of Surface Water in the vicinity of Susquehanna SES ---- 38 C-3 Concentrations of Tritium in Quarterly Composite Samples I of Surface Water in the vicinity of Susquehanna SES ------------ 38 C-4 Concentrations of Garmia Emitters and Sr-89 and Sr-90 in l Fish Flesh in the vicini ty of Susquehanna SES ------------------ 39 C-5 Concentrations of Gantia Emitters in Sediment Samples from the l Susquehenna River in the vicinity cf Su:quehanna SES ----------- 40 Atmospheric Environment C-6 Concentrations of Beta Emitters in Air Particulate Samples i n the vi ci ni ty o f Susquehanna SES -------------------------- 41 C-7 Concentrations of Gamma Emitters in Quarterly Composites of Air Particulate Samples in the vicinity of Susquehanna SES --------- 43 C-8 Concentrations of I-131 in Filtered Air in the vicinity of Susquehanna SES ------------------------------------------------ 45 Terrestrial Environment C-9 Concentrations of Tritium in Well Water in the vicinity of Susquehanna SES ------------------------------------------------ 46 C-10 Concentrations of Tritium, Beta Emitters and Sr-89 and -90 in Potable Water Samples from the vicinity of Susquehanna SES ----- 46 C-11 Concentrations of Strontium-89, Strontium-90 and Gamma Emitters in Mil k i n the vi'cini ty of Susquehanna SES --------------------- 47 I C-12 Concentrations of I-131 in Milk in the vicinity of Susquehanna SES ----------------------------------------------------------- 48 I C-13 Concentrations of Gantia Emitters in Fodder Crops in the vicinity o f S u sq u e h a n n a SE S --------------------------------------------- 48 I C-14 Concentrations of Gamma Emitters in Various Food and Game Sampl es i n the vi cini ty of Susquehanna SES --------------------- 49
~
35 370329 'JWWWBC I
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APPENDIX C (cont.)
DATA TABLES TABLE NO. -
TABLE TITLE PAGE l
. g Direct Radiation g C-15 Results of Quarterly TLD Measurc= cats in the vicinity of Susquehanna SES ----------------------------------------------- 50 C-16 Typi cal MDLs for Ganma Spectrometry --------------------------- 51 I
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mmW me e e m W Wmm e em W W W m W WW TABLE C-1 CONCENTRATIONS OF BETA EMITTERS IN SURFACE WATER SAMPLES 4, IN THE VICINITY OF SUSQUEHANNA SES Results in Units of pCi/l 2 sigma STATION NO. JANUARY FEBRUARY MARCH APRIL MAY JUNE SS-SWA-6S1 2.6 2.2 2.7 1.8 8.812.4 <2.1 4.3 2.1 3.7 2.0 SS-SWA-12F1 3.6 2.3 2.6 1.8 15 3 <2.1 <1.8 3.1 1.9 SS-SWA-12H1 <3.0 2.6 1.8 6.2 2.2 <2.1 <1.8 3.3 2.0 c3 SS-SWA-13E1 <3.0 <1.6 3.5 2.0 <2.1 <1.8 1.9 1.8 w
Average 3.1 0.8 2.4 1.0 8.4 9.8 <2.1 2.4 2.5 3.0 1.6 C.O
=; STATION NO. JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE C3 C.)
C.: SS-SWA-12F1 <2,7 2.5 1.4 3.1 1.8 3.7 2.2 4.2 2.2 <2.5 3.6 3.6 y.
SS-SWA-12F1 <2.7 3.2 1.4 2.7 1.8 3.3 2.2 4.5 2.2 <2.5 3.9 7.1 SS-SWA-12H1 <2.7 2.6 1.4 3.3 1.8 4.2 2.3 3.8 2.2 <2.5 3.2 2.3 SS-SWA-13E1 <2.7 <1.3 <1.6 <2.0 <1.9 <2.5 2.2 1.3 Average <2.7 2.4 1.6 2.7 1.5 3.3 1.9 3.6 2.3 <2.5 3.2 4.3
I TABLE C-2 I
CONCENTRATIONS OF GAMMA EMITTERS
- IN OUARTERLY COMPOSITE SAMPLES OF SURFACE WATER IN THE VICINITY OF SUSQUEHANNA SES Results in Units of pCi/l 2 signa JAN APRIL JULY OCT to to to to STATION N0. MARCH JUNE SEPT DEC SS-SWA-6S1 All <MDL All <t0L All (MDL All <MDL SS-SWA-12F1 All <MDL All <MDL All <MDL All <MDL SS-SWA-12H1 All <MDL All <f0L All <MDL All <MDL SS-SWA-13El All <MDL All <MDL All <MDL All <MDL Typical MDLs are given in Table C-16.
I TABLE C-3 CONCENTRATIONS OF TRITItJ1 IN QUARTERLY COMPOSITE SAMPLES OF SURFACE WATER IN THE VICINITY OF SUSQUEHANNA SES Results in Units of pCi/l 2 signa I
J A*1 APRIL JULY OCT ANNUAL STATION to to to to AVERAGE NUMBER MARCH JUNE SEPT DEC SS-SWA-6S1 110 75 <80 91263 89 73 93 25 SS-SWA-12F1 <79 125 76 125 67 <77 102 54 SS-SWA-12H1 76;75 <80 92 70 <77 81 15 SS-SWA-13El <79 <80 <66 <77 76 13 Quarterly 86t32 91 45 94 48 80 12 88 35 Average woaaz I I
n
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W W W W W W W m W W W W W W M M M M M e M M TABLE C-4 CONCENTRATIONS OF GAMMA f.TTERS* AND STRONTIUM-89** AND -90 IN FISH FLESH IN THE VICINITY OF SUSQUEHANNA SES Results in Units of pCi/g(wet) 2 sigma c
?
STATION SAMPLE SAMPLE 6 NUMBER TYPE DATE Sr-89 Sr-90 K-40 Cs-137 SS-AQF-IND Bullhead 5-08-78 <0.01 <0.006 2.3 0.2 0.007 0.006 SS-AQF-IND Walleye 5-08-73 <0.01 <0.006 2.610.3 <0.005 SS-AQF-IND White Sucker 5-08-78 <0.01 <0.007 2.4 0.2 <0.004 SS-AQF-IND Channel Catfish 9-13-78 to <0.01 <0.004 3.3 0.3 0.013 0.007 9-14-78 -
SS- AQF-IN D White Sucker 9-20-78 <0.02 0.007 0.004 2.7 0.3 <0.004 SS- AQ F-IND Walleye 9-20-78 to <0.01 <:.005 3.0 0.3 <0.005 10-17-78 co SS- AQF-IN D Channel Catfish 5-10-78
")
to <0.01 <0.006 1.6 0.2 0.013 0.007 5-12-78 SS-AQF- 2G1 Walleye 5-10-78 to <0.01 0.004 0.004 2.2 0.2 0.014 0.006 5-12-78 SS-AQF-2G1 White Sucker 5-10-78 to <0.02 0.008 0.006 4.010.4 <0.004 5-12-78 SS-AQF-2G1 Channel Catfish 9-27-78 to <0.01 <0.005 2.8 0.3 0.008 0.007 9-28-78 SS-AQF-2G1 White Sucker 9-27-78 <0.01 0.004 0.003 2.8 0.3 <0.006 (Q SS-AQF-2G1 Walleye 9-27-78 <0.02 <0.005 3.3 0.3 <0.005 C
Q CJ Q
- All other gamma emitters searched for were <MDL; typical MDLs are given in Table C-16.
