ML18086A656
| ML18086A656 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/31/1981 |
| From: | RADIATION MANAGEMENT CORP. (RMC) |
| To: | |
| Shared Package | |
| ML18086A655 | List: |
| References | |
| RMC-TR-81-03, RMC-TR-81-3, NUDOCS 8106120101 | |
| Download: ML18086A656 (113) | |
Text
RMC-TR-81-03 I
/I 1980 RADIOLOGICAL REPORT ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM I
\
(
I*
January 1 to December 31, 1980 \
Prepared for Public Service Electric and Gas Company \
\
by I I
Radiation Management Corporation March 1931 \\.
' \
'\
SUMMARY
During the period January 1 to Deceniler 31, 1980, Radiation Management Corporation participated in the Operational Radiological Environmental Monitoring Program con-ducted by Public Service Electric and Gas Company at Artificial Island, New Jersey.
Salem Nuclear Generating Station (srms) 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 con-centrations of radioactivity in various environmental media and to quantify ambient radiation levels in the environs of Artificial Island. Unit #2 achieved initial chticality on-August 2, 19130. The power level of Unit 2 did not exceed 5% of rated power during the report period. During the operational phase, the program will monitor the operations of SNGS Units #1 and #2, fulfill the requirements of the SNGS Environmental T~chni cal Specifications, and pro vi de background data for the Hope Creek Generating Station. This report presents the results of ther-mol uminescent dosimetry and radiochemical analyses -of environmental samples col-lected during 1980.
A total of 25.62 analyses were performed on 1580 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, and precipitation were collected.
- Therniol uminescent dosimeters were used to measure ambient radiation levels.
A variety of radionuclides, both naturally occurring and man-made, were found in the above samples. These nuclides were detected at levels similar to those found during the preoperational phase of this program. In general, results at indicator stations compared favorably to control stations. It is concluded that the radiological charac-teristics of the environllEnt around Artificial Island were not affected by the operation of SNGS Units #1 and #2 during* 1980.
1
INTRODUCTIOf~
Radiation Management Corporation (RMC) has participated in the Artificial Island Radiological Environmental Monitoring Program (REMP) since January 1973.
RMC has previously reported results from the preoperational phase of the REMP for 1973(1), 1974(2), 1975(3) and 1976(4). On Decerrber 11, 1976, SNGS Unit #1 first achieved criticality, thereby initiating the operational phase of the REMP.
RMC has also reported results from the initial operating period between December 11 and December 31, 1976 (5), January 1 and December 31, 1977 (6), January 1 and December 31, 1978 (7) and January 1 and December 31, 1979 (3). This report surmiarizes the operational period_ between January 1 and December 31, 1930.
Ar.tificial Island will eventually be the site of four nuclear power reactors.
Two of the reactors are part of the Salem Nuclear Generating Station. Units #1 and #2 are pressurized water reactors (P~~R), 1090 MWe and 1115 MWe respectively.*
Both are presently operational. Unit #2 is currently limited to 5% power level.
The remaining two units wil 1 be part of the Hope Creek Generating Station.
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 characterized 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 agricul-tural production. (9)
More specific information on the demography, hydrology, meteorology, and 1and use characteristics of the local area may be found in the Environrnental Report (9), Environmental Statement (10), and the Final Safety Analyses Report (Units 1 and 2) for SNGS ( 11).
2
THE PROGRAM In the operational phase of the REMP, the program was conducted in accordance with Section 3.2 of the SNGS Environmental Technical Specifications (ETS). Radioanalytical data we1~e collected and compared with results from the preoperational phase. Differences between these periods were examined statistically, where applicable, to deterrni ne whether any station operational effects exist.
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 radio~uclides.
- 4. To detect any change in ambient garrma 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 ETS summarizes the findings of the 1980 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 REMP 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 radi onucl ides through the environment to man, and (2) experience gained during the preoperati onal phase. Sampling 1ocati ons were determined from site meteorology, Delaware estuarian 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
Air particulates were collected on Schleicher Schuell ffo. 25 glass fiber filters with low-volume air samplers. Iodine was collected from air by absorption 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 resi.dual particulates in the precipita-tion samples. Results of subsequent analyses were corrected for the increase in volume. Tritium results were also corrected for the tritium content of the dis-tilled water.
Arrbient radiation levels in the environs were measured with energy-compensated Caso * (Tm) thermoluminescent dosimeters (TLDs). Packets containing four TLDs each 4were placed on and around the Artificial Island site at various distances and were exposed on a monthly, quarterly and semi-annual basis.
Monthly well and potable water samples were taken in new two-gallon polyethylene bottles. Separate raw and treated p9table water samples were *composited daily by personnel of the Salem Water Company. The Salem Water Company draws its water from Laurel Lake and adjacent wells, which a*re hot expected to be influenced by SNGS liquid discharge.
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 sumnarizes, in the fonnat of Table 5.6-1 of the Salem ETS, the entire operational program as performed in 1980. Appendix B describes the RMC coding system, which specifies sample type and relative' locations at a glance. Also in Appendix B, Table B-1 gives the pertinent information on individual sampling locations, while maps B-1 and B-2 show the sampling locations.
4
Data Interpretation Radiation Management Corporation has an extensive quality assurance program designed to maximize confidence in the analytical procedures used. The analytical methods utii'ized in this program are su1T111arized in Appendix D.
Approximately 20% of the total analytical effort is spent on quality control, including process quality control, instrument quality control, inter-laboratory cross-check analyses, and comprehensive data review. Results of the EPA inter-1aboratory comparison program appear in Appendix E. A full discussion of these results can be found in the Annual QC Report (12). Several factors are important in the interpretation of the data. These factors are discussed here to avoid repetition in sections that follow.
Grab sampling is a useful and acceptable procedure for taking environmental samples of a medium in which the concentration of radionuclides is expected to vary slowly with time or where intennittent sampling is deemed sufficient to establish the radiological characteristics of the medium. This method, however, is only representative of the sampled medium for that specific location and instant of time. As a result, variation in the radionuclide concentrations of the samples will nomally occur. Since these variations will tend to counterbalance one another, the extraction of averages based upon repetitive grab samples is valid.
- Within the data tables (Appendix C) an approximate 95% (+/-2 sigma) confidence interval is supplied fo*r those data points above the lower limit of detection (LLD). These intervals represent the range of values into which 95% of repeated analyses of the same sample would fall.
Results for each type of sample were grouped according to the analysis per-formed. Means and standard deviations of these results were calculated when applicable. The calculated standard deviations of grouped data found in Appendix C represent sample and not analytical variability. When a group of data was composed of mainl~ (>50%) LLD values, averages were not calculated.
It is characteristic of environmental monitoring data that many results occur at or below the lower limit of detection. For reporting and calculation of averages, any result occurring at or below the lower limit of detection is considered to be at that limit. Averages obtained using this method are there-fore biased high.
5
l RESULTS AND DISCUSSION The analytical results of the 1980 REMP samples are divided into categories based on exposure pathways: airborne, direct, water, aquatic and ingestion. The anal-
. ytical results for the 1980 REMP samples are sunmarized in Appendix A. The data
- for individual samples are presented in Appendix c.
Airborne Air Particulates Air particulate samples were analyzed for alpha, beta and gamma radiation. The weekly air particulate samples were analyzed for gross beta activity at eight stations and for gross alpha activity at two stations. Quarterly composites were prepared using the weekly samples from each station and analyzed for Sr-89, Sr-90 and specific gamma.emitters.
Of the 104 weekly air particulate samples (two stations) analyzed for gross alpha emitters, 98 were above detectable c9ncentrations. The range o~ gros*s alpha acti-vity was from 0.0006 to 0.0076 pCi/m and averaged 0.0018 pCi/m
- Weekl~ gross bet~ analyses showed concentratians ranging from 0.0043 to 0.~58 pCi/m , with the average for the eight sampling stations.being 0.029 pCi/m.
Figure 1 shows the relation between gross beta activity in air and precipitation for the preoperational versus the operatiohal periods, showing both seasonal and weapons-testing fluctuations.
Results of gamma spectrometry showed detectable levels of seve-ral radionuclides, both naturally occurring and man-made (Be-7, K-40, Nb-95, Zr-95., Ru-103, Cs-137, Ce-141 and Ce-144). The man-made nuclides detected during the fourth quarter can be .attri-buted to fallout from the October 15, 1980 atmospheric nuclear weapons test. The presence of Be-7 throughout the year can be attributed to cosmic ray activity.
The Sr-89 ana~yses performed on. t~e quarterly composites showed twelve out of th~ rt~
two samples with detectable act1v1ty. These ranged betwe3n 0;0006 and 0.0082 pC1/m.
The MDLs for Sr-89 ranged between o.ogo6 and 0.0033 pCi/m
- Sr-90 conce~trations ranged between 0.0002 and 0.002 pCi/m with the average being 0.0006 pCi/m
- Air Iodine Iodine cartridges were connected in series behind each of the air particulate filters for absorption of air iodine. The absorption media used in these cartridges was 11 TEDA 11 impre§nated charcoal. All results for *I-131 were below the LLD which averaged 0.013 pCi /m
- Preci pita ti on Although not specifically required by the Salem ETS, precipitation was sampled continuously and collected monthly at the Salem substation sampling location.
6
FIGURE l COMPARISON OF AVERAGE CONCENTRATIONS OF BETA EMITTERS HI PRECIPITATION AND IN AIR PARTICULATES, 1973 THROUGH 1980 p:::i/l - - -;- - - " Precipitat;i.on 10-> P:::i/m 3 - - -
- Air Particulates I
I I I I I I l
/00 'i , 1'
, I 11 I I 11 I I I I
~
I I I ~I I I I I/ I
./
~I 1I\ ~, \*I 1 I I I 1
T \. I I I 1 1I I/
"! I I \/ \
I " I II. £ \ I I ll. I f " 1\ I \ J. II
/I I I I t 1 1
1 I u' & I I 1
I I I ', 1 I Ii I i~ .J~ ~ II 11
/M II I Lt 1 I ._,. I 1*
I I
I "1
11
,1 I
I 10 I I I
- I I I I I I t I\~ II It I I I ,, 1 '1* l
~
"' I "-:. I I I t : ..
l I I I -r I 1_'1 I '\ I / ' I l
I I I I
i~ I 11 1
,~
11
, , I, I\ !i \\/i r \1,i atnospheric weap:ru; test Sept. 17 I 1977
'!'l I
~
I\/ \
J.
111 j 1' 'T
~
I\
II '
I\ /
I I I1 I I I
I I I I
+
I I I I I ,/,.
I I atmospheric weapons test I / II
\I l I I I
\/
I I I f I I\
I / I 11 I
I /
I I I I June 17,1974 I/
11 a!Jrospheric test! l i/ \1 I I II \/ //
.../
i\I \/
11
""'1f0'1S Sept. 26' 1976 1 l ~ : J. J'. \I T
~L*:*.*;*** ~* rII~."". ".........
atnospheric weap::ms test T
s-JGS Unit i1 initial criticality March 14' 1978 Dec. 11, 1976 Oct. 15, 1980 SNGS Unit #2 initial criticality Aug. 2, 1980 19.].,L_ 19 19.z..;::_ 19-2.£,_ 19 :z_:z_ 192.L 19_l{Q_ 19 _ _ 19 _ _
FIGURE 2 AVERAGE AMBIENT RADIATION LEVELS FROM MONTHLY TLDs IN THE VICINITY OF ARTIFICIAL ISLAND, 1973 THROUGH 1980 19...Z.j___ 19--2£__ 192..£__ l92Z__ l~ l9_2L_ 19 _ _ 19 _ _
atrrosfheric weai;ons test at:nospheric weap::ris test , at::m:>sfheric ~test a~ic ~test Three Mile Island atmospheric weapons test June 17,1974 ' Sept. 26, 1976 Sept. 17, 1977 March 14, 1978 March 28, ]g79 Oct. 15, 1980
~GS Unit fl:l initial criticality SNGS Unit #2 initial criticality Dec. ll, 1976 Aug. 2, 1980
-, I The rain water was analyzed for tritium, alpha, beta and gamma radiation monthly.
Concentrations of tritium in all twelve roonthly samples were below LLD and ranged from less than 90 to <124 pCi/l. The concentrations of gross alpha emitters were also below .LLD (0.5-1.1 pCi/l) in nine of the twelve samples. The other samples had gross alpha concentrations of 0.8 to 1.1 pCi/l. Gross beta-emitter concentra-tions ranged from <2. 3 to 26 pCi/l and averaged 9 .5 pCi /1.
Quarterly composites of precipitation were analyzed for radiostrontium and gamna emitters.
No gamma emitters were detected. The Sr-89 levels were below the MDL which ranged between 1.2 and 2.6 pCi/l. The result for one of the four analyses, performed for Sr-90 was below the MDL. Sr-90 concentrations ranged between 0.4 and 2.0 pCi/l with the average being 1.2 pCi /1.
Direct Direct radiation measurements were made at 42 different locations, 25 monthly and quarter-ly ~ocations and 17 semi-annual locations using C?S0 4 * (Tm) thermoluminescent dosimeters.
During 1980, 294 monthly,, 98 quarterly and 33 semi-annual TLD packets* were collected.
Each packet included four dosimeters for a total of 1695 analyses. These analyses resulted in an average dose rate of 5.79 mrads/standard month for monthly TLDs, 5.21 mrads/standard month for quarterly TLDs and 5.32 rnrads/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 i-n exposure periods. ~~hen the mon-thly data is plotted as in Figure 2, a slight peak is observed after June 1979. This peak is attributed to the elevated readings from two on-site TLD stations which are discussed later in the text. Since the two stations, lOSl and llSl, are on-site they do not repre-sent any environmental dose to the public. A comparison of the direct radiation data for 1980 shows the same average monthly dose for. both indicator stations (5.79 mrem/std. month) and control stations (5. 79 mrem/std. month)'.
In order to better evaluate the variation between TLD results a statistical model has been developed/, which is capable of separating a contribution by SNGS from the background component. The statistical method.utilized is a linear regression analysis which involves determining the functions which best describe. the background component by the least squares 1
method. Six models were originally tested and are described in a separate publication (13).
The equation which describes the model selected is:
where:
f = denotes a function of
= predicted value for station j, month m, and year i
= preoperational mean for station j ..
= av~rage of the control stations for month m and year i
= average of the control station for year i (a 11 p 11 in place Of 11 i II represents the preoperational period) 9
A computer program was developed for multiple regression analysis. The least squares fit (LSF) line based on all 1980 data was determined along with the statis-tics for this line. The data for 1980 was tested against predicted values and prediction limits determined from the model period line. Differences between predicted and.observed values are termed residuals .. Residuals outside the prediction limits of the predicted value are identified as outliers. For 1980, 29 outliers were predicted from a possible 294.
Three positive outliers. occurred at 7Sl. These occurred in January, March and.
October. Construction was underway in the area of this station. Since this type of activity has been known to effect the terrestrial component in the past, (7), this invalidates the preoperational mean. Eleven outliers at station lOSl and eleven outliers at station llSl can be attributed to the May 1979 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. No TLDs located beyond the plant boundary indicated any addi-tional dose from SNGS operation.
The remaining four outliers were randomly distributed among the stations and can be attributed to statistical fluctuations.
- Water Surface Water Monthly surface water samples were taken at five locations in the Delaware estuary.
One is downstream from the outfall area, one is in the outfall area, and another is directly west of the outfall area at the mouth of the Appoquinimink River. Two other stations are located upstream--one station is in the river and the other is in the Chesapeake and Delaware Canal. The station located at the mouth of the Appoquinimink River serves as the operational control. Surface water samples were analyzed for tritium, gross alpha emitters, gross beta emitters, strontium-89 and
-90, and gamma emitters.
Analysis of surface water for tritium yielded an average concentration of 122 pCi/l and ranged from 62 to 336 pCi/l. These levels are similar to those measured in the preoperational program as shown in Figure.'3. A gradual decrease in tritium activity
\
from 1973 to 1980 can be attributed to general reduction in the world-wide tritium .
inventory with the cessation of routine atmospheric weapons testing. ,
Gross alpha concentrations were generally below LLD, which ranged from <0.2 to <1.0
- pCi/l. Fifteen of the 60 samples analyzed showed detectable gross alpha acti.vity.
The average (0.3 pCi/l) was within the same range as the LLDs for the year. Gross alpha activity may be expected in suspended solids from naturally occurring radio-nuclides especially during periods of h.igh surface runoff.
Gross beta concentrations ranged from 5.9 to 176 pCi/l and averaged 58 pCi/l.
Nearly all of the beta activity was contributed by K-40, a natural component of salt and brackish waters, as illustrated in Figure 4, comparing 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 variations 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.
10
FIGURE 3 AVERAGE CONCENTRATIONS OF TRITIUM IN THE DELAWARE RIVER IN THE VICINITY OF ARTIFICIAL ISLAND, 1973 THROUGH 1980 10,000 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -....
/000 too 19&__ 192..L_ 19_zL___ 19..t..L_ 19=- 19L!'__ l9.2J_ l9__EQ_ 19_ 19_
FIGURE 4 AVERAGE CONCENTRATIONS OF BETA EMITTERS AND POTASSIUM-40 IN THE DELAWARE RIVER IN THE VICINITY OF ARTIFICIAL ISLAND, 1973 THROUGH 1980
- gross beta O Potassium-40
- rI 9
,1 I
N 'P.....i I
- , I I
19.z:L_ 19~ 19.:zL_ 19.u.._' 19.z.L._ 19.zL_ !9.2L 19...£2.... 19_ 19_
Gamma spectrometric analysis of surface water samples showed detectable concen-trati ans of K-40 in ten of 60 samples. The average K-40 concentration was 61 pCi/l and ranged from <7.8 to*130 pCi/l. K-40 is a natur?lly occurring radio-nuclide which is expecteq to be found in salt and brackish waters.
Levels of Sr-89 were below MDL (0.7 to 2.7 pCi/l) in nineteen of twenty samples.
Sr-89 was found in one sample. The concentration (1.8+/-0.7) pCi/l was comparable to the MDL levels found in the samples. Levels of detectable Sr-90 ranged from.
0.4 to 1.1 pCi/l in three of the twenty samples. The MDLs values ranged from
<0.4 to <1.4 pCi/l. The maximum level of Sr-90 detected in the preoperational program was 1.6 pCi/l (4).
Well ~~ater Monthly well water samples were taken from an on-site (indicator) well and two off-site (control) wells. All well water samples were analyzed for tritium, gross alpha and gross beta activity, and K-40 (by atomic absorption). Quarterly composites were analyzed for galTUlla emitters, and Sr-89 and Sr-90.
- No detectable concentrations of tritium were observed in any of the samples. The LLDs ranged from <96 pCi/l to <125 pCi/l. Gross alpha concentrations were generally below LLD which ranged from <0.6 to <2.8 pCi/l. Six of the 36 samples analyzed showed de-tectable gross alpha activity. The average was 2.1 pCi/l. The concentrations of gross beta .emitters averaged 8.7 pCi/l and ranged from 2.3 to 20 pCi/l. The potassium-40 activity as determined by atomfc absorption averaged 8.0 pCi/l. This indicates that the gross beta activity observed in these samples is primarily the result of naturally occurring K-40, a beta emitter.
No nuclides were detected by gamma spectrometry in any of the samples. Levels of Sr-89 were below MDL (0.6 to 1.3 pCi/l) in ten of twelve samples. The average concentration of Sr-89 found was 0.7 pCi/l which falls within the MDL range. Sr-90 was found in one sample with a concentration of 0.8 pCi/l. The range of MDLs for Sr-90 was 0.4 to 0.8 pCi /1.
Potable Water Both raw and treated water samples were taken at the Salem Water Company, the only drinking water processing plant in the vicinity of Artificial Island. The raw water source for this plant is Laurel Lake (a tributary of the Delaware River) and several
- adjacent wells. Potable water samples were analyzed monthly for tritium, gross alpha and gross beta activity, and K-40 (by atomic absorption); Sr-89 and -90, and gamma emitters were analyzed on a quarterly basis.
The concentration of tritium averaged 110 pCi/l fo.r all analyses, with no significant differences between the raw and treated samples. Detectable gross alpha activity was observed in 16 of 24 samples ranging between 0.4 pCi/l and*3.2 pCi/l in all samples.
Gross beta and K-40 concentrations were lower than in the saline surface water, as is usual for fresh water, with K-40 generally contributing less than 50% of the beta acti-vity. The average gross beta concentrations were 3.2 pCi/l (raw) and 2.5 pCi/l (treated).
The average K-40 results were 1.8 pCi/l (raw) and 2.2 pCi/l (treated).
13
Quarterly composites of raw and treated samples were analyzed for Sr-89 and -90, and gamma emitters. Strontium-89 levels were below MDL (0.9 pCi/l to 2.3 pCi/l). Stron-ti um-90 was observed in six of the eight samples with concentrati ans ranging between 0.4 pCi/l and 2.4 pCi/l, with two samples below the MDL (0.5 pCi/l and 1.1 pCi/l).
No nuclides were detected by ganma spectrometry in any of the samples.
Aguati c Benthos Benthic organisms were collected at four locations and analyzed for Sr-89 and Sr-90.
Levels of Sr-89 were below MDL (0.1-35 pCi/g) for all eight analyses~ The wide fluctuations in MDL are due to inconsistencies in sample size (0.12-25 grams dry).
Four of eight samples showed detectable Sr-90 concentration averaging 0.95 pCi/g-dry.
The detectable activity of these samples is below the MDL range (2.1 to 10 pCi/g-dry) of the other analyses. The MDL for radiostrontium as required by the Environmental Technical Specifications for benthic organisms was not met in all of the samples due to the impracticality of obtaining a sufficiently large sample size of benthic organisms.
Sediment Seqiment was collected semiannually at four locations and analyzed for gamma emitters and Sr-90.
Results of garrma spectrometry showed detectable levels of a variety of naturally occurring radionuclides as well as man-made radionuclides. One fallout nuclide (Cs-137) was observed intermittently at control stations as well as indicator stations.
Sr-90 was observed in two of the eight samples analyzed averaging 0.03 pCi/g-dry. The MDL range was <0.04 pCi/g-dry to <0.06 pCi/g-dry.
Ingestion Milk\
Milk samples were taken *twice a month from six local farms during 1930 and analyzed for I-131; gamma emitters, Sr-89 and Sr-90 were analyzed monthly. Following the atmospheric nuclear weapons test on October 15, detectable concentrations of I-131 were observed.
These concentrations were found in eleven of 24 samples collected from all stations in Novent>er and Decerrber. The I-131 obs_erved ranged between 0.12 and 1.7 pCi/l. Figure 5 shows the average I-131 concentrations in milk samples resulting from atmospheric nuclear weapons tests by the Peoples Republic of China between June 1974 and March 1978, and October 1980 and the Three Mile Island incident in 1979. No other I-131 was observed in any of the samples. . '
Ganma spectrmmtry showed detectable concentrations of K-40 in all samples and Cs-137 in 12 of the 72 samples analyzed. The annual average concentrations were 1500 pCi/l for,K-40 and 1.7 pCi/l for Cs-137. These levels were not significantly different between control and indicator stations.
14
SL J;Ci/l
- O 0 0 Jan.
I
~~
Feb.
r~1~, ,.
Aug.
S.pt Oct.
Nov.
Jan.
Feb.
Apr.
~ !May atnospheric weapons test July
- Sept.
~ .,,..June[~=====~=====J=une=~l~7,~19~74~======-e Jan. <
Feb.
n
- z
~)>
--l<
~ 1::.::~ -<'""
" July atrrospheric weapons test oS'.'!
. Aat. Sept. 26, 1976 -n"'
)>
O<t.
""' =w I ;on '""
N~. --lO
~z
~ .-nn Jan. ---
Feb. ~'""
n z
~__,
)>"'
r- )>
--l
~~
atnospheric weapons test C/lO r- z Sept. 17, 1977 )> (/l -n
- z 00
- -n "'c:
3~ I
- )>0
-< :=:
""" /
atJrospheric weafXJ!15 test ~z
+ March 14, 1978
-..JI
~
...<D'""
__,~
w
- I:
~ "'~
o:z Flg;:;i c:
- i::~
"'"'r-N~.
"* 07<
n~
mz 3
e:>--l m::i::
co 0
Feb.
Mar.
Apr.
10o
"' I""';:;*a atmspheric weapons test
~Aug. Oct. 15, 1980 S.pt Oct. )
Nov. ~
~ Jan.
Feb.
