ML19256D368: Difference between revisions
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13-01-7S 12-01-75 ( 0. 9 < 0. 7 i | 13-01-7S 12-01-75 ( 0. 9 < 0. 7 i | ||
Tit-M- 14 C 1 7-26-75 9-27-75 < 1. 9 4.711.0 g | Tit-M- 14 C 1 7-26-75 9-27-75 < 1. 9 4.711.0 g | ||
))-01-75 32-n]-75 1 . 11 4.310.9 I | |||
* 11-t1-l F 2 7-26-75 9-27-75 - 3. 3 7.911.7 [ | * 11-t1-l F 2 7-26-75 9-27-75 - 3. 3 7.911.7 [ | ||
11-n1-75 12-01-75 < 2. 0 6.910.8) P I | 11-n1-75 12-01-75 < 2. 0 6.910.8) P I | ||
'If t-fi- SA3 8 * | 'If t-fi- SA3 8 * ))-03-75*** 12-01-76*** <1.4 2.010.7 2 | ||
* Ilo samples in December; non-grazing season d | * Ilo samples in December; non-grazing season d | ||
** Management aiulit siunple 3 | ** Management aiulit siunple 3 |
Latest revision as of 15:11, 16 March 2020
ML19256D368 | |
Person / Time | |
---|---|
Site: | Three Mile Island ![]() |
Issue date: | 02/28/1976 |
From: | RADIATION MANAGEMENT CORP. (RMC) |
To: | |
Shared Package | |
ML19256D362 | List: |
References | |
RMC-TR-76-01, RMC-TR-76-1, NUDOCS 7910170924 | |
Download: ML19256D368 (58) | |
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RADICLOGICAL EilVIRCriME.' ITAL M0tlITORIllG PIPORT For The THREE MILE ISLATID ttUCLEAR STATICfl 5 0 - 2 W 7 .s a p 1975 SEMI-AlilUAL REPORT II JULY 1 THROUGH DECEF3ER 31 Prepared for METRCPOLITAri EDIS0?! COMPANY BY RADIATICii MANAGEME:tT CORPORATICil FEBRUARY 1975 --
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t TABLE _OF C0itTE'ITS PAGE LIST OF FIGURES . . . . . . . . . . . . . . . . . . . . . ii LIST OF TABLES . . . . . . . . . . . . . . . . . . . . . ii
SUMMARY
. . . . . . . . . . . . . . . . . . . . 1 I?iTRODUCTION . . . . . . . . . . . . . . . . . . . . . . 2 PROGRAM , . . . . . . . . . . . . . . . . . . . . . . . 3 Objectives . . . . . . . . . . . . . . . . . . . . 3 Cesign . . . . . . . . . . . . . . . . . . . . . . 3 Exceptions . . . . . . . . . . . . . . . . . . . . . 4 RESULTS At40 DISCUSSICN . . . . . . . . . . . . . . . . . . 4 Aquatic Envircnment . . . . . . . . . . . . . . . . . 9 Atmospheric Environment . . . . . . . . . . . . . . . 11 Terrestrial Envirencent . . . . . . . . . . . . . . . 12 Ofrect Radiation . . . . . . . . . . . . . . . . . . 14 ASSESSME?iT OF IMPACT . . . . . . . . . . . . . . . . . . 14 CONCLUSICNS . . . . . . . . . . . . . . . . . . . . . . 19
?.EFEREiiCES . . . . . . . . . . . . . . . . . . . . . . . 20 APPENDIX A Sampling Locations . . . . . . . . . . . . . . 22 APPENDIX 3 Data Tables . . . . . . . . . . . . . . . . . 29 1448 205
LIST OF_ FIGURES PAGE
- 1. PONTHLY AVERAGE TRITIUM C0iiCENTRATIO!!S Ili THE SUSQUEHAtiNA RIVER IN THE VICINITY OF TMINS . . . . . . . . . . . . 10
- 2. M0ftTHLY AVERAGE GROSS BETA CCNCENTRATIONS IN AIRECRiiE PARTICULATES IN THE VICINITY OF TMINS . . . . . . . . . 13
- 3. M0ftTHLY AVERAGE GAlitA COSE RATES AT TMINS . . . . . . . 1S LIST OF,F TABLES PAGE
- 1. SYNOPSIS OF THE CPERATIONAL RADICLOGICAL E?iVIRONMENTAL MONITORING PROGRAM FOR TMItiS . . . . . . . . . . . . . 5
- 2. SUf' MARY OF RADICriUCLIOE C0iiCENTRATIONS Ill EilVIRONMEilTAL SAMPLES FROM TMINS . . . . . . . . . . . . . . . . . 5
- 3.
SUMMARY
OF DIRECT RADIATICM MEASUREMENTS AT TMINS . . . . 8
- 4. JULY-CECEMBER 197S E?iVIRONMENTAL SAMPLE DATA WHICH RESULTED IN N0?l-ROUTIllE REPORTIiiG . . . . . . . . . . 16
- 5. COMPARISCN OF STATION EFFLUENT DATA FOR TRITIUM AND CO-58
'4ITH MEAN RIVER FLOW . . . . . . . . . . . . . . . . 18 pgB$0kb y 1448 206
SUM lGRY Ouring the period July 1 to December 31, 1975, Radiation fianagement Corporation (RMC) participated in the operational radiological environmental monitoring program (REMP) conducted by Metropolitan 5dison C:mcany at Three Mile Islanc Nuclear Station (TMIMS).
The RMC portion of this progrr as designed to aid in meeting the obligations of the Environmental Technical epecifications for TMINS Unit il (TMI-1)(1).
A total of 924 analyses were performed en 554 samples during the period covered by this report. These sampies were taken frca the aquatic, atmospheric, and terrestrial environments and included direct radiation measurements.
Mditional samoles and analyses beyond those recuired by the environmental technical specifications were performed as noted in the data tables of Appendix 3.
Surface water (4 locations, 23 samples) was analyzed for H-3 and gama emitting nuclides. Untreated drinking water (2 locations,12 samoles) was analyzed for H-3, Sr-89, Sr-90 and gan=a emitting .nuclides. Fish (2 locations, 9 samples) and sediment (3 locations, 6 samoles) were also taken frem the aquatic environment and analyzed for Sr-89, Sr-90 and gamma emitting nuclides.
The atmospheric environment sampling program included air particulates, air iodine, and precipitation. Air particulates (10 locations, 253 samoles) were analyzed for gross beta activity and gacTaa emitting nuclides.
Charcoal cartridges (4 locations,106 samples) were analyzed for I-131.
Precipitation, primarily rain water, (a locations, 24 samples) was analyzed for gross beta activity, H-3, Sr-89, Sr-90, and ga=a emitting nuclides.
Milk (6 locations, 27 samples) was taken from the terrestrial environment and analyzed for I-131, Sr-89, Sr-90, and gama emitting nuclide:. In accordance with environmental technical specifications, an update en the milking animal census was performed during this period. A distribution of 1095 milking cows at 35 locations was determined, a decrease of 19 ccws since June 1975. Green leafy vegetables (4 locations, 4 samples) were taken and analyzed for gama emitting nuclides.