- Sr-89 results are decay corrected to the sample stop date.
l 1
TABLE C-5 CONCENTRATIONS OF GAMMA EMITTERS
- IN SEDIMENT SAMPLES FROM THE SUSQUEHANNA RIVER IN THE VICINITY OF SUSQUEHANNA SES Results in Units of pCi/g(dry) 2 sigma STATION NO. SS-AQS-6A2 SS-AQS-11C1 SS-AQS-201 DATE 5-22-78 9-12-78 5-22-78 9-12-78 9-26-78 Be-7 0.4!0.2 0.610.3 <0.1 <0.2 0.4 0.2 K-40 9.1 0.9 1411 9.3 0.9 9.1 0.9 11 1 Mn-54 0.02 0.02 <0.02 0.02 0.01 <0.02 <0.02 Ru-106 <0.2 0.4 0.? <0.1 <0.1 0.3 0.2 Sb-125 <0.05 0.06 0.05 <0.04 <0.05 <0.05 Cs-137 0.09 0.02 0.25 0.03 0.19 0.03 0.06 0.03 0.21 0.03 Ce-141 <0.03 <0.02 <0.02 <0.03 0.03 0.02 Ce-144 <0.1 0.5t0 1 <0.09 <0.1 0.4 0.1 Ra-226 0.68 0.07 0.92 0.09 0.66 0.07 0.70 0.07 0.78 0.08 Th-232 0.8 0.1 1.0 0.1 0.84 0.09 0.78 0.09 0.84 0.09 I
All other garm1a emitters searched for were <MDL; typical HDLs are given in Table C-16.
I I
I I
I
,.xj0334 1
I e sii m m 40 I
I
W W W W W W W W W W W W W W W W W W W W W W TABLE C-6 COECENTRATICNS OF BETA EMITTERS IN AIR PARTICULATE SAMPLES IN THE VICINITY OF SUSQUEHANNA SES 3
Results in Units of 10-3 pEi/m t 2 signa SAMPLE SAMPLE STATION NO. SAMPLE SAMPLE STATION N0, START DATE STOP DATE SS-APT-553 SS-APT-12E1 SS-APT-3D1 SS-APT-ID1* AVE RAGE *
- START DATE STOP DATE SS-APT-7H1 12-31-77 1-07-78 70 7 67 7 80t8 72114 1-01-78 1-11-78 171220 1-07-78 1-15-78 5325 55t5 50t5 53!5 1-11-78 1-17-78 68t7 1-15-78 1-22-78 83 8 8619 88t9 86t5 1-17-78 1-23-78 88 9 1-22-78 1-28-78 8619 78 8 74 7 79212 1-23-78 1-30-78 5626 1-28-78 2-04-78 6116 59 6 57 6 59t4 1-30-78 2-08-78 5516 2- 04 -78 2-11-78 70 7 74 7 76t8 73!6 2-08-78 2-13-78 78t8 2-11-78 2-19-78 6126 64!6 58t6 61t6 2-13-78 2-21-78 4815 2-19-78 2-26-78 60 6 6226 6126 61t2 2-21-78 2-28-78 6817 45
- 2-26-78 84!8 3- 04 -78 89 9 87!9 87!5 2-28-78 3-06-78 94t9 3-04-78 3-11-78 111t11 114!11 110t11 11234 3-06-78 3-13-78 117 12 3-11-78 3-18-78 73 7 6226 77!8 71t16 3-13-78 3-20-78 89t9 3-18-78*** 3-24-78 908 91 1170t120 1140 110 1930t190 1287 889 3-20-78 3-27-78 10602110 3-24-78 4-01-78 149 15 144214 155t15 159216 152113 3-27-78 4-03-78 214!21 4-01-78 4-07-78 126i13 133213 131113 132 13 131t6 4-03-78 4-10-78 181118 4-07-78 4-14-78 181 18 171 17 192!!9 165 17 177 24 4-10-78 4-17-78 265!27 4-14-78 4-22-78 62 6 66 7 65t7 65 7 65 3 4-17-78 4-24-78 222!22 4-22-78 4-30-78 182118 194 19 193t19 183t18 188113 4-24-78 5-01-78 199120 4-30-78 5-07-78 129 13 127 13 124 12 117212 124 11 5-01-78 5-08-78 153115 5-07-78 5-13-78 72 7 56 6 6326 62 6 63t13 5-D8-78 5-15-78 71 7 5-13-78 5-20-78 39 4 4124 37!4 37 4 39!4 5-15-78 5-22-78 9129 5-20-78 5-27-78 119!12 124t12 132113 118t12 123 13 5-22-78 5-30-78 83 8 5-27-78 6-03-78 80 8 7928 79t8 85t9 8126 5-30-78 6-05-78 143!14 6-03-78 6-11-78 99 10 117 12 108t11 102 10 107!16 6-05-78 6-12-78 130213 6-11-78 6-18-78 155!16 135 14 136 14 124 12 138t26 6-12-78 6 19-78 171117 (l36-18-78 6-25-78 147 15 158 16 147 15 146 15 150t11 6-19-78 6-26-78 79t8
.j6-25-78 7-02-78 101 10 104!10 109t11 99!10 103 9 6-26-78 7-05-78 129t13 (2? '
C,J CJ Cl1
TABLE C-6 (cont.)
CONCENTMTIONS OF BETA TMITTERS IN AIR PARTICULATE SAMPLES IN THE VICINITY OF SUSQUEHANNA SES Results in Units of 10 -3 pC1/m 3 2 sigma SAMPLE SAMPLE STATION NO. SAMPLE SAMPLE STATION NO.
START DATE STOP DATE SS-APT-553 SS-APT-12E1 SS-APT-3D1 SS-APT-101 AVERAGE" START DATE STOP DATE SLAPT-7H1 7-02-78 7-09-78 105210 114!11 111 11 109 11 11028 7-05-78 7-10-78 181118 7-09-78 7-16-78 107211 % 10 106ill 85 9 99 21 7-10-78 7-17-78 112211 7-16-78 7-23-78 93t9 95t10 98 10 95!10 95t4 7-17-78 7-24-18 59 6 7-23-78 7-30-78 61 6 60!6 60!6 6126 61 1 7-24-7F 7-31-78 4425 7-30-78 8-06-78 37t4 35t4 37 4 37!4 37t2 7-31-7e ^ 8-00-78 44 5 8-06-78 8-13-78 37 4 44t4 48t5 39!4 42 10 o 8-CR; p S-16-78 50 5 8-13-78 8-20-78 4224 4415 4424 44t4 44t2 8-li-?d 8-22-78 , 5026 8-20-78 8-27-78 53!5 50t5 47t5 59 6 52t10 8-22-78 ,
3-28-78 5626 8-27-78 9-04-78 42t4 39t4 39t4 4124 40t3 8-28-78 9-05-78 53t5 9-04-78 9-10-78 45 5 36 4 40!4 4224 41 8 9-05-78 9-11-78 54t6 9-10-78 9-17-78 32 3 36 4 34t4 35t4 34t3 9-11-78 9-18-78 4815 9-17-78 9-23-78 1813 20!3 22t3 18t3 20t4 9-18-78 9-25-78 30 4 9-23-78 9-30-78 2623 25!3 28!3 23 3 26!4 9-25-78 10-02-78 2223 9-30-78 10-07-78 24t3 18 3 23t3 2223 22 5 10-02-78 10-09-78 2424 10-07-78 10-14-78 28t3 29 3 27 3 27!3 28t2 10-09-78 10-16-78 18t4 10-14-78 10-23-78 25 3 20t2 25 3 2723 24 6 10-16-78 10-23-78 38 5 10-23-78 10-29-78 28 4 31 4 3014 28t3 29 3 10-23-78 10-30-78 1713 10-29-78 11-04-78 20t6 34 4 33t4 29t4 29 13 10-30-78 11-06-78 33t5 11-04-78 11-12-78 43 5 52 5 53!6 SSt6 52212 11-06-78 11-13-78 372s ,
11-12-78 11-18-78 3314 31 4 32 4 32 3 32 2 11-13-78 11-20-78 19t3 11-18-78 11-26-78 2823 26 3 28 3 24t3 27:4 11-20-78 11-28-78 0524 11-26-78 12-03-78 26 3 29!4 29!4 26t3 28 3 11-28-i3 12-05-78 3225 12-03-78 12-10-78 3724 3924 37 4 88t10 50250 12-05-78 12-11-78 43t6 12-10-78 12-17-78 35t4 34!4 34 4 33t4 34t2 12-11-78 12-19-78 1713 .
