ML20150E945
| ML20150E945 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 08/31/1970 |
| From: | INTERNATIONAL CHEMICAL & NUCLEAR CORP. |
| To: | |
| References | |
| NUDOCS 8804040200 | |
| Download: ML20150E945 (50) | |
Text
. _ _ _ - - _ - - . - . .
'T ~ ~ '
. .l-Re: n.;; n;: . Q[jyj -
4
- PILGRIM NUCLEAR STATION O - (
e rld '
- p pu-g e.
- 7.,
a
. .s
.< a eenlf Q\ *deq fjt
(" % %3 w:
- PREOPERATIONAL :: D ENVIRONMENTAL RADIATION SURVEY PROGRAM Summary Report through August 31, 1970 for Boston Edison Co.
Boston, Mass.
January, 1971
'l l
l I
I ICN/Tracerlab-Chemical and Radioisotope Division International Chemical and Nuclear Corp.
1601 Trapelo Road, Waltham, Massachusetts 02154 G30 8804040200 70083123 ,
DR ADOCK 050 I
- ~.- -
PILGRIM NUCLEAR STATION PREOPERATIONAL ENVIRONMENTAL RADIATION SURVEY PROGRAM Summary Report thro >gh August 31, 1970 for Boston Edison Co.
Boston, Mass.
January, 1971 ICN/Tracerlab Chemical and Radioisotope Division International Chemical and Nuclear Corp.
1601 Trapelo Road, Waltham, Massachusetts 02154
TABLE OF CONTENTS P. age 1.0 Introduction 1 2.0 Discussion of Results 1 3.0 Summary 4 4.0 Analytical Procedures 5 5.0 Counting Procedures 12 6.0 Analytical Sensitivities and 14 Sample Size Used 7.0 Data 17 1
l l
l i
i 1
l l
i l
l l
l i
l l
1.0 INTRODUCTION
A pre-operational environmental radiation surveillante program is being perform-ed in relation to the Pilgrim Nuclear Power Station located in Plymouth, bassachusetts for the Boston Edison Company. The survey has been designed to establish existing levels of radioactivity in various types of samples of the environment. Levels ob-served af ter initiation of operation of the station will be compared to these values ,
to determine the effect of the facility on the radioactivity in the environment.
This report summarizes the results obtained through August 31, 1970.
Samples are obtained by Boston Edison Company personnel and are forwarded to an independent laboratory for analysis. The analyses resulting in the data pre-sented in this report were performed by ICN/Tracerlab which also prepared the report.
2.0 DISCUSSION OF RESULTS 2.1 Air Surveillance This section discusses the results obtained for air particulate samples and ga=ma dose rate measurement.
2.1.1 Air Particulates l Air particulate gross beta activity showed the seasonal variation l
which is normally observed in this hemisphere. Low values in winter are followed by 1 increasing values in spring generally reaching a broad maximum in June, July and I
August. This is usually followed by a gradual decline during the fall and early winter. ;
The gross ga=ma values indicated the same trend.
The comparative monthly averages show no significant differences between the on-site, of f-site and reference areas which will permit valid intercom-parison of data between areas.
2.1.2 Gacna Dose Rate The values for gamma dose rate are app;oximately the expected values for this geographical area. The lack of response to very low gamma energies would 1
l l
l tend to make the values lower than data measured using ion chambers or scintillation 1
detectors. This is of no significance in evaluating the effect of plant operation. l There is somewhat more variability between the data than desirable, however the use ,
of new dosimcters at some locations and the stabilization of dosimeter assignment l l
should cause this to improve.
2.2 Aquatic Surveillance Results for domestic and recreational water, sea water and marine life an-alyses are discussed below.
2.2.1 Domestic and Recreational Water The gross beta and Sr values observed for well water samples were generally comparable to each other and significantly lower than the surface water samples. This is to be anticipated since the surface water is effected by fallout, both by direct deposition and by accumulation of runoff from the watershed. Gamma peaks of unknown origin at approximately 0.32 MeV were observed in both June well samples which were the only recent such samples computer processed.
The three ponds exhibit essentially comparable levels of activity.
90 Great Pond gross beta values may be slightly higher. Sr values continued in the 1 pC1/1 range.
2.2.2 Seawater Seawater data from the Pilgrim site showed consistent values through-out. The variability in gross beta results are probably due to the small aliquot ;
used because of the high solids content.
l 2.2.3 Marine Life :
1 i
Irish moss samples from 1970 are somewhat higher in gross beta and l gross gamma activity than observed previously. There is also a large difference be-90 l tween the gross gamma and Sr values obtained for samples from Rocky Point and 1 Manomet Point. Additional samplir3 is being carried out to determine whether the i
2 l
i two locations are comparable.
95 A gamma peak at 0.76 MeV, possibly due to Zr, was observed in both Irish moss samples and to a lesser extent in the rockweed samples.
Within the sample types, fish and lobster yielded results which were generally similar except for the high 90 Sr value in the June 1970 lobster from Rocky 137 Point and the high Cs value found in the April 1970 fish sample. The reason for these differences is not known.
2.3 Terrestrial Surveillance Milk and crop analysis results are discussed below.
)
2.3.1 Milk !
l Milk results are generally as anticipated. The variability between <
locations is greater than observed when samples composited from large areas are used and is probably due to the specific conditions prevailing at each farm. The presence 1O or absence of Ba and I will be most valuable in evaluating future data. No change in the sampling program is indicated.
2.3.2 Crops 90 i Cranberries from both 1968 and 1969 show consistent gross beta, Sr l 1
137 137 and Cs values. Cs is significant and was readily observed in the gamma spectra 1 of all or'the samples. Th'e presence of Cs at the levels seen is probably related to the relatively high potassium concentration in cranberries.
Lettuce and cabbage samples from Plymouth and Bridgewater were l similar for 1970. The cabbage sample from Plymouth in 1969 showed a significant1v 90 higher Sr value than seen in the 1970 samples.
Winter feed samples were comparable between both farms in all values except the higher gross ga=ma result for the sample from Bridgewater. Major peaks at 95 106 0.76 MeV, possibly due to Zr, and lesser peaks at 0.40 MeV, possibly due to Ru were observed in both samples.
3 1
j
l l
1 3.0
SUMMARY
Results from the pre-operational environmental site survey program through August
- 1. 1970 indicate that the selection of sampling locations, sampling frequency and sample 1
types will permit establishment of baseline activity levels and the validity of refer-ence locations.
Where possible problems do exist e.g. Irish moss and gamma dose rate, program modifications to resolve the problems are already being implemented.
The program in general is satisfactory.
l l
4
i l
l 4.0 ANALYTICAL PROCEDURES The procedures outlined in this section are used in sample analysis and dose rate measurement. The details of the procedures have been omitted where they are not important in evaluating the analycical results. Counting procedures are given in section 5.0.
4.1 Air Particulate Samples 4.1.1 Gross Beta The filter paper (Gelman Type A glass fiber) is placed on a 2 inch diameter planchet and beta counted. The air volume sampled is measured using the volume indicated on the sampler meter and correcting to the true sample volume by means of the vacuum reading obtained at the start and end of the sampling period.
4.1.2 Gross Gamma The filter papers representing one months collection from a given location are rolled together and placed in a vial for gamma well counting.
4.2 Water Samples 4.2.1 Gross Beta Water samples are evaperated in a beaker and transferred to a 1 inch diameter planchet with the aid of dilute acid. The sample is evaporated to dryness, weighed to permit self absorption correction and counted in a low level beta counter.
4.2.2 Gross Gamma Gross ga=ma activity is determined by placing the untreated sample in a Marinelli beaker and counting on a multichannel gamaa ray spectrometer. The net gamma count rate between 80 kev and 2.0 MeV is used to calculate the gross gamma activity.
5
4.2.3 Gamma Spectrum The gamma spectrum is measured as described above for gross gamma.
The data are computer processed to accentuate photopeaks. Identification of nuclides is done by the analyst from the computer output using the observed energies.
4.2.4 Strontium-90 Strontium carrier and strontium-85 spike are added to an acidified aliquot of the unfiltered sample. The sample is evaporated to a smaller volume and made basic. Strontium is precipitated as strontium carbonate. The carbonate is dis-solved and strontium is precipitated twice as the nitrate. The nitrates are dissolved, the sample is scavenged with iron hydroxide and barium and radium are removed as the chromates. Strontium carbonate is then precipitated, dissolved in dilute acid and counted fo. strontium-85 activity to determine the chemical yield. Yttrium carrier is then added and the sampic is stored for two weeks to allow for yttrium grow-in.
ittrium is separated and purified by successive hydroxide precipita-tions. The final hydroxide precipitate is dissolved and yttrium oxalate precipitated.