In addition, 320 analyses for ic=ersion dose (21 locations, 50 packets) using TL0s were made during this period. \
All radienuclide concentrations were similar to these normally found in local unaffected areas, except for H-3, Co-60 and I-131 in surface
\
water and Co-53 in sediment. 9%
The H-3 ::ncentratiens in surface water at the dcwnstream incicator k
locatiens (0.5 inc 1.5 miles downstream) shewed elevatec levels relative 9 to the u: stream sam les twice during the reporting :eriod. No increase %
in the H-3 levels at the ccwnstream locations wnere river water is used %
as a drinking water scurce was observed. Theref:re, no measurable dose 9 ,
can be a :ributed : :ne release of H-3 fr:m TMIMS.
Curing July Co-53 was :stec ed in 2 sedimen; sam:les; :rcoa iy the nasult of staticn :cerati:n. Since nc Co-58 was detected in surface water er fish, the only significant dose ;a:nway resui ing #r:: :nis C:-58 acult
. 1448 207
- c be fe;m standing
- n the sncreline. A highly conservative dose estimated yields an insignifican: dose := a hy:othetical maximum individual of 0.08 mrem / year.
Co-60 was detected during July at station EE1 and during August at station 9A2 in surface water samples. The maximum level observed was 2.4 pCi/1.
A maximum individual drinking 21/ day of this water for a 30 day period cculd receive an insignificant dose of <0.006 mrem. 1-131 was detected in surface water frem station 9A2 d ring August at a level of 50 ;Ci/1, but was undetec ted in all drinking water samples. Therefore, no measurable dose can be attributed to this level of I-131.
It is therefore concluded that statien operation produced only insignificant and temporary changes in the observed environmental levels of radioactivity.
These temporary changes could have resulted in an insignificant dose to a hypothetical maximum individual of <0.1 mrem.
INTR 00V(TI0t1 A c mplete radiological environmental monitoring program (FEMP) for Three Mile Island Nuclear Station (TMINS) has been conducted by Metropolitan Edison Ccmpany since June 1969. Radiation Management Corporation has participated in this program since February 21, 1974. Results of the preoperational phase of the REMP up to June 5,1974, and of the a:erational pnase (June 5,1974 to June 30,1975) were reported in previcus RMC documents (2,3,t). This report continues the operational series with coverage of the second six months of 1975. It presents in detail the type and number of samoles analyzed, the analyses :erfor ed and the data generated by P,MC during the period July 1 to Cecember 31, 1975. Interpretation of the data and conclusions are presented.
Three Mile Island is the site of an operating nuclear pcwer unit of the pressuri:ed water reactor (PWR) type. When complete the station will consist of two reactor units. Unit 1, rated at 871 ale, achieved criticality on June 5, 1974. This marked the beginning of the operational pnase of the REMP. Unit 2, rated at 959 MWe, is under construction and scheduled for c mmercial operation in 1978.
The station is located on Three Mile Island in the Susquehanna River, in Cauphin County, ten miles southeast of Harrisburg, Pennsylvania.
The average flow of the river at this point is 34,000 cfs(5). The site consists of an 314 acre tract on Three Mile Island and several smaller adjacent islands. General climatic conditions are characterized by a mild continental-type climate with little severe weather. Agricul ture is the largest land usage in the area (45%), with the empnasis on poultry, dairy cattle and field croos(6).
The census of milking c:ws located wi-hin five miles of TMDS(5) was u:da:ed g in *he previcus semi-annual re ort (4) and again during this recor cericd.
The distributien anc acproximate lccations of these animals are civen in taole 3-19 (a:::endix 3).
M0re s;ecific info'r aticn On the de gra;:hy, eteoroi gy and land use naracteristics o' the local area may be found in the Environmentai Re:or:(-', Environmentai Sta e en-(3), Final Safety Analysis Re:cr #ce 9k 7:1I-2(3', , and the Environmen:ai te: r: Su:: leman- ::( 0).
L448 208
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PROGRAM In the operational phase of the REMP, racioanalytical data are collected for comparison to that generated in the preoperaticnal Chase. Di ffe rences between these two periods are examined statistically to determine whether any station effects exist basd on the magnitude and fluctuations of radi; activity levels determiaed in the preoperational phase.
Cbjectives The objectives of the operational radiciogical environmental program are:
- 1. To fulfill the cbligations of the Radiological Surveillance-Environmental sections of the Environmental Tachnical Specificatiens for TMI-1.
- 2. To determine whether any statistically sicnificant increase occurs in the concentration of radionuclides, in critical pathways.
- 3. To detect any builduo of long-lived radionuclides in the envircnment.
- 4. To detect any change in ambient gama radiation levels.
- 5. To verify that radioactive releases are within alicwable limits and that TMI-1 operations have no detrimental effects on the health and safety of the puoTic or on the envirer. ment.
This recort provides information for the Metropolitan Edison Ccccany, regulatory agencies and the public record toward these objectives.
Cesien In order to meet the stated objectives, an appropriate ocerational RE?'P was develooed by RMC in cooperation with Metro, olitan Edison Comoany.
Samples for the cperational REMP were taken from the aquatic, atmospheric, and terrestrial environments. Samples of various media were selected to obtain data for che evaluation of the radiation dose to man and imcortant organisms. Sample tyces were based on (1) established critical Oathways for the transfer of radionuclides througn the environment to man, and (2) experience gained during the preo;erational and initial operational phases. Sampling locations were determined fr:m site e:eorciogy, Susquehanna River hydrology, local demography and land uses.
Samoling locaticns were divided into two classes--indicator and control.
Indicat:r staticns are those which are expected to manifes: sta:ica effects, if any exist; con rol samoles are collected at locaticrs which g are :elieved to be unaffected by station ocerations. Fluctuations in
- ne evels Of radionuclides and cirect radiation at incicator staticr.s are evaluated with res;ec: to analogous 'iuctuations a: c:n:r:1 sta:icns, wnicn are unrelated to staticn :cer a:icn. Indicator s:sti:n data are 9 aisc avaluated relative :: bacx;r:und cnaracteristics estaa:isned ;rier %
23 station 0:eraticn. -dditicnal sa=les beyond acse recuired by -he g Envir:r en:al Tecnnicai S:eci#icati:ns were =llectec and analy:ac; nev are as:ee as una;e=e, auei:
sa=;as in =e :ata :2:les a=e,cu sg g 4, 709
The analysis of sam:les and the analytical data generated during the program are routinely evalua ed by the RMC project laader wna is the liaison with Metrocolitan Edisen Ocm:any personnel. Further review c' REMF design and analytical data is perfor ed by RMC and Metropolitan Edison Company :.5-EE professional staff in li.ght of current regulatory trends and Operating experience. The analytical procedures and cuality control methods utilized by RMC(11) meet or exceed the minimum sensitivities required by the Environmental Technical Specifications (1).
Table i summarizes infomation en the Three Mile Island :luclear Station operational REMP as performed by RMC. Appendix A explains the RMC samole coding system which specifies sample type and relative locations at a glance. Table A-1 gives the pertinent information on individual sam: ling locaticns, while Maps A-1, -2 and -3 show their secgraphic iccations.
Exceotions The operational REMP was conducted in accordance with the Environmental Technical Specificatiens for TMI-1(1). Ceviations fr:m the program as described in table 3 of these specifications occurred during this period.
Because aquatic plants are very scarce in the vicinity of TMIIS, none were available for sampling during this report period. This problem was aggra-vated by heavy floods on the Susquehanna in the fall when a record flow rate of 73,9C0 cfs was established at Harrisburg for the month of Sectamber.
Milk samples were not available at st< tion 5A3 for the acnths of July, August and September since -he single cow at that location was not producing during these mcnths. Mcwever, samples were collected and analy ed routinely during those months at station 5B1, only 0.1 mile fu ther frca the site in the same easterly direction. This second farm (70 c:,M) adequately covered the need for samples.