12-17-78 12-24-78 29t3 34t4 31 4 28!3 31 5 12-19-78 12-27-78 39 4 12-24-78 12-31-78 44t4 39 4 43!4 43 4 4224 12-27-78 1-03-79 3025 Avera9e 86t248 91 317 92 309 1142588 972371 10;t297
- Station IDI was placed in operation on March 21, 1978; therefoi*. the first collection period was from March 21 to March 24,1-78.
(vf ** Average of indicator stations.
N *** Elevated gross beta observed during the period between March 18 and March 27 1978 is the result of the atmospherf s nuclear weapons test
(*) by the Peoples Republic of China on March 14, 1978.
O o _
O aus uma smus amm num ase use amm eum ums eums aus amm aus mas use uma e e ens ate aus
W W W W W W W W W W W W W W W W W W W W W W TABLE C-7 CONCENTRATIONS OF GAffiA EMITTERS
- IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES IN THE VICINIl f 0F SUSQUEHANNA SES
-3 3 Results in t' nits of 10 pC1/m 2 2 sigma
. STATION NO.
ANO DaTE Be-7 Zr-95 Nb-95 Ru-103 Ru-106 Sb-125 I-131 1-132 Te-132 Cs-137 Bala-140 Ce-141 Ce-144 SS- APT-SS 3 12-31-77 to 6119 2.0 0.8 3.120.7 6.011.0 1014 2.321.7 7.3 1.5 - <0.4 2.010.6 8.122.2 4.611.0 23t4 4-01-78 4-01-78 to 72 9 1.210.8 2.6t0.8 0.820.6 12 6 4.121.5 <0.4 -
<0.3 4.811.1 <0.8 0.6t0.5 3013 7-02-78 7-02-78 to 60110 <0.9 (0.6 <0.4 <6.0 <2.0 <0.4 - <0.2 2.8 0.9 (0.5 <0.4 1012 9-30-78 ,
9-30-78 to 68111 '1.0 <0.6 <0.6 <6.0 <2.0 (0.5 - <0.4 <0.8 <0.9 '<0.5 <3.0
- > 12-31-78 co SS-APT-301 12-31-78 to 63 8 2.210.9 2.610.8 8.421.1 1116 <1.0 8.711.5 0.610.4 4.213.4 3.110.8 11t2 5.310.7 2023 4-01-78 4-01-78 to 8319 <1.0 2.4 0.7 <0.6 1526 3.3 1.6 <0.4 -
<0.4 3.811.0 <0.9 <0.7 4215 7-02-78 7-02-78 to 65 14 <0.3 <0.5 <0.5 <6.0 <2.0 <0.4 -
<0.4 1.721.0 <0.9 <0.6 <4.0 9-30-78 9-30-78 to 106 14 <0.9 <0.6 <0.6 <6.0 <2.0 <0.6 -
<0.5 1.010.7 <1.0 s1.0 <5.0 12-31-78 (l)
., 1 SS- APT-101
, , it 3-21-78 ri to 6417 1. S t 0. 7 2.6 0.6 1.9 0.6 1215 2.621.3 <0.3 - <0.3 3.6 0.7 <0.6 1.4 0.9 3324 4e) 7-02-78 C.i ag} 7-02-78 to 55110 <0.9 <0.5 <0.4 <6.0 <1.0 <0.3 -
<0.2 1.4 0.7 <0.7 <0.3 1222 9-30-78 9-30-78 to 6819 <0.7 <0.4 <0.5 <6.0 <1.0 <0.3 -
<0.4 <0.7 <1.0 1.221.0 4.023.0 12-31-78
TABLE C-7(cont.)
CONCENTRATIONS OF GAMM EMITTERS
- IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES IN THE VICINITY Of SUSQUEHANNA SES 3
Results in Units of 10-3 pCi/m 12 sitya
( STt. TION NO.
i AND DATE Be-7 Zr-95 Nb-95 Ru-103 Ru-106 Sb-125 I-131 1-132 Te-132 Cs-137 8aLa-140 Ce-141 Ce-144 SS-APT-12E1 12-31-77 to 60113 4.9 2.9 4.511.3 8.8tl.6 11 8 <2.0 7.3 2.0 0.920.7 1418 2.321.1 13t4 4.621.4 2615 4-01-78 4-01-78 to 76t10 <1.0 2.210.8 <0.5 1416 3.521.4 <0.4 -
<0.3 3.3 0.9 <0.7 <0.6 29 4 7-02-78 7-02-78 to 54 11 <1.0 <0.5 ' <0.4 <5.0 <1.0 <0.3 -
<0.3 1.410.8 <0.7 <0.5 9.015.0 9-30-78
, t 9-30-78 a to 76t12 <1.0 <0.6 <0.6 <5.0 <1.0 <0.6 -
<0.4 <0.8 <0.9 2.511.8 5.024.0 12-31-78 SS-APT-7H1 1-03-78 to 4019 2.911.3 2.710.9 7.211.2 8.016.0 <3.0 9.6 2.2 -
<0.6 1.6i0.8 10t2 5.511.3 21t5 4-03-78 4-03-78 to 62211 1.611.6 1.7 0.8 <1.0 1117 2.3tl.9 <0.5 -
<0.6 2.511.0 <1.0 <1.0 24 3 b3i 7-05-78
- d C 7-05-78 Q to 64217 <1.0 <0.7 <0.5 <7.0 <2.0 <0.6 -
<0.5 1.811.1 <1.0 <0.7 1116 g 10-02-78 O 10-02-78 to 70 14 <2.0 <0.9 <0.8 <7.0 <1.0 <0.8 -
<0.6 1.2 1.1 <1.0 <0.8 5.014.0
. 1-03-79 4
All gama emitters decay corrected to sample stop date with one exception. Since Nb-95 does not reach equilibrium with Zr-95, it was not decay corrected. All other gamma emitters are <MDL. Typical MDLs are found on Table C-16.
- Indicate", that no MDL was calculated for that nuclide.
