Text

Radiological Environ Monitoring Rept, Jul-Dec 1975
	ML19206A219
Person / Time
Site:	Crane
Issue date:	02/28/1976
From:	; Metropolitan Edison Co, Radiation Management Corp
To:	;
References
	RMC-TR-76-01, RMC-TR-76-1, NUDOCS 7904180397
	Download: ML19206A219 (58)
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RADIOLOGICAL EilVIR0iiMEllTAL F0ilITORIfiG REPORT For The THREE MILE ISLAtlD fiUCLEAR STATI0il 5 0.'A'7l3 3 c 1975 SEMI-A:liiUAL REPORT II JULY 1 THROUGH DECEFSER 31 Prepared for METROPOLITAtl EDISCil COMPA?!Y BY RADIATICil MA:lAGEME?tT CORPORATIOil FEBRUARY 1976 Y,h//[~

UU'259

2.,

h TABLE _OF CO.1 TENTS PAGE LIST OF FIGURES.

ii LIST OF TABLES ii

SUMMARY

1 INTROCUCTION 2

PROGRAM 3

Objectives 3

Design 3

Exceptions.

4 RESULTS AND DISCUSSION.

4 Aquatic Environment 9

Atmospheric Environment 11 Terrestrial Envircnment 12 Direct Radiation 14 ASSESSMENT OF IMPACT 14 CONCLUSIONS

. 19 KE-tn[.,CrS.

20

- rD h C APPENDIX A Sampling Locaticrs 22 APPENDIX B Data Tables

. 29

,.()

' F)60

+

i

I s *,

LIST OF FIGURES PAGE 1.

M0itTHLY AVERAGE TRITIUM CONCEliTRATI0 tis Ill THE SUSQUEHAfiNA RIVER Ill THE VICIflITY OF THINS 10 2.

M0ffTHLY AVERAGE GROSS BETA C001CEi4TRATI0 tis Ill AIRS 0 Rile PARTICULATES IN THE VICINITY OF TMIils 13 3.

M0flTHLY AVERAGE GAi41A DOSE PATES AT TMINS 15 LIST OF, TABLES PAGE 1.

SYNOPSIS OF THE OPERATIGifAL RADIOLOGICAL ENVIRONMENTAL 5

MONITORING PROGRAM FOR TMINS 2.

SUt' MARY OF PADI0fiUCLICE C0fiCENTRATIONS Ill EliVIR0flMENTAL SAMPLES FRCM TMIllS 6

3.

SUiO!ARY OF DIRECT RADIATIOil MEASLREMEf4TS AT TMINS 8

4.

JULY-DECEMBER 1975 ENVIRONMENTAL SAMPLE DATA WHICH 16 RESULTED Ill N0ft-ROUTINE REPCRTING 5.

COMPARISON OF ST;. TION EFFLUENT DATA FOR TRITIUM Arid C0-58 WITH MEAN RIVER FLOW 18 o0 Tc1 ii

h h

SUMMARY

Ouring the period July 1 to December 31, 1975, Radiation Management Corporation (RMC) participated in the operational radiological environme~ntal monitoring program (REMP) conducted by Metropolitan Edison Ccmpany at Three Mile Island Nuclear Station (TMINS).

The RMC portion of this program was designed to aid in meeting the obligations of the Environmental Technical Specifications for IMINS Unit #1 (TMI-1)(1).

A total of 924 analyses were performed on 554 samples during the period covered by this report. These samples were taken from the aquatic, atmospheric, and terrestrial environments and included direct radiation measurements.

Mditional samples and analyses beyond those required by the environmental technical specifications were perfor.ed as noted in the data tables of Appendix B.

Surface water (4 locations, 23 samples) was analyzed for H-3 and ga ma emitting nuclides. Untreated drinking water (2 locations,12 samples) was analyzed for H-3, Sr-89, Sr-90 and gamma emitting nuclides. Fish (2 locations, 9 samples) and sediment (3 locations, 6 samples) were also taken from 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, 263 samples) were analyzed for gross beta activity and gama emitting nuclides.

Charcoal cartridges (4 locations,106 samples) were analyzed for I-131.

Precipitation, primarily rain water, (4 locations, 24 samples) was analyzed for gross beta activity, H-3, Sr-89, Sr-90, and gamma 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 nuclides.

In accordance with environmerital technical specifications, an update on the milking animal census was performed during this period. A distribution of 1095 milking cows at 35 locations was determined, a decrease of 19 cows since June 1975. Green leafy vegetables (4 locaticne, 4 samples) were taken and analyzed for gama emitting nuclides.

In addition, 320 analyses for imersion dose (21 locations, 80 packets) using TLDs were made during this period.

All radicnuclide concentrations were similar to those normally found in local unaffected areas, except for H-3, Co-60 and I-131 in surface water and Co-53 in sediment.