Pump outages resulted in the loss of 5 air particulate and air iodine sam les.
Flooding conditions in late September resulted in the loss of 2 additional air particulate and one air iodine samples. However, the overall air sample recovery rate was greater than 96.
RESULTS Af!D DISCUSSIC:1 The averages and ranges of analytical results are sumarized in tables 2 and 3. Table 2 is a su=ary of gross beta, H-3, Sr-89 and Sr-30, I-131 and ga=a spectr: metric results for various samcles. Table 3 is a s amary of amoient radiaticn levels as measured by thermoluminescent dosimeters.
Results for each type of sample were grouped accorcing to the analysis perfor ed. :'eans and standard deviati:ns of these results were calculated when 3:plicable. These standard deviaticns re: resent sample po ulatien variability rather than analytical variability. For this ca .ulaticn, all resui:s teicw -he MCL . vere considered t: :e it the '<CL.
The :ata for incivitual samoles are :resen:ed in ta:ular fem in accendix 5 , ta e s 5 - 1 th r0 ugn 3 '.S . Within 't he data tables 1 ?5'; (= 2 si: .a}
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All resul ts Occur-ing 1: cr :el:w :he relevant mini, um de:ac:3:le leye; ,'
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TAf tLl' 3 Stat'ftAftY OF DistFCT ftADI ATInra sti'AritiMI:!ti:ttTS AT THIflS JllLY l TI'ItOlk;ts DirI3 tits It 11, 1975-IlO . OF SAHP!.It4G !!O. ABOVI: AVicitAGI!
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t'on th l y ~ r '.. c ,.. . - sr:les ,.ere callected at 5 locations en the dates shcwn "inhl<. ..[.",;eekly grat sa. oles frca stations 103, 9A2 and 931 were taken and . :ositet m:n:nly. Samples from stations SE A, Isr1 and 7G1 were :n.v. v a semi-con:inucus basis and co=osited to acnthly sa ;1es. Beginning with the :: vember samples, H-3 analyses were reduced fr:m en:hij :o quar:erly. Hence, the !!avember and Cecember samples were c:m:osited prior :o H-3 analysis in accordance with TMI-1 ETS table 3.
Each sacole was analyzed for H-3 and garma emitting nuclides by RMC procedures HXH and TSC, respectively. Samoles frca SEl,15F1 and 7G1 (drinking wa:er treatment facilities) were also analy:ed fcr Sr-89 and-Sr-90. A new u: stream sampling location (1C3) was established on Swatara Creek in January 1975 for assessrent of any radionuclides which may be acded by :nat tributary. The results therefrem are included in this reco rt .
Resul:s of M-3 analyses are presented in table S-2 and figure 1. Concen-trations of H-3 were observed to increase in August, Sept' ember and Oct:ber at one or both of the two ccwnstream indicator stations 9A2 and 931. lo increase was cbserved at the:e times at station 7G1 (Columbia). These concentrations returned to bac.yreund levels in the !!avember-Cecember c:c:osi:e at all downstream locati:ns. The dose implications of these H-3 levels and a comparisen with if cuid effluent data are discussed under
" Assessment of Impact".
Lults of analyses of surface water for Sr-89 and Sr-90 are presented in taole S-3. These analyses were made en untreated water from the Srunner Island water treatment facility (SE1), the Steelton munici:al water works (ISF1) and the Columbia water treatment plant (7GI). All Sr-59 concentra-tiens were below the MCL (0.3 ;Ci/1); Sr-90 concentratiens were at or below MCL (1.0 pCi/1) in all of the samples analyzed.
Gama spectremetric analysis of surface water samples (table B-4) shcwed that the naturally occurring nuclides X-10 and Se-7 were present at concentratiens above their respective M0ls in 2 samples each. The ga=a emitting nuclides Co-50 and I-131 were detected in the surface w?ter sample from station 9A2 during August at concentrations of 2.4 and 50
- Ci/1, res:ectively. Since I-131 was not found in any of the drinking wi;ter samples or in any other aouatic pathway, no significant dose can be attributed to this nominal level. The maximum dose imolications of the coserved Cc-50 concentrations are discussed under " Assessment of I ;act".
Fish Fish sam:les were colle: ad at 2 locations each in July and Oc :bar cf this recorting ;eriod. Only acult fish were taken for sam:les.
These were separa:ed in:o classes :f bottom feeder versus credator-game s;ecies; fillets were analy:ed. Ga=a spectr retry (T3C) anc Se-39 and Sr-90 analyses (SRS, SRD) were perferred en subdivided 'ish sam les. \
' results of these analyses are given in table 5-5. Sr-a? was :etectac 0
... :ne of ne 9 sacoles. Sr-?C <<as de:actac in 5 of :he 9 sa=les wi:n N,N e hignest value of .t.2 :Ci/K; de ac ac in the a:: stream sa :le(155'-). k 1418 ,.13 9 d"
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Three soci e . . . - - .. , , . . . . ; . ;n in July and again in October. All samoles w e 2 .: ,. : 5 e '.r-U and Sr-90 and gamma emi' ting nuclides, by R11C ana',.- .
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S tren ti.n ir. .: ,.r . re nt:s are given in table 3-6. Sr-89 was not detected in ej af :ne sarples. Sr-;0 was detected in two samples.
The resul t; :r :ne p.ra analyses are given in table B-7. The naturally Cc:urring raci nuclices (X 20, Ra-225 and Th-232) were found in all 6 sediment samples. In ic::ter, Cs-137 was detected in a sample from Station 11A1 at a level af .33 ;Ci/g. This level was greater tnan 4 times the c ntrol staticn value of 0.19 pCi/g but not significantly different from those values observec during the preoperaticnal period. A number of radienuclides typically found in fallout also were cresent in detectable amounts.
Inese incluced ab-95, Zr-95, Ru-106, Sb-125 and Ce-144, all of which were present in 20-3C': of the samples. Except for Co-58, all nuclides found were cetected in :cch upstream and downstream samples and no significant variations ~ ' ::ncentration were a: parent.
Co-58 was cete".e1 in 2 downstream samples during July, buc not in October.
fac: that 0 43 was detected in July and not in October, is probably the r== ult of the September ficod which removed the nor: al sediment load in this reach of the river. The bigliest concentration cbserved in July was 0.47
- C1/g. This, when conpared to upstream values of <0.02 pCi/g and T:iIt!S dis-charge data, can be attributed to station operatien. The imolicaticns of these Co-58 levels are discussed under " Assessment of Impact".
Atmoscheric ~nvirencent The atmospheric environment around TMIlls was examined by analyzing air particulate filters, charcoal cartridges and precipitatien. Air particulate samoles were collected at 10 locations with icw volume air samolers using Hollingsworth and Voss HV-70 gau:e backed filters. At 4 cf these locations, air iocine samoles were collected on Cesco "B" charcoal flow through cartridges connected in series following the air particulate filters.
Air volumes sampled were measured wi'h temperature : mcensated dry gas aters and recorded. Both air particulate and air iocine samples were
- 011ected weekiy.
- eci itatica was c:llected by using a 12 inch diameter funnel draining into a 5 gallen polye nylene :ottle. The ac:.mulated samcles were collected inc ::mcosited f:r mon:hly analysis. Tha accunt of precipitation jhg 8 2 } 7 fell turing the saccling period was measured and recor:ec.