W W W W W W W W W W W W W W W W W W W W W O
TA8LE CP CONCENTRATIONS OF I-131 IN FILTERED AIR IN THE VICINITY OF SUSQUEHANNA SES 3
Results* in Units of 10-3 pC1/m 12 signa i
START STOP STATION START STOP STATION DATE DATE SS-AIO-12E1 DATE DATE SS-AIO-7H1**
12-31-77 1-07-78 <3.7 1-07-78 1-15-78 <2.9 1-15-78 1-22-78 <3.0 5 1-22-78 1-28-78 <3.6 1-28-78 2-04-78 (4.1 I 2-04-78 2-11-78 2-19-78 2-11-78 2-19-78 2-26-78
<3.9
<3.0
<2.9 2-26-78 3-04-78 I
<3.4 3-04-78 3-11-78 <4.0 3-11-78 3-18-78 <3.9 3-18-78 3-24-78 55i11***
3-24-78 4-01-78 <3.8 I 4-01-78 4-07-78 4-07-78 4-14-78
<5.0
<3.8 4-14-78 4-22-78 <3.3 I 4-22-78 4-30-78 5-07-78 4-30-78 5-07-78 5-13-78
<3.0
<3.3
<3.9 I 5-13-78 5-20-78 <4.4 5-20-78 5-27-78 <4.1 5-27-78 6-03-78 <4.1 5-30-78 6-05-78 <6.1 6-03-78 6-11-78 <3.0 6-05-78 6-12-78 <7.3 6-11-78 6-18-78 <3.7 6-12-78 6-19-78 <4.4 8 6-18-78 6-25-78 6-25-78 7-02-78
<3.8
<4.7 6-19-78 6-26-78 6-26-78 7-05-78 (4.6
<3.2 7-02-78 7-09-78 <3.0 7-05-78 7-10-78 <5.6 7-09-78 7-16-78 <4.0 7-10-78 7-17-78 <4.4 7-16-78 7-23-78 <4.2 7-17-78 7-24-78 (4.0 7-23-78 7-30-78 <3.6 7-24-78 7-31-78 <4.5 I 7-30-78 8-06-78 8-13-78 8-06-78 8-13-78 8-20-78
<3.5
<3.8
<5.0 7-31-78 8-08-78 8-16-78 8-08-78 8-16-78 8-22-78
<3.8
<4.1
<5.3 8-20-78 8-27-78 <3.7 8-22-78 8-28-78 <5.4 I 8-27-78 9-04-78 9-10-78 9-04-78 9-10-78 9-17-78
<2.6
<4.2
<3.5 8-28-78 9-05-78 9-11-78 9-05-78 9-11-78 9-18-78
<3.2
<6.4
<4.1 9-17-78 9-23-78 <4.7 9-18-78 9-25-78 (4.0 I 9-23-78 9 78 9-30-78 10-07-78
<4.3
<4.1 9-25-78 10-02-78 10-02-78 10-09-78
<4.5 10-07-78 10-14-78 <4.7 10-09-78 10-16-78 <6.0 l 10-14-78 10-23-78 10-29-78 10-23-78 10-29-78 11-04-78
<2.5 (4.0
<6.3 10-16-78 10-23-78 10'-30-78 10-23-78 10-30-78 11-06-78
<5.1
<3.9
<5.5 11-04-78 11-12-78 11-06-78 I
<4.7 11-13-78 <5.2 11-12-78 11-18-78 <4.8 11-13-78 11-20-78 <4.1 11-18-78 11-26-78 <3.3 11-20-78 11-28-78 <4.4 11-26-78 12-03-78 <4.2 11-28-78 12-05-78 '7.0 12-03-78 12-10-78 <3.7 12-05-78 12-11-78 .6.8 1 12-10-78 12-17-78 12-17-78 12-24-78
<4.5
<3.6:
12-11-78 12-19-78 12-19-78 12-27-78
<4.2
<4.4 12-24-78 12-31-78 <4.8 12-27-78 1-03-79 (5.9 I
- Iodine-131 results are decay corrected to sample stop date.
Station 7H1 was placed in operation on May 30, 1978.
The I-131 activity cbserved is the result of the atmospheric nuclear weapons test by the Peoples Republic of China on March 14, 1978.
i ****
Cartridge was not counted because it was delayed in shipment, 45 370339 I
I I
TABLE C-9 CONCENTRATIONS OF TRITIUM IN WELL WATER IN THE VICINITY OF SUSQUEHANNA SES Results in Units of pC1/1 2 sigma STATION NO. I DATE SS-WWA-552 SS-WWA-12F2 5 3-28-78 96 73 127 74 6-28-78 <80 138 78 9-27-78 <69 78 60 12-20-78 92268 104 69 I
I TABLE C-10 CONCENTRATIONS OF TRITIlM, BETA EMITTERS AND Sr-89* AND -90 IN POTABLE WATER SAMPLES FROM THE VICINITY OF SUSQUEHANNA SES Results in Units of pCi/1 2 sigma 12-28-77 3-29-78 6-27-78 9-27-78 STATION NO. to to to to RADI0 ACTIVITY 3-29-78 6-27-78 9-27-78 12-26-78 SS-PWT-12F2**
H-3 123 75 <80 152 64 106 69 Beta <1.8 <1.7 3.6 1.8 2.3 2.1 Sr-89 <0.9 <0.9 <0.6 <0.9 Sr-90 <0.5 <0.6 <0.4 <0.5 SS-PWT-12H2 H-3 <79 <80 75 63 111 69 Beta 4.5 1.2 <1.7 2.2 1.7 3.1 2.2 Sr-89 0.9t0.9 0.4 0.4 <0.6 <0.8 Sr-90 <0.8 <0.4 <0.4 0.3 0.3 giO3cio g
- Sr-89 results are decay corrected to sample stop date.
- The sampling dates for station SS-PWT-12F2 were: 3-28-78; 6-28-78; 9-27-78; and 12-26-78., ,
46 I
I I
TABLE C-11 CONCENTRATIONS OF GAMMA EMITTERS
- AND STRONTIUM-89** AND -90 IN MILK IN THE VICINITY OF SUSQUEHANNA SES Results in Units of pCi/l 2 signa i STATION N0.
ANO DATE K-40 Sr-89 Sr-90 Cs-137 I SS-MLK-1281 3-31-78 1400 140 1.5 1.0 2.8 0.6 1.9 1.5 6-27-78 10002100 1.6 1.1 2.4 0.7 2.0 0.8 5 9-29-78 1600 160 3.5 1.9 2.4 0.8 7.4 1.4 12-26-78 1300 130 <1.2 1.1 0.5 2.8 1.0 I
SS-MLK-12B2 I 3-31-18 6-27-78 9-29-78 1200 120 900 90 1300 130 3.5 1.6 2.1 1.8
<3.5 7.4 1.0 12 1 9.4 1.1 7.9 2.1 6.0 0.7 6.9 1.3 4.5 0.7 I 12-26-78 1300 130 <1.4 6.8 1.i SS-MLK-7H2
$ 2-25-78 1700 170 <2.3 2.8 0.9 1.9 1.1 5 6-19-78 1000 100 <1.8 3.6 0.8 3.410.8 SS-MLK-9G1 i 9-28-78 1400 140 <3.9 8.2 1.1 4.6 1.2 12-26-78 1400 140 <1.4 4.2 0.7 9.8 1.3 8
I
- All other gama emitters searched for were <MDL; typical MDLs are found on Table C-16.
Sr-89 results are decay corrected to the sample stop date.
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I 370341 I
I I 47 I
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TABLE C-12 CONCENTRATIONS OF I-131* IN MILK IN THE VICINITY OF SUSQUEHANNA SES Results in Units of pC1/1 2 sigma STATION NO. 3-31-78** 6-19-78 9-29-78 12-26-78 SS-MLK-12B1 0.15 0.07 <0.05 <0.07 <0.1 SS-MLK-1282 4.7 0.5 <0.05 <0.06 <0.08
<0.04 *** ***
SS-MLK-7H2 <0.05(1)
SS-MLK-9G1 *** *** <0.08 <0.07 I
I
- Iodine-131 results are decay corrected to the sample stop date.
- The I-131 activity observed at stations 12B1 and 1282 is the result of the atmospheric nuclear weapons test by the Peoples Republic of China on March 14, 1978.
- Sampling location changed from 7H2 to 9G1 effective 3rd quarter.
(1) Sampling date was 2-25-78.
l I
TABLE C-13 CONCENTRATIONS OF GAMMA EMITTERS
- IN F0DDER CROPS IN THE VICINITY OF SUSQUEHANNA SES Results in Units of pCi/g(dry) 2 sigma STATION NtfiBER SAMPLE DATE DESCRIPTION Be-7 K-40 i
SS-PAS-15A2 9-27-78 Grass 1.5 0.2 3.4 0.3 SS-PAS-15A2 1-01-79 Grass 9.1 1.5 13 2 370342 I
- m I
- All other gama emittars searched for were <MDL; typical MDLs are found on Table C-16.