I~I:~,,.
Mt Aug.
N~.
~ Jen.
Feb, Apr.
July Aug.
I~I"""'"*
N~.
D~.
Strontium-89 was detected in three of the seventy-two samples analyzed with results ranging between 1.7 pCi/l and 5.9 pCi/l. The range of MDL values for Sr-89 was <1.3 pCi/l to <4.4 pCi/l. The wide range of values for the MDL was due to low chemical yields in some of the analyses. All of the positive results detected were within the MDL range. The concentration of Sr-90 was positive in 58 of the 72 samples analyzed and averaged3.7 pCi/l. The MDL range was <1.5 pCi/l to <6.7 pCi/l. Sr-90 concentrations were similar at indicator and control stations, indicating *no contri-bution from SNGS. Due to the 28 year half-life and biological assimilation, Sr-90 can be expected to remain long after routine atmospheric testing has ceased. All Sr-89 and -90 analyses have been chemical yield verified by atomic absorption to determine ~alcium interference.
Fish Edible fish samples (Aroorican Eel, White Perch, Channel Catfish, Spot, etc.) were collected at three locations and analyzed for gamma emitters and tritium. Fish*
bones were analyzed* for Sr-89 and Sr-90. '
Gamma spectrometry of these samples showed K-40 in all six samples analyzed at an average concentration of 3.8 pCi/g-wet with a range of 3.3-4.9 pCi/g-wet.
Tritium analyses were performed on both aqueous and organic fractions of the flesh portions of these samples. The average concentration of tritium was 112 pCi /1 with a range of 69-192 pCi/l for the aqueous fraction and 167 pCi/l for the organic fraction with a range 'of <90-249 pCi/l. Of the six samples analyzed, all results are essentially the same as those found in surface water for the same period.
Five of six bone samples analyzed for Sr-89 were below the MDL (0.06 to 0.2 pCi/g-dry).
One sample showed a detectable concentration of 0.3 pCi/g-dry. Four of the six samples analyzed for Sr-90 had detectable concentrati ans of 0 .03-0.09 pCi /g-dty.. The maximum level detected during the preoperational period was 0.94 pCi/g-dry.
Blue Crab Blue crab samples were collected at two locations and the flesh was analyzed for tritium in the aqueous fraction, ganma emitters and Sr-89 and -90. The shells were analyzed for Sr-89 and Sr-90.
K-40 was the only gamma emitter detected with an average of 2.4,pCi/g-wet.
Tritium concentrations were found in all of the samples analyzed with an average of 155 pCi/l. This comparable to tritium values found in surface water for this same period.
All results for Sr-89 in both the flesh and the shells were MDL with that value being
<0.03 pCi/g-wet for both flesh and shells. Two of four samples showed detectable activity with concentrations of 0.006 and 0.008 pCi/g-wet of Sr-90 in flesh. The MDL value was <0.005 pCi/g-wet. All of the shells had Sr-90 detectable activity.
The range of activities was 0.09 to 0.1 pCi/g-dry with no difference observed be-tween indicator and control stations.
Food Products A wide variety of other human food products was sampled and analyzed for ganma emitters, 16
and Sr-89 and -90. These included cucumbers, asparagus, peppers, cabbage, corn, squash and tomatoes. All samples contained K-40 at concentrations from* 1.5 to 3.9 pCi/g-wet.
No other gamma emitters were detected in these food products. Sr-89 concentrations were all below MDL, which ranged from 0.02 to 0.1 pCi/g-wet. Six of the seventeen samples analyzed showed detectable Sr-90 activity ranging from 0.004 to 0.018 pCi/g(wet). The MDLs ranged from 0.003 to 0.005 pCi/g-wet.
Game Four samples of muskrats and one sample of venison were taken during this period. Flesh from all five samples was analyzed for gamma emitters while muskrat bones were analyzed for Sr-89 and Sr-90. Only naturally occurring K-40 was detected in all five samples ran-ging from 2.5 to 3.5 pCi/g. Muskrat bones showed detectable Sr-89, with concentrations*
ranging between 0.09 and 0.3 pCi/g-dry. One sample had an MDL of <0.1 pCi/g-dry. Detec-table Sr-90 concentrations were observed in all samples ranging from 0.10 to 2.3 pCi/g-dry.
Beef Three beef samples were collected during this reporting period. Only *naturally occurring K-40 was detected in these samples at a concentration ranging between 1.5 and 2.3 pCi/g-wet.
Beef Thyroid Three 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 concentration of 0.9 pCi/g-wet. The other samples had LLDs for K-40 of 0.6 and 1.1 pCi/g-wet. No I-131 was detected in the samples with LLDs between <0.049 and <0.087 pCi/g-wet.
Fodder Crops Twelve .fodder crop samples were taken at nine local farms and analyzed for ganma emitters.
Only naturally occurring K-40 was observed in all samples, with an average of 10 pCi/g-dry.
17
CONCLUSIONS The Radiological Environmental Monitoring Program for Salem Nuclear Generating Station at Artificial Island was conducted during 1980 in accordance with th~
- 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 environment. In addition no increases were observed in either radionuclide concentrations in critical pathways or with respect to radionuclide build up.
Ambient radiation levels were relatively low, averaging about 5.79.mrem/std.
month. I-131 detected in a few samples was attributed to atmospheric fallout from the nuclear weapons test by the Peoples Republic of China in October 1980.
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.
18 .
REFERENCES (1) Radiation Management Corporation. 11 Salem Nuclear Generating ~tation -
Radiological Environmental Monitoring Program - 1973. 11 RMC-TR-74-09, 1974.
( 2) Radiation Management Corporation. "Artificial Island Radiological Envi ronment1al Monitoring Program - 1974 Annual Report. 11 RMC-TR-75-04, 1975~ '
( 3) Radiation Management Corporation "Artificial Island Radiological Environmental Monitoring Program - 1975 Annual Report. 11 RMC-TR-76-04, 1976.
( 4) Radiation Management Corporation. "Artificial Island Radiological Environmental Monitoring Program - Preoperational Summary - 1973 through 1976. 11 RMC-TR-77-03, 1978. {
(5) Radiation Management Corporation. "Artificial Island Radiological Environmental Monitoring Program - Decerrt>er 11 to December 31, 1976. 11 RMC- TR- 77-02 , 19 77. ,
(6) Radiation Management Corporation. 11 Artificial Island Radiological Environmental Monitoring Program - 1977 Ann1Jal Report11 RMC-TR-78-04A, 1978.
( 7) Radiation Management Corporation. "Artificial Island Radiological Environmental Monitoring Program - 1978 Annual Report" RMC-TR-79-03, 1979.
( 8) Radiation M<magement Corporation. "Artificial Island Radiological Environmental Monitoring Program - 1979 Annual Report" RMC-TR-80-03:11 1980.
(9) Public Service Electric and Gas Company. "Environmental Report 31 Operating License Stage - Salem Nuclear Generating Station Units 1 and 2. 11 1971.
( 10) United States Atomic Energy Commission. 11 Final Environmental Statement -
Salem Nuclear Generating Station, Units 1 and 2. 11 Docket No. 50-272 and 50-311, 1973.
( 11) Public .Service Electric and Gas Company. 11 Final Safety Analysis Report -
Salem Nuclear Generating Station, Units 1 and 2. 11 1972.
(12) Radiation Management Corporation. 11 Qual ity Control Data 1980 - Annual Report", i981.
(13) Radiation Management Corporation. "Artificial Island Radiological Environmental Interpretation of Results of the Thermoluminescent Dosimetry Program" RMC-TR-78-11, 1978.
19
APPENDIX A PROGRAM
SUMMARY
21
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 SALEM COUNTY, NEW JERSEY JANUARY 1, 1980 TO DECEMBER 31, 1980 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Air Particulates Alpha 104 0.7 1.7 (49/52) 3H3 110 mi. NE 1.9 (49/52) 1.9 (49/52) 0
( 10- 3 pCi /m 3) (0.6-4.1) (0.6-7.6) (0.6-7.6)
Beta 416 29 ( 364/364) lFl 5.8 mi. N 32 (52/52) 26. (52/52) 0 (4.3-158) (15-158) (7.9-74)
Sr-89 32 0.6 2.4 ( 11/28) 5Dl 3.5 mi. E 4.4 (2/4) 0.8 (1/4) 0 (0.6-8.2) (0.6-8.2l Sr-90 32 0.2 o. 7 ( 13/28) 2F2 8. 7 mi. NNE 1.1 (2/4 0.5 (2/4) (J (0.2-2.0) (0.4-1.8) (0.2-0.7)
Gamma 32 Be-7 81 (28/28) 2S2 0.4 mi. NNE 97 (4/4) 84 (4/4) 0 (43-150) (60-150) (42-120)
N K-40 5.8 6.0 (3/28) 2S2 0.4 mi. NNE 8.1 (1/4) 3.6 ( 1/4) 0 w (4.2-8.1) -
Nb-95 0.2 8. 7 (7/28) lFl 5.8 mi. N 11 (1/4) 5.4* (1/4) 0 (6.9-11) .
Zr-95 0.6 5. 3 ( 7/28) lFl 5.8 mi. N 6 .8 ( 1/4) 3.2 ( 1/4) 0 Ru-103 0.4 (4.1-6.8) 4.4 (7/28) 2F2 8. 7 mi. NNE 4.8 ( 1/4) 3.8 (3/4) 0 (3.8-4.8)
Cs-137 0.3 0.9 (19/28) 2S2 0 .4 mi. NNE 1.2 (2/4) 0.8 (3/4) 0 (0.5-1.6) (0.7-1.6) (0. 5-1. 2) lFl 5.8 mi. N 1.2 (2/4) 0 (0.8-1. 5l Ce-141 0.5 4.8 (7/28) lFl 5.8 mi. N 5.8 ( 1/4 3.2 (1/4) 0 (4.3-5.8) - -
Ce-144 1.5 2.7 (9/28) 5Sl 1.0 mi. E 3.0 (2/4) - (0/4) 0 (1.8-3.3) (2.8-3.2) 5Dl 3.5 mi. E 3.0 (1/4) 0 Air Iodine I-131 370 5.7 - (0/370) None Detected - (0/52) 0' (lo- 3 pCi /m 3)
Precipitation Alpha 12 0.5 0.9 (3/12) 2F2 8.7 mi. NNE 0.9 (3/12) No Control 0
( pCi /1) (0.8-1.1) (0.8-1.1) Location Beta 12 2.3 11 ( 10/12) 2F2 8. 7 mi. NNE 11 ( 10/12) No Control 0 (2.9-26) (2. 9-26) Lo ca ti on H-3 12 90 - (0/12) None Detected No Control 0 Location
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM NUCLEAR GENERATING.STATION DOCKET NO. 50-272 SALEM COUNTY, NEW JERSEY JANUARY 1, 1980 TO DECEMBER 31, 1980 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NON ROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Precipitation (cont.) Sr-89 4 1.2 - (0/4) None Detected No Control 0 (pCi/l) Location Sr-90 4 0.8 1.2 (3/4) 2F2 8. 7 mi. NNE 1.2 (3/4) No Control 0 (0.4-2.0) (0.4-2.0) Location Gamma 4 - (0/4) None Detected No Control 0 Location Direct Radiation Gamma 294 5.79 (246/246) llSl 0. 09 mi. SW 14. 28 ( 12/12) 5.79 (48/48) 0 (mrem/std. month) Dose (monthly) (3.65-26.60) (5.32-26.60) (4.17-6.96)
Gamma 98 5. 22 ( 82/82) US 1 O. 09 mi. SW 13.14 (4/4) 5.15 {16/16) 0 Dose (quarterly) (3.23-23.52) {7.35-23.52) (4.37-6.14)
Gamma 33 5.17 (28/28) 1G3 19 mi. N 6.84 {1/1) 6.16 (5/5) 0 Dose (semi-annual) (3.84-6.42) (5.23-6.84)
N Surface Water Alpha 60 0.2 0.3 (12/48) 16Fl 6.9 mi. NNW 0.6 (3/12) 0.3 (3/12) 0
..;:::,. (0.4-0.9)
( pCi /1) (0.1-0.9) (0.2-0.4)
Beta 60 58 (48/48) 7El 4.5 mi. SE 85 (12/12) 57 (12/12) 0
{5.9-176) (19-176) (6.0-98)
H-3 59 91 138 (18/48) 7El 4.5 mi. SE 150 (7/12) 136 (5/11) 0 (62-336) (67-336) (82-275)
Sr-89 20 0.7 1. 8 ( 1/16) 7El 4.5 mi. SE 1.8 {1/4) - (0/4) 0 Sr-90 20 0.4 0.8 (2/16) 1F2 7.1 mi. N 1.1 {1/4) 0.4 ( 1/4) 0 (0.5-1.1)
Gamma 60 K-40 7.8 71 (40/48) 7El 4.5 mi. SE 90 (12/12) 60 ( 10/12) 0 (23-130) (23-130) (28-99)
Well Water Alpha 36 0.6 2.1 (4/12) 5D13.5mi.E 2.9 (l/12) 2.1 (2/24) 0 (pCi /1) ( 1.4-2.8) ( 1. 3-2. 9)
Beta 36 3.5 13 ( 12/12) 4Sl Site Well #5 ENE 13 (12/12) 6.8 (23/24) 0 (3.3-27~ (3.3-27) (2.3-20)
H-3 36 96 - (0/12 None Detected - (0/24) 0 K-40 36 12 ( 12/12) 4Sl Site Well #5 ENE 1 ( 12/12) 6.0 (24/24) 0 (2.4-16) (2.4-16) (2.5-12)
Sr-89 12 0.6 0.7 (2/4) 4Sl Site Well #5 ENE 0.7 (2/4) - (0/8) 0 Sr-90 12 0.4 -
(0/4) 3El 4.1 mi. NE 0.8 (1/4) 0.8 ( 1/8) 0 Gamma 12 - (0/4) None Detected* - (0/4) - (0/8) 0
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM NUCLEAR .GENERATING STATION DOCKET NO. 50-272 SALEM COUNTY, NEW JERSEY JANUARY 1, 1980 TO DECEMBER 31, 1980 ANALYSIS AND LOWER NUMBER OF f.EDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NON ROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* . (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Potable Water Alpha 24 0.4 1.0. (16/24) 2F3 8.0 mi. NNE 1.0 (16/24) No Control 0 Raw-Treated (0.3-3.2) (0.3-3.2) Location (pCi /1) Beta 24 2.8 (24/24) 2F3 8.0 mi. NNE 2.8 (24/24) No Control 0 (1.8-4.0~ (1.8-4.0~ Location H-3 24 90 92 ( 3/24 2F3 8.0 mi. NNE 92 (3/24 No Control 0 (81-103) (81-103) Location Sr-89 8 0.9 - (0/8) None Detected - (0/8) No Control 0 Location Sr-90 8 0.5 1.0 (6/8) 2F3 8.0 mi. NNE 1.0 (6/8) No Control 0 (0.4-2.4) (0.4+/-2.4) Location K-40 24 2.0 (24/24} 2F3 8.0 mi. NNE 2.0 (24/24) No Control 0 (0.6-5.0) (0.5-5.0) Location N Gamma 8 - (0/8) None Detected - (0/8) No Control 0 (Jl Location Benthos Sr-89 8 0.1 - (0/6) None Detected - (0/2) 0 (pCi /g-dry)
Sr-90 8 2.1 0.3 (3/6) llAl 0.2 mi. SW 0.3 ( 1/2) 2.9 (1/2) 0 (0.1-0.5)
?El 4.5 mi. SE 0.3 (2/2) 0 Sediment Sr-90 8 0.04 0.03 (1/6) 12Cl 2.5 mi. WSW 0.03 (1/2) 0.03 (1/2) 0
' (pCi/g-dry)
_,. ?El 4.5 mi. SE 0.03 (1/2) 0 Gamma 8 K-40 15 (6/6) 12Cl 2.5 mi. WSW 18 (2/2) 18 (2/2) 0 (14-16) ( 17-18) (17-18)
Mn-54 0.02 0.06 (1/6) llAl 0.2 mi. SW 0 .06 ( 1/2) - (0/2) 0 Co-60 0.03 0.21 (2/6) llAl 0. 2 mi. SW 0.21 (2/2) - (0/2) 0 (0.09-0.32) (0.09-0.32)
Cs-137 0.03 0.11 (5/6) llAl 0.2 mi. SW 0.19 (2/2) 0.06 (1/2) 0 (0.06-0.20) (0.17-0.20)
Ra-226 0.71 (6/6) llAl 0.2 mi. SW 0.77 (2/2) 0.70 (2/2) 0 (0.58-0.89) (0.7-0.84) (0.54-0.85)
Th-232 0.93 (6/6) 16Fl 6.9 mi. NNW 1.0 (2/2) 0.8 (2/2) 0 (0.67-1.1) ( 1.0) (0.8)
ARTIFICIAL ISLAND RADIOLOGICAL ENVJRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 SALEM COUNTY, NEW JERSEY JANUARY 1, 1980 TO DECEMBER 31, 1980 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR.LOCATIONS LOCATION.WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Milk I-131 144 0.06 o.51 (81/20) 3Gl 17 mi. NE 0.94 (3/24) 0.94 (3/24) 0 (pCi /l) (0_.15-L 7~ (0.12-1.6l (0.12-1.6)
Sr-89 72 1.4 4.0 (3/60 5F2 7.0 mi. E 8.0 (1/12 2.5 (3/12) 0 Sr-90 72 1.1 (1.7-8.0) 3.3 (56/60) 5F2 7.0 mi. E 5.3
-(11/12) (1.3-3.4) 3.9 (11/12) 0 (0.5-9.1) (1.2-9.1) (2.5-5.6)
Gamma 72 K-40 1482 (60/60) 15Fl 5.2 mi. NW 1533 ( 12/ 12) 1567 (12/12) 0 (890-2000) ( 1300-1900) (1400-1900)
Cs-137 0.8 3.4 (12/60) 5F2 7.0 mi. E 4.9 (5/12) 2.1 (1/12) 0 (1.5-6.3) (3.7-6.3) f'.) Edible Fish H-3 6 99 192 (1/4) 7El 4.5 mi. SE 192 ( 1/2) 69 ( 1/2) 0 m (pCi /l) (aqueous)
H-3 '6 90 184 (3/4) llAl 0.2 mi. SW 202 (2/2) 180 (2/2) 0 (organic) (147-249) (155-249) ( 117-243)
(pCi /g-dry) Sr-89 6 0.06 - (0/4) 12Cl 2.5 mi. WSW 0.3 (1/2) 0.3 (1/2) 0 (bones)
Sr-90 6 0.07 0.05 (3/4) llAl 0.2 mi. SW 0.06 (2/2) -0.03 (1/2) 0 (bones) (0.03-0.09) (0.03-0.09)
(pCi /g-wet) Gamma 6 K-40 3.8 (4/4) llAl 0.2 mi. SW 4.1 (2/2) 3.8 (2/2) 0 (3.3-4.9) (3.3-4.9) (3.5-4;0)
Blue Crab Sr-89 2 0.02 - (0/1) None Detected - (0/1) 0 (pCi /g-dry) (shells) sr.;.go 2 0.087 (1/1) 12Cl 2.5 mi. WSW 0.10 (1/1) 0.10 (1/1) 0 (shells) -
(pCi/l) H-3 4 99 339 (1/2) llAl 0.2 mi. SW 339 (1/2) 82 (1/2) 0 (pCi I g-wet)
(flesh)
Sr-89 4 0.01
- (0/2) None Detected -
( 0/2) 0 (flesh)
Sr-90 4 0.004 0.006 (1/2) 12Cl 2.5 mi. WSW 0.008 (1/2) 0.008 (1/2) 0 (flesh)
Gamma 4 K-40 2.8 (2/2) llAl 0.2 mi. SW 2.8 (2/2) 2.0 (2/2) 0 (2.7-2.8) (2.8) (2.0)
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 SALEM COUNTY, NEW JERSEY JANUARY l, 1980 TO DECEMBER 31, 1980 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) .PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Fruits &Ve~etables Sr-89 17 0.02 - (0/10) None Detected - (0/7) 0 (pCi / g-wet)
Sr-90 17 0,003 0.01 (5/10) 1F3 5.9 mi. N 0. 02 {1/1) 0.01 {1/7) 0 (0.004-0.018)
Gamma 17 K-40 2.7 (10/10) 1F35.9mi.N 3.9 (1/1) 2.3 (7/7) 0 (2.0-3.9) (1.5-2.6)
Game. Sr-89 4 0.1 0.3 (2/2) 3El4.lmi.NE 0.3 (2/2) 0.09 (1/2) 0 (pCi/g-dry) (bones) (0.2-0.3) (0.2-0.3)
Sr-90 4 1.4 (2/2) 3E 1 4. 1 mi . NE 1.4 (2/2) 0.2 (2/2) 0 (bones) (0.56-2.3) (0.56-2.3) (0.1-0.31)
(pCi/g-wet) Gamma 5 (flesh)
K-40 2.8 (3/3) 3El 4.1 mi. NE 3.0 (2/2) 3.1 (2/2) 0 (2.5-3.0) (2.9-3.0) (2.6-3.5)
Beef Gamma 3 (pCi/g-wet) K-40 1.9 (3/3) 3El 4.1 mi. NE 2. 0 (1/1) No Control 0 (1.5-2.3) Sample Available Beef Thyroid Gamma 3 (pCi I g-wet) K-40 0.6 0.9 (1/3) 14Fl 5.5 mi. WNW 0.9 (1/2) No Control 0 Sample Available Fodder Crops Gamma 12 (pCi/g-dry) K-40 9 .8 ( 10/10) 5F3 7.4 mi. E 15 ( 1/1) 11 (2/2) 0 (5 .4-19) (6.9-15)
- LLD listed is the lowest calculated LLD during reporting period. Strontium-89 and -90 detection levels are Minimum Detectable Levels (MDL).
APPENDIX B SAMPLE~OESIGNATION AND LOCATIONS 29
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 11 SA 11
- The next three letters are for the media sampled.
AIO = Air I.odine GAM = Game APT = Air Particulates GAD = Deer ECH = Hard Shell Blue Crab IDM = Immersion Dose (TLD)
ESB = Benthos MLK = Milk ESF = Edible Fish PWA = Potable Water;* (PWR = raw, PWT = treated)
ESS = Sediment RWA = Rain Water FPB = Beef SWA = Surface Water FPV = Food Products, Various THB = Bovine Thyroid FPG = Corn VGT = Fodder Crops FPL = Green leafy Vegetables WWA = Well Water The last four ?Ymbols 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 num-bered in a clockwise direction; i.e., 2=NNE, 3=NE, 4=ENE, etc. The next digit is a letter which represents the radial distance from the plant:
s = On-site location E = 4-5 miles off-site*
A = 0-1 miles off-site F = 5-10 miles off-site B 2 miles off-site G = 10-20 miles off-site c = 2-3 miles off-site H' = >20 miles off-site D = 3-4 miles.off-site The last number 1s the station numerical designation within each sector and zone; e.g., 1,2,3, .*** Fpr example-, the designation SA-WWA-5Dl would indicate a sample in the SNGS program SA, consisting of well water (WWA), which had been collected in the 22.5 degree sector centered on east 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.
31
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~l STATION STATION SAMPLE CODE LOCATION TYPES
\\
lFl 5.8 mi. N of vent; Fort El fsborg APT ,IDM 1F2 7.1 mi. N of: vent; midpoint of Del aware River SWA 1F3 5.9 mi. N of vent; local farm FPL lGl 13 mi. N'of vent; local farm IDW,MLK, FPG, VGT 1G3 19 mi. N of vent; Wilmington, Del aware IDM 2S2 O. 4 mi. NNE of vent APT ,AID, IDM 2El 4.4 mi. NNE of vent; local fann IDM,FPV 2F2 8.7 mi. NNE of vent; Salem Substation APT ,AID ,RWA, IDM 2F3 8.0 mi. NNE of vent; Salem Water Company PWR,PWT 2F4 6.3 mi. NNE of vent; local. farm MLK,FPG,VGT 2F5 7.4 mi. NNE of vent; Salem High School IDM 2H1 34 mi. NNE of 'vent; RMC, Phil a. IDM 3El 4.1 mi. NE of vent; local farm IDM,WWA,THB,FPV, FPG,GAM,FPB 3F2 5.1 mi. NE of vent; Hancocks Bridge Municipal Bldg. IDM 3F3 8.6 mi. NE of vent; Quinton Township School IDM 3Gl 17 mi. NE of vent; local fann IDM,MLK,FPG,VGT 3Hl 32 mi. NE of vent; National Park, N.J. IDM 3H3 110 mf. NE of vent; Maplewood Laboratories APT ,AID,IDM 3H4 18 mi. NE of vent; local farm FPV,FPG 4Sl 1400 ft. ENE of vent; site well #5 WWA 4S2 1700 ft. ENE of vent; production well #5 WWA 4D2 3.7 mi. ENE of vent; Alloway Creek Neck Road IDM 32
TABLE B-1 (CONT.)