The filtered oxalate is converted to the oxide by ignition, weighed and mounted for counting in the low level beta counter.
4.2.5 Tritium An aliquot of the sample is acidified and distilled. A portion of the distilled sample is introduced into liquid scintillation counting solution and counted for tritium content in a refrigerated liquid scirtillation counter.
4.3 Crops 4.3.1 Gross Beta l
A weighed aliquot of the raw sample is wet ashed using nitric acid.
The wet ashed sample is ashed in a muffle furnace at 600 C overnight. An aliquot 1 I
of the ashed sample is transferred to a 2 inch diameter planchet for beta counting.
6 i
I 4.3.2 Gross Gamma l
l l
1 An aliquot of the untreated sample is placed into a Marinelli beaker !
and counted for gross gamma activity as' described above in section 4.2.2.
4.3.3 camma Spectrum The gamma spectra of crop samples are measured as described above in section 4.2.3.
4.3.4 Strontium-90 Strontium carrier, cesium carrier and strontium-85 spike are added to an aliquot of untreated sample. The sample is then wet ashed using nitric acid followed by ashing in a muffle furnace at 600 C. The resulting ash is digested in dilute nitric acid several times and any insoluble residue removed by filtration.
Cesium is separated by precipitation using ammonium phosphomolybdate. Strontium is separated from the supernate of the cesium precipitate by precipitation as the oxalate.
The oxalate is converted to carbonate by ignition. The remainder of the procedure is as described above under section 4.2.4.
4.3.5 Cesium-137 The cesium phosphomolybdate precipitate obtained from the strontium procedure above is dissolved and the cesium precipitated as the cobaltinitrite. The precipitate is dissolved and cesium precipitated as the chloroplatinate which is filtered, weighed and mounted for counting in a low level beta counter.
4.4 Marine Life 4.4.1 Gross Beta Gross beta radioactivity is measured as described above in section 4.3.1.
4.4.2 Gross Gamma Gross gamma radioactivity is measured as described above in section 4.2.2.
7
4.4.3 Gamma Spectrum The gamma spectrum is measured as described above in section 4.2.3.
4.4.4 Strontium-90 Strontium-90 is determined as described above in section 4.3.4.
4.4.5 Cesium-137 Cesium radioactivity is determined as described above in section 4.3.5.
4.4.6 Fbnganese-54, Cobalt-58, Cobalt-60, Zine-65 Manganese, cobalt and zinc carriers are added to an aliquot of the untreated sample which is then wet ashed. The wet ashed sample is then dry ashed in a muffle furnace at 600 C. The resulting csh is leached several times by boiling with 6N hydrochloric acid. The final hydrochloric acid solution is made 9N and the sample is passed through an ion exchange column. Manganese is eluted using 6N hydro-chloric acii. Cobalt is cluted using 4N hydrochloric acid. The column is washed with water and zinc is eluted with water made just basic with ammonium hydroxide.
Cobalt is separated from the eluate as the hydroxide. The precipitate is dissolved, scavenged with ferric hydroxide and cobalt re precipitated as the hydrox- )
ide after removing excess ammonium by boiling. The precipitate is dissolved and cobalt precipitated as the cobaltinitrite which is weighed and mounted for gamma cour. ting. i l
The manganese fraction is boiled dcwn several times with nitric acid and the manganese precipitated as the dioxide using sodium bromate. The precipitate l
is dissolved and manganese precipitated with acsonium phosphate. The precipitate is filtered, weighed and mounted for gamma counting.
The zinc is separated from the zine fraction by precipitation as the hydroxide. The precipitate is dissolved and scavenged with ferric hydroxide.
The acidity of the solution is adjusted and zinc precipitated as zinc mercuric thio-8
i t
1 l
cyanate which is then filtered, weighed and meunted for gamma counting. l l
4.5 Seawater l
4.5.1 Gross Beta An aliquot of the unfiltered seawater sample is evaporated into a !
2 inch diameter planchet wich is beta counted.
4.5.2 Gross Gamma l Gross gamma is determed as described above in section 4.2.2.
l 4.5.3 Gamma Spectrum Gamma spectra of seawater samples are measured as described above !
I in section 4.2.3.
1 4.5.4 Tritium l Tritium is measured in seawater samples as described above in section 4.2.5.
4.5.5 Strontium-90 Strontium carrier, cesium carrier and strontium-85 spike are added l
to an unfiltered aliquot of the sample. Cesium is separated from the sample as the j i
phosphomolybdate and strontium separated from the supernate as the oxalate. The )
I oxalate is converted to carbonate by ignition. The remainder of the strontium pro-cedure is as given above in section 4.2.4.
4.5.6 Cesium-137 The cesium which has been separated from the sample as the phospho-molybdate is treated as given above in section 4.3.5.
4.3.7 Manganese-54, Cobalt-58, Cobalt-60, Zinc-65 Manganese, cobalt and zine carriers are added to an aliquot of the unfiltered sample. The sample is boiled down using dilute hydrochloric acid and treated several times with 9N hydrochloric acid. Residual salts are removed by filtra-tion and the filtrate is put through an ion exchange column.
9
The remainder of the procedures are as given above in section 4.4.6.
4.5.8 Fractional Gross Beta An aliquot of the sample is acidified and filtered. The filter paper containing the insoluble material which is designated as f raction I is trans-ferred to a 2 inch planchet for beta counting.
Strontium, zinc, iron, nickel, cobalt and cesium carriers are added to the filtrate, the solution is made basic and the sulfides are precipitated. The precipitate is filtered, ignited and transferred to a planchet for beta counting.
This fraction is designated fraction II.
The filtrate is acidified and the volume reduced by boiling. Carb-onates are precipitated from a basic solution, converted to nitrates, dissolved and re-precipitsted as carbonates. The precipitate is filtered and transferred to a planchet for beta counting. This precipitate is fraction III.
The filtrate is made basic, ammonium phosphomolybdate added and t, precipitate is formed by acidifying the solution. The precipitate is disrolved, the I
solution buffered and cobaltinitrites precipitated. The precipitate is filtered, i
ignited and transferred to a planchet for beta counting. This fraction is fraction IV.
4.6 Milk 4.6.1 Strontium-90 Strontium, barium and cesium carriers and strontium-85 spike are added to an aliquot of the raw sample which is then wet ashed. The sample is then ashed in a muffle furnace at 600 C. The resulting ash is acid leached and any residue removed by filtration. Cesium is separated from the filtrate as the phosphomolybdate. ,
1 Strontium and barium are then precipitated as the oxalates from the cesium filtrate.
The oxalate is converted to carbonate by ignition. The remainder of the strontium 10
l l
1 procedure is as given in section 5.2.4 cxcept that the barium chromate precipitate is retained for barium analysis as described below.
4.6.2 cesium-137 The cesium phosphomolybdate prec ;cate is dissolved and treated as described in section 4.3.5.
4.6.3 Barium-140 The barium chromate precipitate is dissolved in acid and the chloride precipitated with an hcl-ether mixture. The precipitate is dissolved and barium pre-cipitated as the sulfate. The precipitate is filtered, weighed and mounted for count-ing in the low level beta counter.
4.6.4 Iodine 131 Iodine carrier is added to an aliquot from the sample which has been made basic with sodium hydroxide. Sodium bisulfite is then added and the sample evaporhted to dryness under a heat lamp. The sample is then ashed in a muffle furnace i
and the ash digested with a very slightly basic sodium hydroxide solution. Residual solids are removed by filtration.
Iodine is extracted into carbon tectrachloride frot. the filtrate after oxidizing and acidification. The organic phase is washed, the iodine reduced with sulphurous acid and back extracted into the aqueous phase. Silver iodide is precipitated from the acidified aqueous phase. The precipitate is filtered, weighcd and counted for counting in the low level beta counter.
4.7 Gamma Dose Rote Gamma dose rates are measured using EG&G TL-15 dosimeters. Dosimeters I are placed at the point of interest for one conth or six months periods. After exposure they are returned to the laboratory for read-out. Control dosimeters are used during distribution and pick up of the dosimeters to permit correction for any .
I 11 l 1
i
extraneous radiation received by the dosimeter during transit. Sufficient dosimeters are used such that there is always at least one dosimeter at a given sampling site at all times.
The average gamma dose rate for the period of exposure is calculated from the measured accumulated dose and the exposure time after cortection for the dose rece!.ved by the control dosimeters. Dosimeter calibration is against cobalt-60 or cesium-137.