48 I
m M M M e e me e m W Sus e e m' e m m m mm Gut en TABLE C-14 CONCENTRATIONS OF GAMMA EMITTERS
- IN VARIOUS FOOD AND GAME SAMPLES IN THE VICINITY OF SUSQUEHANNA SES
, Results in Units of pCi/g(wet) 2 sigma i.
s STATION NO. SAMPLE DATE DESCRIPTION K-40 Cs-137 SS-FPP-1282 6-26-78 Chicken 5.4 0.5 <0.02 SS-FPE-12B2 6-26-78 Eggs 1.0 0.1 <0.005 SS-FPL-11D1 8-30-78 Cabbage 2.5 0.3 <0.02 SS-FPL-2H1 8-30-78 Cabbage 2.8 0.3 <0.02 SS-FPG-12B1 8-30-78 Corn 1.9 0.2 <0.004 SS-FPF-781 9-28-78 Apples 0.54 0.07 <0.004 SS-FPF-1281 9-27-78 Apples 1.2 0.1 <0.004 SS-GAS-25 11-16-78 Squirrel 2.7 0.3 0.57 0.06 SS-GAS-2S 11-20-78 Squirrel 2.1 0.3 2.3 0.2 SS-GAD-3SI 12-05-78 > Deer 2.8 0.3 0.29 0.03 h SS-FPB-1283 12-26-78 Beef 2.1 0.2 <0.007 SS-FPE-1282 12-28-78 Eggs 1.1 0.2 <0.01
- All other gamma emitters searched for were <MDL; typical MDLs are found on Table C-16.
8 TABLE C-15 RESULTS OF QUARTERLY TLD MEASUREMENTS IN THE VICINITY OF SUSQUEHANNA SES Results in Units of nrem/ standard month 12-31-77 4-04-78 6-28-78 9-29-78 I
STATION to to to to ANNUAL g NO. 4-04-78 6-28-78 9-29-78 12-30-78 AVERAGE g SS-I DM-351 5.44 0.43 6.40 1.23 6.19 0.33 6.52 0.91 6.14 J.97 SS-IDM-451 4.56 0.12 5.39 0.15 5.47 0.26 5.58t0. 9 5.25 0.93 SS-IDM-551 4.46 0.22 4.95 0.56 5.3610.69 5.23!0.55 5.00 0.80 SS-IDM-751 5.60 0.33 7.36 0.42 7.73 0.21 7.96 0.59 7.16 2.14 SS-IDM-11S1 6.21 0.63 7.09 0.50 7.34 0.58 7.56 0.71 7.05 1.18 SS-IDM-101 4.8810.38 6.40 0.27 6.61 0.32 6.84 0.16 6.18 1.77 SS-IDM-12 F1 7.22 0.49 II) 7.55 0.53 7.36 0.44 7.44 0.23 7.39 0.28 I 4.35 0.27 SS-IDM-7H1 4.48 0.20 4.52 0.57 4.65 0.49 4.50 0.25 SS-IDM-8Fil(3) 5.60 0.33 5.85 0.14 5.17 0.16 5.27 0.40 5.47 0.62 AVERAGE 5.37 1.87 6.16 2.16 6.19 2.27 6.34 2.39 6.02 2.22 I
(1) Sa,apling dates were 1-01-78 to 4-04-78.
(2) The sampling dates for station 7H1 were: 12-29-77 to 3-31-78; 3-31-78 to 6-29-78; 6-29-78 to 9-29-78; and 9-29-78 to 1-03-79.
(3) The sampling dates for station 8H1 were: 12-28-77 to 4-07-78; 3-29-78 to 6-29-78; 6-28-78 to 10-02-78; and 9-27-78 to 1-03-79.
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I I TABLE C-16 TYPICAL W Ls* FOR GAMMA SPECTROMETRY I SURFACE AIR PARTICULATES FISH MILK WATER I NUCLIDE (pC1/1) (10- pCi/m3 )
(pCi/ g-wet) (pCi/1)
Be7 -
i Na-22 0.5 0.4 0.005 0.6 K-40 6.0 10 I Cr-51 3.0 3.0 0.03 5.0
- 0. 8 Mn-54 0.5 0.6 0.004 I Co-58 0.5 0.4 0.005 0.6 2.0 Fe-59 0.9 1.0 0.01 i Co-60 0.6 0.6 0.C05 0.6 2.0 Zn-65 1.0 1.0 0.01 I Zr-95 - 1.0 - -
Nb-95 - 0.6 - -
ZrNb-95 0.4 1.0 0.004 0.8 Mo-99 3.0 3.0 0.03 5.0 i Ru-103 - 0.6 - -
Ru-106 4.0 6.0 0.04 5.0 I Ag-110m 0.4 1.0 0.004 0. 8 Sb-125 - 1.0 - -
I Te-129m 7.0 7.0 0.06 10 0.6 I-131 0.4 0.4 0.004 I Te-132 0.3 0.3 0.003 0.004 0.5 0.7 I-133 0.5 0.4 I Cs-134 0.6 0.6 0.005 1.0 Cs-136 0.6 0.7 0.006 1.0 I Cs '?7 0.5 0.5 0.8 0.7 0.005 0.005 0.7 Bala-l40 i Ce-141 - 1.0 - -
Ce-144 2.0 4.0 0.01 1.0 Ra-226 0.8 1.0 0.007 1.0 Th-232 2.0 2.0 0.02 3.0 g
anaw I
Tl4LE C-16 (cont.)
TYPICAL MDLs* FOR GAMMA SPECTROMETRY VARIOUS FOOD MEAT F0DDER PRODUCTS AND SEDIMENT CR0PS GAME NUCLIDE (pCi/g-wet) (pCi/g-wet) (pCi/g-dry) (pC1/g-dry)
Be-7 - - 0. 2 **
Na-22 0.005 0.02 0.02 0.1 K-40 ** ** ** **
Cr-51 0.03 0.09 0.1 0.8 Mn-54 0.004 0.01 0.02 0.1 Co-58 0.005 0.02 0.02 0.1 Fe-59 0.01 0.03 0.03 0.2 Co-f3 0.005 0.02 0.02 0.3 Zn-65 0.01 0.02 0.04 0.3 Zr-95 - - 0.03 -
Nb-95 - -
0.02 -
ZrNb-95 0.004 0.02 0.03 0.1 Mo-99 0.03 0.04 0.1 0. 7 Ru-103 - -
0.02 -
Ru-106 0.05 0.2 0.2 1.0 Ag-110m 0.004 0.01 0.05 0.1 Sb-125 - -
0.05 -
Te-129m 0.06 0.2 0.2 2. 0 I-131 0.004 0.01 0.02 0.1 Te-132 0.003 0.009 0.01 0.1 I-133 0.004 0.02 0.02 0.1 Cs-134 0.005 0.02 0.02 0.1 Cs-136 0.006 0.02 0.02 0.1 g
Cs-137 0.004 0.02 ** 0.1 W Bala-140 0.005 0.01 0.03 0.1 Ce-141 - -
0.03 -
Ce-144 0.01 0.04 0.1 0.07 Ra-226 0.007 0.03 ** 0.2
,=>,8, o a s Th-232 0.02 0.05 ** 0.4
- At time of counting. l
- Indicates a positive concentration was measured in all samples analyzed. 3 Indicates that no MDL was calculated for that nuclide in that media.
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APPENDIX D SYN 0PSIS OF ANALYTICAL PROCEDURES I
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I I GROSS BETA ANgtySIS OF SAMPLES Total Water (BD) l A 250 ml aliquot is evaporated to dryness on 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 l measured residue weight and calculated thickness. The calibration standard used is Sr Y-90. A 250 ml sample of distilled water is evaporated in the same manner and used as a blank.
I Air Particulates (BD) l After a decay period of three to seven days, to allow for the decay of short lived radium and thorium daughter products, the filters are counted in a gas-flow proportional counter for 20 minutes. The beta activity is calculated l from the volume of air fil tered. An unused filter paper is used as a blank.
Calculation of results and two sigma error
= C(s+b) C(b) x I x I x I x 1
RESULT ,
(pCi/vol) _
T(s+b) T(b) ,
2.22 E V TF
=
2 SIGMA ERROR 2 (s+b) , C(b) x 1
x 1
x 1
x 1
(pCi/vol) T(s+b) T(b) 2.22 E V TF where:
gross counts of sample I
=
C(s+b)
C(b) = counts of blank E = fractional Sr Y-90 counting efficiency number of minutes sample was counted I
=
T(s+b)
T(b) = number of minutes blank was counted V = volume of aliquot utilized TF = transmission factor Calculation of minimum detectable levels (MDLs)
The detection limit is assumed to be exceeded when the counting result for the sample is different from the blank reading by at least three times the standard deviation of that background.