STATION STATION SAMPLE CODE LOCATION TYPES 4El 4-5 mi. ENE of vent GAD 5Sl 1.0 mi. E of vent; site access road APT ,AIO, IDM 501 3.5 mi. E of vent; local farm APT ,AIO,IDM, WWA,FPG,VGT 5Fl 8.0 mi. E of vent IDM,FPV 5F2 7.0 mi,. E of vent; local farm MLK,VGT 5F3 7.4 mi. E of vent; local farm FPG 6Sl 0.2 mi. ESE of vent; observation platform IDM 6S2 0.2 mi. ESE of vent; observation bldg. IDM 6Fl 6.4 mi. ESE of vent; Stow Neck Road IDM 7Sl 0.12 mi. SE of vent; station personnel gate IDM 7El 4.5 mi. SE of vent; 1 mi. Wof Mad Horse Creek SWA,ESB,ESS,ESF 7F2 9.1 mi. SE of vent; Bayside, New Jersey IDM 9E1 4.2 mi. S of vent IDM lOSl 0.14 mi. SSW of vent; site shoreline IDM 1001 3.9 mi. SSW of vent; Taylor's Bridge Spur APT ,AIO, IDM 10F2 5.8 mi. SSW of vent IDM lOGl
- 12 mi. SSW of vent; Sll\Yrna, Delaware IDM 11Sl 0.09 mi. SW of vent; site shoreline IDM 11Al 0.2 mi. SW of vent; outfall area SWA,ESB,ESS, ESF,ECH 1101 3.5 mi. SW of vent GAM 11E2 5.0 mi. SW of vent IDM 11Fl 5.2 mi. SW of vent; Taylor's Bridge, De'laware IDM,GAM 12Cl 2.5 mi. WSW of vent; west bank of Delaware river S~~A, ESF, ECH, ESB,ESS 33
TABLE B-1 (CONT.)
STATION STATION SAMPLE CODE LOCATION TYPES 12El 4.4 mi. WSW of vent; Thomas Landing IDM 12Fl 9.4 mi. WSW of vent; Townsend Elementary School IDM 13El 4.2 mi. Wof vent; Diehl House Lab IDM 13E3 4.9 mi. Wof vent; 1ocal fa.rm MLK,VGT 13Fl 9.8 mi. Wof vent; Middletown, Del aware IDM 13F2 6.5 mi. Wof vent; Odessa, Delaware IDM 13F3 9.3 mi. Wof vent; Redding Middle School, Middletown, DE IDM 1401 3.4 mi. WNW of vent; Bay View, Delaware IDM 14Fl 5.5 mi. WNW of vent; 1ocal farm MLK,FPV,FPG, FPB, THB-, VGT 14F2 6.6 mi. WNW of vent; Boyds Corner IDM 15Fl 5.2 mi. NW of vent; 1ocal farm MLK,FPG,VGT
.15F3 5. 4 mi. NW of vent IDM 16El 4.1 mi. NNW of vent; Port Penn APT ,AIO,IDM 16Fl 6.9 mi. NNW of vent; C & D Canal SWA,ESB,ESS 16F2 8.1 mi. NNW of vent; Delaware City Public School IDM 16Gl 15 mi. NNW of vent; Greater Wilmington Airport IDM 34
MAP 8-1 ON SITE SAMPLING LOCATIONS ARTIFICIAL ISLAND 0
SCALE OF l.'llLES 35
MAP B-2 OFF SITE SAMPLING LOCATIONS ARTIFICIAL ISLAND
!OF2 I
- ..I 2 3 OB-H I I I SCALI Of MILIS 36
APPENDIX C 1980 DATA TABLES 37
DATA TABLES Appendix C presents the analytical results of the 1980 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 Beta Emitters in Air Particulates 41 C-2 Concentrations of Gross Alpha Emitters in Air Particulates 43 C-3 Concentrations of Garrma Emitters in Quarterly Composites of Air Particulate Samples **********.*********.********************** 44 C-4 Concentrations of Strontium-89 and -90 in Quarterly Composites of Air Particulate Samples **.*****.****.************************* 48 C-5 Concentrations of Iodine-131 in Filtered Air..................... 49 C-6 Sampling Dates for Air Samples ****.********.********************* 51 C-7 Concentrations of Tritium, Gross Alpha and Gross Beta Emitters in Precipitation . . . ... . . . . . . . . . . . . . . . . . . . . . . . . . . ... . . . . . . . . . . . . . . . . . . . 56 C-8 Concentrati ans of Stronti um-89 and -90 and Gamma Emitters in Quarterly Composites of Precipitation **************************** 57 C-9 Direct Radiation Measurements*- Monthly TLD Results ************** 58 C-10 Direct Radiation Measurements - Quarterly TLD Results * * * ** * *** **
- 59 C-11 Direct.Radiation Measurements - Semi-Annual TLD Results........... 60 C-12 Concentrations of Tritiu~ in Surface Water ****************** ~***** 61 C-13 Concentrations of Gross Alpha Emitters in Surface Water * * *.* * * * * *
- 62 C-14 Concentrations of Gross Beta Emitters in Surface Water * * * * * * * * * *
- 63 C-15 Concentratiqns of Gamma Emitters in Surface Water................ 64 C-16 Concentrations of Strontjum-89 and -90 in Surface Water.......... 65 C-17 Concentrations of Tritium, Gross Alpha and Gross Beta Emitters, and Potassium-40 in Well Water*****~********************************* 66 C-18 Concentrations of Strontium-89 and -90, and Garrina Emitters in Quarterly Composites of Well Water............................... 67 C-19 Concentrations of Tritium, Gross Alpha and Gross Beta Emitters, and Potassium-40 in Raw and Treated Potable Water.................... 68 39
DATA TABLES (cont.)
TABLE TABLE TITLE PAGE NUMBER C-20 Concentrations of Strontium-89 and -90, and Gamma Emitters in Quarterly Composites of Potable Water ************************ 69 C-21 Concentrations of Strontium-89 and -90 in Benthos ............ /
70 C-22 Concentrations of Strontium-90 and Gamma Emitters in Sedime~-v.' 71 C-23 Concentrations of Iodine-131 in Milk ************************* 72 C-24 Concentrations of Gamma Emitters and Strontium-89 and -.90 in Mi.lk ******************************.************************** 73 C-25 Sampling Dates for Milk Samples * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
- 75 C-26 Concentrations of Gamma Emitters in Edible Fish ************** 78 C-27 Concentrations of Strontium-89 and -90, and Tritium in Edible Fish *Samples *.*.* *...... *..*......*... ~ .*.**. "*** ........ ~. 79 C-28 Concentrations of Gamma Emitters in Blue Crab Samples ********* 80 C-29 Concentrations of Strontium-89 and -90, and Tritium in Blue Crab Samples .*.*. ~ *..*.*....*... ! * * * * * * * * * * * * * . * ** * * * * * * * * *
- 81 C-30 Concentrations of Strontium-89 and ~90, and Gamma Emitters in Food Products * * * * * * * * * * * * * * * * * * * * * * * * * * . * * * * * * * * * * * * * * * * * * * *
- 82 C-31 Concentrations of Strontium-89 and -90, and Gamma Emitters in Meat, Game and Bovine Thyroid ******************************** 83 C-32
- Concentrations of Gamma Emitters in Fodder Crop Samples ****** 84 C-33 Typical LLDs for Gamma Spectrometry .************************** 85
/ ,/
40
TABLE C-1 CONCENTRATIONS OF GROSS BETA EMITTERS IN AIR PARTICULATES Results in Units of 10- 3 pCi/m3 +/- 2 sigma STATION NUMBER MONTH SA-APT-2S2* SA-APT-5Sl SA-APT-501 SA-APT-1001 SA-APT-16El SA-APT-lFl SA-APT-2F2 SA-APT-3H3 AVERAGE JANUARY** 24+/-6 24+/-6 24+/-7 27+/-6 20+/-6 26+/-7 25+/-7 21+/-6 24+/-5 35+/-6 34+/-6 36+/-6 29+/-5 30+/-6 34+/-6 37+/-6 36+/-6 34+/-6 24+/-5 22+/-5 22+/-5 28+/-6 16+/-5 24+/-5 21+/-5 21+/-5 22+/-7 21+/-3 20+/-3 23+/-3 24+/-3 23+/-3 19+/-3 24+/-3 19+/-3 22+/-4 FEBRUARY 22+/-5 23+/-5 18+/-5 26+/-5 26+/-5 23+/-5 21+/-5 22+/-5 23+/-5 17+/-4 16+/-4 17+/-5 14+/-4 18+/-5 15+/-5 16+/-5 22+/-5 17+/-5 33+/-5 26+/-5 30+/-5 33+/-5 27+/-5 30+/-5 36+/-6 32+/-5 31+/-7 18+/-5 22+/-5 14+/-5 17+/-4 23+/-5 19+/-5 17+/-5 23+/-6 19+/-7
-~ 21+/-5 21+/-4 23+/-5 23+/-5 20+/-5 25+/-5 22+/-5 26+/-5 23+/-4 MARCH 22+/-5 21+/-5 25+/-5 20+/-4 23+/-5 23+/-5 24+/-5 27+/-5 *23+/-4 21+/-5 20+/-4 20+/-5 19+/-5 17+/-5 25+/-5 29+/-6 19+/-5 21+/-8 17+/-4 16+/-4 20+/-5 15+/-4 19+/-4 18+/-5 18+/-4 19+/-5 18+/-3 5.4+/-3.7 4.3+/-3,3 5.2+/-3.8 4.1+/-3.5 8.3+/-4.* 3 4.4+/-3. 7 6.5+/-4.2 8.2+/-3.9 5.8+/-3.4 APRIL 23+/-5 25+/-5 20+/-5 26+/-5 26+/-5 24+/-5 27+/-5 22+/-5 24+/-5 23+/-5 19+/-4 23+/-5 16+/-4 16+/-5 20+/-5. 22+/-5 18+/-4 20+/-6 25+/-5 23+/-5 26+/-5 23+/-5 23+/-5 25+/-5 24+/-5 22+/-5 24+/-3 14+/-4 13+/-4 9.4+/-3.8 14+/-4 9.3+/-4.5 15+/-4 14+/-4 7.9+/-3.5 12+/-5 MAY 21+/-5 20+/-4 16+/-4 23+/-4 18+/-4 20+/-4 14+/-4 16+/-4 19+/-6 24+/-5 22+/-5 20+/-5 20+/-5 23+/-5 21+/-5 21+/-5 20+/-5 21+/-3 14+/-4 16+/-4 20+/-4 73+/-3 18+/-5 15+/-4 14+/-4 13+/-4 23+/-41 22+/-4 21+/-4 13+/-4 22+/-4 23+/-5 23+/-5 23+/-5 29+/-5 22+/-9 29+/-6 32+/-6 33+/-7 30+/-6 30+/-7 33+/-6 31+/-6 27+/-6 31+/-4 JUNE 26+/-5 24+/-5 24+/-6 24+/-4 23+/-5 26+/-6 22+/-5 21+/-5 24+/-4 20+/-5 24+/-5 26+/-6 20+/-5 22+/-5 23+/-5 20+/-5 20+/-5 22+/-5 23+/-5 16+/-4 18+/-6 18+/-4 20+/-5 18+/-5 20+/-5 18+/-5 19+/-4 22+/-5 28+/-5 32+/-6 27+/-6 23+/-6 22+/-5 22+/-5 27+/-5 25+/-7
TABLE C-1 (cont.)
CONCENTRATIONS OF GROSS BETA EMITTERS IN AIR PARTICULATES Results in Units of 10- 3 pCi/m 3 +/- 2 sigma STATION NUMBER MONTH SA-APT-2S2* SA-APT-5Sl SA-APT-501 SA-APT-1001 SA-APT-16El SA-APT-lFl SA-APT-2F2 SA-APT-3H3 AVERAGE JULY 25+/-5 24+/-5 23+/-6 28+/-5 28+/-2 28+/-6 22+/-5 20+/-2 25+/-6 28+/-3 27+/-3 26+/-3 24+/-2 25+/-3 28+/-3 25+/-3 22+/-2 26+/-4 28+/-5 28+/-5 38+/-7 31+/-6 31+/-7 26+/-6 27+/-6 32+/-6 30+/-8 27+/-5 20+/-4 26+/-5 21+/-4 21+/-4 18+/-5 20+/-4 25+/-5 22+/-7 AUGUST 42+/-7 40+/-6 40+/-8 43+/-7 45+/-8 35+/-7 37+/-7 29+/-6 39+/-10 28+/-5 28+/-5 26+/-6 24+/-6 26+/-6 28+/-6 29+/-5 26+/-6 27+/-3 23+/-5 21+/-5 24+/-5 23+/-5 27+/-6 27+/-6 22+/-5 22+/-5 24+/-5 15+/-5 22+/-5 23+/-5 11+/-4 19+/-5 19+/-5 20+/-5 16+/-5 18+/-8 32+/-5 31+/-5 32+/-6 24+/-5 35+/-7 28+/-6 32+/-7 29+/-5 30+/-7 SEPTEMBER 34+/-6 29+/-6 29+/-7 28+/-5 26+/-6 29+/-7 26+/-7 22+/-6 28+/-7
+::> 24+/-5 26+/-5 22+/-5 20+/-5 29+/-7 *23+/-5 28+/-7 26+/-5 25+/-6 N
20+/-5 18+/-4 18+/-5 24+/-5 23+/-5 36+/-6 21+/-5 16+/-4 22+/-13 17+/-5 14+/-4 15+/-5 19+/-5 13+/-5 15+/-5 12+/-6 15+/-4 15+/-4 OCTOBER 20+/-2 18+/-2 21+/-2 20+/-2 19+/-2 18+/-2 21+/-2 17+/-2 19+/-3 28+/-5 26+/-4 27+/-5 20+/-4 22+/-4 27+/-5 25+/-7 19+/-4 24+/-7 34+/-6 23+/-6 30+/-7 31+/-6 33+/-7 24+/-6 33+/-7 28+/-6 30+/-8 14+/-4 19+/-4 15+/-5 20+/-5 16+/-4 19+/-5 19+/-5 13+/-4 17+/-5 NOVEMBER 24+/-5 23+/-5 25+/-5 24+/-5 26+/-5 21+/-5 23+/-5 17+/-4 23+/-6 50+/-7 45+/-6 44+/-7 52+/-7 45+/-8 46+/-7 54+/-7 38+/-5 47+/-10 46+/-6 49+/-6 53+/-6 50+/-6 47+/-6 158+/-16 43+/-6 37+/-5 60+/-79 46+/-7 46+/-6 38+/-6 36+/-5 42+/-5 38+/-6 39+/-6 49+/-6 42+/-9 36+/-6 40+/-5 41+/-6 40+/-6 42+/-6 34+/-6 38+/-6 47+/-6 40+/-8 DECEMBER 73+/-8 123+/-12 77+/-8 88+/-9 94+/-9 102+/-10 75+/-8 58+/-7 86+/-40 109+/-11 75+/-8 84+/-8 69+/-7 78+/-8 78+/-8 78+/-8 69+/-7 80+/-25 60+/-7 65+/-7 61+/-7 65+/-7 56+/-6 57+/-7 62+/-7 51+/-6 60+/-10 59+/-7 62+/-7 75+/-8 57+/-7 66+/-8 72+/-8 77+/-8 74+/-8 68+/-16 AVERAGE 29+/-34 29+/-37 29+/-32 29+/-33 28+/-32 31+/-49 28+/-31 26+/-27 29+/-35
- Location of station SA-APT-2Sl was moved to station SA-APT-2S2 on 4-28-80.
- Sampling dates can be found on Table C-6.
TABLE C-2 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN AIR PARTICULATES Results in Units of 10- 3 pCi/m3 +/- 2 sigma STATION NUMBER JANUARY* FEBRUARY MARCH APRIL MAY JUNE SA-APT-16El 0.9+/-0.7. 2. 8+/-1. 0 1.8+/-0.9 1.3+/-0.8 1.1+/-0.6. 2.6+/-1.1 2.1+/-0.8 1.4+/-0. 7 1.3+/-0.6 2.0+/-0.8 1. 7+/-0, 7 1.9+/-0.7 1.0+/-0. 7 3.5+/-0.9 1.0+/-0.6 1.6+/-0. 7 1.4+/-0. 7 1.1+/-0. 7 2.0+/-0.7 1.2+/-0.8 1.1+/-0.6 1.1+/-0.8 1.2+/-0.6 1.2+/-0.7
<0.8 2. 2+/-1. 0 SA-APT-3H3 1.0+/-0.8 2. 4+/-0., 9 2.4+/-0.8 1.4+/-0, 8 0.7+/-0.6 1.7+/-0.8 2.5+/-0.8 1.6+/-0.7 1.8+/-0.8 1.7+/-0.7 J.5+/-0.7 1.9+/-0. 7 1.4+/-0.7 2.6+/-0.7 1. 7+/-0. 7 1.5+/-0.7 1.7+/-0.8 1.1+/-0. 7 0.7+/-0.5 1.7+/-1.1 0.7+/-0.5 0.6+/-0.6 1. 5+/-0. 6 1.8+/-0.8
<0.7 1. 5+/-0. 8 w
STATION NUMBER JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE SA-APT-16El 1.7+/-0.9 4.1+/-1.2 2.8+/-1.0 1.8+/-1.0 <1.3 1.3+/-0.7 2.4+/-0.8 1.1+/-0. 7 1. 7+/-0.8 l. 7+/-0. 7 <1.2 3.0+/-0.8
- 1. 7+/-0.9 2.8+/-1.0 2.1+/-0 .9 3.0+/-1.0 1.2+/-0.7 2.2+/-0.7 1.5+/-0.6 1.2+/-0.8 1.1+/-0.6 1. 2+/-0. 6 1.2+/-0.6 1.7+/-0.8 0.6+/-0.5 1.2+/-0.7 1.7+/-1.5 SA-APT-3H3 1.0+/-0. 7 2. 9+/-0. 9 2.3+/-0.8 7.6+/-0.7 <1.1 1.4+/-0.6 2.2+/-0.8 1.9+/-0.8 1. 9+/-0. 9 1.0+/-0.5 1. 0+/-0. 6 2.0+/-0~8 1.5+/-0. 7 2.5+/-0.8 2.4+/-0.9 3.6+/-1.0 1.2+/-0.7 2.2+/-0.7 2.9+/-0.9 <1.1 5.8+/-0.5 1.4+/-0.6 1. 9+/-0. 7 1. 3+/-0. 8 1.1+/-0.6 2.1+/-0.8
- 1. 9+/-2. 4
- SalJ1lling dates can be found on Table C-6.
TABLE C-3 CONCENTRATIONS OF GAW-lA EMITTERS* IN QUARTERLY COMPOSITES OF AIR P~RTICULATE SAMPLES I
Results in Units of 10- 3 +/- 2 sigma STATION NUMBER AND DATE Be-7 K-40 Nb-95 Zr-95 Ru-103 Cs-137 Ce-141 Ce-144 SA-APT-2S2**
1-02-80 to 91+/-9 <7.8 (D.4 <D.8 <0.4 0.7+/-0.3 <0.9 <3.2 3*31-80 3-31-80 to 150+/-15 <9.3 <0.5 <0.8 <0.7 1.6+/-D.4 <1.1 <3.3 6-30-80 6-30-80
-~
.. p, to 86+/-9 <7.8 <0.5 <0.6 <0.5 <0.3 <0.5 <1.5 9-29-80 9-29-80 to 60+/-6 8.1+/-3.8 8,8+/-0.9 5.9+/-0. 7. 4.4+/-0,6 <0.4 4.5+/-0. 7 2;5+/-1.5 12-29-80 SA-APT-5Sl 1-02-80 to 67+/-7 <6.2 <0.2 <0.7 <0.4 0.6+/-0.3 <0.7 <3.2 3-31-80 3-31-80 to 100+/-10 <9.3 <0.5 <1.0 <0.5 1.5+/-0.3 <0.8 3,2+/-1.2 6-30-80 6-30-80 to 72+/-7 <6.2 <0.2 <P.6 <0.5 0.7+/-0.3 <0.7 <1. 6 9-29-80 9-29-80 to 45+/-5 <5.8 10+/-1 6.0+/-0.6 4.3+/-0,5 <0.3 4.5+/-0.6 2.8+/-1.4 12-29-80
/
TABLE C-3 {CONT.)
CONCENTRATIONS OF GAMMA EMITTERS* IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES Results in Units of 10- 3 +/- 2 sigma STATION NUMBER AND DATE Be-7 K-40 Nb-95 Zr-95 Ru-103 Cs-137 Ce-141 Ce-144 SA-APT-5Dl 1-02-80 to 84+/-8 <7.8 <0.5 <o.6 <0.4 1.1+/-0. 3 <0.9 <3.3 3-31-80 3-31-80 to 130+/-13 <9.3 <0.8 <0.8 <0.8 1.3+/-0.4 <1.4 <3.3 6-30-80 6-30-80
+::> to 67+/-7 <7.8 <0.5 <0.8 <0.5 0.5+/-0.2 <0.5 <1.6 (J1 9-29-80 9-29-80 to 51+/-5 <6.2 8.4+/-0.8 5.2+/-0.6 4.5+/-0.6 <0.5 5.0+/-0.7 3.0+/-1. 7 12-29-80 SA-APT-lODl 1--02-80 to 65+/-7 <i.8 <0.4 <0.8 <0.4 0.5+/-0.3 <0.9 <1.6 4-01-80 4-01-80 to 97+/-10 <7.8 <0.6 <0.8 <0.5 0.9+/-0.4 <0.9 3.3+/-2.3 6-30-80 6-30-80 to 62+/-6 <7.8 <0.5 <0.6 <0.5 0.6+/-0.2 <0.8 <1.7 9-30-80 9-30-80 to 43+/-5 <6.2 6.9+/-0.7 4.4+/-0.6 4.5+/-0.6 <0.4 4.5+/-0.6 2.1+/-1. 3 12-29-80
TABLE C-3 (CONT.)
CONCENTRATIONS OF GA!f.1A EMITTERS* IN QUARTERLY COMPOSITES OF. AIR.PARTICULATE SAMPLES Results in Units of 10- 3 +/- 2*sigma STATION NUMBER AND DATE Be-7 K-40 Nb-95 Zr-95 Ru-103 Cs-137 Ce-141 Ce-144 SA-APT-16El 1-02-80 to 80+/-8 <7.8 <0.7 <0.8 <0.4 0.6+/-0.3 <0.7 <1.6 4-01-80 4-01-80 to 120+/-12 <9.3 <0.8 <0.8 <0.8 1.4+/-0.4 <1.1 <3.3 6-30-80 6-30-80 to 60+/-6 <6.2 <0.3 <0.6 <0.5 0.5+/-0.3 <0,5 <1.6 9-30-80 9-30,.BQ to 61+/-6 '5.6+/-3.9 8.0+/-0.8 4.1+/-0.9 4.4+/-0.6 <0.5 5.3+/-0.7 <2.6 12-29-80
.j:::>.
O'I SA-APT-lFl 1-02-80 to 88+/-9 <7.8 <0.4 <0.8 <0.4 0.8+/-0.4 <0.7 2.2+/-2.0 3-3,1-80 3-31-80 to 120+/-12 <9.3 <0.5 . <1.0 <0.7 1.5+/-0.4 <1.4 <3.3 6-30-80 6-30-80 to, 64+/-6 <7.8 <0.5 <0.8 <0.5 <0.5 <0.5 <1.6 9-29-80 9-29-80 to 44+/-5 <6.7 11+/-1 6.8+/-0.8 3.8+/-0.6 <0.4 5.8+/-0.7 -3. 1+/-1. 2 12-29-80
TABLE C-3 (CONT.)