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mi air : articulate sam:les were analy:ac weekly for gr:ss beta activity x
- y E."C :rececure 730 and monthly :m:csites Of all incicat:r and of all O4 gn r:1 sam:les were examined for ;a=1 emi :ing nuclices by R:1C pr::acure 9
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Results of the gross te:a analyses are listed in table E-2. Gr ss cor.centratiens Of b2ta emi::ers in air decreased sli;htly fr:n July thr:ugn :ecember.
This decrease was similar :: :ne ;ree:eraticnal trend. The indicat:r H control monthly avera;es clotted in figure 2 dem:nstrate these annual
. .nds and shew similar behavior at teth indicator an ::ntr:1 locati:ns.
- cathly gross beta activity in all samples averaged 0.029 pCi/m3.
The gamma s: ectr: metric results en monthly c:mposites of air particulate filters are presen:ed in table 3-9. prominent nuclides founo in most sam les were naturally occuring Se-7 and the probable falicut nuclides, Ce-144, Cs-137, Zr-95 and fib-95. In addition, Mn-54 and 5b-125 were detected in 3 of 12 and 5 of 12 samples, respectively. The short-lived fallout nuclide Ce-141 was detected in 1 of 12 samples. No significant differences were Observed between indicator and control c:=posites and previously obtained data. Typical MCLs for gama spectremetric analysis of air particulate samples are listed in table 3-18.
Air Iodine 3asecus iodine was collected :n char::al cartridges at 4 locations. The resulting saroles were analy:ed weekly for I-131 by EtC procecure D8.
Results are listed in table 3-10. All results were less than the respective MCLs wnich were of the Order of 0.01 pCf /m3.
Preci pi ta-icn
- cn:hiy crecipitaticn samoles were analy:ed for ;ress beta activity by RMC Or:cedure T3A. The RMC analytical precedures nXH and TGC were u*ili:ed for the analysis of H-3 anc gama emitting nuclides, respectively, quarterly composites of precipitation fr:m each station. Concentrations of Sr-89 and Sr-90 (UtC precedures SRC, SRA) were determined in semi-annual c =posites frcm each station. The results of gross beta activity measurements in precipitation samples are presented in table 3-11.
The data' for this period ranged from 3.3 to la pCi/l while averaging 5.7 ;Ci/1. The wet desposition of beta activity averaged 0.5 nCi/m2, ranging from 0.2 to 1.7 nC1/m2. 10 significant differences between indicator and control locations were observed.
Be results of analyses of cuarterly c:mcosites of precipitation for M-3 and ;amma emitting nuclides are presented in table 3-12. Tri tium
- ncentrations averaged 37 pCi/l slightly lower than pre-operational levels. The gama emitting nuclides Se-7 and Zr-NS-95 were the only ones detected in precipitatien. The cbserved levels of these nuclides were similar at both indicator and control locations. Typical MCLs for gama s:ectrometric analyses of precipitatien are listed in table 3-18.
Semi-annual ::m;csites of recipitati:n sampies from each station were anaij:ed for 3r-59 and Se-90 anc the resuits are presented in table 5-13.
- f :ne a sam:!ss analy:ed, Sr-29 and Sr-iC were tel:w PCL in all .
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-a terrestrial environmen around 7: 4I:iS was examined y analy:ing } 4 4 b 2lb
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Veg9tahles en an annual basis. Two gallen milk samples were c:llected and shi::ed fresh to ^2C. Each sample was analyzed for I-131 using ::'.C 9cedure IXD. Quarterly cer:osites #r:m each staticn were analyzed Sr-59 (SRC) and Sr-90 (SRA). Green leafy vegetables (cabbage) were taken in July at c stations. Each sam le was analyzed for ga ma emitters by RMC procedure 73C.
The results of I-131 analyses are presented in table 3-14 None of the 27 milk samples analyzed shcwed detectable levels of I-131. Concentrations of Sr-89 and Sr-90 in quarterly composites of milk samples are listed in table B-15. Of the 12 samples analyzed, Sr-29 was not detected while Sr-90 was detected in 9. Results from indicator stations were similar to those fecm the control staticn and all results were similar to precperational levels.
The results of ga ma spectrometric analysis of green leafy vegetable samples (tacle 3-15) shcwed detectable levels of natural K 40 only. No other ga :ma emitters sere detected.
Direct Radiation The a :ient radiaticn levels in the area of Three Mile Is' land :luclear Statien were determined with energy compensated calciem sulfate (Tm) the moluminescent dosimeters. A total of 80 monthly TLD packets (4 TL0s each) were placed at 21 locations around TMINS. The results of the TL3 measurements are presented in table 3-13. All TLD results
- resented in this racor: nave been nor alized to a standard =cnth (30.2 cays) to eliminate ce differences in exposure periods. The resulting e rate was similar :n :recperational levels averaging 5.3 mrad / standard ecn th .
The projected annual dose computed from results for this re;orting pericd is 54 mracs, or 64 mrem assuming a quality factor of 1. An annual dose ecuivalent of 52 mrem was computed for the Harrisburg area and published by the E? A( ~.2) . The difference between this calculated value and the measured RMC value is not considered significant because of the differences in technique and the statistical variability of each. The average monthly ambient adiation dose rates for indicator and centrol statiens are clotted in figure 3. No trends in ambient gar.ma radiaticn levels as a result of TMI-1 operaticns are apparent from this graph.
ASSESSMENT _OF IMPACT The gasecus and licuid effluent streams from TMI-1 were contincusly sampled and/or :cnitored for the presence of radicactive materials by S'atro:clitan Edisen Company. The REMP was designed and c:nducted in a manner :: cermit identification of the racicnuclices ac ualij released fr:m the stati:n.
1448 920
't -he radioactive raterials released fr = TMI-1 to the environs, aniy
,-3, 2-50, and I-131 in surface water and "c-53 in seciment snewed a statistically significant contri:uticn fr:m TMI-1. These samoles g snowinc ::ncen:rati:ns statis:i:allv diffaren: fr:m preccera:i:nal r a tr ! statien values are listed in acle A. Thus , the Only pathways k
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for potential ex;osure of individuals or of a segment of the population to radicactive materials from station coeration is fr:m consumotion of river water or from shoreline de:osits. Table 5 compares TidI.S discharce data f r H-3 and Cc-58 with mean river flow. Since the H-3, CO-50, and I-i?1 were not detected in any other acuatic pathways (e.g. fish or sediment) except surf ace water, no significant dose can be attributed to these Other potentiai pathways.
Untreated river water is monit: red as part of the TMIliS R5MP at 2 locations (Brunner Isiand, SEl, and Columbia, 7G1) in the downstream vicinity which use treated river water c:ntinuously for human censumption. At no time during the reporting period did H-3 or I-131 levels at these stations differ statistically frc= those at the uostream statien. It can then be : ncluded tnat tnese H-3 and I-131 levels did not result in a significant dose to man.