5.0 COUNTING PROCEDURES AND EQUIPMENT The detectors used are described in detail since they are most significant.
Supporting electronics are standard and are mentioned only briefly.
5.1 Gross Beta The detector used for gross beta reasurement is a Tracerlab FD-2 gas flow 2
counter with a FDW-2 Mono Mol window apprraimately 150 ug/cm thick. The window diameter is approximately 2 inches. An automatic sample changer (Tracerlab SC-100) is used and positions the sample approximately 1 cm from the counter window.
Argon-methane proportional counting gas or helium-isobutane Geiger gas is used depending on the desired mode of operation.
Samples are counted at least twice for a total accumulated time of at least 60 minutes. A counter standard is included in each set of samples counted to insure proper counter operation. Couc.ter efficiencies are based on 90Sr OY in equilibrium.
5.2 Low-Level Beta The low-level beta flow counters are Isotopes Inc. Model LLD. These con-sist of a guard counter with a 4 1/2" x 4 1/2" x 3/8" counting volume positioned directly above the sample counter which has a 1 1/4" diameter counting volume and a height of 5/16". A manual sample changer places the sample, which is 3/4" diameter 12
I approximately 2 mm from the counter window.
l The guard and sample counters are operated in anti-coincidence. Both use helium-isobutane Geiger gas.
90 131 140 Counter efficiency is determined using a 7, 1 or Ba-La standard.
90 Y is counted as soon as possible after milking and always within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
At least two counts are taken within the first 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> and additional counts are obtained on the third and fifth day. These data are plotted and examined to insure decay with the proper half-life. If necessary additional points are obtained. !
O Similar procedures are followed for 1 and Ba-La except that longer intervals are taken between counts due to the longer half-life.
5.3 Gacma Well For gamma well counting a Tracerlab P-51 LW-1 detector is used. This con-sists of a 2" x 2" cylindrical NaI(Tl) scintillation crystal with a 23/32" diameter x 19/16" deep well, an RCA 6342A photomultiplier and the required socket assembly.
Pulses are fed through a two-channel analyzer set to accept counts f rom the major photopeak(s) of the nuclide being counted in one channel and all pulses greater than 30 kev in the other. The channel ratio is used as a purity check. Standardization is against the nuclide of interest.
5.4 Gross Gamma, Gamma Spectrum These are measured using a 3' x 3' NaI(Tl) scintillation crystal coupled to a photomultiplier. Pulses are fed into a Nuclear Data Model 130A 512 channel analyzer using 256 channels. The spectrum is printed out digitally by channel. For gross gamma, the counts in the spectrum between 80 kev and 2.0 MeV are summed.
Gamen spectrum analysis is performed by computer processing of the data using a prograu which subtracts linear portions of the net spectrum thereby accentuat-ing non-11acar portions i.e. photopeaks. Output is signal-to-noise ratio as a function 13
1 of channel number. Energy and nuclide identification is performed by the analyst.
Semi-quantitative estimates of the amount of activity can be made from the signal-to-noise ratio.
5.5 Liquid Scintillation 1
The sample aliquot is introduced into a 25 m1 low background glass vial containing scintillation s 9ution. Samples are counted against a tritium standard in a Packard Tri-Carb Scintillation Spectrometer Model 3003 which is cooled to 3-5 C.
6.0 ANALYTICAL SENSITIVITIES AND SAMPLE SIZE USED The sensitivities which generally can be attained using the procedures given in section 5.0 are listed below by sample type and type of analysis. The values are determined both by the counting error and by the efficiency of the procedure.
The percentage error quoted is valid where the counting error is not limiting and reflects the overall unc9rtainty of the type of analysis being performed.
The sensitivities given for specific nuclides depends to some extent on the presence of other nuclides in the sample such as cobalt-60 and cobalt-58. The values given are typical for the generally encountered situation. l 14
Sample Type Analysis 'letection Limit Aliquot % Error
-3 3 3 Air Particulate Gross Beta 4 x 10 pC1/m 10,800 ft 210 Gross Gamma -2 cpm /m3 (a) 10,800 ft 3 3 x 10 ?lo Non-Saline Water Gross Beta 1 pCi/1 1000 m1 210 Gross Gamma 10 cpm /1(b) 1000 ml 110 l
Gamma Spectrum (c) 1000 ml Strontium-90 0.5 pCi/1 1000 ml 115 Tritium 2.5 pC1/ml 2 ml !10 Crops, Marine Life Gross Beta 0.2 pC1/g 20 g 210 Gross Gamma 0.01 cpm /g(b) 1000 g t10 Gamma Spectrum (c) 1000 g Strontium-90 0.005 pCi/g 100 g !10 Cesium-137 0.05 pC1/g 100 g !10 Manganese-54 0.1 pC1/g 100 g !20 Cobalt-58 0.1 pC1/g 100 g 220 Cobalt-60 0.1 pCi/g 100 g t20 Zinc-65 0.1 pCi/g 100 g 220 Seawater Gross Beta 60 pC1/1 30 g 120 Fractional Gross Beta 5 pC1/1 500 ml 120 Gross Gamma 10 cpm /1(b) 1000 ml 10 Gamma Spectrum (c) 1000 ml Tritium 2.5 pCi/mi 2 m* 110 Strontium-90 0.5 pCi/1 1000 ml 115 Cesium-137 1 pCi/1 1000 ml !15 Hanganese-54 5 pCi/1 1000 ml 120 Cobalt-58 5 pCi/1 1000 m1 120 Cobalt-60 5 pCi/1 1000 ml 220 Zine-65 5 pC1/1 1000 ml !20 15
Srnple Type Analysis Detection Limit Aliquot % Error Milk Strontium-90 0.5 pCi/1 1000 ml 215 Cesium-137 1 pCi/1 1000 ml 215 Barjum-140 5 pC1/1 1000 ml 215 Iodine-131 5 pC1/1 1000 ml 215 Gamma Dose Rate 1 uR/hr 1 month exposure 210 l
I l
1 l
l i
l l
l I
! (a) In the counter used, 1 cpm curresponds to 1.5 pCi of cesium-137.
l (b) In the counter used, 1 cpm corresponds to 4.5 oCi of cesium-137.
(c) Sensitivity depends en the specific nuclide and the presence of interfering nuclides.
A typical sensitivity is 30 pCi/ sample counted.
16
_ ___ d
l 7.0 DATA Data are presented under tnjor divisions of air surveillance, aquatic sur.cil-1 lanco and terrestrial surveillance.
Sampling locations are shown on the raaps following.
i l
17
INu titubKoi'DUCCll Pilgrim Statien ee e s.Hingham o.
@E. Brain 'T hore A rgs- _4p Air particulate + Desimeter g -( IE.Weymouk co u Weym9uth Beechwoodcg*,cp Egypt j , no,1,, tor
'O '
outh fb* 'GreenbushO e Accord Norwelle - ' -
15 miles Marshiield Hills '
9 ,
Abington North Hanover
'e e gRockland 9g owest Hanover Hanoverr O c c o n Bluli e Abington e M rshpeld Whitman North Pembro er
}\
s @ G E. Pembroke I Hanson ,
Gr,een rbor 6ckton Pem ke ow. Duxbury j
)
I Bryantville 07 xbury oEast Bridgewote s b Duxbury g
est Bridgewater O N $ miles Elmwood Kingf,on e eBridgewater 0 Halifax Nortt Plymouth' MOUTH '
elymptono Plymoutir 4 .
o h
- State Farm \
og (a,,,,
"4 e\
O Cinnon i
Th Green Nort k Maaoriet4 Carvef \
@ Middle oro rver o
. . . . a n ~. . - - }
otakevih 0FFSITE AIR SURVEILLANCE STATIONS
_~
18 BournedalEn g*!hy itownO areham [ qaoamnrae 'h m.i _a _ _ _ _ _ _ _
$ n
~.
ul'1:;:!:
n . . M.,.: h; i.'. .
m[Tk r}:k 26.f.'giF .h. 4_')g%.MR i .
& q.: Mc N 'n
%- L. k.
8 .? .
o y; '% %;
9,c,9s?5.,u .Al:
+ .
... Ai
- /*L 3 \
[ .-
ff - f *'" y N x - y..w
. s.. s f r ,,a.q s-( < .
-f f h_
h,..k' qic7[c:
h ![4-.2w % ,_p ,y j
' 1. ',/-'] i .. .
,I
'R - ( . h . ' ,/ D 1 a.