CONCENTRATIONS OF GAMMA EMITTERS* IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES Results in Units of 10- 3 +/- 2 sigma STATION NUMBER ANO DATE Be-7 K-40 Nb-95 Zr-95 Ru-103 Cs-137 Ce-141 Ce-144 SA-APT-2F2 1-02-80 to 84+/-8 <9.3 <0.4 <0.8 <0.4 0.7+/-0.3 <0.9 <3.2 3-31-80 3-31-80 to 120+/-12 <11 <0.8 <1.0 <0.5 1.4+/-0.4 <0.8 1.8+/-1. 3 6-30-80 6"'30-80 to 82+/-8 <7.8 <0.5 <0.6 <0.5 0.7+/-0.3 <0.8 <3.3 9-29-80
..p.
'..J 9-29-80 to 61+/-6 4.2+/-3.4 8.1+/-0.8 4.4+/-0.6 4-.8+/-0.6 <0.4 4.3+/-0.8 <2.6 12-29-80 SA-APT-3H3 1-02-80 to 84+/-8 <9.3 <0.5 <0.6 <0.5 0.5+/-0.3 <1.0 <3.3 3-31-80 3-31-80 to 120+/-12 <7.8 <0.8 <0.9 <0.5 1.2+/-0.4 <0.9 <1.7 6-30-80 6-30-80 to 90+/-9 <6.2 <0.5 <0.6 <0.5 0.7+/-0.2 <0.8 <1.6 9-29-80 9-29-80 to 42+/-4 3.6+/-3.4 5.4+/-0.6 3.2+/-0.6 3.8+/-0.4 <0.3 3.2+/-0.6 <2.2 12-29-80
- All other famma emitters searched for_ were <LLD; typical LLDs are given in Table C-33.
- Location o station SA-APT-2Sl was rooved to station SA-APT-2S2 on 4-28-80.
TABLE C-4
. CONCENTRATIONS OF STRONTIUM-89* AND -90 IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES Results in Units of 10- 3 pCi/m- 3+/- 2 sigma Jan to March April to June July to Sept Oct to Dec STATION NUMBER Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 SA-APT-2S2** <1.1 <4.4 . I 5.3+/-1.7 0.9+/-0.4 <0.8 0.3+/-0.2 0.6+/-0.5 <0.3
+::> SA-APT-5Sl <O. 7 0.3+/-0.2 <3.3 2. Q+/-0.'6 <1.2 0.4+/-0.2 0.8+/-0.6 <0.2 00 SA-APT-501 <0.9 <0.4 8.2+/-2.9 <1.1 <1. 7 <0.4 0.6+/-0.6 0.2+/-0.2 SA-APT-1001 <0.8 0.2+/-0.2 1.9+/-1.3 <0.5 <1.8 0.6+/-0.3 1.7+/-0.5 <0.3 SA-APT-16El <1.6 <0.7 3.5+/-1.8 0.8+/-0.5 <0.6 <0.2 <0.9 0.2+/-0.2 SA-APT-lFl <1.0 <0.4 2.1+/-1. 2 <0.5 <1.2 0.3+/-0.2 . 0.9+/-0.7 <0.4 SA-APT-2F2 <1.0 <0.4 <2.8 1.8+/-0.5 <1.0 0.4+/-0.2 1.0+/-0.4 <0.3 SA-APT-3H3" <0.9 <0.4 <2.4 0.7+/-0.4 <0.8 0.2+/-0.1 0.8+/-0.3 <0.2
- Strontium-89 results are corrected for decay to sample stop date.
- Location of station SA-APT-2Sl was moved to SA-APT-2S2 on 4-28-80.
TABLE C-5 CONCENTRATIONS OF IODINE-131* IN FILTERED AIR Results in Units of 10- 3 pCi/m3 MONTH SA-AI0-252** SA-AI0-5S 1 SA-AI0-501 SA-AI0-1001 SA-AI0-16E 1 SA-AIO- lFl *** SA-AI0-2F2 SA-AI0-3H3 JANUARY**** <13 <11 <15 <9.7 <11 <15 <12
<7*.2 <6.8 <8.2 <6.6 <7.7 <7.9 <7.8
<12 <9.3 <11 <11 <13 <12 <10
<10 <9. 9 <9.1 <8.6 <10 <9.4 <9.3 FEBRUARY <9. 3 <8.4 <9.0 <8.7 <18 <9.9 "<9.4
<8.1 <9.0 <9.3 <8.6 <18 <9.9 <9.9
<11 <18 <8.8 <6.9 <13 <9.3 <8.3
<13 <15 <15 <11 <15 <17 <23
<7.3 <7.6 <9.1 <8.9 <9.8 <8.9 <9.0
~
\.0 MARCH <7.0 <7.5 <8.9 <6.6 <7.4 <7.6 <8.2 <9.3
<7.5 <7.0 <8.2 <9.* 3 <11 <8.1 <8.3 <8. 7
<6.8 <7.4 <7.5 <6.1 <6.5 <7.4 <7.6 <9.1
<7.1 <6.3 <8.0 <5.7 <7.2 <7.5 <7.9 <7.8 APRIL <7.0 <7.2 <7.6 <6.6 <6.8 <6.9 <7.2 <8.5
<11 <10 <11 <10 <12 <11 <11
<7. 3 <7.8 <7.9 <6.8 <8.0 <6.9 <8~8
<8.2 <7.3 <8.1 <9.0 <10 <7.2 <10 MAY <8.1 <7.2 <8.0 <6.6 <6.8 <7.6 <9. 3
<8.8 <6.4 <8.2 <7.6 <8.3 <8.2 <9.3
<10 <14 <16 <15 <16 <16 <20
<17 <9.4 <11 <10 <11 <13 <12
<8.4 <11 <12 <14 <16 <11 <12 JUNE <8.9 <7.8 <11 <10 <8.8 <11 <10
<14 <11 <15 <13 <13 <13 <15
<11 <7.6 <13 <9.2 <9.8 <10 <14
<9.1 <8.9 <14 <17 <17 <13 <14
TABLE C-5 (cont.)
CONCENTRATIONS OF IODINE-131* IN FILTERED AIR Results in Units of 10- 3 pCi/m3 MONTH SA-AI0-2S2** SA-AI0-5Sl SA-AI0-5Dl SA-AIO-lODl SA-AI0-16El SA-AIO-lFl*** SA-AI0-2F2 SA-AI0-3H3 JULY <9.5 <7.5 <12 <9.4 <11 <9.4 <13
<9. 7 <7.9 <14 <8.1 <9.7 <9.1 <12
<7.4 <7.5 <11 <16 <17 <10 <15
<11 <8.5 <12 <8.5 <8.7 <9.2 <15 AUGUST <11 <11 <13 <15 <14 <13 <13
<9.6 <8.7 <11 <9.5 <15 <12 <9.2 <15
<8.8 <7.8 <10 <11 <14 <12 <10
<9.6 <7.7 <9.4 <7.4 <7.6 <8.9 <12
<12 <13 <16 <16 <135 (1) <20 <104 ( 1)
SEPTEMBER <62 ( 1) <65 ( 1) <16 <53 ( 1) <56 (1) <17 <83 ( 1)
<27 ( 1) <27 ( 1) <32 (1) <31 (1) <38 (1) <38 ( 1) <26 (1)
U1 <11 <12 <14 <12 <11 <13 <11 0
<12 <12 <14 <12 <14 <18 <12 OCTOBER <9.9 <11 <13 <14 <16 <12 <13
<15 <13 <15 <13 <16 <25 <12
<14 <13 <17 <16 <17 <16 <22
<9.8 <7.9 <11 <10 <11 <9.8 <10 NOVEMBER <10 <9.0 <11 <11 <11 <11 <11
<14 <11 <15 <14 <17 <13 <9.9
<9.5 <8.4 <9.5 <9.6 <9.8 <10 <11
<11 <11 <11 <7.4 <8.2 <9.7 <9.4
<11 <11 <9.8 <10 <11 <9.9 <iO DECEMBER <12 <9.1 <12 <8.5 <9.3 <11 <11
<13 <9.9 <12 <12 <13 <12 <12
<13 <11 <12 <8.9 <9.8 <12 <12
<11 <11 <12 <13 <20 <12 <20
- I-131 results are corrected for decay to sample stop date.
- Location of station SA-AI0-2Sl was moved to station SA-AI0-2S2 on 4-28-80.
- Station SA-AIO-lFl is not a routine sampling location.
- Actual sampling dates can be found on Table C-6.
( 1) High LLD due to delay in counting resulting from a counter malfunction.
TABLE C-6 SAMPLING DATES FOR AIR SAMPLES STATION NUMBER MONTH 2S2* 5Sl 5Dl lODl 16El lFl 2F2 3H3 (l JANUARY 1-02-80 1-02-80 1-02-80 1-02-80 1-02-80 1-02-80 1-02-80 1-02-80 to to to to to to to to 1-07-80 1-07-80 1-07-80 1-08-80 1-08-80 1-07-80 1-07-80 1-07-80 1-07-80 1-07-80 1-07-80 1-08-80 1-08-80 1-07-80 1-07-80 1-07-80 to to to to to to to to 1-14-80 1-14-80 1-14-80 1-15-80 1-15-80 1-14-80 1-14-80 1-14-80 1-14-80 1-14-80 1-14-80 1-15-80 1-15-80 1-14-80 1-14-80 1-14-80 to to to to to to to to 1-21-80 1-21-80 1-21-80 1-21-80 1-21-80 1-21-80 1-21-80 1-21-80 1-21-80 1-21-80 1-21-80 1-21-80 1-21-80 1-21-80 1-21-80 1-21-80 to to to to to to to to 1-28-80 1-28-80 1-28-80 1-28-80 1-28-80 1-28-80 1-28-80 1-28-80 FEBRUARY 1-28-80 1-28-80 1-28-80 1-28-80 1-28-80 1-28-80 1-28-80 1-28-80
(.)l to to to to to to to to 2-04-80 2-04-80 2-04-80 2-04-80 2-04-80 2-04-80 2-04-80 2-04-80 2-04-80 2-04-80 2-04-80 2-04-80 2-04-80 2-04-80 2-04-80 2-04-80 to to to to to to to to 2-11-80 2-11-80 2-11-80 2-11-80 2-11-80 2-11-80 2-11-80 2-11-80 2-11-80 2-11-80 2-11-80 2-11-80 2-11-80 2-11-80 2-11-80 2-11-80 to to to to to to to to 2-19-80 2-19-80 2-19-80 2-19-80 2-19:-80 2-19-80 2-19-80 2-19-80 2-19-80 2-19-80 2-19-80 2-19-80 2-19-80 2-19-80 2-19-80 2-19-80 to to to to to to to to 2-25-80 2-25-80 2-25-80 2.. 26-80 2-26-80 2-25-80 2-25-80 2-25-80 2-25-80 2-25-80 2-25-80 2-26-80 2-26-80 2-25-80 2-25-80 2-25-80 to to to to to to to to 3-03-80 3-03-80 3-03-80 3-03-80 3-03-80 3-03-80 3-03-80 3-03-80 MARCH 3-03*80 3-03-80 3-03-80 3-03-80 3-03-80 3-03-80 3-03-80 3-03-80 to to to to to to to to 3-10-80 3-10-80 3-10-80 3-11-80 3-11-80 3-10-80 3-10-80 3-10-80 3-10-80 3-10-80 3-10-80 3-11-80 3-11-80 3-10-80 3-10-80 3-10-80 to to to to to to to to 3-17-80 3-17-80 3-17-80 3-17-80 3-17-80 3-17-80 3-17-80 3-17-80 3-17-80 3-17-80 3-17-80 3-17-80 3-17-80 3-17-80 3-17-80 3-17-80 to to to to to to to to 3-24-80 3-24-80 3-24-80 3-25-80 3-25-80 3-24-80 3-24*80 3-24-80
TABLE C-6 (cont.)
SAMPLING DATES FOR AIR SAMPLES STATION NUMBER MONTH 2S21' 5Sl 501 1001 16El lFl 2F2 3H3 1
MARCH 3-24-80 3-24-80 3-24-80 3-25-80 3-25-80 3-24-80 3-24-80 3-24-80 to to to to to to to to
. 3-31-80 3-31-80 3-31-80 4-01-80 4-01-80 3-31 .. 80 3-31-80 3-31-80 APRIL 3-31-80 3-31-80 3-31-80 4-01-80 4-01-80 3-31-80 3-31-80 3-31-80 to to to to to to* to to 4-07-80 4-07"'80 A-07-80 4-08-80 4-08-80 4-07-80 4-07-80 4-07-80 4-07-80 4-07-80 4-07-80 4-08-80 4-08-80 4-07-80 4-07-80 4-07-80 .
to to to to to to to to 4-14-80 4-14-80 4-14-80 4-15-80 4-15-80 .4-14-80 4-14-80 4-14-80 4-14-80 4-14-80 4-14-80 4-15-80 4-15-80 4-14-80 4-14-80 4-14-80 to to to to to to to to 4-21-80 4-21-80 4-21-80 4-22-80 4-22-80 4-21-80 4-21-80 4-21-80 4-21-80 4-21-80 4-21-80 4-22-80 4-22-80 4-21-80 4-21-80 . 4-21-80 to to to to to to to to U1 4-28-80 4-28-80 4-28-80 4-28-80 4-28-80 4-28-80 4-28-80 4-28-80 N
MAY 4-28-80 4-28-80 4-28-80 4-28-80 4-28-80 4-28-80 4-28-80 4-28-80 to to to to to to to to 5-05-80 5-05-80 5-05-80 5-06-80 5-06-80 5-05-80 5-05-80 5-05-80 5-05-80 5-05-80 *5-05-80 5-06-80 5-06-80 5-05-80 5-05-80 5-05-80 to to to to to to to to 5-12-80 5-12..,80 5-12-80 5-13-80 5-13-80 5-12-80 5-12-80 5-12-80 5-12-80. 5-12-80 5-12-80 5-13-80 5-13-80 5-12-80 5-12-80 5-12-80 to to to to to to to to 5-19-80 5-19-80 5-19-80 5-20-80 5-20-80 5-19-80 5-19-80 5-19-80 5.-19-80 5-19-80 5-19-80 5-20-80 5-20-80 5-19-80 5-19-80 5-19-80 to to to to to to to to 5-27-80 5-27-80 5-27-80 5-28-80 5-28-80 5-27-80 5-27-80 5-27-80 5-27-80 5-27-80 5-27-80 5-28-80 5-28-80 5-27-80 5-27-80 5-27-80 to to to to to to to to 6-02-80 6-02-80 6-02-80 6-02-80 6-02-80 6-02-80 6-02-80 6-02-80 JUNE 6-02-80 6-02-80 6-02-80 6-02-80 6-02-80 6-02-80 6-02-80 6-02-80 to to to to to to to to 6-09-80 6-09-80 6-09-80 6-10-80 6-10-80 . 6-09-80 6-09-80 6-09-80 6-09-80 6-09-80 6-09-80 6-10-80 5.. 10-80 6-09-80 6-09-80 6-09-80 to to. to to to to to to 6-16-80 6-16-80 6-16-80 6-17-80 6-17-80 6-16-80 6-16-80 6-16-80
TABLE C-6 (cont.)
SAMPLING DATES FOR AIR SAMPLES STATION NUMBER MONTH 2S2* 5Sl 501 1001 16El lFl 2F2 3H3 JUNE 6-16-80 6-16-80 6-16-80 6-17-80 6-17-80 6-16-80 6-16-80 6-16-80 to to to to to to to to 6-23-80 6-23-80 6-23-80 6-24-80 6-24-80 6-23-80 6-23-SO 6-23-80 6-23-80 6-23-80 6-23-80 6-24-80 6-24-80 6-23-80 6-23-80 6-23-80 to to to to to to to to 6-30-80 6-30-80 6-30-80 6-30-80 6-30-80 6-30-80 6-30-80 6-30-80 JULY 6-30-80 6-30-80 6-30-80 6-30-80 6-30-80 6-30-80 6-30-80 6-30-80 to to to to to to to to 7-07-80 7-07-80 7-07-80 7-07-80 7-07-80 7-07-80 7-07-80 7-07-80 7-07-80 7-07-80. 7-07-80 7-07-80 7-07-80 7-07-80 7-07-80 7-07-80 to to to to to to to to 7-14-80 7-14-80 7-14-80 7-15-80 7-15-80 7-14-80 7-14-80 7-14-80 01 w 7-14-80 7-14-80 7-14-80 7-15-80 7-15-80 7-14-80 7-14-80 7-14-80 to to to to to to to to 7-22-80 7-21-80 7-21-80 7-21-80 7-21-80 7-21-80 7-21-80 7-21-80 7-22-80 t-21-80 7-21-80 7-21-80 7-21-80 7-21-80 7-21-80 7-21-80 to to to to to to to* to 7-29-80 7-29-80 7-29-80 7-30-80 7-30-80 7-29-80 7-29-80 7-29-80 AUGUST 7-29-80 7-29-80 7-29-80 7-30-80 7-30-80 7-29-80 7-29-80 7-29-80 to to to to to to to to 8-04-80 8-04-80 8-04-80 8-05-80 8-05-80 8-04-80 8-04-80 8-04-80 8-04-80 8-04-80 8-04-80 8-05-80 8-05-80 8-04-80 8-04-80 8-04-80 to to to to to to to to 8-11-80 8-11-80 8-11-80 8-12-80 8-12-80 8-11-80 8-11-80 8-11-80 8-11-80 8-11-80 8-11-80 8-12-80 8-12-80 8-11-80 8-11-80 8-11-80 to to to to to to to to 8-18-80 8-18-80 8-18-80 8-18-80 8-18-80 8-18-80 8-18-80 8-18-80 8-18-80 8-18-80 8-18-80 8-18-80 8-18-80 8-18-80 8-18-80 8-18-80 to to to to to to to to 8-25-80 8-25-80 8-25-80 8-26-80 8-26-80 8-25-80 8-25-80 8-25-80 8-25-80 8-25-80 8-25-80 8-26-80 8-26-80 8-25-80 8-25-80 8-25-80 to to to to to to to to 9-02-80 9-02-80 9-02-80 9-02-80 9-02-80 9-02-80 9-02-80 9-02-80
TABLE C-6 (cont.)
SAMPLING DATES FOR AIR SAMPLES STATION NUMBER MONTH 2S2* 5Sl 501 1001 16El lFl 2F2 3H3 SEPTEMBER 9-02-80 9-02-80 9-02-80 9-02-80 9-02-80 9-02-80 9-02-80 9-02-80 to to to to to
- to to to 9-08-80 9-08-80 9-08-80 9-09-80 9-09-80 9-08-80 9-08-80 9-08-80 9-08-80 9-08-80 9-08-80 9-09-80 9-09-80 9-08-80 9-08-80 9-08-80 to to to to to to to to 9-15-80 9-15-80 9-15-80 9-15-80 9-15-80 9-15-80 9-15-80 9-15-80 9-15-80. 9-15-80 9-15-80 9-15-80 9-15-80 9-15-80 9-15-80 9-15-80 to to to to to to to to 9-22-80 9-22-80 9-22**80 9-23-80 9-23-80 9-22-80 9-22-80 9-22-80 9-22-80 9-22-80 9-22-80 9-23-80 9-23-80 9-22-80 9-22*-80 9-22-80 to to to to to to to to 9-29-80 9-29-80 9-29-80 9-30-80 9-30-80 9-29-80 9-29-80 9-29-80 c.n
.p. OCTOBER 9-29-80 9-29-80 9-29-80 9-30-80 9-30-80 9-29-80 9-29-80 9-29-80 to to to to to to to to 10-06-80 10-06-80 10-06-80 10-06-80 10-06-80 10-06-80 10-06-80 10-06-80 10-06-80 10-06-80 10-06-80 10-06-80 10-06-80 10-06-80 10-06-80 10-06-80 to to to to to to to to 10-14-80 10-14-80 10-14-80 10-14-80 10-14-80 10-14-80 10-14-80 10-14-80 10-14-80 10-14-80 10-14-80 10-14-80 10-14-80 10-14-80 10-14-80 10-14-80
. to to to to to to to. to 10-20 i)
- 10-20-80 10-20-80 10-20-80 10-20.,-80 10-20-80 10-20-80 10-20-80 10-20-80 10-20-80 10-20-80 10-20-80 10-20-80 10-20-80 10-20-80 10-20-80 to to to to to to to to 10-27-80 10-27-80 10-27-80 10-27-80 10-27-80 10-27-80 10-27-80 10-27-80 NOVEMBER 10-27-80 10-27-80 10-27-80 10-27-80 10-27-80 10-27-80 10-27-80 10-27-80 to to to to to to to to 11-03-80 11-03-80 11-03-80 11-03-80 11-03-80 11-03-80 11-03-80 11-03-80 11-03-80 11-03-80 11-03-80 11-03-80 11-03-80 11-03-80 11-03-80 11-03-80 to to to to to to to to 11-10-80 11-10-80 11-10-80 11-10-80 11-10-80 11-10-80 11-10-80 11-10-80 11-10-80 11-10-80 11-10-80 11-10-80 11-10-80 11-10-80 11-10-80 11-10-80 to to to to to to to to 11-17-80 11-17-80 11-17-80 11-17-80 11-17-80 .11-17-80 11-17-80 11-17-80
TABLE C-6 (cont.)
SAMPLING DATES FOR AIR SAMPLES STATION NUMBER MONTH 2S2* 5Sl 501 lODl 16El lFl 2F2 3H3 NOVEMBER 11-17-80 11-17-80 11-17-80 11-17-80 11-17-80 11-17-80 11-17-80 , 11-17-80 to to to to to to to to 11-24-80 11-24-80 11-24-80 11-25-80 11-25-80 il-24-80 11-24-80 11-24-80 11-24-80 11-24-80 11-24-80 11-25-80 11-25-80 11-24-80 11-24-80 11-24-80 to to to to to to to to 12-01-80 12-01-80 12-01-80 12-01-80 12-01-80 12-01-80 12-01-80 12-01-80 (jl (jl DECEMBER 12-01-80 12-01-80 12-01-80 12-01-80 12-01-80 12-01-80 12-01-80 12-01-80 to to to to to to to to 12-08-80 12-08-80 12-08-80 12-09.:.30 12-09-80 12-08-80 12-08-80 12-08-80 12-08-80 12-08-80 12-08-80 12-09-80 12-09-80 12-08-80 12-08-80 12-08-80 to to to to to to to to 12-15-80 12-15-80 12-15-80 12-15-80 12-15-80 12-15-80 12-15-80 12-15-80 12-15-80 12-15-80 12-15-80 12-15-80 12-15-80 12-15-80 12-15-80 12-15-80 to to to to to to to to 12-22-80 12-22-80 12-22-80 12-23-80 12-23-80 12-22-80 12-22-80 12-22-80 12-22-80 12-22-80 12-22-80 12-23-80 12-23-80 12-22-80 12-22-80 12-22-80 to to to to to to to to 12-29-80 12-29-80 12-29-80 12-29-80 12-29-80 12-29-80 12-29-80 12-29-80
- Location of station SA-APT-2Sl was moved to station SA-APT-2S2 on 4-28-80.
TABLE C-7 CONCENTRATIONS OF TRITIUM, GROSS ALPHA AND GROSS BETA EMITTERS IN PRECIPITATION Station SA-RWA-2F2 Results in Units of pCi/l +/- 2 sigma COLLECTION PERIOD H-3 ALPHA BETA 1-03-80 to 1-29-80 <116 <0.6 2.9+/-2.0 1-29-80 to 3-04-80 <120 <1.1 8.7+/-2.7
()1 3-04-80 to 3-31-80 <124 <0.5 <3.3
°' 3-31-80 to 4-29-80 <122 <1.0 . 11+/-2 4-29-80 to 6-02-80 <90 <1.0 8.0+/-2.6 6-02-80 to 7-01-80 <105 <0.6 3.3+/-0.8 7-01-80 to 7-29-80 <117 <0.8 4.9+/-1.2 7-29-80 to 9-03-80 <114 0.8+/-0.7 18+/-2 9-03-80 to 9-29-80 <114 <0.7 <2.3 9-29-80 to 11-03-80 <102 1.1+/-0.8 9.5+/-1.5 11-03-80 to 12-01-80 <107 <0.7 26+/-3 12-01-80 to 12-29-80 <110 0.9+/-0.6 16+/-3
TABLE C-8 CONCENTRATIONS OF STRONTIUM-89* AND -90, AND GAMMA EMITTERS**
IN QUARTERLY COMPOSITES OF PRECIPITATION Station SA-RWA-2F2 Results in Units of pCi/l +/- 2 sigma 1-03-80 3-31-80 7-01-80 9-29-80 to to to to (Jl NUCLIDE 3-31-80 7-01-80 9-29-80 12-29-80
-....J Sr-89 <1.2 <1.4 <2.6 <1.6 Sr-90 <0.8 1.1+/-0.5 2.0+/-0.6 0.4+/-0.3 Gamma Emitters <LLD <LLD <L.LD <LLD
- Sr-89 results are decay corrected to sample stop date.