Cn one occasien during the reporting seriod (July) Co-50 was detected at a cencentration of 2.1 pCi/l in untreated drinking water fr:m staticn SII.
ine maximum dose which c:uld be attributed to this level is 0.005 mrem to the GI tract or 0.0006 mrem to the total body from c:nsumation of this un-treated water for One month. In addition, a similarly small dose (0.08 mrem) c:uld have been received from standing 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> en the sediment in which 0.47 ;Ci/g of C -58 was detected during July. These dose calculations were performed using the basic equations ecoloyed in '.! ASH-1258(15). These Insignificant doses are the maxima which c:uld be attributed to the radic-nuclides released to the Susquehanna River by TMI-1, 1448 223
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T1.f I.B: 5 COVI'Alti fDtl Ol' SI'ICirIC itAllIONICf.Illi:S I'I itil:I'AC): l'ATI:R l'ITil STATIOtt l'tTI. tall? IM*A JIlf. AIG Sa 'l* OCT llOV prc lic.an itivur Vlou 15,500 8,600 73,900 61,700 35,400 32,l:00
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C0t;CLUSIC:45 Tne prec;eraticnal :.adiclogical Environmental "0nitoring program (RE:4?)
conducted by R:<C and efe :ropolitan Edison C:mpany was continued as the acera:icnal crecram after TMI-1 initial criticality en June 5,1974 The REM? (from July 1 throuen December 31, 1975) described in this report was conducted according to the Environmental Te"hnical Specifications for TMU;5 which permitted the objectives of the program :o be met. Additicnal sampling and analyses beycnd those required by the Technical Specifications were performed. All results therefrem were reviewed by ?SC and Metrocolitan Edison to assess all possible environmental pathways.
Although other possible dose pathways to man were considered in the environs of the TMIl:S site, tritium, Cc-60, I-131 and Co-58 were the only radionuclides of TMIi!S origin detected above backgr0und levels with only Co-53 and Co-60 potentially contributing to dose. The radiation dose to people frcm ambient ga=a raciation, as measured by ther luminescent dosimeters, averaged 5.3 mrem / month and shcwed9 . o evidence of a TMI!S centributien during this operational period of TMI-1. The radiation dose to ; ecole in .he TMI!S environs is compared with the exposure from other artificial and natural sources in tne following table:
Source of Ex osure Annual Ccse in cr=m
.ve dical 72(14)
. Ambient Ga. ma (TLD) 64 Radienuclides in bcdy .
(primarily K-40) 18(14)
Global fallout a(14)
TMIt15 (Co-58 in sediment, <0.1 Co-60 in water)
Even though the TMI-1 c ntribution to population exposure is very small (approximately 0.1", of that frem other sources), the TMIiS has a continuing program to improve operating techniques and to maintain equi; ment directed toward reducing releases of radioactive' materials to the environmen:.
Therefore, it can be concluded that opera:icn of TMI-1 did not significantly alter the radiological characteristics of the TMIliS environs. The radienuclides and radiation levels Observed were principally due to natural radicactivity and global fallout, s
1448 225 6
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REFERET:CES (1) Metrocolitan Edison Company. "Three Mile island Nuclear Station-Technical Specifications." Appendix 3. OPR 50,1972.
(2) Radiation Management Corporation. "Three title Island *!uclear Generating Station-Preoperational Radiological Environmental Monitoring Program". RMC-TR-75-17,1975.
(3) Radiction Management Corporation. "Three Mile Island tiuclear Statien-Radiological Environmental Monitoring Program-First Operational Period." RMC-TR-75-02, 1975.
(4) Radiation Management Corporation. "Three Mile Island Nuclear Statien-1975 Semi-annual Report". RMC-TR 13, 19 75.
(5) United States Cepartment of the Interior-Geological Survey.
" Water Resources Data for Pennsylvania, Part-1." 1973 (5) Radiation Management Corporation. "Three Mile Island Tiuclear Generating Station-Agricultural Land Use Survef". RMC-TR-75-1, 1975.
(7) Metrocolitan Ecison Cc=cany. " Environmental Report, Operating License Stage-Three Mile Islano fluclear Station Uni- 1 and Unit 2", 1971.
(S) United States Atomic Energy Cent:issicn. "FinC Environmental '
Statement-Three Mile Island Nuclear Generating Station Units 1 and 2". Occket tios. 50-289 and 50-320,1972.
(9) Metropolitan Edison Comcany, Jersey Central Pcwer and Light Company, Pennsylvania Electric Comoany. " Final Safety Analysis Report, Three Mile Island Nuclear Station-Unit 2". Docket tio. 50-320, 1974 (10) Yetropolitan Edisen Comoany, Jersey Central Power and Light Cemcany, Pennsylvania Electric Ccmpany. " Environmental Re: ort Supplement II, Three Mile Island tiuclear Station." Occket tio.
50-320, February 1975.
(11) Radiation Management Carecration " Analytical and Quality Control Program. " RMC-TM-75-3,1975.
(12) Canald T. Oakley, " Natural Raciaticn Exposure in the United States ," U.S. Environmental Protection Agency, OR?/SID 72-1, June 1972.
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1448 226 ,
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REFERE*;CES (C:nc.)
t' 13 ) S. E. ~incepson, C. A. Burton D J- Quinn and T. C. .'ig, "Concen-tration Factors of Chemical 'E1 " #98"I8 8 "
UCRL-50564 (Rev.1). October 19f2 (14) " 'he Effects en Populations f-Radiation" (BEIR REPORT). fia iona f cadem. r s c '19h?
Sc ission. " Final Envirarmental aee Lfphff;c_I 3e gy ;g Cj.
1448 227 g 4
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APPE!! Dix A ,
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- Samelinc Locations Samole ! centi fice:ien FCIC identifies sam;:les by a :hree part code. The first two letters are the oower station identification code, in this case TM. The next one to three let:ers are for the media sampled.
AI = Air Iodine F?L = Green Leafy A? = Air Particulates Vegetables AQF = Fish ID = Icr.ersion Oose (TLD)
ACP = Aqua:ic Plants M = Milk AQS = Sediment :W
, = Precipitation E = Soil SW = Surface ' dater The last four symbols are a location code based on direction and distance ~
from ne site. Of the last four symbols, the first rao represent each of the sixteen angular sectors of 22-1/2 degrees centered about the reactor site. Sector one is divided evenly by the north axis and other sectors are numbered in a clockwise direction; i.e., 2=3rlE, 3=NE, 4=ENE, E=E, etc. The next digit is a letter which represents the radial distance fr:m the plant:
S = On-site location E = d-5 miles off-site A = 0-1 miles off-site F = 5-10 miles off-site 3 = 1-2 miles off-site G = 10-20 miles off-site C = 2-3 miles off-site H = >20 miles off-site 0 = 3-.1 miles off-site The last number is the station numerical designation within each sector and :One; e.g. 1, 2, . . .
The location portions of these codes (i.e.151, 3A1, etc.) are shown in t'le attached table along with more detailed information and a map coordinate numoer used to indicate the sampling locations. This sample identification system is used to designate the individual samoies in the analytical result tables, Appendix 3.
1448 229
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APPElDIX 3 1448 ?,35 hbObObb zg
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APPENDIX 3 Data Tables Appendix 3 is a presentation of the results of the 'MI:iS Radiological Environmental Monitoring Program.