MDL =
3YC(b) x I x 1
x 1
x 1
l (pCi/vol) T(b) 2.22 E V TF g/03%
where:
l C(b) = blank counts g I
T(b) = background counting period in minutes V = volume of aliquot utilized E = fractional Sr Y-90 counting efficiency l TF ' ,
= transmission factor 55 I
I At;ALYSIS OF SAMPLES FOR TRITIUM I
Water (H2)
A 15 ml aliquot of the sample is vacuum distilled to eliminate dissolved gases g 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 sample is then counted for tritium in a liquid scintillation counter. A sample of low tritium (< 50 pCi/1) water is vacuum distilled as a blank and is counted with each batch of samples.
In the calculation of the result it is assumed that the condensated and original sample are of eouivalent 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.
RESULT _ C(s+b) C(b)~ x 1 1 x
1 (picocuries/l) -T(s+b) T(b) 2.22 E V of water) t 2 SIGMA ERROR =
2 C(s+b) , Cp x 1
x 1
x 1
(picocuries/l T(s+b) T(b) 2.22 E V of water) where:
I gross counts of sample
~
=
C(s+b)
C(b) = counts of blank E = fractional H-3 counting efficiency g T(s+b) = number of minutes sample was counted e T(b) = number of minutes blank was counted V =
volume (ml) of distillate counted Calculation of minimum detectable levels (MDLs)
The detection limit is assumed to be exceeded when the counting result is different from the blank reading by at least three times the standard deviation of that background, b 1 l
1 1 HDL = 3 *
- Y T
b 2.22 E (picocuries/l) where:
= blank counts ,,,*: h C(b)
= background counting period in ninutes " *n ~ q g T(b)
= volume of distillate counted l
V -
E = fractional H-3 counting efficiency 56 I
I 8
ANALYSIS OF SAMPLES FOR STRONTIUM-89 AND -90 8 Total Water (TO, S0) h 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 I realized by at least two precipitations of strontium nitrate in concentrated nitric acid. Additional carbonate precipitations and barium chromate separations are performed to remove suspected interferring nuclides. The purified strontium I is converted to a carbonate for weighing and counting. Soon after the separati;.,
the sample is counted in a low-background gas-flow proportional counter. After about 14 days, the sample is recounted, then Sr-89 and -90 activities are calcu-lated on the basis of Y-90 ingrowth and Sr-89 decay. A sample of distilled water is used as a blank.
l Milk (S4, T4)
A one and half liter' aliquot of milk is ashed to destroy organic material and then dissolved in concentrated mineral acid. Stable strontium is added to the eluted liquid or dissolved ash to facilitato chemical separation of Sr-89 and -90, and to determine the strontium recovery. Strontium concentration and purification I is ultimately realized by at least two precipitations of strontium nitrate in concentrated nitric acid. Additional carbonate precipitations and barium chromate separations are performed to remove suspected interferring nuclides. The purified strontium is converted to a carbonate for weighing and counting. Soon after the l separation, the sample is counted in a low-background gas-flow proportional counter.
After about 14 days, the sample is recounted, then Sr-89 and -90 activities are calculated on the basis of Y-90 ingrowth and Sr-89 decay. A sample of distilled h water is used as a blank.
l Organic Solids (S8, T8)
A 250 g wet portion of the sample is ashed, then dissolved in concentrated acid.
Stable strontium carrier is added to the solubized 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 precipita-tions of strontium nitrate in concentrated nitric acid. Additional carbonate precipitations, iron rare earth hydroxide scavenging, and barium chromate sepa-rations were perfomed. The purified strontium is connected to a carbonate for weighing and counting. Soon after the separation, the sample is counted in a low-background gas-flow proportional counter. After about 14 days, the sample is recounted, then Sr-89 and -90 activities are calculated on the basis of Y-90 l ingrowth and Sr-89 decay. A sample of distilled water is used as a blank.
Calculation of results and two sigma error i A(Sr-90) = Z (C(1) Total - C(1) Bkg) - (C(2) Total - C(2) Bkg)
(pCi/vol. or wt.) K (vol. /wt.) (eff Sr-90) (yield) (time) (2.22) i 2dZ(C(1) 2 Total +C(1)Bkg)+C(2)Bkg+C(2) Total ERROR Sr-90 =
I bCi/vol. & M.)
(v 1. /wt.) (eff Sr-90) (yield) (time) (2.22) g ,
. 5/0350 M.
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A(Sr-89) = F(C(1) Total - C(1) Bkg) + H(C(2) Total - C(2) Bkg) ; .693T(4)
(pCi/vol. or wt.) (v 1./wt.) (etf Sr-89) (time) (yield) (2.22) e 52.7 s ERROR Sr-89 =
2dF2 (C(1) Total + C(1) Bkg) + H2 (C(2) Total + C(2) Bkg) . .693T(4)
(pCi/vol. or wt.)
(v 1./wt.) (eff Sr-89) (yield) (time) (2.22) e 52.7 where:
S r-89 1 =
Sr-89 counts on first count S r-90 = counts of Sr-90 Y-90 1
=
counts of Y-90 on first count Y-90 2
=
counts of Y-90 on second count Cy total = "
Sr-897 + Sr-90 + Y-901+C1B 1T Sr-892 + Sr-90 + Y-902+C2B =C 2T C2 total =
C1 BKG =
BKG counts on first count =C 1B C2 BKG =
BKG counts on second count = C 2B
-0.693T
- 52.7 days K =
7 (E1/p+1) E /2R h
F = 1- - Z( 1)
K KR E
1 y
+
H =
(7) KR I
TC1 - t sep hours ty =
= days t
2 tC2 - t sep t
3
=
tC2 - tC1 days [f/0TS- g sampling date -t sep days t = t 4
I 58 e 3
41 8
counting eff. of Sr-90 = .3590 .7082 X wt in g of strontium carbonate counting eff. of Y-90 = .4380 .1337 X wt in g of strontium carbonate counting eff. of Sr-89 = .4568 .2060 X wt in g of strontium carbonate
.693T y E
1
=
(1 - e )
64.0 hrs.
-0.693t 2 I E 2
=
(1 - e 2.667 days
)
Calculation of minimum detectable levels (MDLs)
Due to the method of calculating the activity of Sr-90 in the presence of l Sr-89, the form used in the NBS Handbook 80 for calculating minimum detectable activities is not applicable.
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I ANALYSIS OF SAMPLES FOR 10 DINE-131 Milk or Water (IO) h The initial stable iodide concentration in milk is determined with an iodide h ion specific electrode. Thirty milligrams of stable iodide carrier is then added to four (4) liters of milk. The iodide is removed from the milk by passage through ion-exchange resin. The iodide is eluted from the resin with sodium hypochlorite, and ourified by a series of solvent extractions with the l final extraction into a toluene phase. The toluene phase is mixed with a toluene-based liquid scintillation solution. The sample is then counted in a l beta-gated gamma coincidence detector, shielded by six inches of steel. Distilled water is used as a blank. The yield is calculated from stable iodide recovery based on an average recovered volume of 13.2 ml. Results are corrected for decay from the sampling time to the middle of the counting period, using a l half-life value for I-131 of 8.06 days.
Air Cartridges (II) I An iodine absorber composed of charcoal is emptied into an aluminum can (6 cms high by 8 cms in diameter) and counted with a NaI (Tl) detector, coupled to a multi-channel pulse height analyzer.
Calculation of results and two sigma error I
The spectrum obtained is smoothed to eliminate spurious statistical noise. The presence of Iodine-131 is identified by the presence of a 364 Kev peak. The l peak is fitted with a Gaussian curve and the net counting rate above the base-line projection is calculated. This counting rate is converted to activity in curie ur.its, making allowance for counting efficiency and photon abundance.