- All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-33.
TABLE C-9 DIRECT RADIATION MEASUREMENTS - MONTHLY TLD RESULTS mrad/standard llXlnth*
STATION NUMBER JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-IDM-2S2** 5. 97+/-0. 29 5.95+/-0.18 6.46+/-0.48 5.90+/-0.59 5.11+/-0. 77 4.97+/-0.45 SA-IDM-5Sl 4.93+/-0.42 4.67+/-0.27 5.43+/-0.33 4.52+/-0.40 4.46+/-0.27 4.47+/-1. 07 SA-IDM-6Sl 5. 76+/-0. 65 5.56+/-0.29 6.52+/-0.43 5.20+/-0.20 5 .13+/-0. 51 5.51+/-0.51 SA-IDM-6S2 5. 39+/-0.49 5.27+/-0.23 5.48+/-0.44 4.* 94+/-0.24 5.03+/-0.30 5.28+/-0. 75 SA-IDM-7Sl 6.59+/-0.66 6.45+/-0.47 7 .19+/-0. 77 6.10+/-0.37 6. 33+/-0 .18 6.08+/-0.45 SA-I DM-lOS 1 9.87+/-0.54 10.16+/-0.46 11.22+/-0.47 8.26+/-0.29 7.66+/-0.77 7.49+/-0.58 SA- IDM- llS 1 21.61+/-2. 72 26.60+/-2.51 25.63+/-1.74 13.86+/-0.77 12.18+/-1.37 10.10+/-0.81 SA-IDM-501 5.11+/-0.40 4.84+/-0.37 5.48+/-0.76 4.43+/-0.47 5.12+/-0.20 5.04+/-0.79 SA-IDM-1001 6.03+/-0.41 5.83+/-0.24 5.91+/-0.67 5.82+/-0.29 5.46+/-0.33 5.39+/-0.09 SA-IDM-1401 5. 91+/-0, 54 5.61+/-0.23 5.82+/-0.59 5.50+/-0.32 5.54+/-0.25 5.79+/-0.60 SA-IDM-2El 5.62+/-0.16 5.05+/-0.30 5.97+/-0.33 5.23+/-0.32 5.03+/-0.43 5.58+/-1.32 SA-IDM-3El 5.14+/-0.46 4.86+/-0.30 5.73+/-0.43 4.84+/-0.73 4.67+/-0.27 5.05+/-0.29 SA- IDM-13El 5.36+/-0.44 5.32+/-0.67 5.51+/-0.15 4.62+/-0.21 4.78+/-0.33 4.92+/-0.48 SA-IDM-16El 5.65+/-0.26 5.77+/-0.46 5.79+/-0.58 5.71+/-0.60 5.37+/-1.07 5.66+/-0.97 SA-IDM-lFl 5.60+/-0. 58 5. 71+/-0.28 5. 77+/-0.38 5.05+/-0.68 5.27+/-0.43 5. 35+/-0 .18 SA-IDM-2F2 4.87+/-0.34 4.62+/-0.22 4.87+/-0.32 4.27+/-0.19 4.42+/-0.54 4.48+/-0.54 SA-IDM-5Fl 5.19+/-0.53 5.35+/-0.24 5.11+/-0. 64 4.67+/-0.23 5.16+/-0.31 4.60+/-0.75 SA-IDM-6Fl 4.56+/-0.57 4.39+/-0.49 4.97+/-0.40 4.21+/-0.51 4.52+/-0.57 4.32+/-0.49 SA-IDM-7F2 4.01+/-0. 36 3.96+/-0.16 4.39+/-0.33 3. 71+/-0.19 3.85+/-0.27 3.94+/-0.29 SA- I DM-11 Fl 5.89+/-0.27 5.94+/-0.59 5.98+/-0.36 5.94+/-0.72 5.72+/-0.32 5.63+/-0.45 SA- IDM-13 Fl 5.69+/-0.32 5.61+/-0.16 5.91+/-0.48 5.33+/-0.62 5.13+/-0.15 5.06+/-0.41 SA-IDM-3Gl 5.99+/-0. 39 5.93+/-0.49 6.96+/-0.32 5.76+/-0.54 6.09+/-0.60 5.81+/-1.15 SA-IDM-2Hl 6.28+/-0.51 6.10+/-0.24 6.42+/-0.66 6.07+/-0.11 5.59+/-0.44 5.26+/-0.03 SA-IDM-3Hl 5.87+/-0.60 6.07+/-0.48 6.27+/-0.56 5.76+/-0.29 5.24+/-0.32 5.33+/-0.47 SA-IDM-3H3 6.18+/-0.67 5.82+/-0.24 6.03+/-0.52 5.29+/-0.49 5.32+/-0.29 5. 78+/-1.41 AVERAGE 6.36+/-6.68 6.46+/-8.69 6.83+/-8.22 5.64+/-3.86 5.53+/-3.13 5.48+/-2.38 STATION NUMBER JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE SA-IDM-2S2** 4.86+/-0.41 5.27+/-0.50 4.52+/-0.10 5.60+/-0.05 4.85+/-0.36 5.20+/-0.25 5.39+/-1.17 SA-IDM-5Sl 4.52+/-0.46 4.56+/-0.33 3.90+/-0.44 4.48+/-0.43 4.31+/-0.08 4.67+/-0.52 4.58+/-0.72 SA-IDM-6Sl (1) 5.61+/-1.00 SA-I DM-6S2 5.06+/-0.78 5.22+/-0.36 4.81+/-0.42 4.93+/-1. 73 5.06+/-1.00 5.69+/-0.54 5.18+/-0.51 SA-IDM-7Sl 6.23+/-0.17 6.08+/-0.36 5.20+/-0.51 6.55+/-0.47 5.94+/-0.37 6.22+/-0.24 6.25+/-0.94 SA- I DM- lOS 1 7.57+/-1.07 7.19+/-0.53 5.15+/-0.46 8.68+/-2.09 6. 77+/-0. 74 8.12+/-0.94 8.18+/-3.28 SA- IDM- llS 1 10.64+/-1.04 10.78+/-0.74 5.32+/-0.32 9.44+/-0.47 10.49+/-0.38 14.67+/-0.81 14.28+/-13.49 SA-IDM-501 5.17+/-0.79 4.90+/-0.50 4.25+/-0.45 4. 72+/-0.82 4.53+/-0.41 4.76+/-0.32 4.86+/-0.70 SA-IDM-1001 5.42+/-0.42 5.80+/-0.74 5.23+/-0.62 6.16+/-0.23 5.42+/-0.61 5.69+/-0.46 5.68+/-0.58 SA-IDM-1401 5.57+/-0.65 5 .91+/-0.93 5.21+/-0.05 6.21+/-0.38 5.36+/-0.50 6.00+/-0.62 5.70+/-0.57 SA-IDM-2El 5.06+/-0.18 5.34+/-0.74 4.95+/-0.33 5.37+/-0.54 5.08+/-0.36 5.02+/-0.52 5.28+/-0.63 SA-IDM-3El 5.56+/-0.63 5.33+/-0.47 5.09+/-0.59 5.46+/-0.59 4.75+/-0.24 5.10+/-0. 71 5.13+/-0.66 SA- IDM-13El 5. 85+/-0.61 5.09+/-0.47 5.36+/-0.73 5.26+/-0.64 4.54+/-0.36 5.11+/-0.42 5.14+/-0.76 SA-I DM-16El 5.36+/-0.25 5.37+/-0.53 5.26+/-0.31 5.82+/-0.55 4.61+/-0.40 5.21+/-0.61 5.47+/-0.69 SA-IDM-lFl 5.83+/-0.55 5.58+/-0.25 5.93+/-0.21 5.24+/-0.32 5.88+/-1.56 5.23+/-0.45 5.54+/-0.60 SA-IDM-2F2 4.45+/-0.15 4.29;t0.14 3.83+/-0. 70 4.38+/-0.54. 3.90+/-0.63 4.31+/-0.40 4.39+/-0.64 SA-IDM-5Fl 5.40+/-0. 52 4.91+/-0.38 4.30+/-0.17 4.84+/-0.16 4.84+/-0.45 4.96+/-0.95 4.94+/-0.64 SA-IDM-6Fl 5.30+/-0.43 4.53+/-0.76 4.97+/-0.80 4.35+/-0.31 3.84+/-0.70 4.30+/-0.31 4.52+/-0.79 SA-IDM-7F2 4. 30+/-0.19 4.01+/-0.28 3.66+/-0.61 4.02+/-0.21 3.65+/-0.48 3.72+/-0.31 3.94+/-0.47 SA- IDM-11 Fl 6.26+/-0.44 5.75+/-0.60 5.65+/-0.32 6.41+/-0.56 5.74+/-0.94 5.82+/-0.39 5.89+/-0.48 SA- IDM-13 Fl 6.06+/-0.85 5.43+/-0.38 5.50+/-0.91 5.78+/-0.31 5.02+/-0.21 5.54+/-1.20 5.51+/-0.66 SA-IDM-3Gl 5.96+/-0.34 5. 71+/-0.47 5.86+/-0.47 6.05+/-0.56 5.61+/-0.52 5.83+/-0.41 5.96+/-0.69 SA-IDM-2Hl 5. 89+/-0. 37 5.36+/-0.33 6 .00+/-0.40* 4.17+/-0.60 5.19+/-0.28 6.29+/-1.04 5. 72+/-1. 29 SA-IDM..:3Hl 5.75+/-0.51 5.58+/-0.42 5.65+/-0.20 6.17+/-0.52 5.46+/-0.28 5.67+/-0.40 5.74+/-0.64 SA-IDM-3H3 6.49+/-0.78 5.85+/-0.20 5.66+/-0.19 5.98+/-0.42 5.16+/-0.27 5.39+/-0.60 5.75+/-0.80 AVERAGE 5.77+/-2.52 5.58+/-2.57 5.05+/-1.33 5.67+/-2.57 5.25+/-2.65 5. 77+/-4.15 5.79+/-4.74
- The standard month = 30.4 days.
- Location of station SA-IDM-2Sl was moved on 4-28-80 to station SA-IDM-2S2.
( 1) Station SA-IDM-6Sl was stopped on 6-30-80.
58
TABLE C-10 DIRECT RADIATION MEASUREMENTS - QUARTERLY TLD RESULTS mrad/standard month*
JANUARY APRIL JULY OCTOBER to to to to AVERAGE STATION NUMBER MARCH JUNE SEPTEMBER DECEMBER SA-IDM-2S2** - 5.59+/-0.18 4.74+/-0.51 4.59+/-0.15 4.64+/-0.68 4.89+/-0.94 SA-I DM-5Sl 4.58+/-0.29 3. 80+/-0. 30 3.71+/-0.35 3. 72+/-0. 35 3.95+/-0.84 SA-IDM-6Sl 5.45+/-0.36 4. 82+/-0. 34 (1) 5.14+/-0.89 SA-IDM-6S2 5.11+/-0. 25 4.59+/-0.84 3.84+/-0.07 4.47+/-0.63 4.50+/-"1.04 SA-I OM- 7Sl 7. 15+/-1.19 5.42+/-0.25 5. 31+/-0. 54 5.62+/-0.70 5.88+/-1. 72 SA-IDM-lOS 1 10.17+/-0.97 6.79+/-0.37 5.84+/-0.44 6.86+/-0.53 7.42+/-3.79 SA-IDM-llS 1 23.52+/-1.35 10. 53+/-0. 54 7.35+/-0.38 11.15+/-0. 77 13.14+/-14.24 SA-IDM-5Dl 4.67+/-0.10 4. 31+/-0. 39 4.36+/-0.71 4.47+/-0.47 4.45+/-0.32 SA-IDM-1001 5.62+/-0.31 4.89+/-0.24 4.56+/-0.57 4. 96+/-0. 74 5. 01+/-0. 89 (J1 l.D SA-IDM-1401 5. 64+/-0 .09 4.90+/-0.45 5.02+/-0.35 4. 90+/-0. 84 5.12+/-0.71 SA-I DM-2E 1 5.20+/-0.37 4.86+/-0.24 4.37+/-0.25 4.69+/-0.69 4.78+/-0.69 SA-IDM-3El 5.07+/-0.22 4.75+/-0.54 4. 55+/-0. 55 4.90+/-0.66 4.82+/-0.44 SA-IDM-13E 1 4.91+/-0.49 5.38+/-0.53 4.34+/-0.45 4.67+/-0.32 4.83+/-0.88 SA-I DM-16E 1 5.59+/-0.39 4.90+/-0.66 4.47+/-0.80 4.93+/-0.33 4.97+/-0.92 SA-IDM-lFl 5.33+/-0.39 4.65+/-0.57 4.12+/-0.15 4.57+/-0.63 4.67+/-1.00 SA-IDM-2F2 4. 13+/-0. 35 3.74+/-0.48 3.67+/-0.25 3.78+/-0.40 3.83+/-0.41 SA-IDM-5Fl 4.84+/-0.48 4. 41+/-0. 94 4.45+/-0.58 4.26+/-0.38 4.49+/-0.49 SA-IDM-6Fl 4.41+/-0.21 4.74+/-1.52 3.44+/-0.42 3.76+/-0.33 4.09+/-1.19 SA-IDM-7F2 4.03+/-0. 35 3.38+/-0.47 3.23+/-0.45 3.25+/-0.53 3.47+/-0.76 SA-IDM-11 Fl 5.90+/-0.33 4.98+/-0.16 4.93+/-0.17 5.30+/-0.73 5.28+/-0.89 SA-IDM-13Fl 5.38+/-0.29 4.73+/-0.53 4.62+/-0.42 4.76+/-0.94 4.87+/-0.69 SA- I DM-3Gl 5. 94+/-0. 41 5.27+/-0.12 4.53+/-0.12 5.54+/-0.26 5. 32+/-1.19 SA-IDM-2Hl 5.82+/-0.06 5.40+/-0.46 4.58+/-0.40 5.16+/-0.45 5.24+/-0.52 SA-I DM-3H 1 6 .14+/-0 .17 4.83+/-0.61 4.37+/-0.19 5.34+/-0.25 5.17+/-1.52 SA-I DM-3H3 5.80+/-0.16 4.-65+/-0.42 4. 39+/-0.18 4.57+/-0.54 4.85+/-1.28 AVERAGE 6.24+/-7.58 5.02+/-2.63 4. 53+/-1. 66 5.01+/-3.00 5. 21+/-4. 51
- The standard month = 30.4 days.
- Location of stationSA-IDM-2Sl was moved to station SA-IDM-2S2 on 4-28-80.
(1) Station SA-IDM-6Sl was discontinued on 6-30-80.
TABLE C-11 DIRECT RADIATION MEASUREMENTS - SEMI-ANNUAL TLD RESULTS mrad/standard month*
JANUARY APRIL STATION NO. TO TO MARCH SEPTEMBER SA-IDM-402 5.45+/-0.48 4.62+/-0.44 SA-IDM-9E 1 6.01+/-0.19 4.76+/-0.28 SA-IDM-11E2 6.16+/-0.31 4.85+/-0.27 SA-I DM-12E 1 6.14+/-0.31 4.99+/-0.42 SA-IDM-2F5 5.57+/-0.40 4.44+/-0.32 SA-IDM-3F2 5.19+/-0.07 3.93+/-0.35 SA-IDM-3F3 5.17+/-0.53 3.84+/-0.29 SA-I DM-10 F2 5.94+/-0.54 4.94+/-0.42 SA-I DM-12 Fl 5.88+/-0.14 4.47+/-0.32 SA-I DM-13F2 5.56+/-0.34 4.72+/-0.15 SA- IDM-13 F3 5.89+/-0.31 4.62+/-0.43 SA-IDM-14F2 5.49+/-0.62 4.58+/-0.50 SA-I DM-15 F3 6.42+/-0.48 5.14+/-0.09 SA- I DM-16 F2 5.75+/-0.29 4.21+/-0.34 SA-IDM-1G3 6.84+/-1.40. ( 1)
SA-IDM-lOGl 6.59+/-0.44 5.23+/-0.19 SA-IDM-16Gl 6.63+/-0.36 5. 51+/-0 .18 AVERAGE 5.92+/-0.99 4.68+/-0.90
- The standard month = 30.4 days.
(1) TLD lost in field.
60
TABLE C-10 DIRECT RADIATION MEASUREMENTS - QUARTERLY TLD RESULTS mrad/standard month*
JANUARY APRIL JULY OCTOBER to to to to AVERAGE STATION NUMBER MARCH JUNE SEPTEMBER DECEMBER SA- IDM-2S2** 5.59+/-0.18 4.74+/-0.51 4. 59+/-0 .15 4.64+/-0.68 4.89+/-0.94 SA-IDM-5Sl 4.58+/-0.29 3.80+/-0.30 3. 71+/-0. 35 3.72+/-0.35 3.95+/-0.84 SA-IDM-6Sl 5.45+/-0.36 4.82+/-0. 34 (1) 5.14+/-0.89 SA-I DM-6S2 5.11+/-0. 25 4.59+/-0.84 3.84+/-0.07 4.47+/-0.63 4.50+/-1.04 SA-I DM- 7S 1 7. 15+/-1.19 5.42+/-0.25 5.31+/-0.54 5.62+/-0.70 5.88+/-1. 72 SA-IDM-lOS 1 10.17+/-0.97 6. 79+/-0. 37 5.84+/-0.44 6.86+/-0.53 7.42+/-3.79 SA- IDM- llS 1 23. 52+/-1. 35 10.53+/-0.54 7.35+/-0.38 11.15+/-0. 77 13.14+/-14.24 SA-IDM-5Dl 4. 67+/-0 .10 4. 31+/-0. 39 4.36+/-0.71 4.47+/-0.47 4.45+/-0.32 SA-IDM-lODl 5.62+/-0.31 4.89+/-0.24 4.56+/-0.57 4.96+/-0.74 5.01+/-0.89 CJl
\.0 SA-IDM-14Dl 5.64+/-0.09 4.90+/-0.45 5.02+/-0.35 4.90+/-0.84 5.12+/-0. 71 SA-I DM-2E 1 5.20+/-0.37 4.86+/-0.24 4.37+/-0.25 4.69+/-0.69 4.78+/-0.69 SA-IDM-3El 5.07+/-0.22 4.75+/-0.54 4.55+/-0.55 4.90+/-0.66 4.82+/-0.44 SA-IDM-13E 1 4.91+/-0.49 5.38+/-0.53 4.34+/-0.45 4.67+/-0.32 4.83+/-0.88 SA-IDM-16E 1 5.59+/-0.39 4.90+/-0.66 4.47+/-0.80 4.93+/-0.33 4.97+/-0.92 SA-IDM-lFl 5.33+/-0.39 4.65+/-0.57 4.12+/-0.15 4.57+/-0.63 4.67+/-1.00 SA-IDM-2F2 4.13+/-0. 3S 3.74+/-0.48 3.67+/-0.25 3.78+/-0.40 3.83+/-0.41 SA-IDM-5Fl 4.84+/-0.48 4.41+/-0.94 4.45+/-0.58 4.26+/-0.38 4.49+/-0.49 SA-IDM-6Fl 4.41+/-0.21 4.74+/-1.52 3.44+/-0.42 3.76+/-0.33 4.09+/-1.19 SA-IDM-7F2 4.03+/-0. 35 3.38+/-0.47 3.23+/-0.45 3.25+/-0.53 3.47+/-0.76 SA-IDM-llFl 5.90+/-0.33 4.98+/-0.16 4.93+/-0.17 5.30+/-0.73 5.28+/-0.89 SA-IDM-13Fl 5.38+/-0.29 4.73+/-0.53 4.62+/-0.42 4.76+/-0.94 4.87+/-0.69 SA-IDM-3Gl 5.94+/-0.41 5.27+/-0.12 4.53+/-0.12 5.54+/-0.26 5. 32+/-1.19 SA-I DM-2H 1 5.82+/-0.06 5.40+/-0.46 4.58+/-0.40 5.16+/-0.45 5.24+/-0.52 SA-I DM-3H 1 6 .14+/-0.17 4.83+/-0.61 4.37+/-0.19 5.34+/-0.25 5.17+/-1.52 SA-IDM-3H3 5. 80+/-0.16 4.65+/-0.42 4.39+/-0.18 4.57+/-0.54 4.85+/-1.28 AVERAGE 6.24+/-7.58 5.02+/-2.63 4. 53+/-1. 66 5.01+/-3.00 5.21+/-4.51
- The standard month = 30.4 days.
- Location of stationSA-IDM-2Sl was moved to station SA-IDM-2S2 on 4-28-80.
( 1) Station SA-IDM-6Sl was discontinued on 6-30-80.
TABLE C-11 DIRECT RADIATION MEASUREMENTS - SEMI-ANNUAL TLD RESULTS mrad/standard month*
JANUARY APRIL STATION NO. TO TO MARCH SEPTEMBER SA-IDM-402 5.45+/-0.48 4.62+/-0.44 SA-IDM-9El 6.01+/-0.19 4.76+/-0.28 SA-IDM-11E2 6.16+/-0.31 4.85+/-0.27 SA- IDM-12 E1 6.14+/-0.31 4.99+/-0.42 SA-IDM-2F5 5.57+/-0.40 4.44+/-0.32 SA-IDM-3F2 5.19+/-0.07 3.93+/-0.35 SA-IDM-3F3 5.17+/-0.53 3.84+/-0.29 SA- I,DM-10 F2 5.94+/-0.54 4.94+/-0.42 SA-IDM-12fl 5.88+/-0.14 4.47+/-0.32 SA-I DM-13F2 5.56+/-0.34 4.72+/-0.15 SA-IDM-13F3 5.89+/-0. 31. 4. 62+/-0.43 SA- I DM-14 f2, 5.49+/-0.62 4.58+/-0.50 SA-IDM-15F3 6.42+/-0.48 5.14+/-0.09 SA- I DM-16 F2 5.75+/-0.29 4.21+/-0.34 SA-IDM-1G3 6.84+/-1.40 ( 1)
SA-I DM-lOGl 6.59+/-0.44 5.23+/-0.19 SA-IDM-1661 6.63+/-0.36 5.51+/-0.18 AVERAGE 5.92+/-0.99 4.68+/-0.90
- The standard month = 30.4 days.
(1) TLD lost in field.
60
TABLE C-12 CONCENTRATIONS OF TRITIUM IN SURFACE WATER Results in Units of pCi/l +/- 2 sigma STATION NO. 1-08-80 2-20-80 3-07-80 4-10-80 5-06-80 6-05-80 SA-SWA-llAl 116+/-64 116+/-77 215+/-74 217+/-73 <124 62+/-59 SA-SWA-12Cl 275+/-66 <125 157+/-74 83+/-71 <124 ( 1)
SA-SWA-7El 79+/-63 <125 175+/-74 <115 <124 67+/-65 SA-SWA-1F2 78+/-63 <125 209+/-74 <115 <124 <96
())
SA-SWA-16Fl 107+/-64 <125 151+/-74 <115 <124 <105 STATION NO. 7-10-80 8-06-80 9-03-80 10-06-80 11-04-80 12-01-80 SA-SWA-llAl <125 <106 <97 <91 <103 <109 SA-SWA-12C1 82+/-72 <106 82+/-60 <91 <112 <109 SA-SWA-7El <125 <106 84+/-60 180+/-57 336+/-67 131+/-68 SA-SWA-1F2 <125 <106 85+/-64 <121 <103 <109 SA-SWA-16Fl <117 <106 73+/-60 <91 <11,2 <109
( 1) Insufficient sample for analysis.