TABLE JUF8ER TITLE PAGE AQUATIC E:iVIR0iiME:iT 3-1 Sampling periods for Surface Water . . . . . . . . . 32 3-2 Concentrations of Tritium in Surface Water . . . . . . 33 3-3 Concentrations of Sr-89 and Sr-90 in Untreated Drinking Water . . . . . . . . . . . . . . . . . . . . . 34 34 Concentrations of Gamma Emi.ters in Surface Water . . . 35 3-5 Concentrations of Sr-39 and Sr-90 and Gamma Emitters in Fish . . . . . . . . . . . . . . . . . . . . 36 3-6 Concentrations of Sr-89 and Sr-90 in Sediment . . . . 37 3-/ Concentrations of Gamma Emitters in Sediment . . . . 38 ATMOSPHERIC ENVIR0iiMENT B-3 Concentrations of Seta Emitters in Air Particulates . . 39 3-9 Ccncentrations of Gamma Emitters in Air Particulates . 23 3-10 Concentrations of I-131 in Filtared Air . . . . . . . 4:
3-11 Concentrations and Deposition of Seta Emitters in Precipitation. . . . . . . . . . . . . . . . . . 46 3-12 Ccncentraticns of Tritium and Gamma Emitters in Precipitation. . . . . . . . . . . . . . . . . . 47 3-;3 C:ncentraticns af Sc-29 and Sr-90 in Precipitati:n . . as TERRESTRIAL E:!VIRCUPE:!T 3 '. 4 Concentraticns Of I-131 in Miik . . . . . . . . 49 } 440 , bb
- 1 Concentrations of Sr-39 and Sr-90 in Milk . . . . . 50 h D
3-16 C:ncen: rations of 3amma Emitters in Green '.eafy g j @
Vegetables . . . . . . . . . . . . . . . . . 51 g
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4 APPEi! DIX 3 Data Tables (Cont.)
TABLE iluMSER TITLE PAGE DIRECT RADIATI0tl 3-17 TLD Dose Rate . . . . . . . . . . . . . . . . . 52 MI?lIMUM DETECTABLE LE'/ELS 3-13 Typical MOLs for Ga.ma Scectr marry . . . . . . . . 53 COW CE?iSUS 3-19 Distribution of Milk C0ws '.lithin Five Miles of TMIllS . . . . . . . . . . . . . . . . . . . 54
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- 7-05-75 8-02-75 9-06-75 10-04-75 11-Of-75 12-03-75 to to to to to to 7-26-75 0-10-75 9-27-75 11-01-75 11-26-7a 12-11-75 171-StM 51'l 6-29-75 7-27-75 0-31-75 9-30-75 11-02-75 12-03-75 to to to to to to 7-26-75 R 7 5 9-29-75 11-01-75 11-26-75 12-31-75 111- S t.'- 9 A 2 7-05-75 0-02-75 9-nc-75 10-0.q -7 5 11-06-75 12-03-75 ta to ta to to to
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-* 111- Sil- 7 C l 6-23-75 7-26-75 11-10-75 9-26-75 10-25-75 12-03-75 p::,. to io ta ta to to y 7-26-75 6-30-75 c-20-75 10-25-75 12-03-75** 12-11-75 m
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cot lCEllTRATIOllS Ol' TitITIllit 111 Sil!(FACC llATI:lt Itusult.s in linit ; of sci /1 1 2 sigma 2:TATIOli !!O. Jill AllG SFP OCT tlOV I DECA Ayg npcy; til'STitl'AM IDCATIOllS 111- St!- IC 3 *
- 430166 250161 170160 150158 120164 2401250 1tt-St!-l SP1 220163 290161 200160 96164 540161 2701330 Ill'STiti'Att tvritAGI: 3201300 270156 100145 12017' 3301500 2501200 l>OnlllSTit0AM I.OCATIOllS I,*, Tf t-Sil 4A 2 90163 3900190 420167 3490196 300166 166013700 Til-St!- 9f t 1 170163 27201111 1200176 1930176 3110159 123012100 Tri-Sil-sti:l *
- 200163 ;t70159 200160 120160 200157*** 2001110 T!*- Sif- 7 G1 4 fl016 6 260161 410166 150164 220165 3001270 I)Ol'I'STitPNI I Vrlt AGl: 260 2'60 1110013600 5601000 145013200 2001160 26012400
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COrlCI:llTitATIO!!S OF Stt-09 AIID Sit-90 At1D GAMith I?lITTI'!tS Ill PISit Itos ul ts in Ifnits of IC1/b aj i 2 sirJm.1 S AMPI.I t!G STA'rlott flO. SAttPT.I'. Typg:a MO!!Til Sit-fl9 Sit-90 l~~40** CS-137"*
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TAI!I.1: P- fl col'Cl3ITitATIO!!S OF PJ7FA 134IT11:RS lil AIlt PARTICIII.ATI:S Results in linit.s of 10-3 pC1/m 1 2 sisjmi 3
STATIOli l'O.
START STOP IlATI: DATI: Til-AP-]P1 TM-AP-SP1 TM-AP-7P1 TM-AP-9P1 Til AP-15G1 6-211-75 7-05-75 6 3 tit 6117 tis a 4416 5117 7-05-75 7-12-75 4 17 4616 IIS
- 4416 5517 7-12-75 7-19-75 2616 3716 183 8 3216 1814 7-19-75 7 - 2 r.-7 5 2115 2216 <10 2115 2415 7-26-75 1:-02-75 3417 3617 3016 3416 4217 o, 1-02-7S e-n9-7 5 2516 3317 2616 2916 3517
.u
!!- 0 9 -7 5 (1-16-75 3617 4217 4617 4117 5019 n-16-75 !!- 21-7 5 2716 2716 32t6 2616 1515 (1-23-75 11-10-75 2616 1916 2716 2 fli 6 2216 n 7 5 9-n6-75 1815 2217 1315 2016 Illi 5 9 --0 6 '/ 5 4-11 '/5 .:616 tlS
- 2116 1715 2216 9-11-7S 9-20-75 1514 7215 Illi s Ifli4 1214 4-20-75 9-27-75 9 f.139 2015 1114 11115 1715
/ 9-27-75 It)- 04 -7 5 2315 2515 1715 2415 It!i5 d
- I?o a. amp l e , pinnp inoperative s
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COttPI'lltitATIO!!S OP Pl*PA l't1ITa1:ltS Ifl Allt PA!4TICt!I.ATI:S Itu stil t s 1:1 tinits of 10 Ici/m i 2 siimat f: TAT 10tl 110
';TA'tT S'!OP DA'11: InATl! Tit-AP-IFl Ttt- AP- 51'l Tit-AP-7P1 Tri-AP-9G1 H- AP- 15 G 1 10-04-75 10-21-75 2426 2716 1414 2615 2215 l
I 10-11-75 10-1 ft-7 5 2216 lit i6 3016 2916 3116 10-l!!-75 10-25-75 1915 21116 2015 2616 2716 f
I
. 10-25-75 11-01-75 1514 1515 97143 1214 1715 11-01-75 11-06-75 2317 2718 271fl 2217 1917 a
11-06-75 11-13-75 1816 1716 1715 1615 1015 4>
' 4 2715 4627 11-13-75 11-20-75 2016 2315 1414 i(*) CO 11-20-75 11-26-75 2416 2216 2216 2315 2516
- )
1 1 - 2 6 - 7 '> 17-03-75 2916 2516 fl5137 2417 2915 O
12-01-75 12-01-75 1315 2216 1715 34110 1715 12-10-75 12-17-75 2616 19 15 2215 J 2'18 2116 12 7'a 12-24-75 2116 2216 1716 2215 2116 c4gm i 2-u-7 5 > 2-n-7 5 1616 i215 Ins 1015 u 16 AvntAct: 20134 23220 2fli4 3 26116 26124
TAl'f.I! Il 81 (('on t. . )
cot!CEllT!tATInflS OP It!'rA l'ItIT'11:ltS Ill AIll PAllTICIII.AT!'S Itesults in Unit.s of 10' pCi/m' i 2 s19 min STATIOrg glo,
.iTAltT fi'fDP I m TI: DATI' Tit .5.P-1S2 T't-AP-2S3 '11 - Al -0.*11 TI'- AP- sal ?"- AP-? ?til A'.': '! C 6-211-75 7-05-75 6117 5617 5317 5019 6318 5(11?