A PDP-11 computer program is used for spectrum analysis.
C(s+b) C(D) I 1 1 1 ,
x x RESULT =
T( s+b ) _ 1(b) 2.22 E xV- x Y g (pCi/vol ) - -
5 at time of analysis 2 SIGMA ERROR =
2 C(s+b) , C(b) x 1 x
1 x
1 x
I (P 2.22 7
T(s+b)2 T(b)2 E V Y .
analysis where:
= gross counts in channels containing I-131 peak l
C(s+b) j 3'-(),g g C(b) = background counts in channels containing I-131 peak g T(s+b) = number of minutes aliquot was counted T(b) = number of minutes blank was counted E
V Y
=
=
=
I-131 counting efficiency volume of aliquot utilized chemical yield of iodine (for milk or water) x l
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ANALYSIS OF SAMPLES FOR IODINE-131 (cont.)
Calculation of minimum detectable level (MDL) .
I MDL =
3V6 x C y x x
1 x
1 x
1 (pCi/vol) 2.22 E V Y l at time of T(s+b) analysis where:
Cy = number of counts in the channel that would have been the centroid if a peak were there.
E = I-131 counting efficiency V = volume of aliquot utilized Y = chemical yield of iodine (for milk or water) 8 T(s+b) = number of minutes aliquot was counted I
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I GAMMA SPECTROMETRY OF SAMPLES Water (N1)
I Four liters of sample is reduced to 100 ml and sealed in a standard container g and counted with a NaI(Tl) detector coupled to a multi-channel pulse-height analyzer. The counting time is 50,000 seconds.
Milk (N7)
A three liter aliquot is dried at 175 C, ashed at 500 C until no carbon residue g 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. g 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, compressed to unit density, 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 g sample if less than 100 grams) is taken, compressed to unit density, sealed e in a standard container and counted with a NaI(Tl) detector, coupled to a multi-channel pulse-height analyzer. The counting time is 50,000 seconds.
Air Particulate (GB)
All samples received for the month are mixed and sealed in the standard container, and counted with the high resolution Ge(Li) detector, coupled to a multi-channel pulse-height analyzer.
Calculation of result and two sigma error The spectrum obtained is smoothed to eliminate spurious statistical noise.
Peaks are identified by changes in the slope of the gross spectrum. Identi fied individual peaks are fitted with Gaussian curves and the net counting rate l above the baseline projection is calculated. This counting rate is converted W to activity in curie units, making allowance for counting efficiency and photon abundance. A PDP-11 computer program was introduced for spectrum unfolding.
C(s+b) C(b) 1 1 1
1 RESULT =
T(s+b)
(pCi/vol or wt W ~
X 2.22 x
E V Garmia Ab
,s) 2 SIGMA ERROR = 2 C(s+b) C(b) x 1
x 1
1 1 T(s+b)2,T(b)2 2.22 E V Gamma Ab (pCi/vol or wt.)
62 970355 g
I 8
where:
I C(s+b) = gross counts in channels containing peak of nuclide being quantized l C(b) = background counts in channels containing peak of nuclide being quantized T(s+b) = number of minutes aliquot was counted l T(b)
E
=
=
number of minutes blank was counted measured from efficiency curve for a given energy Gamma Ab = fractional gamma abundance l V = volume or wt. of aliquot utilized Calculation of minimum detectable levels (MDLs)
MDL = 3 G6 x C I 1 1 1 1
- * * -V
- T(s+b) 2.22 E Gamma Ab (pCi/vol or wt) l where:
C = number of counts in the channel that would have been l I Eff =
=
the centroid if a peak were there.
measured from efficiency curu for a given energy fractional gamma abundance (specific for each nuclide)
Gamma Ab i V T(s+b)
=
=
volume or wt. of aliquot utilized number of minutes aliquot was counted i
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I ENVIRONMENTAL DOSIMETRY (D0)
Measurement Techniques Each dosimeter utilized is a capillary tube containing calcium sulfate (Tm) g powder as the TLD material. This was chosen primarily for its high light output, minimal themally induced signal loss (fading), and lack of self-dosing. The energy response curve has been flattened by a complex multiple element energy compensation shield supplied by Panasonic Corporation, manufacturer of the TLD reader. The four dosimeters per station are sealed in a polyethylene bag to demonstrate integrity at t'me 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 3 is placed in a field lead shield on the RMC roof and is used in calculating 5 the intransit dose.
Following the pre-designated exposure period the TLD is heated with hot gas and the luminescer.se measured with a TLD reader. Data are nonnalized to standard machine conditions by correcting machine settings to zero before read out. 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 : 0.9555 rad / Roentgen 3 and to dose equivalent by using a quality factor of 1. 5 Calculation of results and two sigma error gross TLD(i) = TLD(i) - I0 x - DO(i) CF(i) x 0.955 mrad I
ITD = NET (site 0) - NET (rmc0) x s te }
D 0 NET TLD(i) = gross TLD(i) - ITD n
l NET TLD(i)
AVG - -i"I x D(std) n D(EX)
ERROR (95% CL) = t(n-1) x sigma NET TLD(i) x D T) j.g3rg/
I
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64 I
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ENVIRONMENTAL DOSIMETRY (cont.)
where:
gross TLD(i) = individual TLD reading corrected to standard instrument conditions TLD(i) = gross reading of dosimeter i NET TLD(i) = net dose obtained during exposure period in l
the field 10 = instrument zero LS = instrument light source reading D0(i) = zero for cosimeter, i l CF(i)
ITD
=
=
calibration factor for dosimeter i in-transit dose NET (site)0 =
mean of n dosimeters in site lead shield l NET (rmc)0 D(site 0)
=
=
mean of n dosimeters in RMC lead shield exposure period of site 0 D(rmc0) = exposure period of rmc0 AVG = mesa exposure per standard expo:ure period at a given station n = nL aber of readings l D(EX)
D(STD)
=
=
days exposed days in standard exposure period t(n-1) =
t-distribution (student) factor for 95% CL l sigma NET TLD(i)
=
=
standard deviation of n readings of NET TLD(i) light source normal reading ERROR =
the 95% confidence limit error of AVG I .-
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370358 I
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APPENDIX E I RESULTS OF INTER-LABORATORY COMPARISON PROGRAM i
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370359 I
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I I RMC participates in the EPA radiological interlaboratory comparison (cross check) program. This participation includes a number of analyses on various sample media as found in the Susquehanna SES REMP. As a result of participation in the program an objective measure of analytical precision and accuracy as well as a bias estima-tion in RfiC results is obtained. Reference 12 discusses discrepancies between the data when they occurred.
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INTER-LABORATOSY COMPARISONS GROSS ALPHA AND'CETA IN WATER (pCi/ liter and AIR PARTICULATES (pCi/ sample)
TABLE E-1 TYPE OF RMC EPA All Participants DATE RMC # RADIATION MEAN S.D. MEAN S.D. MEAN S.D.