, .' t' . h 'll ()7,' ll , '
- E :. ,
i 11
- C';g[~;
i t li 3 b ' '
/ --
.)- s g 'ij(h .1, o;
.g 4,( & '.i, ' (i,'
Q -v+
c
_f 3
in y, '
4,.
hi $1. u;A))))L(1'j{f'[!.r6'\-
L Y,' l }glhl', : ..
9
' T> ' ~A i 4, ,:
sn 3 .
.+
ln t 3v iQe. %,n se s. 'fw 4
/g
<?
\
~. ..
. g y
e/ .g6 ,
. ,. , 'o d , ,d; .
<p , g Mx
, <, s c :
) $
[
h e i *.,\,. ', Vy m\ g *# a- , , . .
f
- 'f ', '
j s'
.:. . '*. . ~ -' % v. l
'\
'i,
\
? ,\ '
i
/'
$.f ' t.:*f & ' [ *.% ' \\,l-
'< effs . / 7 \ ,\ ' -
4;
.%h l',? s, ~,&k~ Q O 19
f numaswroeacu
.Wey out "" "'"8'*" "
Hingham Cohasset i E p\$qot hore Acres-g @.Braintree hE. SymoU geS.Hingtiam FOLK dSand Non- HiHs 9 Domestic & Recreation Vater Weymputh Beechwood l,o Egypt @ seawater
@, oCituate O Crops sc Greenbush0 outh 6 Milk 9 O Accord Norwelle 's\ "..
15 miles Marshfield Hills
. Abinlgton g North Hanover O
' e @Rockland Hupefact:
oWest Hanover /
o anopMarshfield # " 8 '" "
o Abington p
Q W ilman S.Hanover North Pembro
/ o R"' - 10 miles E. Pembroke ff f eHanson e
o .,g;cen yc,go, cckton eem ue , ,_ o ,,s ,,
8
.i /
Du/xbury
> oEast Bridgewatef Bryantville
- est Bridgewater , so[h Ouxburyo 5 miles O
Elmwood [
Halifax
' "O eBridgewater )
Nortl( Plymouth 0 MOUTH -
8.
80
- State Farm l Plympton o Plymouth
\As w
oE. Carver
( > o choltonvn 'o Manonet ,
Th Green Nort Carver p
@Middl oro o rver j i
- ....a,...,
ho 1
olOkCVEIl0 l l A;UATIC AND TERRESTRIAL l l
SURVEILLAEE STATIONS So Bournedal
- "" RacamoroO 4,
l i 7.1 Air Surveillance Data pertinent to air surveillance are given as follows:
Table IA Comparative Monthly Values for Gross Beta Radioactivity Table 1B Comparative Monthly Values for Gross Beta Radioactivity Table IIA East k'eymouth Gross Beta Radioactivity Table IIB Plymouth Center Gross Beta Radioactivity Table IIC Cleft Rock Area Gross Beta Radioactivity Table IID Manomet Substation Gross Beta Radiocctivity i
Table IIE Overlook Area Gross Beta Radioactivity Table III Monthly Composites Gross Gamma Radioactivity Table IVA Monthly Average Dose Rate Off-Site Table IVB Monthly Average Dose Rate On-Site Figure 1 Comparative Monthly Values, Gross Beta Radioactivity, Air Part.iculates I
z 21
I TABLE IA AIR PARTICULATES COMPARATIVE MONTHLY VALUES FOR GROSS BETA RADIOACTIVITY (Concentrations in pCi/m )
Means Collection 3 Period Reference Off-Site On-Site RAN Data 1970 (EW) _(PC) (CR) (MS) (OA) (A) (Bl March 0.16 0.16 0.16 (a) 0.18 0 1 April 0.19 0.20 0.20 0.21 0.18 1 1 May 0.33 0.33 0.33 0.36 0.39 1 1 June 0.43 0.43 0.42 0.50 0.48 1 1 3 July 0.46 0.46 0.46 0.44 0.48 1 1 August 0.34 0.32 0.31 0.34 0.32 o Radiation Alert Network, U. S. Public Health Service. Data are reported to nearest integer.
EW - East Weymouth PC - Plymouth Center CR - Cleft Rock Area MS - Manomet Substation OA - Overlook Area A - Winchestc , Mass.
B - Providence, R. I.
(a) Station not yet in operation 22
TABLE in AIR PARTICULATES COMPARATIVE MONTHLY VALUES FOR GROSS BETA RADIOACTIVITY (Concentrations in pCi/m )
Collection _Raference__ Off-Site On-Site Period (EW) gQ (CR) (MS) (OA) 1970 Min. Max. Min. Max. Min. Max. Min. Max. Min. Max.
March 0.13 0.20 0.14 0.18 0.14 0.20 (a) (a) 0.14 0.19 April 0.15 0.23 0.13 0.26 0.14 0.24 0.15 0.26 0.14 0.23 May 0.26 0.42 0.28 0.41 0.24 0.40 0.23 0.45 0.32 0.44 June 0.25 0.60 0.27 0.63 0.27 0.61 0.30 0.66 0.29 0.72 July 0.34 0.63 0.35 0.55 0.36 0.58 0.34 0.58 0.38 0.58 U August 0.20 0.46 0.20 0.43 0.20 0.37 0.19 0.49 0.21 0.48 e
(a) Station not yet in operation
l TABLE IIA AIR PARTICULATES EAST WEYMOUTH Gross Beta Radioactivity Collection Collection Period pCi/m Period pCf/m 2.17-2.24.70 0.16 2 0.02 5.26-6.2.70 0.27 2 0.03 2.24-3.3.70 0.13 0.02 6.2-6.9.70 0.25 1 0.03 3.3-3.10.70 0.15 : 0.02 6.9-6.15.70 0.35 ! 0.04 3.10-3.17.70 0.13 ! 0.02 6.15-6.23.70 0.53 ! 0.06 3.17-3.24.70 0.15 2 0.02 6.23-6.30.70 0.60 2 0.06 3.24-4.2.70 0.20 1 0.02 6.30-7.7.70 U.34 1 0.04 4.2-4.7.70 0.23 2 0.03 7.7-7.14.70 0.63 2 0.07 4.7-4.14.70 0.17 0.02 7.14-7.23.70 0.46 2 0.05 4.14-4.21.70 0.15 2 0.02 7.23-7.30.70 0.42 2 0.05 4.21-4.28.70 0.22 2 0.03 7,30-8,5.70 0.41 2 0.05 4.28-5.6.70 0.26 1 0.03 8.5-8.11.70 0.46 2 0.05 5.6-5.12.70 0.36 1 0.04 8.11-8.19.70 0.36 2 0.04 5.12-5.20.70 0.33 2 0.04 8.19-8.25.70 0.25 2 0.03 5.20-5.26.70 0.42 0.05 8.25-9.1.70 0.20 2 0.02 24
I TABLE IIB AIR PARTICULATES PLYMOUTH CENTER Gross Beta Radioactivity Collection Collection Period pCi/m Period pCi/m 2.17-2.24.70 0.16 2 0.02 5.26-6.2.70 0.41 : 0.05 2.24-3.3.70 0.13 0.02 6.2-6.9.70 0.27 : 0.03 3.3-3.10.70 0.16 0.02 6.9-6.15.70 0.32 0.04 3.10-3.17.70 0.14 ! 0.02 6.15-6.23.70 0.51 0.06 3.17-3.24.70 0.17 0.02 6.23-6.30.70 0.63 2 0.07 3.24-4.1.70 0.18 2 0.02 6.30-7.7.70 0.35 1 0.04 4.1-4.7.70 0.23 2 0.03 7.7-7.14.70 0.55 2 0.06 4.7-4.14.70 0.16 1 0.02 7.14-7.23.70 0.41 0.05 4.14-4.21.70 0.13 1 0.02 7.23-7.29.70 0.52 2 0.06 4.21-4.28.70 0.26 2 0.03 7.29-8,5.70 0.35 ! 0.04 4.28-5.6.70 0.28 0.03 8.5-8.11.70 0.43 2 0.05 5.6-5.12.70 0.31 0.04 8.11-8.19.70 0.36 2 0.04 5.12-5.20.70 0.30 2 0.03 8.19-8.25.70 0.26 2 0.03 5.20-5.26.70 0.36 2 0.04 8.25-9.1.70 0.20 2 0.02 25
l l
TABLE IIC l