7-05-7S 7-12-75 1614 6218 4617 4216 2717 4?!:"
7-19-75 3516 3116 1014 3216 3017 2? 114 7-12-75 7-19-75 7-26-75 1114 2016 2615 04136 1216 27141 7-26-75 0-02-75 1615 3213 42114 3917 351C 3Jil$
A 11-02-75 0-09-75 3116 2618 3016 99142 2716 3(145 g
- P 0-16-75 3416 2127 3016 3417 4417 3r1!7 OO st-09-75 0-23-75 2416 2117 3017 2616 3016 26t io N ti-16-7 S 4 2617 1916 90142 2.':16 3 a 1.i 2
-y !!-2 3-7 5 e-30-75 1415 18-30-75 9-0/-7S 2115 2014 2416 1014 2015 l') ! !:
9-06-75 9-13-75 1615 2015 2016 lit i5 2215 20 s r.
9- 2')-7 5 fl9116 116129 2015 60136 2015 41164 9-1l-75 9-20-75 9-27-75 1615 2016 1716 1614 1514 25150 9-27-75 10-04-75 tlS
- MS* 1514 1915 2217 2017
- Ilo sample , pmrp inoperativo o
l
';'Alif.!? It-il (ConL.)
l f COi!CI'llTitATJnflS OF Ill'rA IP I T't1s f tS Ill A?.It PAllTICt1T.A'11'S Itenults in t! nits of Isl~3 1C1/58 1 2 sigina STATIOil flO.
STA lt* S1Vil' D A'll: DATI: Tit-AP-IS2 111- A P- 25 3 it t- AP-C S I ilt-AP-sal TM-AP-12nl AVI:l'I.('I:
10-01-75 10-11-75 73139 25116 1915 94137 2615 35153 i
10-11-75 10-111-75 2214 2116 2516 1914 1715 2.1110 10-111-75 10-25-75 1514 2416 1315 2616 2215 22110 10-25-75 11-01-75 90140 114152 771<4 1014 2625 ali?C 11-01-75 11-06-75 33110 2019 2217 1417 2217 2211'
. 11-06-75 11-13-75 1314 1216 1715 1319 2316 171t.
I A) 11-1.1-75 11-20-75 2615 94150 1414 2215 2015 3?i*?
11 75 11-26-75 20111 2617 2216 90142 2216 jo!
11-2ti-75 l'!-03-75 IIS
- 1616 il5133 2115 1715 3715 12-03-75 12-10-75 1717 <5'* 1114 <1** 1f15 23315 12-10-75 12-17-75 2015 15110 10i'i 1014 2415 20: 2 12-17-75 12-24-75 1315 2113 1716 2616 2616 211:
.5:>
p 12-24-75 12-30-75 1615 1217 1415 <4** 1115 1511:
- Q m
. v. Avi Ic A(;I: 30146 3214ft 2:1137 39159 25121 291 w:
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Cot!CEt'TilATIOt35 Ol' I-131 Ill PIf.TI:Ittin Allt Ile stil t s
- in Ifnits of IF pCi/m 3 S rA RT STOP STATIO11 tio.
DAll: DATI! Tit-AI-IS2 'nt- A I- 3 S 1 Tit-AI-5Al T'l- A I- I S G1 6-20-75 7-05-75 <8 <a <13 <a 7-05-75 7-12-75 <h <a <7 <3 7-12-75 7-19-75 w il <3 <n <7 7-19-75 7-26-75 <G <0 < !! < ft 7-26-75 B-02-75 <9 *:29 <10 <9 8-02-75 0-09-75 <a <9 <a <10 A-09-7S u-17-75 < 10 <10 <16 <20 l-
" a-16-75 0-23-75 <11 <5 <10 < :1 11-23-75 8-30-75 <8 <9 <7 <7 n-30-75 9-06-75 <7 <7 <7 <7 9-06-75 9-13-75 <7 <3 <7 <7 9-11-75 9-20-75 <7 <10 <8 <7 9-20-75 9-27-75 < 10 <10 <7 (8 4-27-75 10-n4-75 inia * <7 <7 4
A
- Ih3sulta corrected for des:ay to siwnplinq stop da tes
- !!o samplo, Inung inoperativo 00 G- Q rd Ln
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TAI 11.1: E-10 (Cont.)
COlfCI'.flTRATIOr!S OP I-111 Iti FII.TI'ItI:D AIII Ito sul t u
- in linits of 10' JC1/m' STAltT STOP STATIOtlllO.
I)ATI; DAT!! TM-AI-IS2 Tit- AI-IIS I 'IN- AI- 5 A l Tt-AI-15G1 10-04-75 10-11-75 <8 <7 <7 <8 10-11-75 10-10-75 s7 <9 s' 7 -9 10-13-75 10-25-75 <7 <9 <7 <7 10-25-75 11-01-75 <7 <D <7 <7 11-01-75 11-06-75 <16 <12 <12 <12 11-06-75 11-13-75 <6 <6 <6 -: A 11-13-75 11-20-75 <0 '8 <3 <0 4
11-20-75 11-26-75 <15 ' 12 O 6 31-26-75 12-03-75 ilS * * <5 <5 :7 12-03-75 12-10-7S <13 <a '
llo <10 12-10-75 12-17-75 <6 <7 <6 '6 12-17-75 12-24-75 <7 <7 <9 '
-9 12-24-75 12-31-75 <10 413 <10 - 12 I%sul ts corrected for decay t o sainpling stop date
- rio s.unple, pmup inoper.ntve
[@)
,o
~
n CD g 70 m
a TAIT! I' P-11 .
('(PICI'llTilATIO!!S Ol' Itl*rl. l'It1T11:ItS Ill l'III'CI PITATIO!!
IMa ul t s in Units of gri/l i 2 sisjiu 6-2ft-75 7-76-7S 0-30-75 9-27-75 11-01-75 11-26-75 to to to to to to STAT 10:1 110 7-26-75 0-30-75 9-27-75 11-01-75 11-26-75 12-31-75 AVI:!:ACI:
Tit-ftti 'IS 1 1114 6.714.3 <4 3.012.4 <3 7.113.1 0.015.8 Tit-itti-5Al 7.713.5 1215 <4 4.112.4 <4 1213 7.317.7 Tit-Idl-71'l 9.413.7 5.014.2 <4 5.512.5 5.fli3.5 1213 7.016.0 1*t- !:1!- 15 G1 1114 0.014.4 <4 6.412.6 <3 5.913.0 6.515.5
- Avi'leAGI: 9.013.2 7.916.0 -
5.n12.4 -
9.216.4 6.716.0 4
- s. 4
"* IlETA l'rf PrTI'It DI:ICFITIO'l g
iv flesul ts in tinits of nCl/m# 1 2 sig M LT1 .