TABLE C-13 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN SURFACE WATER Results in Units of pCi/l +/- 2 sigma STATION NO. 1-08-80 2-20-80 3-07-80 4-10-80 5-06-80 6-05-80 SA-SWA-llAl <0.2 0.2+/-0.2 <0.2 <0.3 <0.3 0.4+/-0.3 SA-SWA-12Cl 0.3+/-0.2 <0.2 <0.2 <0.4 <0.2 0.4+/-0.3 SA-SWA-7El <0.2 <0.2 <0.2 <0.2 <0.3 <0.4 m SA-SWA-1F2 <0.2 <0.2 <0.2 <0.3 0.2+/-0.2 <0.3 i"-)
SA-SWA-16Fl <0.2 <0.2 <0.2 <0.2 <0.2 0.9+/-0.7 STATION NO. 7-10-80 8-06-80 9-03-80 10-06-80 11-04-80 12-01-80 SA-SWA-llAl 0.1+/-0.1 <0.2 <0.5 <0.2 <0.4 <1.0 SA-SWA-12Cl 0.2+/-0.2 <0.2 <0.6 <0.2 <0.4 <0.3 SA-SWA-7El 0.2+/-0.2 <0.3 0.4+/-0.3 0.3+/-0.2 0.2+/-0.2 <0.3 SA-SWA-1F2 0.2+/-0.2 <0.3 <0.5 <0.2 <0.4 <0.3 SA-SWA-16 Fl 0.4+/-0.2 <0.2 <0.6 <0.2 0.5+/-0.4 <0.4
TABLE C-14 CONCENTRATIONS OF GROSS BETA EMITTERS IN SURFACE WATER Results in Units of pCi/l +/- 2 sigma STATION NO. 1-08-80 2-20-80 3-07-80 4-10-80 5-06-80 6-05-80 SA-SWA-1 lAl 39+/-5 68+/-7 97+/-10 12+/-3 32+/-3 42+/-4 SA-SWA-12Cl 39+/-5 70+/-7 88+/-9 6.0+/-2.1 12+/-2 43+/-4 SA-SWA-7El 44+/-5 116+/-12 84+/-8 19+/-3 33+/-3 72+/-7 SA-SWA-1F2 16+/-3 36+/-5 54+/-6 6 .1+/-2 .1 6.2+/-1.4 20+/-2
- 0) SA-SWA-16Fl 16+/-3 61+/-7 71+/-7 5.9+/-2.1 9.9+/-1.6 32+/-3 w
AVERAGE 31+/-27 70+/-58 79+/-33 10+/-12 19+/-26 42+/-39 STATION NO. 7-10-80 8-06.:..80 9-03-'80 . 10'-06-80 11-04-80 12-01-80 SA-SWA-11Al 62+/-7 128+/-13 66+/-7 108+/-11 95+/-10 79+/-8 SA-SWA-12C1 38+/-5 98+/-10 53+/-6 88+/-9 73+/-7 71+/-7 SA-SWA-7El 71+/-8 176+/-18 75+/-8 115+/-11 134+/-13 83+/-8 SA-SWA-1F2 19+/-4 83+/-8 32+/-4 76+/-8 60+/-6 51+/-6 SA-SWA-16 Fl 34+/-5 62+/-6 17+/-3 73+/-7 66+/-7 41+/-5 AVERAGE 45+/-43 109+/-89 49+/-48 92+/-38 86+/-60 65+/-36
TABLE C-15 CONCENTRATIONS OF GAMMA EMITTERS* IN SURFACE WATER Results in Units of pCi/l +/- 2 sigma STATION NO. NUCLIDE 1-08-80 2-20-80 3-07-80 4-10-80 5-06-80 6-05-80 SA-SWA- llAl K-40 36+/-8 97+/-10 95+/-10 <9.3 25+/-7 59+/-8 SA-SWA-12Cl K-40 28+/-8 56+/-7 79+/-10 <7.8 <11 61+/-10 SA-SWA-7El K-40 54+/-9 110+/-11 120+/-12 23+/-9 28+/-8 98+/-10 SA-SWA-1F2 K-40 <9.3 31+/-9 54+/-8 <7.8 <9.3 <11 SA-SWA-16F1 K-40 <9.3 74+/-10 96+/-10 <7.8 <9.3 32+/-9 (J)
AVERAGE 27+/-38 74+/-63 89+/-49 11+/-13 16+/-18 52+/-66 STATION NO. NUCLIDE 7-10-80 8-06-80 9-03-80 10-06-80 11-04-80 12-01-80 SA-SWA-llAl K-40 100+/-10 88+/-10 90+/-9 130+/-13 67+/-9 84+/-9 SA-SWA-12Cl K-40 72+/-9 71+/-10 58+/-9 99+/-10 86+/-10 96+/-11 SA-SWA-7El K-40 110+/-11 120+/-12 61+/-9 110.+/-11 130+/-13 110+/-11 SA-SWA-1F2 K-40 31+/-8 47+/-8 39+/-10 69+/-9 46+/-8 53+/-9 SA-SWA-16Fl K-40 60+/-8 25+/-8 27+/-9 75+/-8 84+/-10 47+/-10 AVERAGE 75+/-63 70+/-73 55+/-48 97+/-50 83+/-62 78+/-54
- By gamma spectrometry, all other garruna emitters searched for were <LLD; typical LLDs are given in Table C-33.
TABLE C-16 CONCENTRATIONS OF STRONTIUM-89* AND -90 IN SURFACE WATER Results in Units of pCi/l +/- 2 sigma 1-08-80 4-10-80 7-10-80 10-06-80 STATION to to to ta NUMBER 3-07-80 6-05-80 9-03-80 12-01-80 Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 CJ)
<..ii SA-SWA-llAl <0.9 <0.4 <2.7 <0.5 <2.7 <1.4 <0.9 <0.5 SA-SWA-12Cl <1.0 '0.4+/-0.4 <0.8 <0.5 <1.3 <0.7 <1. 0 <0.6 SA-SWA-7El <1.1 <0.5 <1. 0 <0.7 <1.3 <0.7 1.8+/-0.7 <0.7 SA-SWA-.1F2 <1.2 <0.6 <O. 7 <0.5 <2.0 1.1+/-0. 6 <1.3 <0.8 SA-SWA-16Fl <0.8 <0.4 <1.3 0.5+/-0.3 <1.5 <0.8 <1.2 <0.7
- Sr-89 results are corrected for decay to sample stop date.
TABLE C-17 CONCENTRATIONS OF TRITIUM, GROSS ALPHA AND GROSS BETA EMITTERS, AND POTASSIUM-40 IN WELL WATER Results in Units of pCi/l +/- 2 sigma STATION NO.
RADIOACTIVITY 1-14-80 2-11-80 3-10-80 4-14-80 5-12-80 6-09-80 SA-WWA-4Sl H-3 <103 <121 (1) <119 <115 <124 <96 Alpha <1. 2 <1. 7 <2.8 <2.3 1.9+/-1.7 1.4+/-1.l Beta 12+/-3 3.3+/-2.4 15+/-3 12+/-3 14+/-2 12+/-1 K-40 10+/-1 2.4+/-0.2 16+/-2 16+/-2 9. 7+/-1.0 15+/-1 SA-WWA-5Dl H-3 <103 <121 <119 <115 <124 <96 Alpha 2. 9+/-1.4 <1.5 <1.8 <1.6 <1. 2 <0.8 Beta 5.8+/-2.3 <3.5 4.0+/-2.2 3.8+/-1.9 5.1+/-1.3 3.1+/-0.8 K-40 4.3+/-0.4 4.1+/-0.4 3.8+/-0.4 3.3+/-0.3 2.6+/-0.3 2.6+/-0.3 SA-WWA-3El H-3 <103 <121 <119 <115 <124 <96 Alpha <1.1 <1.8 <2.2 <1. 9 <1.5 <1. 0 Beta 9.5+/-2.2 6.6+/-2.6 8.7+/-2.5 10+/-2 9.0+/-1.5 9.5+/-1.0 K-40 5.5+/-0.6 7.8+/-0.8 7. 2+/-0. 7 12+/-1 7.6+/-0.8 11+/-1 STATION NO.
RADIOACTIVITY 7-14-80 8-:11-80 9-08-80 10-14-80 11-10-80 12-08-80 SA-WWA-4Sl H-3 <125 <97 <105 <97 <103 <123 Alpha 2.1+/-1. 7 <2.7 <1.8 <2.8 <2.2 2. 8+/-1. 6 Beta 13+/-2 16+/-3 10+/-2 10+/-3 13+/-2 13+/-3
- K-40 11+/-1 12+/-1 12+/-1 13+/-1 14+/-1 12+/-1 SA-WWA-5Dl H-3 <125 <106 <119 <97 <103 <120 Alpha <1. 2 <1.0 <1. 2 <2.0 <1. 5 <0.6 Beta 3.0+/-1.2 4.0+/-2.4 3.4+/-1. 2 2.6+/-1.9 2. 3+/-1. 1 3.3+/-1. 9 K-40 3.8+/-0.4 2.5+/-0. 3 2.9+/-0.3 2.7+/-0.3 3.0+/-0.3 2.9+/-0.3 SA-WWA-3El H-3 <125 <97 <119 <97 <103 <120 Alpha <1. 5 <1. 5 <1.4 <2.4 <1.8 1.3+/-1.1 Beta 9.0+/-1.5 9.0+/-2.2 7.7+/-1.5 8.6+/-2.4 8.9+/-1.5 8.6+/-2.3 K-40 12+/-1 8.0+/-0.8 8.4+/-0.8 8.8+/-0.9 9.4+/-0.9 8.3+/-0.8 (1) Station SA-WWA-4S2 was used for the February s amp 1e due to extreme icing conditions at station SA-WWA-4S 1.
66
TABLE C-18 CONCENTRATIONS OF STRONTIUM-89* AND -90, AND GAMMA EMITTERS** IN QUARTERLY COMPOS !TES OF WELL WATER Results in Units of pCi/l +/- 2 sigma 1-14-80 4-14-80 7-14-80 10-14-80 STATION NUMBER to to to to RAD IOACTI VITV 3-10-80 6-09-80 9-08-80 12-08-80 SA-WWA-4Sl Sr-89 <0.8 <1.2 0.7+/-0.4 0.7+/-0.4 Sr-90 <0.4 <0.8 <0.4 <0.4 C'\ Gamma Emitters <LLD <LLD <LLD <LLD
'.J SA-WWA-5Dl Sr-89 <0.8 <0.6 <0.7 <0.6 Sr-90 <0.4 <0.5 <0.4 <0.4 Gamma Emitters <LLD <LLD <LLD <LLD SA-WWA-3El Sr-89 <0.9 <1.3 <0.7 <0.6 Sr-90 * <0.4 0.8+/-0.3 <0.4 <0.4 Gamma Emitters <LLD <LLD <LLD <LLD
- Sr-89 results are corrected for decay to sample stop date.
- All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-33.
TABLE C-19 CONCENTRATIONS OF TRITIUM, GROSS ALPHA AND GROSS BETA EMITTERS, AND POTASSIUM-40 IN RAW AND TREATED POTABLE WATER Station SA-PWA-2F3 Results in Units of pCi/l +/- 2 sigma RADIOACTIVITY JANUARY FEBRUARY MARCH APRIL MAY JUNE H-3 (Raw) 81+/-74 <120 <124 <124 <90 103+/-65 (Treated) <121 <120 <124 <124 <90 <105 Alpha( Raw) 0.4+/-0.4 0.8+/-0.5 0.3+/-0.3 1.1+/-0. 6 <0.9 1.9+/-0.9 (Treated) <0.6 <0.6 <0.5 0.8+/-0.7 <1. 6 <0.6 Beta (Raw) 2. 5+/-0. 5 3.8+/-0.5 1.9+/-0.5 2.9+/-0.4 3.3+/-0.5 4.0+/-0.5 (Treated) 2.7+/-0.5 1.8+/-0.4 2.7+/-0.5 2.8+/-0.4 2.9+/-0.5 2.2+/-0.4 en co K-40 (Raw) 3.0+/-0.3 1.7+/-0.2 1.2+/-0.1 3.4+/-0.3 3.2+/-0.3 1.8+/-0.2 (Treated) 3.6+/-0.4 2.2+/-0.2 1.4+/-0.1 5.0+/-0.5 *5.0+/-0.5 2.3+/-0.2 RADIOACTIVITY JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER ANNUAL AVERAGE H-3 (Raw) <119 <114 <121 91+/-61 <112 <91 (Treated) <119 <114 <121 <99 <112 <91 Alpha (Raw) 1.4+/-0.8 <0.4 1.5+/-0.6 0.8+/-0.5 0.7+/-0.5 0.5+/-0.4 0.9+/-1.0 (Treated) 0.7+/-0.6 0.6+/-0.5 3.2+/-1.0 0.7+/-0.6 0.7+/-0.6 <0.6 0.9+/-.1.5 Beta (Raw) 3.9+/-0.5 2.6+/-0.4 3.1+/-0.5 2.8+/-0.4 3.1+/-0.4 4.0+/-0.5 3.2+/-1.3 (Treated) 2. 5+/-0. 5 2.4+/-0.4 2.2+/-0.5 2.0+/-0.4 3.1+/-0.4 2.7+/-0.4 2.5+/-0.8 K-40 (Raw) 0.64+/-0.06 1.1+/-0.1 1.1+/-0.1 1. 3+/-0.1 1.6+/-0.2 1.3+/-0.1 1.8+/-1.8 (Treated) 0.60+/-0.06 1.3+/-0.1 1.1+/-0.1 1.4+/-0.1 1.6+/-0.2 1.3+/-0.1 2.2+/-3.0
TABLE C-20 CONCENTRATIONS OF STRONTIUM-89* AND -90, AND GAMMA EMITTERS** IN QUARTERLY COMPOSITES OF POTABLE WATER Station SA-PWA-2F3 Results in Units of pCi/l +/- 2 sigina 1-01-80 4-01-80 7-01-80 10-01-80 to to to to SAMPLE 3-31-80 6-30-80 9-30-80 12-31-80 Raw Sr-89 <0.9 <1.2 <1.1 <2.0 Sr-90 0. 4+/-0. 4 1.3+/-0.4 <0.5 <1.1 m Gamma l..O Emitters <LLD <LLD <LLD <LLD Treated Sr-89 <1.0 <2.3 <0.9 <1. 6 Sr-90 0.6+/-0.4 2.4+/-0.8 0.6+/-0.2 0.6+/-0.6 Gamma i Emitters <LLD <LLD <LLD <LLD
- Sr-89 results are corrected for decay to sample stop date.
- All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-33~
TABLE C-21
-CONCENTRATIONS OF STRONTIUM-89* AND -90 IN. BENTHOS Results in Units of pCi/g(dry1) +/- 2 sigma Benthos STATION NUMBER DATE Sr-89 Sr-90 SA-ESB-11Al 6-23-80 <8.9 <2.1 9-23-80 <0.4 0.3+/-0.1
-.....! SA-ESB-12C1 . 6-23-80 <19 2.9+/-2.7 o
9-23-80 <13 <4.4 SA-ESB-7El 6-23-80 <2.8 0.5+/-0.4 9-23-80 <0.1 0.10+/-0.03 SA-ESB-16Fl 6-23-80 <35 <7~8 9-23-80 <29 <10
- Sr-89 results are corrected for decay- to sample stop date.
TABLE C-22 CONCENTRATIONS OF STRONTIUM-90 AND GAMMA EMITTERS* IN SEDIMENT**
Results in Units of pCi/g(dry) +/- 2 sigma STATION NO. SA-ESS-llAl SA-ESS-12Cl SA-ESS-7El SA-ESS-16Fl DATE 6-23-80 9-23-80 6-23-80 9-23-80 6-23-80 9-23-80 6-23-80 9-23-80 Sr-90 <0.04 <0.06 0.03+/-0.03 <0.04 0.03+/-0.02 <0.05 <0.06 <0.06
-.....J K-40 16+/-2 16+/-2 18+/-2 17+/-2 15+/-2 14+/-1 15+/-2 16+/-2 Mn-54 o. 06+/-0.03 <0.03 <0.04 <0.03 <0.04 <0.02 <0.04 <0.05 Co-60
- 0.32+/-0.04 0.09+/-0.02 <0.03 <0;03 <0.05 <0.03 <0.06 <0.08 Cs-137 0.20+/-0.04 0.17+/-0.03 <0.03 0.06+/-0.02 0.06+/-0.03 0.06+/-0.03 <0.05 0.07+/-0.03 Ra-226 0. 7+/-0. l 0.84+/-0.08 0.54+/-0.07 0.85+/-0.09 0.89+/-0.09 0.58+/-0.06 0.6+/-0.,1 0.63+/-0.07 Th-232 0 ~ 9+/-0 .1 0. 91+/-0.09 0.8+/-0.1 0.81+/-0.08 1.1+/-0. l 0.67+/-0.08 1.0+/-0.2 1.0+/-0.1
- All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-33.
- Sediment samples included associated benthic organisms.
TABLE C-23 CONCENTRATIONS OF IODINE-131
- IN MILK Results in Units of pCi/l STATION NO. JANUARY** FEBRUARY MARCH APRIL MAY JUNE SA-MLK-13E3 <0.09 <0.1 <0.1 <0.08 <0.08 <0.1
<0.1 <0.08 <0.07 <O. l <0.1 <0.1 SA-MLK-2F4 <0.08 <0.07 <0.07 ' <0.08 <0.1 <0.2
<0.1 . <0.09 <0.06 <0.1 <0.08 <0.2 SA-MLK-5F2 <0.08 <0.08 <0.09 <0.08 <0.1 <0.1
<0.1 <0.1 <0.08 <0.1 <0.1 <0.1 SA-MLK-14Fl <0.1 <0.08 <0.1 <0.1 <0.09 <0.1
<0.1 <0.08 <0.07 <0.09 <0.08 <0.1 SA-MLK-15Fl <0.1 <0.09 <0.1 <0.1 <0.09 <0.1
<0.1 <0.08 <0.08 <0.1 <0.08 <0.1
......... SA-MLK-3Gl <0.08 <0.08 <0.07 <0.09 <0.1 - <0.1 N <0.1 <0.08 <0.06 <0. 09 <0.09 <0.1 STATION NO. JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER SA-MLK-13E3 <0.08 <0.1 <0.07 <0.08 <0.09 <0.09
<0.07 <0.09 <0.09. <0.1 <0.1 <0.08 SA-MLK-2F4 <0.08 <0.09 <0.08 <0.08 <0.09 <0.1
<0.06 <0.07 <0.07 <0.08 <0.1 <0.08 SA-MLK-5F2 <0.08 <0.1 <0.1 <0.07 0.58+/-0.09 0.42+/-0.07
<0.1 <0.07 <0.08 <0.08 1. 7+/-0.2 0.29+/-0.06 SA-MLK-14Fl <0.09 <0.1 <0.08 <0.07 0.42+/-0.07 <0.08
<0.08 <0.08 <0.09 <O.l 0.32+/-0.07 <0.08 SA-MLK-15Fl <0.1 <0.1 <0.07 <0.08 0.15+/-0.05 <0.2
<0.08 <0.08 <0.08 <0.1 0.16+/-0.07 <0.08 SA-MLK-3Gl <0.1 <0.1 <0.08 <0.09 <0.1 1.1+/-0.1
<0.07 <0.08 <0.08 <0.07 1.6+/-0.2 0.12+/-0.06
- I-131 results are corrected for decay to sample stop date.
- Actual sampling dates can be found on Table C-25.
TABLE C-24 CONCENTRATIONS OF GAMMA-EMITTERS* AND STRONTIUM-89** AND -90 IN MILK Results in Units of pCi/l 2 sigma STATION NO. NUCLIDE JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-MLK-13E3 K-40 1300+/-130 1400+/-140 1500+/-150 1400+/-140 1500+/-150 1600+/-160 Cs-137 <1.2 <1.4 <1. 2 <1.2 <1. 2 1. 8+/-1. 3 Sr-89 <5.3, 1.7+/-1.3 <3.5 <1.4 <2.0 <4.2 Sr-90 3. 0+/-1. 2 3.3+/-0.7 2.1+/-1.4 0.5+/-0.5 1.9+/-0.8 3.9+/-0.9 SA-MLK-2F4 K-40 1300+/-130 1400+/-140 1300+/-130 1900+/-190 1400+/-140 1400+/-140 Cs-137 <1. 6 <1.4 <1.2 2.6+/-1.1 -1.6+/-1.1 <1.2 Sr-89 <4.6 <1.9 <2.5 <2.7 <2.7 <5.7 Sr-90 1.8+/-0. 7 2.4+/-0. 7 3.3+/-1.1 1.5+/-1.1 2.1+/-0.9 <1.8 SA-MLK-5F2 K-40 890+/-89 1200+/-120 1400+/-140 1400+/-140 1500+/-150 *1400+/-140
""-.I Cs-137 <0.8 <1.6 <1.2 <1.2 4.8+/-1.2 6 .3+/-1. 3 w Sr-89 <8.2 <6.1 <5.1 <1. 5 <2.9 <4.8 Sr-90 6.4+/-1.2 6.1+/-1.5 5.5+/-2.2 1. 2+/-0. 6 6.2+/-1.1 9.1+/-1.4 STATION NO. NUCLIDE JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER SA-MLK-13E3 K-40 1600+/-160 1300+/-130 1400+/-140 1400+/-140 1600+/-160 1500+/-150 Cs-137 <1.2 <1.2 <1.2 <1.2 <1.4 <1.2 Sr-89 <5.0 <5.8 <11 <2.3 <4.8 <4.4 Sr-90 3.3+/-0.9 3.2+/-0.9 1. 5+/-0. 6 2.8+/-0.7 3. 8+/-1. 2 4.3+/-1.2 SA-MLK-2 F4 K-40 1700+/-170 1500+/-150 1500+/-150 1700+/-170 1600+/-160 1500+/-150 Cs-137 <1.4 <1.2 <1.4 <1.4 <1.4 <1.4 Sr-89 <8.8 <3.9 <5.7 <3.4 <2.7 <4.2 ~
Sr-90 <1. 6 1. 7+/-0. 5 2.1+/-1.1 1. 8+/-1. 0 1.1+/-0. 8 4.4+/-1.1 SA-MLK-5F2 K-40 2000+/-200 1500+/-150 1200+/-120 1200+/-120 1500+/-150 1400+/-140 Cs-137
- 5.5+/-1.3 3.7+/-1.3 4.4+/-1. 2 <1. 2 <1.4 <1.4 Sr-89 <4.2 <9.2 8.0+/-7.6 <2.2 <4.0 <3.5 Sr-90 <1.1 6.7+/-1.6 3.1+/-0.7 4.7+/-0.8 4.7+/-1.1 4.1+/-1.0
TABLE C-24 (cont.)
CONCENTRATIONS OF GAMMA EMITTERS* AND STRONTIUM-89** AND -90 IN MILK Results in Units of pCi/l +/- 2 sigma STATION NO. NUCLIDE JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-MLK-14Fl K-40 1200+/-120 1400+/-140 1500+/-150 1600+/-160 1500+/-150 1500+/-150 Cs-137 <1.6 <1 .. 2 <1. 2 <1.4 <1. 2 <1.4 Sr-89 <11 <2.5 <2.1 <10 <3.1 <4.2 Sr-90 2.9+/-1.9 2.6+/-0.8 2.0+/-0.8 3. 7+/-1. 7 1. 8+/-1. 0 3.2+/-0.9 SA-MLK-15 Fl K-40 1700+/-170 1800+/-180 1300+/-130 1500+/-150 1300+/-130 1300+/-130 Cs-137 3.0+/-1. 2 2.2+/-1.1 <1.4 <1. 2 3.6+/-1.2 <1.2 .
Sr-89 <5.0 <2.5 <3.1 <2.3 <4.5 2.3+/-2.1 Sr-90 3.4+/-1.1 6.1+/-0.9 4.6+/-1.4 5.3+/-1.1 <2.2 2.4+/-1.0 SA-MLK-3Gl K-40 1700+/-170 1400+/-140 1600+/-160 1400+/-140 1500+/-150 1900+/-190 Cs-137 <1. 2 <1.4 2.1+/-1.0 <1.2 <1.2 <1. 2 Sr-89 2.8+/-2.6 <4.9 <2.2 1.3+/-1.1 <21( 1) <4.2
-...J Sr-90 3.,1+/-1.0 4.8+/-1.5 3.3+/-0.9 3.1+/-0.7 3.4+/-1.2 4.2+/-1.0 STATION NO. NUCLIDE JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER SA-MLK-14Fl K-40 1600+/-160 1600+/-160 1400+/-140 1800+/-130 1600+/-160 1500+/-150 Cs-137 <1. 4 <1.2 <1.2 <1.2 <1.4 1.8+/-1.2 Sr-89 <11 <5.5 <9.2 <3.1 <3.8 <3.5 Sr-90 2.9+/-1.2 4.0+/-0.9 1.2+/-0.5 2. 1+/-0. 9 3.0+/-l.O 3. 7+/-1. 0 SA-MLK-15Fl K-40 1700+/-170 1600+/-160 1900+/-190 1500+/-150 1400+/-140 1400+/-140 Cs-137 <1. 4 <1. 2 <1.2 <1. 2 <1.2 <1.4 .