AIR PARTICULATES CLEFT ROCK AREA Gross Beta Radioactivity Collection Collection Period pCi/m Period pCi/m 2.17-2.24.70 0.16 1 0.02 5.26-6.2.70 0.40 2 0.04 2.24-3.3.70 0.14 2 0.02 6.2-6.9.70 0.28 0.03 3.3-3.10.70 0.14 ! 0.02 6.9-6.15.70 0.27 1 0.03 3.10-3.17.70 0.14 2 0.02 6.15-6.23.70 0.51 t 0.06 3.17-3.24.70 0.16 ! 0.02 6.23-6.30.70 0.61 : 0.07 3.24-4.1.70 0.20 2 0.02 6.30-7.7.70 0.36 1 0.04 4.1-4.7.70 0.24 2 0.03 7.7-7.14.70 0.58 2 0.06 4.7-4.14.70 0.18 2 0.02 7.14-7.23.70 0.40 2 0.05 4.14-4.21.70 0.14 0.02 7.23-7.29.70 0.49 2 0.05 4.21-4.28.70 0.24 ! 0.03 7.29-8.5.70 0.37 : 0.04 4.28-5.6.70 0.24 ! 0.03 8.5-8.11.70 0.36 2 0.04 5.6-5.12.70 0.38 2 0.04 8.11-8.19.70 0.33 2 0.04 5.12-5.20.70 0.30 2 0.03 8.19-8.25.70 0.27 ! 0.03 5.20-5.26.70 0.35 2 0.04 8.25-9.1.70 0.20 2 0.02 l
I l
1 26 l
TABLE IID AIR PARTICULATES MAN 0 MET SUBSTATION Gross Beta Radioactivity Collection Collection Period pCi/m Period pCi/m 3.24-4.1.70 0.19 ! 0.02 6.18-6.23.70 0.63 1 0.07 4.1-4.7.70 0.25 t 0.03 6.23-6.30.70 0.66 1 0.07 4.7-4.14.70 0.16 1 0.02 6.30-7.7.70 .34 ! 0.04 4.14-4.21.70 0.15 2 0.02 7.7-7.14.70 0.58 1 0.06 4.21-4.28.70 0.26 ! 0.03 7.14-7.23.70 0.42 1 0.05 4.28-5.6.70 0.23 1 0.03 7.23-7.29.70 0.42 1 0.05 5.6-5.12.70 0.38 1 0.04 7.29-8,5.70 0.49 2 0.05 5.12-5.20.70 0.32 1 0.04 8.5-8.11.70 0.42 2 0.05 5.20-5.26.70 0.40 ! 0.04 8.11-8.19.70 0.36 1 0.04 5.26-6.2.70 0.45 1 0.05 8.19-8.25.70 0.24 2 0.03 6.2-6.9.70 0.30 2 0.03 8.25-9.1.70 0.19 1 0.02 6.9-6.18.70 0.40 1 0.04 27
l l
TABLE IIE AIR PARTICULATES OVERLOOK AREA j Gross Beta Radioactivity. .
r Collection Collection .
Period p_Ci /m Period pCi/m 2.19-2.24.70 0.15 ! 0.02 5.26-6.2.70 0.44 2 0.05 2.24-3.3.70 0.12 2 0.02 6.2-6.9.70' O.29 2 0.03 3.3-3.10.70 0.15 ! 0.02 6.9-6.15.70 0.32 1 0.04 3.10-3.17.70 0.14 ! 0.02 6.15-6.23.70 0.58 1 0.06 3.17-3.24.70 0.18 1 0.02 6.23-6.30.70 0.72 2 0.08 3.24-4.1.70 0.19 1 0.02 6.30-7.7.70 0.38 2 0.04 4.1-4.7.70 0.23 1 0.03 7.7-7.14.70 0.58 1 0.06 4.7-4.14.70 0.16 : 0.02 7.14-7.23.70 0.44 2 0.05 4.14-4.21.70 0.14 2 0.02 7.23-7.29.70 0.53 2 0.06 4.21-4.28.70 (a) 7.29-8.5.70 0.39 1 0.04 4.28-5.6.70 (a) 8.5-8.11.70 0.48 1 0.05 5.6-5.12.70 0.40 2 0.04 8.11-8.19.70 0.24 1 0.03 5.12-5.20.70 0.32 1 0.04 8.19-8.25.70 0.29 t 0.03 !
5.20-5.26.70 0.40 ! 0.04 8.25-9.1.70 0.21 1 0.03 i i
1 1 :
I l (a) No sample l
28
TABLE III k
AIR PARTICULATES Monthly Composites Gross Gamma Radioactivit (Concentrations in epm /m )
Co11cetion Period Reference Off-Site On-Site 1970 (EU) (PC) (CR) (MS)
(OA)
March (3 2 2)10 ' (3 ! 2)10 ' (3 ! 2)10 ' (a) (4 2)10
-2
-2 April (5 2 2)10- (5 ! 2)10- (5 2)10- (5 ! 2)10 (5 1 2)10-May (9 ! 2)10- (10 2 2)10- (9 ! 2)10- (10 ! 2)10- (13 2)10-
-2 June (10 ! 2)10- (10 ! 2)10- (9 2 2)10- (11 2)10 (7 ! 2)10-g July (12 ! 2)10- (11 ! 2)10- (8 t 2)10- (12 2)10- (13 2)10-August (12 ! 2)10- (9 2 2)10- (12 ! 2)10- (10 ! 2)10- (13 ! 2)10-(a) Station not yet in operation
TABLE IVA
}DNTHLY AVERAGE DOSE RATE ("
uR/hr .
Off-Site Station March April May June July August Eas t k'eymouth 9.2 8.3 (b) 7.4 8.8 9.5 Kingston 6.8 8.7 6.5 7.1 8.1 7.5 Sagamore 7.8 8.7 7.4 8.5 (b) 9.4
, Plymouth (c) 6.2(d) 5.7 i
Duxbury 6.8 Plymouth 6.6 North Plymouth 7.9 7.2 8.5 Plymouth Center 7.8 6.5 7.1 c.0 6.4 8.8 South Plymouth 7.9 8.6 7.6 8.4 9.8 9.1 Manczet 5.3 Manomet 8.1 8.9 8.6 8.4 9.7 9.3 Manomet 7.4 8.6 9.3 8.5 i Manomet 8.3 5.8 6.4 i Cleft Rock Area 7.1 7.4 7.4 6.5 9.0 7.7 Rocky Hill Road 7.1 9.2 6.8 Bayshore Drive 7.7 Rocky Hill Road 9.2 7.2 9.2 l
l l
(a) Net dose rate after subtraction of 6.6 uR/hr dose rate inherent in dosimeter.
(b) Instru=ent malfunction (c) k'here no value is given, dosimeter was not in place during period. !
(d) June and July i
30 1 l
{
TABLE IVB I
, MONTHLY AVERAGE DOSE RATE (*}
uR/hr On-Site Station March April May June July August. ,
Overlook Area 7.0 8.3 8.1 6.8 10.4 6.8 Public Parking Area (c) 9.7 9.8 7.7 9.1 7.1 l Rocky Hill Road, SW 7.2 7.8 6.3 7.4 6.7 Rocky Hill Road, SSE 8.0 8.0 6.8 8.3 7.8 East Breakwater 10.4 Microwave Tower 7.0 5.3 7.3 13'.0 6.7 Property Line, ESE to SE 5.5 Property Line, SE to SSE 7.6 6.8 Property Line, SE to SSE 9.3 8.4 11.5 Property Line, SSE to S 6.2 6.6 5.9 (b) 6.0 Property Line, SSW 6.9 8.5 9.1 9.7 Prope rty Line, WSW 6.5 10.4(d) 7.4 Property Line, W 7.1 6.7 3.9 9.4 5.4 I
Property Line, NW 7.1 8.0 9.1 Property Line, NNV 8.0 6.4 9.6 10.3 j
a d
i l (a) Net dose rate after subtraction of 6.6 uR/hr dose rate inherrent in dosimeter :
- (b) Instrument malfunction ,
! (c) Where no value is given, dosimeter was not in place during period.
I l (d) June and July i i
l u
1 31 I
l I
FIGURE 1 10 _ . .
g . r t. H. . 2 4 i. - i. i p . ; t i i .- -, - 4 -> .i ti. 4 i .
l l
1i
- i ..' 1-2
..1
? .~ .* .
COMPARATIVE MONTHLY VALUES 7
r - +
GROSS BETA RADIOACTIVITY i 11 AIR PARTICULATES
-1 !'. : L: . .
3
. --.- +
---o- On -S i t e
..-.~.
_4 . . . . . .
. ....- : Off-Site +
4 - -x - Reference
(.g q- 2 . t2 4
~
- 3. .>
t
.a .u ..a..e i ,
. I.
. _ . .. . 4
. . 4, . . , ,. . . . . -. . . .t. . . , o
- o. . . .- . ,
.n n, .v. ... n , . . . , . .+ .. . . .,
, ,. . . 4 .~. . . - . _ , - . . . .a. .m . , . . ,. . .