I') 6-20-75 7-26-75 0-30-75 9-27-75 11-01-75 11-26-75 to to to to to to STATIOri 110 7-26-75 0-30-75 9-27-75 11-01-75 11-26-75 12-31-75 A vn A ct' Tri- 111- f t S 1 0.910.3 0.210.1 <1.5 0.310.7 < 0. 3 0.410.2 0.611.9 1 1- I t.*- 5A 1 0.510.2 0.410.2 < l .2 0.210.1 30.2 0.010.2 0.'i10.7 it'- 1:t i- 7 I'1 0.319.3 0.210.2 < l.7 0.310.1 0.510.3 0.(10.2 0.711.1 d 111-Itt i- I S G1 0.010.3 0.610.4 < l .7 0.410.2 ( 0. 2 0.410.2 0.711.1 AVI:t:Act: 0.310.4 0.410.4 -
0.310.2 -
0.510.2 0.610.9 t
Ij -
f TAIII.f-: P-1? -
1
! ('O'ICI:"ITitATIOM.<1 Of' TPITIllM At!n GAttitA 1 *ll TTF Rf1 lll I'It!'C J PITATIOi!
F Itesul ta in Units of ici/l i 2 sigma
,, r':.uT e-v1
!?!'ATIOll ?!O . I)ATI-: IsA"'l: I:- 3 Ito-7 OT!!!'!!r 1
s
')- 27-7 5 fl 6164 l')]
[ '!T 1- 1:11-:1!!1 6- 2 f;-7 5 9-27-75 12-31-75 < fl 0 f 1 DI.
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<ltIE
' Mi%
5, Tr i- itt !- SA 1. 6- 2 f t -7 'i 9-27-75 120161 ] r.17 - tilir.
0 9-27-75 32-31-75 < fl 0 1317 < 711E
( TM-Itt i- 1 S G I 6-28-75 9-27-75 < !I O 2317 'MI?T.
f.' 9-27-75 .12-31-75 < !!O l'117 c I!PT.
f 's' .
'!?1- 1 t1-71'l 6 - 2 H -7 'i 'n- 27 -7 5 111I164 1417 < M DT.
l- 9-27-75 12-31-75 -:llo
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1 -
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TAF.T.!! !!-13 CO!!CEllTitA*IO!!S OF SP-8 9 AtlO SR-90 Jfl PRITIPITATIO!!
Ilestalts in Ifnits of PCi/l STATIOfl 110 STAltT DATE STO P DATF Sit-il9 S 81 - 9 0 Tri-itti-l S 2 6-2ft-7 5 12-3]-75 20.4 <0.3 Tit-1:ll 81S] 6-2 ft -7 5 12-31-75 < 0. 5 <0.4
'It t- Itt i-7 P1 6-20-7S 12-31-75 <0.5 ~~. 0 . A
- itt- 1:ll-15 G 1 6-23-75 12-31-75 < 0, 5 '
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U C C C C C C
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M E M N
Z M M U L
m r~ c = = t'.
M b C C C C C C M C A . . . . . .i. u v 1 R C C C C C t c:
- - M I 4 01 41 \/ V V '/ V tO L1 G". L *4 OC C c : o i O w 41 4 40 e
% C
< C
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- c om r C C = C c- 41 N
< D C C C' C C 4
= .J c . . . . . + ch b & C C C C C C + Mm U E :
< V V V V V T -
- >,= .1 C C OC =
2 = 0= m C c m U T .- C c hH >
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- . . . . . + tC 1 C C C C C C + 00aE
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6- .t O L =
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TAP T.F. IT-I S COllCl:tITitATIOrlS Ol' Ell- H '1 AllD Sit- 9 0 Ill MIT.K I:e sul ts in Ifnits of pC1/1 1 2 sigma l
STAitT STOP*
STATIO!! !!O. DATI' DATI: Sit-il 9 Sit 810 Tri-F1- 4lil 7-26-75 9-27-75 <2.1 3.911.1 11-02-75 12-01-75 <1.5 2.710.7 i s
o TM-N- Sil l 7-26-75 9-27-7S (1.4 1. !! 10 . 7 l 11-01-7S 12-01-75 1.5 2.510.7 j e
Tri-f t-7D 3 7-26-75 9-27-75 < 2. ] 4.311.1 [
13-01-7S 12-01-75 ( 0. 9 < 0. 7 i
Tit-M- 14 C 1 7-26-75 9-27-75 < 1. 9 4.711.0 g
))-01-75 32-n]-75 1 . 11 4.310.9 I
- 11-t1-l F 2 7-26-75 9-27-75 - 3. 3 7.911.7 [
11-n1-75 12-01-75 < 2. 0 6.910.8) P I
'If t-fi- SA3 8 * ))-03-75*** 12-01-76*** <1.4 2.010.7 2
- Ilo samples in December; non-grazing season d
- Management aiulit siunple 3
^ **^ Cow d ry .Tuly t.o September - no sample availabic b I.
fN n
4 CD E TJ
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'I Altf.f' D-17 TI.D DOSI: ItATI:
Results in Ifnits of mrem / standard month 6-28-75 7-26-75 8-30-75 10-04-75*
to to to to STATIOf f t!O. 7-26-75 fl-30-75 10-04-75 12-24-75 AvrRAcr COrivitOT. IDCATIOttS Tit-I n- I t'l 6.010.6 6.210.2 6.410.3 6.210.3 6.210.3 vit-ID-7P1 7.210.2 7.710.2 7.410.4 7.A10.2 7.410.4 T:t-It)- 4 01 5.510.2 5.f10.3 5. 710.1t 5.010.3 5.710.3
?'t- I n- 9e ' ) 5.710.1 6.210.7 6.210.4 6.010.7 6.010.5 TH-1D-15G1 5.410.2 5.1120.3 5.(.10.5 5.?10.2 5.610.4 T.'t- I D- S ti l 5.510.4 5.110.4 4.710.0 5.210.4 5.110.7 IllDICATOrt I.OCATInt!S tit- Ill- 18 2 4.0*0.4 5.210.6 5.410.3 5.510.5 5.110.5 Tit-ID- 2 S 2 4.710.4 4.410.2 4.710.A 4.010.5 4.(10.3 Tri-I ri- 4 S t 5.010.5 5.210.4 5.dio.2 5.310.3 5.210.3 tit- ID- S S 2 4.(10.1 4 . f 410. 2 4 . 'i t o .1 - 5.110.3 4.310.4 Tit-II5-IIS 1 5.310.2 5.(10.1 5.110.2 5.310.4 5.110.4 Tit-ID-932 5.010.4 5.610.4 5.510.5 5.410.3 5.410.5 te s-Its- 11 r 1 5.e10.4 5.710.6 5. f.10. 6 5.910.2 5.(10.4 mr t-In- 14 S2 *" 4.110.4 5.110.5 *** 4.711.1 Tit- ID-16 S 1 5.210.2 5.510.1 5.410.1 5. fl 10. 3 5.510.5
?!!-In-AA] A.910.5 5. 210. .; 5.010.5 5.110.2 S.010.3
- vtt- I n ~ '. A l 5.010.5 5.210.2 5.210.5 5.110.1 5.110.2
..- m T!t- In- 16 A l 4.410.3 4.710.1 4.510.7 *** 4 . 510. 't ph 4 7 tt- In- 10iil 5.710.1 5.910.4 5.710.5 ***
- 5. r:10.2
) T*-In-12ft1 T't- I D- 1(* )
4.210.2 4.310.1 4.Sto.s 4.410.2 4.110.4 4.110.4 jg 4.710.2 4.310.3 4.710.2 4.510.5 Avrtw;I* 5.211.4 5.411.5 5.311.4 5.511.4 5.111.e ev C a
[d CO **
changed to quart.eirly exposure petrials Pr.n stolen
- TIA not. collecteed due to river Frem lert
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