Sr-89 <5.9 <5.5 <4.8 <2.3 <3.0 <3. 0 sr~9o 2.1+/-1.0 2 .5+/-0. 7 3.0+/-0.9 2.4+/-0.7 3.0+/-0.8 1.1+/-0. 5 SA-MLK-3Gl K-40 1400+/-140 1700+/-170 1500+/-150 1900+/-190 1400+/-140 1400+/-140 Cs-137 <1.4 <1. 2 <1. 2 <1. 4 <1.2 <1. 2 Sr-89 3.4+/-2.9 . <6.5 <3.9 <7.7 <3.7 <3.9 Sr-90 2.5+/-0.8 5.6+/-1.1 4.1+/-1.1 <2.1 4. 3+/-1.0 4.2+/-1.1
- All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-33.
- Sr-89 results are corrected for decay to sample stop date.
(1) High MDL due to low chemical yield. Sample consumed in reanalysis.
TABLE C-25 SAMPLING DATES FOR MILK SAMPLES MONTH 2F4 5F2 14Fl 15Fl 3Gl 13E3 JANUARY 1-07-80 1-05-80 1-06-80 1-06-80 1-07-80 1-07-80
~ to to to to to to 1-08-80 1-07-80 1-07-80 1-07-80 1-08-80 1-08-80 1-21-80 1-21-80 1-20-80 1-20-80 1-21-80 1-21-80 to to to to to to 1-22-80 1-22-80 1-21-80 1-21-80 1-22-80 1-22-80 FEBRUARY 2-04-80 2-02-80 2-03-80 2-03-80 2-04-80 2-04-80 to to to to to to 2-05-80 2-04-80 2-04-80 2-04-80 2-05-80 2-05-80 2-18-80 2-16-80 2-19-80 2-19-80 2-18-80 2-19-80 to to to to to to
........ 2-19-80 2-19-80 2-20-80 2-20-80 2-19-80 2-20-80 U1 MARCH 3-03-80 3-02-80 3-02-80 3-02-80 3-03-80 3-03-80 to to to to to to 3-04-80 3-03-80 3-03-80 3-03-80 3-04-80 3-04-80 3-17-80 3-14-80 3-16-80 3-16-80 3-17-80 3-17-80 to to to to to to 3-18-80 3-17-80 *3-17-80 3-17-80 3-18-80 3-18-80 APRIL 4-06-80 4-07-80 4-07-80 4-07-80 4-06-80 4-07-80 to to to to to to 4-07-80 4-08-80 4-08-80 4-08-80 4-07-80 4-08-80 4-20-80 4-20-80 4-21-80 4-21-80 4-20-80 4-21-80 to to to to to to 4-21-80 4-21-80 4-22-80 4-22-80 4-21-80 4-22-80 MAY 5-04-80 5-05-80 5-05-80 5-05-80 5-04-80 5-05-80 to to to to to to 5-05-80 5-05-80 5-06-80 5-06-80 5-05-80 5-05-80 5-18-80 5-19-80 5-19-80 5-19-80 5-18-80 5-19-80 to to to to to to 5-19-80 5-20-80 5-20-80 5-20-80 5-19-80 5-20-80
TABLE C-25 (cont.)
SAMPLING DATES FOR MILK SAMPLES MONTH 2F4 5F2 14Fl 15Fl 3Gl 13E3 JUNE 6-01-80 6-02-80 6-02-80 6-02-80 6-02-80 6-02-80 to to to to to to 6-02-80 6-03-80 6-03-80 6-03-80 6-03-80 6-03-80 6-15-80 6-16-80 6-16-80 6-16-80 6-16-80 6-16-80 to to to to to to 6-16-80 6-17-80 6-17-80 6-17-80 6-17-80 6-17-80 JULY 7-07-80 7-06-80 7-06-80 7-06-80 7-06-80 7-07-80 to to to to to to 7-08-80 7-08-80 7-07-80 7-07-80 7-07-80 7-08-80 7-21-80 7-20-80 7-20-80 7-20-80 7-20-80 7-21-80 to to to to to to
--..! 7-22-80 7-21-80 7-21-80 7-21-80 7-21-80 7-22-80 O'l AUGUST 8-04-80 8-03-80 8-03-80 8-03-80 8-03-80 8-04-80 to to to to to to 8-05-80 8-04-80 8-04-80 8-04-80 8-04-80 8-05-80 8-18-80 8-17-80 8-17-80 8-17-80 8-17-80 8-18-80 to to to to to to 8-19-80 8-18-80 8-18-80 8-18-80 8-18-80 8-19-80 SEPTEMBER 9-01-80 9-02-80 9-02-80 9-02-80 9-02-80 9-02-80 to to to to to to 9-02-80 9-03-80 9-03-80 9-03-80 9-03-80 9-03-80 9-15-80 9-14-80 9-14-80 9-14-80 9-14-80 9-15-80 to to to to to to 9-16-80 9-15-80 9-15-80 9-15-80 9-15-80 9-16-80 OCTOBER 10-05-80 10-06-80 10-06-80 10-06-80 10-06-80 10-06-80 to to to to to to 10-06-80 10-06-80 10-07-80 10-07-80 10-07-80 10-07-80 10-19-80 10-20-80 10-20-80 10-20-80 10-20-80 10-20-80 to to to to to to 10-20-80 10-21-80 10-21-80 10-21-80 10-21-80 10-21-80
TABLE C-25 (cont.)
SAMPLING DATES FOR MILK SAMPLES MONTH 2F4 5F2 14Fl 15Fl 3Gl 13E3 NOVEMBER 11-02-80 11-01-80 11-02-80 11-01-80 11-02-80 11-02-80 to to to to to to
-...J 11-03-80 11-02-80 11-02-80 11-03-80 11-03-80 11-03-80
-...J 11-16-80 11-18-80 11-17-80 11-17-80 11-17-80 11-17-80 to to to to to to 11-17-80 11-18-80 11-18-80 11-18-80 11-18-80 11-18-80 DECEMBER 11-30-80 12-01-80 12-01-80 12-01-80 12-01-80 12-01-80 to to to to to to 12-01-80 12-02-80 12-02-80 12-02-80 12-02-80 12-02-80 12-14-80 12-15-80 12-15-80 12-15-80 12-15-80 12-15-80 to to to , to to to 12-15-80 12-16-80 12-16-80 12-16-80 12-16-80 12-16-80
TABLE C-26 CONCENTRATIONS OF GAMMA EMITTERS* IN EDIBLE FISH Results in Units of pCi/g(wet) +/- 2 sigma STATION NUMBER SAMPLING DATE K-40 SA-ESF-11Al 5-15-80 to 4.9+/-0.5 8-08-80 9-15-80 to 3.3+/-0.3 10-03-80
-....J co SA-ESF-12Cl 5-15-80 to 4.0+/-0.4 8-08-80 9-15-80 to 3.5+/-0.4 10-03-80 SA-ESF-7El 5-15-80 to 3.5+/-0.4 8-08-80 9-15-80 to 3.3+/-0.1 10-03-80
- All other gamma emitters searched for were <LLD; typical LLDs are given in Table C~33.
TABLE C-27 CONCENTRATIONS OF STRONTIUM-89* AND -90, AND TRITIUM IN EDIBLE FISH SAMPLES Bones Flesh Aqueous Fraction Organic Fraction (pCi /g( dry) +/- 2 sigma) (pCi/l +/- 2 sigma) (pCi/l +/- 2 sigma)
STATION DATE Sr-89 Sr-90 H-3 H-3 SA-ES F-llAl 5-15-80 to <0.2 0.09+/-0.05 <99 155+/-67 8-08-80 9-15-80 to <0.06 0.03+/-0.02 <106 249+/-57 10-03-80
""-J l.D SA-ESF-12Cl 5-15-80 to 0. 3+/-0.1 <0.07 <107 243+/-68 8-08-80 9-15-80 to <0.07 0.03+/-0.02 69+/-56 117+/-56 10-03-80 SA-ESF-7El 5-15-80
\ to <0.2 <0.07 <99 147+/-67 8-08-80 9-15-80 to <0.09 0.03+/-0.03 192+/-67 <90 10-03-80
- Sr-89 results are corrected for decay to sample stop date.
TABLE C-28 CONCENTRATIONS OF GAMMA EMITTERS* IN BLUE CRAB SAMPLES Results in Units of pCi/g(wet) +/- 2 sigma STATION NUMBER DATE SAMPLE TYPE K-40 SA-ECH-llAl 5-15-80 to Flesh 2.8+/-0.3 8-08-80 co 9-15-80 0
to Flesh 2.7+/-0.3 10-03-80 SA-ECH-12Cl 5-15-80 to Flesh 2.5+/-0.3 8-08-80 9-15-80 to Flesh 1. 5+/-0. 2 10-03-80
- All other gamma emitters <LLD; typical LLDs are given in Table C-33.
TABLE C-29 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND TRITIUM IN BLUE CRAB SAMPLES STATION Sr-89 Sr-90 H-3 (Edible Portion) _
NUMBER DATE SAMPLE pCi/g(wet) +/- 2 sigma pCi/g +/- 2 sigma pCi/l +/- 2 sigma SA-ECH- llAl 5-15-80 Flesh <0.03 0.006+/-0.004 <99 to 8-08-80 Shell ( 1) ( 1) 9-15-80 Flesh <0.01 <0.005 340+/-68 to co 10-03-80 Shell <0.03 0.087+/-0.009 SA-ECH-12Cl 5-15-80 Flesh <0.02 <0.004 <99 to 8-08-80 Shell (1) (1) 9-15-80 Flesh <0.01 0. 008+/-0. 003 82+/-65 to 10-03-80 Shell <0.02 0 .10+/-0. 01
- Sr-89 results are corrected for decay to sample stop date.
Indicates tritium analysi-s not performed on shells.
(1) Sample lost in analysis.
TABLE C-30 CONCENTRATIONS OF GAtt~A EMITTERS* AND STRONTIUM-89** AND -90 IN FOOD PRODUCTS Results in Units of pCi/g(wet) +/- 2 sigma STATION NO. DATE SAMPLE TYPE K-40 Sr-89 Sr-90 SA- FPV-2E 1 5-05-80 Asparagus 3.0+/-0.3 <0.02 0.012+/-0.005 SA-FPV-3El 8-03-80 to Tomatoes 3.7+/-0.4 <0.08 0. 005+/-0. 002 8-04-80 SA-FPV-3El 8-04-80 Squash 2.0+/-0.2 <0.1 o. 011+/-0. 004 SA-FPG-5Dl 8-04-80 Corn 2.3+/-0.2 <0.08 <0.004 SA-FPG-2F4 8-05-80 Com 2.0+/-0.2 ~0.1 <0.005 SA-FPV-3H4 8-10-80 Cucumbers 1. 5+/-0.2 <0.1 0.014+/-0.003 co N SA-FPV-3H4 8-10-80 Tomatoes 2.2+/-0.2 <0.07 <0.004 SA-FPG-3H4' 8-11-80 Corn 2.6+/-0.3 <0.07 <0.004 SA-FPV-3H4 8-li-80 Peppers 2.6+/-0.3 <O .1 <0.005 SA-FPG- lGl 3..:11-80 Corn 2.4+/-0.2 <0.09 <0.004 SA-FPV-lGl . 8-11-80 Peppers 2.4+/-0.2 <0.1 <0.005 SA-FPV-lGl 8-11,-80 Tomatoes 2.5+/-0.3 <0.08 <0.004 SA-FPL-1F3 8-11-80 Cabbage 3.9+/-0.4 <0.3 0.018+/-0.007 SA-FPV-2El 8-11-80 Peppers 2.2+/-0.2 <0.09 0. 004+/-0. 003 SA-FPV-5Fl 8-11-80 Peppers 2.7+/-0.3 <0.1 <0.005 SA-FP G-14 Fl 8-11-80 Corn 2.4+/-0.2 <0.07 <0.003 SA-FPV-14Fl 8-11-80 Tomatoes 2.3+/-0.2 <0.07 <0.004
- All other garrma emitters searched for were <LLD; typical LLDs are given in Table C-33.
- Sr-89 results are corrected for decay to sample stop date.
TABLE C-31 CONCENTRATIONS OF GAMMA EMITTERS* AN,D STRONTIUM-89 AND -90** IN MEAT, GAME, AND BOVINE THYROID Results in Units of pCi/g(wet) +/- 2 sigma STATION NO. DATE SAMPLE TYPE K-40 Sr-89 Sr-90
-~
/ pCi/g(dry)+/-2 sigma SA-GAM-3El 2-24-80 Muskrat 2.9+/-0.3 0.3+/-0.2 2.3+/-0.2 SA-GAM-1101. 2-25-80 Muskrat 2.6+/-0.3 <O .1 . 0.31+/-0.05 SA-GAM-3El 12-07-80 Muskrat 3.0+/-0.3 0.2+/-0.1 0.56+/-0.06 SA-GAM-llFl 12-08-80 Muskrat 3.5+/-0.4 0.09+/-0.07 0.10+/-0.04 co w
SA-GAD-4El 12-08-80 Deer 2.5+/-0.3 SA-FPB-3El 2-06-80 Beef 2.0+/-0.2 SA-THB.:..3El 2-06-80 Bovine Thyroid <1.1 SA-FPB-14Fl 5-06-80 Beef 2.3+/-0.2 SA-THB-14 Fl 5-06-80 Bovine Thyroid <0.6 SA- FPB-14Fl 10-24-80 Beef 1. 5+/-0. 2 SA-THB-14Fl 10-24-80 Bovine Thyroid 0.9+/-0.5
- All other gamma emitters searched for were <LLD; typical LLDs are given in Table. C-33.
- Radiostrontium performed on muskrat only. Sr-89 results are corrected for decay to sample stop date.
TABLE C-32 CONCENTRATIONS OF GAMMA EMITTERS* IN FODDER CROP SAMPLES Results in Units of pCi/g(dry) +/- -2 sigma STATION SAMPLE NUMBER DATE TYPE K-40 SA-VGT-13E3 9-11-80 Silage 3.7+/-0.4 SA-VGT-2F4 9-11-80 . Sil age 3.0+/-0.4 SA-VGT-5F2 9-11-80 Sil age 8.4+/-0.8 SA-VGT-3Gl 9-11-80 Sil age 6.9+/-0.7 SA-VGT -15 Fl 9-14-80 Sil age 5.4+/-0.5 co
+:> SA-VGT*l4Fl 12-01-80 Silage 7.1+/-0. 7 .
SA-VGT-5Dl 10-14-80 Grass 6.6+/-0.7 SA-FPG-3El 10-14-80 Soybeans 14+/-1 SA-FPG-5Dl 10-14-80 Soybeans 16+/-2 SA-FPG-5F3
- 10-14-80 Soybeans 15+/-2 SA- FPG-15F1 10-18-80 to Soybeans 19+/-2 10-19-80 SA-FPG-3Gl 10-24-80 Soybeans 15+/-2
- All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-33.
TABLE C-33 LLDs FOR GAMMA SPECTROMETRY SURFACE AIR WELL/POTABLE WATER FISH SEDIMENT PARTICULATES PRECIPITATION WATER NUCLIDES (pCi/l) (pCi/g) (pCi/g) ( 10- 3 pCi /m 3 ) (pCi/l) ( pCi /1 )
Be-7 *
- 0.2 *
- Na-22 0.6 0.01 0.03 31 1.0 0.6
.K-40 7.8 -* 5.8 9.3 7.8 Cr-51 7.4 0.1 0.3 2.7 13 7.4 Mn-54 0.7 0.009 0.02 0.2 0.9 0.7 Co-57 * ' *
- 0.2 *
- Co-58 0.8 0.01 0.02 0.4 1. 2 0.8 Fe-59 1.7 0.03 0.08 0.4 3.0 1. 7 Co-60 0.6 0.01 0.03 0.3 1.0 0.6 Zn-65 1.5 0.02 0.05 0.5 1. 7 1. 5 Zr-95 *
- 0.07 0.6 *
- Nb-95 *
- 0.03 0.2 *
- OJ ZrNb-95 0.6 0.008 *
- 0.8 0.6 c..n Mo-99 500 100 1500 500 Ru-103 *
- 0.03 0.4 *
- Ru-106 6.4 0.08
- 2.9 8.4 6.4 Ag-llOm 0.7 0.009 0.05 0.3 0.9 0.7 Sb-125 *
- 0.06 0.8 *
- Te-129m 14 0.3 0.6 4.9 29 14 I-131 3.1 0.2 0.2 1.3 22 3.1 Te-132 25
- 13 11 600 25 Cs-134 0.6 0.008 0.03 0.3 0.8 0.6 Cs-136 2.2 0.1 0.2 0.8 10 2.1 Cs-137 0.6 0.009 0.03 0.3 0.8 0.6 Ba-140 * *
- 6.0 *
- La-140 * *
- 2.7 *
- BaLa-140 1. 7 0.08 0.3 1. 2 8.9 1. 7 Ce-141 *
- 0.06 0.5 *
T8BLE C-33 (cont.)
LLDs FOR GAMMA SPECTROMETRY FOOD FODDER MILK PRODUCTS CROPS GAME SHELLFISH SOIL NUCLIDES (pCi/l) (pCi/g-wet) (pCi/g-dry) (pCi/g-wet) (pCi/g-wet) (pCi/g-dry)
Be-7 * * * *
- 0.2 Na-22 1.0 0.003 0.03 0.01 0.01 0.02 K-40 0.6 Cr-51 8.2 0.04 . 0.4 0.1 0.3 0.2 Mn-54 0.8 0.003 0.03 0.009 0.009 0.02 Co-57 * * * * *
- Co-58 1.0 0.004 0.04 0.01 0.01 0.02 Fe-59 2.2 0.01 0.1 0.01 0.03 0.04 Co-60 0.8 0.003 0.03 0.01 0.01 0.02 Zn-65 1. 7 0.007 o. 07. 0.02 0.02 0.03 Zr-95 * * * *
- 0.04 co (J)
Nb-95 * * * *
- 0.02 ZrNb-95 0.8 0.003 0.03 0.008 0.008
- Mo-99 200 0.9
- 6.5
- 14 Ru-103 * * * *
- 0.02 Ru-106 6.5 0.02 0.2 0.09 o. 09 0.2 Ag-llOm 0.8 0.002 0.03 0.009 0.009 0.05 Sb-125 * * '* *
- 0.05 Te-129m 17 0.1 1. 0 0.2 0.4 0.2 I-131 2.8 0.02 0.4 0.04 0.6 0.08 Te-132 12 0.02 14 0.3
- 0.8 Cs-134 0.8 0.003 0.03 0.008 0.008 0.02 Cs-136 3.2 0.02 0.3 0.04 0.2 0.04 Cs-137 0.8 0.003 0.03 0.009 0.008 Ba-140 * * * * *
- La-140 * * * * *
- BaLa-140 1.8 0.01 0.2 0.03 0.2 0.09 Ce-141 * * *
- 0.02 Ce-144 1.6 0.007 .o *.1 0.03 0.04 0.1 Ra-226 1. 2 0.005 0.05 0.01 0.01 Th-232 3.1 0.01 0.09 0.03 0.03 Dash (-) indicates a positive concentration was ITEasured in all samples analyzed.
- Indicates that no LLD was calculated for that nuclide in that ITEdia.
APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES 87
GROSS ALPHA ANALYSIS OF SAMPLES Total Water (A0, Al)
A 250 ml (A0) or one 1 (Al) aliquot of the sample is evaporated* to dryness on a hot plate in a preweighed, 211 X 1/4 11 ringed planchet, allowed to cool, and re-weighed. The planchet is counted in a low-background, gas flow proportional counter. Self-absorption corrections are made based on the measured sample weight and calculated thickness. The cali.bration 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 cQunted in a low back-ground gas-flow proportional counter. Self-absorption corrections are made on the basis of the weight of the precipitate.
Calculations are made utilizing the following equations:
Result (pCi/l) = ((S/T) (B/t)) I (2.22 VE TF) 2 sigma error (pCi/l) = 2 ((S/T2) + (B/t 2))11 2 / (2.22 VE TF) where:
S = Gross counts of sample B = *counts of blank E = Fractional Pu-239 counting efficiency T = Number of minutes sample was counted t = Number of minutes blank was counted V = Sample aliquot size (liters)
TF = Transmission factor (based on net weight of sample in counting planchet)
Calculation of lower limit of detection (LLD)
The detection limit is assumed to be exceeded when the .counting result is different from the blank reading by at least 4.66 times the standard deviation of that back-ground.
LLD (pCi/l) = 4.66 (B 112) I (2.22 VE TF t) 89
where:
B = Counts of blank E = Fractional Pu-239 counting efficiency t = Number of minutes blank was counted v = Volume of aliquot (liters)
TF = Transmission factor (based on net weight of sample in counting planchet)
Air Particulates (AD)
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. The alpha activity per unit volume is calculated from the volume of air filtered. An unused filter is used as a blank.
Calculations are made utilizing the following equations:
Result (pCi/m 3) = ((S/T) - (B/t)) I (2.22 V E) 2 sigma error (pCi/m 3) = 2 ((S/T 2) + (B/t 2)) 112 / -(2.22 V- E) where:
s = Gross counts of sample B = Counts of blank E = Fractional Pu-239 counting efficiency T = Number of minutes sample was counted_
t = Number of minutes blank was counted V = Volume of aliquot (cubic meters)
Calculation of lower limit of detection (LLD)
The detection limit is assumed to be exceeded when the counting result is different*
from the blank reading by at least 4.66 times the standard deviation of that back-ground.
LLD (pCi/l) = 4.66 (8 112 ) I (2.22 VE t) where:
B = Counts of blank E = Fractional Pu-239 counting efficiency t = Number of minutes blank was counted V = Volume of aliquot (cubic meters) 90
GROSS BETA ANALYSIS 'OF SAMPLES Total Water (B~, Bl)
A 250 ml (B0) or one l (Bl) aliquot is evaporated to dryness on a hot plate in a preweighed, 211 x 1/4 11 , ringed planchet and reweighed. The planchet is then counted fn a low background gas-fl ow 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)) I (2.22 VE TF) 2 sigma error (pCi/l) = 2 ((S/T 2) + (B/t 2)) 1' 2 I (2.22. v E TF) where.:
s = Gross counts of sample B = Counts of b1an k E = Fractional Sr-90-Y-90 coun*ting efficiency T = Number of minutes sample was counted t = Number of minutes blank was counted v = Volume of aliquot (liters)
- TF = Transmission factor (based on net weight of sample in counting pl anchet) *
)
Calculation of lower limit of detection (LLD)
The detection limit is assumed to be exceeded when the counting result for the sample is different fro.m the blank reading by at least 4.66 times the standard deviation of that background.
LLD (pCi/l) = 4.66 (B 112) I (2.22 VE TF t)
.where:
B = Counts of blank E = Fractional Sr-90-Y-90 counting efficiency t = Number of minutes blank was counted /
v = Volume of aliquot (liters).
TF = Transmission factor (based on net weight of sample in counting planchet)
Air Particulates (BD)
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. The beta activity is calculated from the volume of air filtered. An unused filter paper is used as a blank.
Cal cul at ions are made utilizing the foll owing equations:
Result (pCi/m 3) = (S/T) - (B/t)) I (2.22 V E) 91
2 sigma error (pCi/m 3) = 2 ((S/T 2 ) + (B/t 2)) 1/ 2 / (2.22 VE)
- where:
S = Gross counts of sample B = Counts of blank E = Fractional Sr-90-Y-90 counting efficiency T = Number of minutes sample was counted t = Number of minutes blank was counted V = Volume of sample (cubic meters)
Calculation of lower limit of detection (LLD)
The detection limit is assumed to be exceeded when the counting result for the sample is different from the blank reading by at least 4.66 times the standard deviation of that background.
LLD (pCi/m 3) = 4.66 (8 112) / (2.22 V.E t) where:
B = Counts of blank E = Fractional Sr-90-Y-90 counting efficiency t = Number of minutes blank was counted V = Volume of sample (cubic meters) 92
GAMMA SPECTROMETRY OF SAMPLES Water (Nl)
Four liters of sample is reduced to 100 ml and sealed in a standard container and counted with a NaI{Tl) detector. coupled to a multi-channel p*ulse-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 coµnted with a NaI(Tl) detector, coupled to a multi-channel pulse-height analyzer.