. ,i 1
...t . ., . .
i I
_6 .
- .t . .!
?
. .J . _. .
l
(
( $ , i k
'.,l. .' , . . . ' .- . . . .
q
..,'. . . .I -. 4 . ._ . .i .b . .. . . .4 -.4.
. 7 -- .h i . .
4
+ .I I. i l
._.I . - -
! l }
.h ..Ir. A! '-. '
p... ,.f_, e'
._.f..$ .f i'
.I
.? , - ,!
)
31.0 i ' i f I i . > . t
, i. !
- s. ;- t *
- i g !l !* i t-
, . - i- ; - .; - . ~
, . t ,
i .
. = . - .. _. ..
- 6 n . _
4 . . .._. . . .
a ,
..i w.,. . .,
. b
-4 .. , . .. . - . . . - -.._. .. . - . .. ...-.i _ . . .
u +... .
. _ , . . .. .. . ~ .. .. .
s._ ,,. N~. c m. .. .
a g
_. - _ - v. %.
- .[ - ;.W:
p e-
+ 4
%~. .
~
o c
... ,. r,.n.c. - .
- x. .n. . .
y r. ,. .
a,, ., .. . . . . - .. .. ... . .
.e , . .-.-..
s.<
..a.-... . ...- . . .
. .4 u
c v . . s, .. . .. .~ - .. . , . .. ... ,
u 2 c .- .-..-. e. w>- . .- - ,-. . - . - . - . - . . . . . . ,
.o, . .
, a .- . . c . . -.. .
.-+,.-u.
-. . . . . ~ .i ... .... . . . - . .. . .
. 4 . . . . . . - . . . . -
. . . . . . - . . ... .-4 .. . _ , . . - . . . . . . . .
... . 4 _ . ..;. a ., . . .
, ., u . . . . , . . .
. .. .. . . _ . . . ... . - . . . _. . . . . . . . . . -4 01 i i ; i 2 i i t :
< : ; . i
- . t ,
.. _..... 4 ..
. . - . . .. .~ . . . . .. _. . . - _ . . . . .. , . , . . ,
.~ . . .
3 g . ... ... .. . . .. .. - . . 4 .. . . . . . . . -.
4 ...
. ,1 .
_. L-.. ._. .
2a. ~ .
.44....
. ~. , - .4 4 ,i ...t_ .l - .., -. .... .. . . .
q
)
.-a -.. a..,. a, _ 4, . + . - . . . . . +..,-- .+.-... .
.t. 4,- .. .. -,a,... . . . . . . . 4. a.
., i - . . . _ .
,. . . . i. . . .
I A _. _.i 4 & , + .i ?# g
$ __l .. .f l
,. -I t
.i ..
j j
.-.i.4.,
j
,e_.4.. -.
l L... , .. .. .I .
.1 : , i e i
...t__ __.t _i i L. .' t . .
.l
-. i _ .I . . .i 6 . 4_ ....i . ... .t - .r . ... 4- , _ . . . - . . . .. . .
- i i i i I i i 1- 1. i i i i i ! ' I i t i ! i t i , I. i i i i
- ii 1 6 i ,
1 March April May June July August pa.
f l 1
l 7.2 Aquatic Surveillance Data from the aquatic surveillance sampics are presented as follows:
Table V Domestic and Recreational Water -
1 Figure 2 Domestic and Recreation Wster - Gross Beta Figure 3 Domestic and Recreation Water - Strontium-90 Table VIA Seawater Table VII Marine Life d
I l
33 1
l
TABLE V DOMESTIC AND RECREATIONAL WATER Collection Cross Beta Cross Gamma Location Date pCi/L cpm /L 90 3 Sr pCi/L Il pCi/ml Little South Pond 8.28.68 6.3 1 0.5 30 t 10 0.8 0.2 8.27.69 6.6 2 1.0 < 10 1.6 2 0.5 < 2.5 9.24.69 6.0 1 1.0 17 1 10 < 0.5 < 2.5 10.21.69 4.2 1 1.0 < 10 < 0.5 < 2. 5 11.20.69 4.7 2 1.0 < 10 < 0. 5 < 2.5 12.22.69 8.0 2 1.0 < 10 < 0. 8 1 0. 5 (a) < 2.5 2.17.70 3.5 1.0 < 10 1.1 0.5 < 2. 5 3.24.70 5.3 1 1.0 < 10 1.1 2 0.5 < 2.5 y 4.21.70 5.5 1 1.0 < 10 < 0. 5 < 2. 5 5.20.70 13.4 2 1.0 < 10 < 0.5 < 2.5 6.23.70 5.6 1 1.0 < 10 0.8 2 0.5 < 2.5 7.29.70 3.8 ! 1.0 < 10 1.3 2 0.5 < 2.5 8.19.70 4.2 2 1.0 27 1 10 0.6 1 0.5 < 2.5 College Fond 11.21.69 4.82 1.0 12 ! 10 < 0.5 < 2.5 3.24.70 5.8 1 1.0 < 10 1.3 2 0.5 < 2.5 4.28.70 11.4 t 1.0 < 10 < 0.5 < 2.5 5.20.70 8.6 2 1.0 < 10 1.3 1 0.5 < 2.5 6.23.70 7.4 2 1.0 < 10 1.0 1 0.5 < 2.5 7.31.70 3.8 1 1.0 20 t 10 1.1 2 0.5 < 2.5 8.19.70 4.8 2 1.0 14110 0.8 1 0.5 < 2.5 o One (1) cpm is equivalent to 4.5 pCi if activity is assumed due to Cs.
(a) Yttrium fraction lid not exhibit normal decay.
TABLE V cont.
DOMESTIC AND RECREATIONAL WATER A
Collection Cross Beta Gross Gamma Location Date pCi/L cpm /L 90 3 Sr pCi/L H 1,* i/ml Lout Pond Well 8.27.69 2.5 1.0 13 ! 10 < 0.5 < 2.5 9.24.69 5.4 1 1.0 < 10 < 0.5 < 2.5 10.21.69 5.2 1 1.0 < 10 < 0.5 < 2.5 11.20.69 1.9 1 1.0 < 10 < 0.5 < 2.5 12.22.69 7.5 t 1.0 < 10 < 0. 5 < 2.5 1.22.70 1.5 ! 1.0 < 10 < 0.5 < 2.5 2.17.70 2.2 ! 1.0 < 10 < 0.5 < 2.5 3.24.70 1.3 2 1.0 18 ! 10 < 0. 5 < 2.5 4.21.70 1.8 2 1.0 < 10 < 0.5 < 2.5 v.
5.20.70 2.7 2 1.0 < 10 < 0.5 < 2.5 6.23.70 2.6 2 1.0 52 1 10 < 0. 5 < 2.5 7.29.70 1.7 1 1.0 < 10 < 0.5 < 2.5 8.19.70 < 1. 0 < 10 < 0.5 < 2.5 Manomet Well 8.28.68 < 2.0 < 10 < 0.5 8.27.69 3.5 1.0 < 10 < 0. 5 < 2.5 9.24.69 2.8 2 1.0 < 10 < 0.5 < 2.5 10.21.69 3.0 2 1.0 < 10 < 0.5 < 2.5 11.20.69 1.1 1 1.0 < 10 < 0. 5 < 2.5 12.22.69 4.4 2 1.0 12 ! 10 < 0. 5 < 2. 5 1.22.70 1.1 2 1.0 12 10 0.8 2 0.5 < 2.5 2.17.70 1.9 1 1.0 < 10 < 0.5 < 2.5
- One (1) cpm is equivalent to 4.5 pCi if activity is assumed due to 137 g,
TABLE V cent.