JANUARY 89840 alpha 71 75 73
, 1978 Water beta 4311 39 5 37 6 MARCH 90819 alpha 10 2 11 5 12 3 1978 APT beta 40 2 38 5 40 4 MARCH 90820 alpha 16 2 20 5 1978 Water beta 30 3 29 5 (1)
APRIL 91888 alpha 19 2 20 5 20 7
> 1978 Water beta 58 1 59 5 57 10 MAY 92636 alpha 14 2 13 5 13 4 5 1978 Water beta 25 1 18 5 20 4 JUNE 93393 alpha 10 1 10 5 11 2 1978 APT beta 40 1 36 5 39 3 JULY 94118 alpha 25 2 22 6 17 6 1978 Water beta 42 1 30 5 32 7 rp SEPTEMBER 96793 alpha 21 55 62
.] . 1978 Water beta 13 1 10 5 11 2 C
CJ OCTOBER 98135 alpha 17 1 19 5 19 8
'[;
1978 Water beta 41 1 34 5 35 8 NOVEMBER 98577 alpha 12 1 11 5 11 3 1978 Water beta 29 1 26 5 26 4 1s (1) No final EPA report was received,
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% im e. .mu Ties 4'?< S T.ST TARG.T (MT-3) 1.0 '!BEEM e El i!!n 1.1 E t. ll= IM l.25 1.4 l 1.6 _ L_. . < 6" = '4 ,,// k 4 6 m es ee e es as mM 651m SS mmm eS mM M M MM INTER-LABORATORY COMPARISONS TRITIUM IN WATER All results in pCi/ liter TABLE E-2 RMC EPA All Participants DATE RMC# MEAN S.D. MEAN S.D. MEAN S.D. APRIL 91628 2180 144 2220 349 2198 267 1978 Water APRIL 918U <59 0 1978 Water JUNE 93135 2230 147 2270 249 2259 252 1978 Water AUGUST 95018 1168 49 1230 330 1245 209 C,^ 1978 Water ,$4 C C la INTER-LABORATORY COMPARISONS STRONTIUti-89 AND STRONTIUtt-90 TABLE E-3 RMC EPA All Participants DATE RMC# ISOTOPE UNITS MEAN S.D. MEAN S.D. MEAN S.D. MARCH 90337 S r-89 1978 Food Prod.(1) Sr-90 MARCH 90819 Sr-90 pCi/ sample 41 8 1.5 72 1978 APT APRIL 91888 Sr-89 pCi/l 16 1 21 5 21 3 y 1978 Water Sr-90 pCi/l 81 10 1.5 91 APRIL 91948 Sr-89 pCi/l 82 24 101 5 92 10 1978 Milk Sr-90 pCi/l <10 9 1.5 92 JUNE 93381 Sr-90 pCi/ sample 81 9 1.5 92 1978 AFT JULY 93535 Sr-89 pCi/kg 38 4 39 5 36 4 1978 Food Prod. S r-90 pCi/kg 22 1 15 1.5 17 4 JULY 94132 Sr-89 pCi/l 26 1 41 5 35 9 1978 Milk S r-90 pCi/l 41 4 49 2.5 46 9 OCTOBER 98135 S r-89 pCi/l 51 10 5 10 3 g 1978 Water Sr-90 pCi/l 51 5 1.5 51 ~l. , F-C (1) Sample lost during analysis. C N ee mmm mm es em m en es e em es m m en m es em I I INTER-LABORATORY C0ffARISONS: GAMPA Results reported in pCi/ liter for milk and water, pCi/ sample I for air particulates, and pC1/ kilogram for food products except K which is reported in mg/ kilogram TABLE E-4 i DATE RMC # ISOTOPE RMC MEANiS.D. EPA MEAN 5.D. All Participants MEANiS.D. I FEBRUARY 1978 90041 Water Cr-51 Co-60 Zn-65 Ru-106 <17 38 1 29 1 3621 0 34!5 29 5 3625 33t5 29 5 39 9 i MARCH 90337 Cs-134 Cs-137 I-131 52 1 <2 70 5 52 2 0 74 5 49 6 72 7 1978 Food Prod. Cs-137 5221 4125 39 4 8 Ba-140 K-40 <4 4100 200 0 2930!147 2823t306 i MARCH 1978 APRIL 90819 APT 91638 Cs-1?7 Cr-51 36 10 <15 22i5 0 23!5 l 1978 Water Co-60 Ru-106 Cs-134 Cs-137 46 2 83!8 61 2 <2 49i5 113 6 74 5 0 49i4 100 19 72 7 i APRIL 1978 91888 Water Co-60 Cs-134 Cs-137 17 1 81 <1 20 5 1525 0 21 3 1915 I APRIL 1978 91948 Milk I-131 Cs-137 Ba-140 66 3 2312 <3 8225 23 5 0 8229 25 3 I JUNE 1978 93173 Water K-40 Cr-51 Co-60 1510 50 90212 19!2 1500 75 10225 22 5 1541 102 99 19 22 3 I Zn-65 Ru-106 Cs-134 Cs-137 52 5 43t4 20 2 31 3 54 5 58 5 2215 30 5 51 7 56 12 21 4 32!4 I JUNE 1978 93393 APT Cs-137 16 2 1825 20 5 I JULY 93535 1-131 71 3 83 5 8216 1978 Food Prod. Cs-137 40t2 3715 3814 Ba-140 <1 0 K-40 2507 62 2800 140 27441205 I I I I , g 73 371003 INTER-LABORATORY COMPARIS0NS: GAMMA (cont.) Results reported in pCi/ liter for milk and water, pCi/ sample for air particulates, and pCi/ kilogram for food products except K which is reported in mg/ kilogram TABLE E-4 RMC EPA All Participants DATE RMC # ISOTOPE MEAN S.D. MEAN S.D. MEANiS.D. JULY 94132 I-131 <3 0 1978 Mil k Cs-137 48 3 53 5 54 4 Ba-140 <2 0 K-40 1359 29 1560 78 1547 116 E AUGUST 94903 Cr-51 106 11 105 5 106 21 1978 Water Co-60 29 1 27 5 27 4 Zn-65 58 5 62 5 61 11 Ru-106 48 6 41 5 41 11 Cs-134 81 95 10 2 Cs-137 15 1 15 5 16 3 OCTOBER 97770 Cr-51 152 18 117 6 126 32 1978 Water Co-60 29 1 23 5 23 4 Zn-65 85 2 82 5 82 10 Ru-106 42 3 46 5 47 14 Cs-134 25 1 25 5 25 4 Cs-137 131 1 125 6 127 11 CO 'l OCTOBER 98135 Co-60 <2 0 f~ 1978 Water Cs-134 91 10 5 10 4 ff
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Cs-137 13 1 1315 13 4 MM M W M M MM MM W H M Y M M W WO O MM I I I I I I I I I I APPENDIX F COW AND GARDEN SURVEY I I I I I I I suom I Mi I I I I I TABLE F-1 NEAREST MILK 8 Sector Distance (Miles) 1 N >5 2 NNE >5 3 NE 3.8 4 ENE >5 5 E 2.2 6 ESE 2.4 7 SE 2.5 8 SSE 2.5 9 S 2.4 10 SSW 2.5 11 SW 2.5 12 WSW 1.6 13 W 4.9 14 WNW >5 15 fM .7 16 NNW 4.1 I I I C
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TABLE F-2 I MILK COWS TO 3 MILES f Sector Distance (Mi'es) 1 N >5 2 NNE >5 3 NE 3.8 4 ENE >5 5 E 2.2 6 ESE 2.4,2.6,2.7 7 SE 2.5 8 SSE 2.5 9 S 2.4 10 SSW 2.5 11 SW 2.5 12 WSW 1.6,2.0 13 W 4.9 14 WNW >5 15 NW .7 16 NNW 4.1 I I I I I wasiiiin 3 78 g,1007 I I I TABLE F-3 NEAREST VEGETABLE GARDEN Sector Distance (Miles) 1 N 0.5 1 2 NNE 0.9 3 NE 2.3 4 ENE 2.8 5 E 0.7 6 ESE 1.5 7 SE 0.4 E 8 SSE 0.4 9 S 1.2 10 SSW 0.6 11 SW 0.8 12 WSW 1.2 13 W 0.7 14 WNW 1.3 15 PM 0.7 ,, 16 NNW 0.7 I I e W I I I ! 79 F,>00g I I TABLE F-4 I NEAREST RESIDENCE IN EACH SECTOR WITHIN FIVE MILES OF THE SITE Sector Distance (Miles) 1 N 0.710 2 NNi 1.045 3 NE 2.273 4 ENE 2.367 5 E 1.326 6 ESE 0.473 7 SE 0.378 8 SSE 0.701 9 S 1.136 10 SSW 0.757 11 SW 0.800 12 WSW 1.089 13 W . 1.183 14 WNW 0.710 15 NW 0.805 16 NNW 0.757 I I I I I
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