The counting time _is 50,000 second~. *\
Dried Solids {NS, GS)
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 coun.ted 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) js taken, compressed to unit density, sealed in a standard container and counted with a NaI(Tl) detector, coupled to a multi-channel pulse-height analyzer. The counting time is 50,000 seconds.
Air Particulate (GB)
All samples received for the month are .mixed, compressed, and sealed in the standard container, and counted with the high resolution Ge(Li) detector, coupled to a multi-channel pulse-height an~lyzer.
Calculation of result and two sigma error The spectrum obtained is smoofhed to eliminate spurious statistical noise.
Peaks are identified by changes in the slope of the gross spectrum. The net counting rate above the baseline is calculated. This counting rate is con-verted to activity in curie units, making allowance for counting efficiency and garllila ray abundance *. A PDP-11 computer program was introduced for spectrum analysis. '
- Calculations are made utilizing the following equations:
Result {pCi/l, g or m3) = {(S/T) - {B/t)) I {2~22 VE F) .
2 sigma error (pCi/l, g or m3) = 2 ((S/T 2) + (B/t 2)) 112 / (2.22 VE F) 93
where:
s = Sample counts in energy channels for peak being quantitated
- B = Background counts in energy channels for peak being quanti tated T = Number of minutes sample was counted E = Detector efficiency for energy of interest v = Sample aliquot size F = Fraction al gamma abundance Calculation of lower limit of detection (LLD) for G8 and GB LLD (pCi/l, g or m3) = 4.66 (6 s) 1/ 2 / (2.22 VE FT) where:
s = Sample.counts in-energy channels for peak being quantitated T = Number of minutes sample was counted E = Detector efficiency for energy of interest v = Sample aliquot size F = Fractiona~ gamma abundance Calculation of lower limit of detection *(LLD) for Nl, N7, Na*and NA LLD (pCi/l, g or m3) = 4.66 (.63. 6 s) 112 I (2.22 V E FT) where:
s = Sample counts in energy channels for peak being quantitated....-
T = Number of minutes sample was counted E = Detector efficiency for energy of interest v = Sample aliquot size
- F = Fractional gamma abundance 94
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 spectrophotometrically on a Perkin Elmer Model 373 atomic absorption unit. The result obtained, in micrograms per milliliter, is multiplied by the specific activity of 0.12% for natural potassium to deter-
-mine the amount of potassium-40 present in the sample. The error reported is 10% of KCl are determined with each sample set.
Calculations are made using the following equations:
K-40 (pCi/1) -* Cs D {C/S) K 10 3 LLD (pCi/l) = Cs D (.1/S) K 103 where:
Cs = Concentration of Standard (µg K/ml) c = Sample reading s = Standard reading D = Dilution factor K = Specific activity of K-40 per unit weight of potassium
=
- 852 pCi /mg I
95'
ANALYSIS OF SAMPLES FOR TRITIUM Water (H2)
A 15 ml aliquot of the ~ample.is vacuum distilled to eliminate dissolved gasses 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/l) water is vacuum distilled as a blank and is counted with each batch of samples.
In the calculation of the result it is assumed that the condensated and original sample are of equivalent volurres. The volume change associated with the removal of dissolved gases and non-volatile matter is not significant compared to the other errors in the analysis.
Calculations are made utilizing the following equations:
Result '(pCi/l) = ({S/T) - (B/t)) I (2.22 V E) 2 sigma error {pCi/l) = 2 {(S/T 2 ) + (B/t 2 )) 112 / (2.22 V E) where:
s = Total gross counts of sample B = Counts of blank E = Fractional H-3 counting efficiency T = Number of minutes sample was counted t = Number of minutes blank was counted v = Aliquot volume (liters)
Gross counts of sample may be corrected for the blank activity. If the collection container is rinsed with distilled water and the rinse is added to the sample, the rinse plus sample and a separate aliquot of the distilled water are counted. The corrected gross counts for the sample only are calculated using the following equa- .~
tions:
S = ((s-b)v) I G s = (c(G+H)) I V b = (d(H)) I V V = ((G+H) V) I G where:
s = Gross counts of sample G = Volume of sample H = Volume of rinse s = Volume corrected gross counts of sample pl us rinse b = Volume corrected gross counts of rinse v = Corrected aliquot volume c = Uncorrected gross counts of sample pl us rinse d = Uncorrected gross counts of rinse 96
Calculation of lower limit detection (LLD)
The detection limit is assumed to be exceeded when the counting result is different from the blank reading by at least 4.66 times the standard deviation of that background.
LLD {pCi/l) = 4.66 (B 112) I (2.22 VE t) where:
B = Counts of blank E = Fractional H-3 counting efficiency t = Number of minutes blank was counted V = Aliquot volume {liters)
Aqueous and Organic Fraction of Milk or Organic Solids (H3, H4, H9)
A carefully measured aliquot of a food product, such as milk or fish, is dried in a rotating vacuum flash evaporator~ During the evaporation process, the evaporated water fraction is trapped out by a dry ice isopropanol mixture for counting as in (a) below. The dried residue is reserved for (b). The wet sample is analyzed as in (c).
- a. Aqueous H-3 in Food Products An eight (8) ml aliquot of the cold-trapped water is counted in a liquid I.
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 KOH solution is added to remove impurities.
which may cause quenching. An eight (8) ml aliquot is counted in a liquid scintillation counter.* If less than eight (8) ml are collected, the entire portion collected is carefully measured with a 10 ml pipette and then counted.
A sample of deep well water is counted as a blank.
- c. Aqueous and organic Bound H-3 in Food Products A wet weight aliquot is combusted in an RMC designed oxidizer. The collected water fraction is measured and vacuum distilled to remove any impurities. Per-manganate in *KOH solution is added to remove impurities which may cause quenching.
An eight (8) ml aliquot is counted in a liquid scintillation counter~ If less than eight (8) ml are collected, the entire portion collected is carefully measured with a 10 ml pipette and then counted~ _A sample of deep well water is counted as a blank.
Calculations are made utilizing the following equations:
Result {pCi/l) = ((S/T) - (B/t)) I (2.2? VE) of di sti 11 ate 2 sigma error (pCi/l) = 2 ((S/T2) .+ (B/t 2))11 2 / (2.22 VE) of distill ate 97
Result (pCi/g of freeze dried sample) = A (YI) 2 sigma error (pCi/g of freeze dried sample) = C (YI)
Result (pCi/g or l of original sample) = A (VF) 2 sigma error (pCi/g or 1 of original sample) = C (VF) where:
s = Gross counts of sample B = Counts of blank E = Fractional . H-3 counting efficiency T = Number of minutes sample was counted*
t = Number of minutes blank was counted v = Volume of dis~illate counted YI = Liters of water-organic recovered/ g of freeze dried sample VF = Liters of water recovered/ (1 or g) of sample aliquot taken A = Result in pCi/l of distillate c = 2 sigma error in pCi/l of distillate Calculation of lower limit detection (LLD)
The detection limit is assumed to be exceeded when the counting result is dif-ferent from the blank reading by at least 4.66 times the standard deviation of that background.
LLD (pCi/l) = 4.66 (B 112 ) I (2.22 VE t)
LLD (pCi/g of freeze dried sample) = F (YI)
LLD (pCi/l or g) = F (VF) of original sample where:
B = Counts of blank E = Fractional H-3 counting efficiency t = Number of minutes blank was counted v = Volume of dist i 11 ate* counted YI = Liters of water-organic recovered/g of freeze dried sample
. VF = Liters of water recovered/(l or g) of sample aliquot taken F = LLD in pCi/l of distillate 98
ANALYSIS OF SAMPLES FOR IODINE-131 Milk or Water (I@)
The initial stable iodide concentration in milk is detennined with an iodide ion specific electrode. Thirty milligrams of stable iodide carrier is then added to *four (4) liters of milk. The iodide is removed from the milk by passage through ion-exchange resin. The iodide is eluted from the resin with sodium hypochlorite, and purified by a series of solvent extractions with the final extraction into a toluen~ phase. The toluene phase is mixed with a toluene-based l"iquid scintillation solution. The sample is then counted in a beta-gated garruna 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 the recovered volume.
Calculations are made utilizing the following equatiens:
Res ul t = * ( ( S/T) - ( BI t ) ) I ( 2*22 V E F Y)
( pCi /1) 2 si~ma error = 2 ((S/T 2 ) + (B/t 2)) 112 / (2.22 Vt FY)
(pCi/l) I LLD = 4.66, (B 112 ) / (2.22 V E F Y t)
(pCi/l) where:
S = Gross counts of sample in channels containing I-131 peak B = Background counts in channels containing I-131*peak T = Number of minutes sample was counted
- t = Number of minutes background was counted E - . Iodine-131 counting efficiency V = Sample aliquot size F = Fractional gamma abundance Y = Chemical yield of iodine Air Cartridges (Il)
An iodine absorber composed of charcoal is emptied into an aluminum can (6 ans high by 8 ems *in diameter) and counted with a Na! (Tl) detector, coupled to a multi-channel pulse-height analyzer. *-
Calculation -of results and two sigma error Peaks are identified*by changes in the $lope of the spectrum. If peaks are iden-tified the spectrum obtained is smoothed to eliminate spurious statistical noise.
The presence of iodine-131 is identified by the presence of a 3p4 Kev peak. The net counting rate above the baseline is calculated. This counting rate is con-verted 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 decay from the s*ampling 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 fol lowing equations:
Result = ((S/T) - (B/t)) I (2.22 V E FY)
- (pCi /m3) 99
2 sigm~ error = 2 ((S/T 2) + (B/t 2)) 112 / (2.22 V E FY)
(pCi/m )*
LLD 3 = 4.66 (B 112) I (2.22 V E F Y t)
(pCi/m )
where:
s = Gross counts of sample in channels cont'aining* I-131 peak B = Background counts in channels containing I-131 pe~k t = Nunt>er of- minutes background w*as counted E = Iodine-131 counting efficiency - I v = Sample aliquot size F = Fractional ganma abundance 100
ANALYSIS OF SAMPLES FOR STRONTI UM-89 AND -90.
Total Water (S~., T~)
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 s~avenging and barium chromate separations are performed to remove suspected int.erfering nucl ides. The purified strontium is
. converted 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 calcu-lated on the basis of Y-90 ingrowth and Sr-89 decay. A sample of distilled water is used as a blank.
Milk (S4, T4)
A one and half liter aliquot of milk is ashed to destroy organic material and then dissolved in concentrated mineral acid. Stable strontium is added to the dissolved ash to facilitate chemical *separation of Sr-89 and -90, and to determine the strontium recovery. Strontium coAcentrations and purification is ultimately realized by at least two precipitations of strontium nitrate in concentrated nitric acid. Additional i rcin rare earth scavenging and barium chromate separations are performed to remove suspected interfering nuclides. The purified strontium is converted 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, the*n Sr-89 and -90 activities are calculated on the basis of Y-90 ingrowth and Sr~89 decay. A sample of distilled water is used as a blank.
Bones and Shells (SS, TS) .
A large quantity of the sample is dried, ashed and a 2S g portion is then dissolved-in concentrated acid. Stable strontium carrier is added to the dissolved sample.
to facilitate chemical separations of Sr-89 and -90, and to determine the strontium recovery. Strontium concentration and purification is ultimately realized by at least two_precipitations of strontium nitrate in concentrated nitric acid. Addi-tional ir:on rare earth hydroxide scavenging and barium chromate s_eparations are per-formed to remove suspected interfering nuclides~ The purified strontium is converted 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 ingrowth and Sr-89 decay. A sample of distilled water is used as a*blank.
Soil and Sediment (S6, T6)
A large quantity of sample is dried, and a 2S 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 concentrations and purification is ultimately realized by at least two precipitations of strontium nitrate in concentrated nitric acid. Additional iron rare earth scavenging and barium chromate separations are performed to remove suspected interfering nuclides.
The purified strontium is converted to a carbonate for weighing and counting. Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after the separation, the,sample is counted in a low-background gas-flow pro-portional counter. After about 14 days, the sample is recounted, then Sr-89 and -90 l 01
activities are calculated on the basis of Y-90 ingrowth and Sr-89 decay. A sample of disti.lled water is processed with each batch of samples.
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 hydrox-ide scavenging and barium chromate separations .are performed to remove suspected inter-fering nuclides. The purified strontium is converted 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 ingrowth and Sr-89 decay. A sample of distilled water is used as a blank.
Air Particulates (SA, TA)
Stable strontium carrier is added to facilitate chemical isolation of Sr-89 and
-90 and for determination of the strontium recovery in the procedure.
Strontium concentrations and purification is ultimately realized by at least two precipitations of strontium nitrate in concentrated nitric acid. Additional hydrox-ide precipitations and barium chromate separations are performed. * ~
The purified strontium is converted to a carbonate for weighing and counting. Gross beta counts are made soon after the strontium isolation and again after a 7-14 day interval and Sr-90 and Sr-89 activities are calculated on the basis of appropriate Sr-89 decay and Y-90 ingrowth equations. -
Calculations are made using the following equations:
Result Sr-90 = ((Z(Sl-Bl)) - (S2-B2)) I (2.22 KV E9 YT)
(pCi/l, g or m3) _
2 sigma error jr-90 = 2 (Z 2 (Sl+Bl) + S2+B2) 112 / (2.22 (K 2 ) 112 V E9 Y T)
(pCi/l, g or m)
MDL = (-9 -6(~ B2+Z(Sl-B1)) 112 + 2.25 ~ z2(Sl+Bl))/(4.44 V E9 YT)
(pCi/l, g or m )
Result Sr-89 = (F(Sl-Bl) + H(S2-B2)) I (2.22 V E8 YT exp (-.693t4/52.7))
(pCi/l, g or m3) _
2 sigma error ~r-89 = 2(F 2(Sl+Bl) + H2 (S2+B2)) 112 I (2.22 V E8 YT exp(-.693t4/52.7))
(pCi/l, g or m ) .
(pCi/l, g or m ) .
l 02
where:
- Sr-89( 1) = Sr-89 counts on first count Sr-90 = Counts of Sr-90 Y-90( 1) = Counts of Y-90 on first count Y-90(2) = Counts of Y-90 on second (after equil.)
Sl = Sr-89(1) + Sr-90 + Y-90(1) + B(l)
S2 = Sr-89(2) + Sr-90 + Y-90(2) + B(2)
Bl = Blank counts in first count B2 = Blank counts in second count tl = Time in hours. from separation time to Sl t2 = Time in days from separation time to S2 t3 = Time in days from Sl to S2 t4 = Time in days from sampling date to separation date El = 1 - exp (-.693tl/64 hours)
E2 = 1 - exp (-.693t2/2.667 days) z = exp (-.693t3/52.7 days)
R = E9/EY H = (1 + El/R)/K K = Z (El/R + 1) (E2/R)
F = 1 - (2/K) - Z (E~/KR) .
c = (-9 F Bl) - 9 H (S2+B2)+(F B1) 2- 2 F H B2 S2+2 F H Bl B2
+ (H(S2-B2)) 2 B = 2 F2H (S2-B2) 2
- 22 F2 Bl - 9 F22 x = ((B - 4 F c)l/ - B) I (2 F )
E9 = Counting eff. of Sr-90 = .3590 - .7082 X (Wt. in g of strontium carbonate)
EV = Counting eff. of Y-90 = ~4380 - .1337 X (Wt. in g of strontium carbonate)
E8 = Counting eff. of Sr-89 = .4568 -* .2060 X (Wt. in g of strontium carbonate)
T = Number of minutes sample and blank were counted y = Yield v = Sample aliquot size Calculation of minimum detectable levels (MDLs)
Due to the method of calculating the activity of Sr-90 in the presence of Sr-89, the form used in the NBS Handbook 80 for calculating minimum detectable activities is not applicable.
103
ENVIRONMENTAL DOSIMETRY {D0)
Measure11Ent 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 1ack of self-dosing. The energy response curve has been -flattened by a complex multiple ele11Ent 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 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 pl aced in the field stations; one field TLD set is pl aced 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. .
Calculation of results and two sigma error gross TLD(i) = (TLD(i) - D0(i)) (CF {ins)) (CF(i)) 0.955 mrad/mRoentgen ITO= NET(site0) - (NET(RMC0) (D(sta) I D(RMC0)))
NET.TLD{i) =gross TLD(i) - ITO n
AVG = ((sigma NET TLD)/n)(D(STD) I D(EX))
i=l ERROR (95% CL) = t(n-1) sigma NET TLD(i) In) (D{STD)/D{EX))
104
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 iB ~ge field CF( ins) = Correction factor of reader = (6.21) (ELS- * )
ELS = External light .source D0( i) = Zero for dosimeter, i CF(i) = Calibration factor for dosimeter i ITD = In-Transit dose NET(site)0 = Mean of n dosimeters in site lead shield NET(RMC)0 = Mean of n dosirreters in RMC lead shield D(sta) = Exposure period of station D(RMC0) = Exposure period of RMC0 AVG = Mean exposure per standard exposure period at a given station n = Number of readings D(EX) = Days exposed*
D~STD) = Days in standard exposure period t n-1) = t-distribution (student) factor for 95% CL sigma NET TLD(i) = Standard deviation of n readings of NET TLD( i)
ERROR = The 95% confidence limit error of AVG 105
APPENDIX E
SUMMARY
OF INTERLABORATORY COMPARISONS 107
TABLE E-1 INTER-LABORATORY COMPARISONS GROSS ALPHA AND BETA IN WATER (pCi/liter) and AIR PARTICULATES (pCi/filter)
SAMPLE RMC EPA All Participants DATE RMC # TYPE ANALYSIS MEAN+/-s.d. MEAN+/-s. d. MEAN+/-s.d.
Jan, 1980. 25330 Water a 24+/-2 30+/-8 25+/-8 s 55+/-5 45+/-5 46+/-7 Apr, 1980 28995 Water a 13+/-1 13+/-5 13+/-4 s 25+/-1 22+/-5 23+/-5 Apr, 1980 29254 APT a 17+/-1 15+/-5 18+/-4 s 56+/-3 41+/-5 43.+/-17 Apr, 1980 30535 Water a 80+/-11 98+/-25 90+/-32 s 128+/-6 100+/-5 73+/-17 May, 1980 32197 Water a **20+/-3 23+/-5 26+/-7 s 15+/-2 14+/-5 18+/-4 July, 1980 34561 APT a 28+/-1 24+/-6 28+/ s 50+/-1 28+/-5 34+/-5 July, 1980 35623 Water a . 33+/-4 36+/-9 30+/-10 s 43+/-3 38+/-5 41+/ Sept, 1980 38259 Water a 32+/-1 32+/-5
- s 25+/-2 21+/-3
- Oct, 1980 38312 APT a 24+/-1 24+/-3
- s 15+/-1 10+/-3
- Oct, 1980 39340 Water a 30+/-2 39+/-10 36+/-10 s 53+/-1 60+/-5 '57+/-11
- Results are not available at this time.
109
TABLE E~2 INTER-LABORATORY COMPARISONS TRITIUM IN WATER All results-*in p~i/liter*
/
DATE RMC # SAMPLE ANALYSIS RMC EPA All Participants TYPE MEAN+/-s.d. MEAN+/-s.d. MEAN+/-s.d.
Feb, 1980 26747 Water H-3 1673+/-125 1750+/-341 1781+/-272 Apr, 1980 30037 Water H-3 3493+/-68 3400+/-360 3295+/-292 Jun' 1980 33600 Water H-3 1987+/-93 2000+/-345 1995+/-190 Sept, 19'80 36q09 Water H-3 1317+/-47 1210+/-329 1224+/-239 Oct, 1980 38939 Water H-3 3474+/-41 3200+/-360 3132+/-308 110
TABLE E-3 INTER-LABORATORY COMPARISON STRONTIUM-89 AND *STRONTI UM-90 ( l)
DATE RMC # SAMPLE ANALYSIS RMC EPA All Participants TYPE MEAN+/-s.d. MEAN+/-s.d. MEAN+/-s.d.
Jan, 1980 25196 Milk Sr-89 7+/-1 10+/-5 10+/-3 Sr-90 24+/-2 25+/-1.5 23+/-3 Apr, 1980 29254 APT
- Sr-90 10+/-1 10+/-1. 5 10+/-2
,/"
Apr, 1980 30535 Water Sr-89 9+/-1 4+/-5 5+/-3 Sr-90 <3.5 0 2+/-1 May, 1980 31049 Mi 1k Sr-89 23+/-4 10+/-5 9+/-4 Sr-90 10+/-1 15+/-1. 5 14+/-2 July, 1980 34561 APT Sr-90 8+/-1 8+/-1.5 8+/-1 July, 1980 34857 Food Sr-89 120+/-12 94+/-5 90+/-16 Sr-90 11+/-2 13+/-1. 5 14+/-2 Aug, 1980 35906' Milk Sr-89 64+/-7 55+/-5 48+/-12 Sr-90 19+/-2 17+/-1.5 16+/-4 Oct, 1980 38312 APT Sr-90 <1 0 *'
Nov, 1980 39705 Milk Sr-89 21+/-1 23+/-5 20+/-4 Sr-90 <3.7 0 2+/-3 Nov, 1980 39807 Water Sr-89 5.3+/-3.2 *
- Sr-90 <1.3 *
- Dec, 1980 40054 Food Sr-89 <7.0 8+/-5 7+/-1 Sr-90 <3.3 0 2+/-1
- Results not available at this time.
( 1) Data are reported in: pCi/l for milk and water pCi/filter for air particulate pCi /kg for food 111
TABLE E-4 (cont.)
INTER-LABORATORY COMPARISON: GAMMA Results reported in pCi/liter for milk and water, pCi/sample for air particulates, and pCi/kilograms for food products except K which is reported in mg/kilogram DATE RMC # SAMPLE ISOTOPE RMC EPA All Participants TYPE MEAN+/-s.d. MEAN+/-s.d. MEAN+/-s.d.
Sept, 1980 36476 Water 1-131 36+/-1 36+/-5 35+/-4 Oct, 1980 . 39071 Water Cr-51 88+/-6 88+/-5 87+/-15 Co-60 17+/-2 16+/-5 16+/-3 Zn-65 22+/-2 25+/-5 24+/-4 Ru-106 38+/-6 46+/-5 46+/-10 Cs-134 15+/-1 20+/-5 19+/-4 Cs-137 13+/-1 12+/-5 13+/-3 Oct, 1980 39340 Water Co-60 11+/-1 12+/-5 J 13+/-3 Cs-134 11+/-1 12+/-5 11+/-3 Cs-137 21+/-1 20+/-5 20+/-4 Zn-65 <11 0 3+/-6 Nov, 1980 39705 Milk 1-131 <42 18+/-5 19+/-7 Cs-137 22+/-2 21+/-5 2~+/-4 Ba-140 <71 0 3+/-2 K 1519+/-47 1620+/-81 1542+/-174 Dec, 1980 40054 Food 1-131 25+/-3 34+/-6 27+/-5 Cs-137 12+/-1 12+/-5 13+/-4 Ba-140 <32 0 12+/-3 K 2554+/-75 2520+/-120* 2515+/-228 Dec~ 1980 41536 Water 1-131 20+/-1 22+/-6 21+/-4
- Results are not available at this time.
113
APPENDIX F SYNOPSIS OF DAIRY &VEGETABLE GARDEN SURVEY 115
APPENDIX F SYNOPSIS OF DAIRY & VEGETABLE GARDEN SURVEY A door-to-door survey of dairy farms within 5 miles of SNGS was performed in April and July. The results of the April survey were as follows:
One dairy farm, located 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 a dairy farm was located within 5 miles of the site, the vegetable garden survey was performed to a distance of one mile. No vegetable gardens were found in this area.
117
-NOTICE-THE ATIACHED FILES ARE OFFICIAL RECORDS OF THE INFORM,ATION &
REPORTS MANAGEMENT -BRANCH.
THEY HAVE *BEEN CHARGED ~TO YOU FOR A_ LIMITED TIME PERIOD AND
-MUST BE RETURNED TO, THE -RE-CORDS & ARCHIVES SERVICES SEC-TION- P1-22 WHITE FLINT. PLEASE DO NOT SEND DOCUMENTS CHARGED OUT THROUGH THE MAIL. REMOVAL OF ANY PAGE(S) FROM DOCUMENT FOR REPRODUCTION MUST BE RE-FE~RED TO FILE PERSONNEL.
-NOTICE-