DOMESTIC AND RECREATIONAL WATER Collection Oross Beta Gross Cama Iocation Date pCi/L cpm /L Sr pCi/L H pCi/ml Manonet Well 3.24.70 2.4 1.0 12 1 10 < 0.5 < 2.5 4.21.70 1.5 1.0 12 10 < 0.5 < 2.5 5.20.70 1.3 ! 1.0 < 10 < 0.5 < 2.5 6.23.70 1.5 ! 1.0 42 ! 10 < 0.5 < 2.5 7.29.70 1.9 ! 1.0 <10 < 0.5 < 2.5 8.19.70 1.1 ! 1.0 < 10 < 0.5 < 2.5 Great Pond- 8.28.68 < 2.0 40 10 1.4 1 0.1 S uth Weymouth g 8.27.69 6.3 1 1.0 < 10 < 0. 5 < 2.5 9.24.69 7.6 1 1.0 < 10 1.3 ! 0.5 < 2.5 10.21.69 8.9 1.0 < 10 1.2 ! 0.5 < 2.5 11.20.69 6.5 ! 1.0 13 ! 10 < 0.5 < 2.5 12.22.69 2.8 2 1.0 < 10 < 0.8 ! 0.5(a) < 2.5 1.22.70 5.9 ! 1.0 < 10 1.3 ! 0.5 < 2.5 l 2.17.70 6.7 ! 1.0 < 10 1.3 2 0.5 < 2.5 3.25.70 7.3 1.0 < 10 < 0.5 < 2.5 4.22.70 8.7 1.0 < 10 1.3 ! 0.5 < 2.5 5.20.70 11.1 ! 1.0 < 10 1.0 ! 0.5 < 2.5 6.23.70 8.6 ! 1.0 < 10 1.1 0.5 < 2.5 7.31.70 11.1 ! 1.0 < 10 1.1 1 0.5 < 2.5 8.19.70 7.9 1 1.0 < 10 0.6 ! 0.5 < 2.5 137 o One (1) cpm is equivalent to 4.5 pCi if activity is assun:ed due to Cs.
(a) Yttrium fraction did not exhibit no m i decay.
_ = . .
l 10 - -10 '
_ Lou?. Pond Well Manomet Well _
I -
5- -- - - Detection Limit _$ ;
C T - T - < 2- Pi/it**
L_r- -
I I~l 1 l _
____~.
1 _____1 _ ,.
O_ _o i 15 - _15 Great Pond Little South Pond College Pond _
l P i
10 - _10 l
_ 1 I _
t 5- - -5 '
__I _,,j i -- .
1 !
o 0 t 6 9 10 11 12 1 2 3 4 5 6 7 6 6 9' 10 11 12 1 2 3 4 5 6 7 8 11 12 1 2 3 4 5 6 7 8 ;
i 19e;9 1970 1969 1970 1969 1970 FICl3E 2: DOMESTIC & RECREATION WATER I Gross Beta (;Ci/ liter) 1 I
l _ - _ - _ _ _ _ _ _ _ - - - _ _ _ _ - - - _ _ = _ _ _ . _ - - - - - -. - - . - - - . ,. - . - - ,, - , , , . - . , . , . - , . . . - , - , - - , - , , , - - . . . . . . _ - ,. . , , . ,
,1
,lll 0 5 0 5 0 w_
2- _ _ 0 _
. _ _ _ _ 1- - _ _ _ 1- _ _ _ - _ _ _ -
8 7
6
_ t r _
- i e -
m t d 5 i 1 n - 0 L 1 o - 7
/ P 4 9 n i - 1 o C e g
l i p 3 t e -
c 5 l -
e l 2 t o e<
C -
D 1 2
9
- T T 1
1 6
o
- T r 1 t
- 8 7
6 5
0 R d
n T 7 E T
4 9 o - 1 A P -
3 W
h N t - O )
u 2 I r o T e S - A t 1 E i e R l l - I/ i t 2 I t - 1 R c i - p L 1 & (
T 1 C 0 o 9 I 9 T h% 9 1 T
S E a n
- M i
- O t 8 D n
- o
- r 3 t S
E R
U
- G 8 I F
7 6
5 0
- 7 4 9 1
d 3 n -
o -
l P 2 t -
a 1 e
r -
G 2 h
1 1
o 9
- h 6 9
9 1 8
0 5 0 5 0 2 1 1 0 o lllt
w TABLE VIA SEAWATER Fractional Cross Beta ,
Collection Gross Beta pCi/L 3 Gross Gamma II Location Date pCi/1 Frac. I II III IV cpm /1 pCi/ml Pilgrim Site 8.27.69 63 ! 12 <5 <5 <5 <5 < 10 < 2.5 9.24.69 <5 <5 <5 <5 < 10 <2.5 10.21.69 291 2 20 <5 <5 <5 <5 <10 < 2.5 11.20.69 <5 <5 <5 <5 <10 < 2.5 Quarterly <5 s5 <5 <5 < 10 < 2. 5 Composite 12.22.69 <5 <5 <5 <5 <10 < 2.5 1.28.70 <5 <5 <5 <5 < 10 < 2.5 2.17.70 <5 <5 <5 <5 < 10 < 2.5 Quarterly <5 <5 <5 <5 < 10 < 2.5
$ Composite 3.25.70 <S 815 <5 <5 < 10 < 2.5 4.21.70 <5 825 s5 <5 < 10 < 2.5 5.20.70 <5 8!5 815 <S <5 < 10 < 2.5 Quarterly <5 715 <5 <5 < 10 < 2.5 Composite 5.7.3.70 <5 515 72 5 725 < 10 < 2.5 7.29.70 <5 525 <5 <5 < 10 < 2.5 8.26.70 <5 <5 <5 6!5 715 < 10 < 2.5 Quarterly <5 <5 <5 <5 19 2 10 < 2.5 Composite o One (1) c?m is equivalent to 4.5 ff activity is assumed due to Cs.
m -- -
TABLE VIB SEAWATER (Concentrations in pCi/L)
Location Date 90 137 54 58,60 65 Sr Cs Mn Co Zn Pilgrim Site Aug.-Oct. 1969 Composite < 0.5 22 1 <5 <5 <5 Dec. 1969-Feb. 1970 Composite < 0. 5 <1 <5 <5 <5 March-May 1970 Composite < 0.5 <1 <5 925 <5 June-Aug. 1970 ,
y Composite < 0.5 0.20 2 0.01 <5 <5 <5 oo I
- Volume analyzed: 18.93 liters J
ll s
3 nj1 1 1 1 1 1 1 1 1 1 1
) 1 1 1 1 1 If 0 0 D 0 0 'o 0 0 0 0 (
a
$<G 2 < < ( < c < < < <
0 0 0 0 0
~ o 0
6, CE1 /
1 1 1 1 1 1 1 1 1 1 )
a 1 1 1 1 1 i 0 0 0 0 0 D 0 0 0 0 0 ( 0 0 0 0 0 8 C 5 p : < < < c < < < < < < < < < < <
m ng )
1, 1 1 ) ) ) ) 1 1 1 ) 1 1 1 1 1 M/ a a a 2 a a i ( 0 0 0 ( ( ( ( 0 0 0 ( 0 0 0 C 0 0 p - < c < < < < < < < <
5 5 5 6 1 0 0 0 1 1 m
sg 5 5 5 5 5 5 5 5 5 0 5 0 0 5 C/ 0 0 0 0 0 0 1
0 0 0 0 0 0 ) 0 1 a 2 ! 1 1 C 0 0 0 0 0 0 0 0 0 0 ( 0 p < < < c < < < < < 0 <6 9 9 0 0 < 3 4 3 7 0 0 0 0 0 5 5 5 5 5 5 5 5 5 0 0 0 0 0 0 0 0 0 0 0 J. 0 0 0 0 0 rg m 5 0 0 0 5 5 5 5 D 5 0 5 0 0 0 0 0 0 0 0 0 0 ) 0 S/ 0 2 2 ! 0 0 0 0 i 0 2 a 0 2 2 1 2 1 (
Cp 0 8 9 2 0 0 0 0 6 0 5 0 3 7 8 2
< 2 1 3 < < < < 0 < 3 6 1 1 0 0 2 0 0 < 1 0 0 0 0 .
0 0 0 s 0 0 0 0 0 0 C E
I F I I V L o
a 3 1 1 1 1 1 1 3 1 1 E
L B
E N
m m
am 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1
00 1 t e
I 0 0 0 0 3 3 3 3 0 0 0 0 0 0 0 0 0 u A R Cg d
T A / 2 2 2 2 2 2 2 2 1 2 1 ? 2 1 M sm sp 2 3 4 1 2 !
d oc 1 1 6 6 6 0 7 4 4 9 6 5 7 6 e r
0 0 0 0 1 0 0 1 0 7 1 0 0 m 4 6 6 5 u C 0 0 0 0 0 0 0 0 f 0 0 0 0 s s
a a s t 1 2 2 2 6 i em 2 3 2 3 7 2 5 8 2 4 2 2 B g 0 y 0 0 0 0 0 0 0 0 0 O 0 0 0 0 0 0 t
/ 1 i sf ! 2 1 ! t 2 ! 2 i !
sC
! 2 1 2 1 v op 4 3 7 0 i r
1 3 2 2 5 0 2 1 5 2 9 2 0 t C 0 4 1 1 c 2 3 3 6 2 4 2 4 8 6 6 1 4 4 a f
i n i e o 9 C d i 8 9 0 0 8 8 8 8 9 6 0 0 p i t e 6 6 7 7 6 6 6 6 6 0 0 8 7 7 0 0 l ct 7 7 6 1 ea 7 7 5 9 7 7 9 0 7 7 7 5 c lD 2 1 1 2 2 2 1 1 2 9 9 u l 1 1
1 2
0 1 2 1 1 4 n o 8 1 5 6 8 8 8 9 1 4 7 9 1 6 6 4 4 o si C t h
t t n
t t t t t e r n e n n n n e te et t l o i t t e et n e e a f n
t o i n n i i i i o o o o i i i t t t i t t v o P S i i i i n o i i i d P P P P S S S S S i P S S u e i o o o q z t
a t
e i m P P t t t e e e e i i i t m m m m m P i i t
e mm i i e
l y
c m r y y m o o g k k o om om omg rg rg r r r y m g g k o r r g g s a i n L n l c c n n n n l l l l l c n l l a a i o o a a a a i i i i i o a i i m M P R R M M M M P P P P P R M P P p t c o n
)
1 e s s s s ( l e s s s s p l e r r r r o o o o d k e m pp e e e e M M M M e e n a my t e e O S aT t
s s s s t t h h h h h h h h h h h s s s s w w k k S b b b b s s s s s s s i i i i c c )
o oo o L l I l i i i i i i i F F F F F F F I r r r r I I I o o R R * (
a t
i 7.3 Terrestrial Surveillance '
I Terrestrial surveillance data are presented as follows: l Tabic VIII Milk ,
Figure 4 Milk: Cesium-137 Figure 5 Milk: Strontium-90 Table IX Crops t
,)
6 J
)
h I
I l
i 1
i i
I r
l 1
40 l 1
. . _ - . - . - _ _ _ _ - ~ - _ _ _
TABLE VIII MILK (Concentrations in PC1/1) 137 90 140 131 Location Date Cs Sr Ba-La I liingham 9.3.68 26.4 1 0.4 6.7 0.2 (a) (a) 8.28.69 14 1 1 7.4 1 0.5 (a) (a) 10.7.69 92 1 6.9 2 1.4 (a) (a) 10.21.69 16 2 1 9.9 1 0.5 (a) (a)
, 11.20.69 23 1 1 9.3 1 0.5 (a) (a) 12.22.69 24 2 1 14.3 ! 1.3 (a) (a) 1.28.70 20 1 1 9.8 1 0.5 <5 <5 2.19.70 18 1 1 7.4 1 0.5 <5 <5 g 3.24.70 9!1 5.6 2 0.5 <5 <5 4.28.70 921 16.2 1 0.8 <5 <5 j 5.20.70 9!1 7.6 2 0.5 <5 <5 6.22.70 56 1 1 16.9 2 0.6 <5 <5 7.70 (b) 8.31.70 18 1 1 11. t 0.5 <5 <5 B ridgewate r 6.23.70 14 2 1 8.0 2 1.0 49 5(c) <5 7.29.70 1011 7.1 1 0.6 <5 <5 8.18.70 92 1 8.7 1 0.3 <5 <5 (a) Sample not analyred for this nuclide.
(b) No sample taken.
(c) Sample did not show normal decay.
i I
)
TABLE VIII cont.
MILK (Concentrations in pCi/1)
Collec tion 137 60 140 131 Location Date Cs ' Sr Ba-La I Plymouth 8.28.68 9.3 2 0.9 7.2 ! 0.3 (a) (a) 8.28.69 12 1 1 7.8 0.5 (a) (a) 9.24.69 15 1 1 9.0 ! 0.5 (a) (a) 10.21.69 19 1 10.4 0.8 (a) (a) 11.20.69 17 2 12.2 ! 0.5 (a) (a) 12.22.69 18 2 1 7.7 ! 0.5 (a) (a) 1.22.70 14 2 1 5.6 ! 0.5 <5 <5 2.19.70 16 2 1 7.2 2 0.5 <5 <5 O 3.24.70 16 1 1 6.6 1 0.5 <5 <5 4.22.70 13 1 4.7 2 0.8 <5 <5 5.19.70 21 1 12.8 0.5 <5 <5 6.22.70 23 ! 1 9.3 0.8 <5 <5 7.31.70 21 ! 1 11.8 0.5 <5 <5 8.19.70 22 2 1 17.6 1 0.5 <5 <5 i
(a) Sample not analyzed for this nuclide.
i Hingham Plymouth Bridrewater i
50- -50 l 1
i 40- _40 i . ,
i 30- -30 I
l F - '
J A
20- -20 i-
_ i l
10- ,
- ~
t I
4 0 0 8 9 10 11 12 1 2 3 4 5 6 7 8 8 9 10 11 12 1_2 3 4 5 6 7 8 6 7 8 4
1969 1970 1969 1970 1970 FIGURE 4 MILK: Cesium-137 (pCi/ liter)
0 5 0 2 1 1 5 0 r 8 e
t 7 0 a 7 w l 9
e g 6 1 d
i r
B 8
7 6
5 0
7 4 9 1
h 3 t i u 2 o
m y 1 l
P
)
_. 2 1 r e
1 t 1 i L
0 9 K /
L i 1
9 1
% I C M p
(
8 5 0 9
E -
R m U u G i I t F n o
r t
S 8
7 6
5 0
7 4 9 1
3 m
a hg n
2 1
i H
2 1
1 1
0 9 1 6 9
9 1 8
0 5 0 5 0 2 1 1
' 11
ll .
9 7 5 5 5 1 5 1 5 0 0 0 0 0 0 0 m 0 0 0 0 0 0 0 sg 5 5 5 5 5 5 _
C/ ! ! 1 !
0 0 0 0 0 0 i 9 5 6 C 6 4 5 9 0 0 0 0 0 0 2 0 2 p 8 1 6 1 1 1 < < < < < <
0 0 0 0 0 0 0
_ 5 5 7 5 5 5 5 0 6 5 0 0 0 0 0 0 0 4 0 0 0 0 0 0 0 0 0 0 0 0 0
rg m ) )
0 5
0 0 0 0 0 0 0 0 S/ a 1 a ! 0 1 1 a t i ( ( 0 C 2 6 9 9 3 3 1 3 8 6 p 5 3 0 5 5 6 2 2 1 5 5 0 0 < 2 0 0 0 0 9 6 9 0 0 1 0 0 0 0 0 0 0 s
C a 3 1 3 1 1 1 1 1 1 1 1 1 1 m 0 0 0 0 0 0 0 0 0 0 0 0 0 m o am G g 0 0 0 0 0 0 0 0 0 0 0 0 0 t
/ 2 ! 2 1 2 sm 2 ! ! e sp 4 9 6 5 7 8 3 2 u 3 1 8 0 8 d oc 0 0 0 0 0 0 0 0 0 0 1 7 6 r
C 0 0 0 0 0 d 0 0 0 0 0 0 0 0 e m
u X s I S s P a a E O t 2 2 2 2 2 2 2 2 2 2 4 s L
B R
C em B g 4 4 i
0 0 0 0 0 0 0 0 0 0 O 0 0 A / y T s1 ! 1 1 ! 2 ! 1 1 ! 2 t sC i op6 8 9 2 7 r _
9 9 5 1 0 1 6 1 i
v G _ 0 0 0 1 5 6 4 1 2 2 7 6 7 t 1 1 1 c a
f i
n o 1 i 8 9 8 9 0 0 0 0 0 C t e 6 6 6 6 9 9 0 7 7 7 7 7 0 p cr .
6 6 7 7
_ ea 3 9 3 6 8 8 8 9 8 5 lD 1 1 1 5 5 7 1 1 1 1 1 7 l 0 .
o 9 9 9 1 4 .
9 9 7 6 6 6 2 6 7 0 C o 9 t -
r t S n
r r r e r e
l o n e e a f o h h h h h a t
h a t t v i t t t h h a i d t e e u u t t u
t t u u ew t
u egw t t u u ew u e q z a m m o o o o o g o o o g e y c
o on noy m y m m y m m d y y i m d y i m m d l L a a l l l l l r l r l y y i l r s a M M P P P i n P P B P B P P B a m
p t c o n
s s s s )
e e e e 1 e
( l i i i i p e r r r r s
~
e m l e r r r r e e e e e e n a pp my e e e e o g g g c c O S aT b b b b n n n n t
a a a a u u b b b t t S a a a a r r r r t b b t t t y y y )
o a a a C C C C P C C C e e L L a a a a l
l H H * (
S
+ ll!1