The H-3 ccncentratior.s in surface water at the dcwnstream indicator locations (0.5 and 1.5 miles downstream) shcwed elevated levels relative to the upstream samples twice during the reporting period. No increase in the H-3 levels at the dcwnstream locations where river water is used as a drinking water source was observed. Therefore, no measurable dosc can be attributed to the release of H-3 from TMINS.

During July Co-53 was detected in 2 sediment samples; probably the result of station operation. Since no Co-58 was detected in surface water or fish, the cnly significant dose pathway resulting from this Co-58 would oO 262

g g

be fron standing on the shoreline. A highly conservative dose estimated pelds an insignificant dose to a hypothetical maximum individual of 0.03 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 could receive an insignificant dose of <0.006 mrem.

I-131 was detected in surface water from station 9A2 during August at a level of 50 pCi/1, b9t was undetected in all drinking water samples. Therefora, no measurable cos can be attributed to this level of I-131.

It is therefore concluded that station operation produced only insignificant and temporary changes in the observed environmental levels of radioactivity.

These temporary ;hanges could have resulted in an insignificant dose to a hypothetical maximum individual of <0.1 crem.

INTRODUCTION A complete radiological environmental monitoring program (REMP) for Three Wie Island Nuclear Station (TMINS) has been conducted by Metropolitan Edison Company 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 operational phase (June S,1974 to June 30,1975) were reported in previous RMC documents (2,3,4). This report continues the operational series with coverage of the second six months of 1975.

It presents in detail the type and number of samples analyzed, the analyses performed and the data generated by RMC during the period July 1 to December 31, 1975.

Interpretation of the data and conclusions are presented.

Three Mile Island is the site of an operating nuclear power unit of the pressurized water r actor (pWR) type. When complete

.e station will consist of two reactor units. Unit 1, rated at 871 s, achieved criticality on June 5, 1974. This marked the beginning of the operational phase of the REMP. Unit 2, rated at 959 MWe, is under construction and scheduled for commercial operation in 1978.

The station is located on Three Mile Island in the Susouehanna River, in Dauphin 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. Agriculture is the largest land usage in the area (48%), with the emphasis on poultry, dairy cattle and field crops (6).

The census of milking cows located within five miles of TMINS(6) was updated in the previous semi-annual report (4) and again during this report period.

The distributicn and acproximate locations of these animals are given in table B-19 (appendix 8).

More specific information en the demography, metecrology and land use characteristics of the local area may be found in the Environmental Repcrt(7), Environ:rertal Statement (8), Final Safety Analysis Report for TMI-2(9), and the Environmental Report Supplement II(10).

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PROGRAM In the operational phase of the REMP, radioanalytical data are collected for comparison to that generated in the preoperational phase. Di ffe rence s between these two periods are examined statistically to determine whether any station effects exist based on the magnitude and fluctuations of radioactivity levels determined in the preoperational phase.

Objectives The objectives of the operationel raciological environmental pr ogram a re :

1.

To fulfill the cbligations of the Radiological Surveillance-Environmental sections of the Environmental Technical Specifications for TMI-1.

2.

To determine whether any statistically significant increase occurs in the concentration of radionuclides in critical pathways.

3.

To detect any buildup of long-lived radionuclides in the environment.

4.

To detect any change in ambient gama radiation levels.

5.

To verify that radioactive releases are within allowable limits and that TMI-1 operations have no detrimental effects on the health and safety of the pul5 Tic or on the environment.

This report provides information for the Metropolitan Edison Companj, regulatory agencies and the public record toward these objectives.

Cesign In order to meet the stated objectives, an appropriate acerational RE".P war ped by RMC in cooperation with Metropolitan Edison Company.

Sam;.

.;r the operational REMP were 3.aken from the aquatic, atmospheric, and mstrial environments. Samples of various media were selected to obtain data for the evaluation of the raClation dose to man and important organisms. Sarple types were based on (1) established critical pathways for the transfer of radionuclides through the environment to man, and (2) experience gained during the preoperational and initial operational phases. Sampling locations were determined from site meteorology, Susquehanna River hydroicgy, local demography and land uses.

Sampling locations were divided into two classes--indicator and control.

Indicator stations are those which are expected to manifest stacion effects, if any exist; control samples are collected at locations which are believed to be unaffected by station operations. Fluctuations in the levels of radionuclides and direct radiation at indicator stations are evaluated with respect to analogous fluctuations at control stations, which are unrelated to station operation. Indicator station data are also evaluated relative to background characteristics establisned prior to station operation. Additional samples beyond those required by the Envircnmental Technical Specificaticns were collected and analyzed; they are listed as management audit samples in the data tables (Appendix 3).

GO "y

Q The analysis of samples and the analytical data generated during the program are routinely evaluated by the R?iC project leader who is the liaison with Metropolitan Edison Company personnel. Further review of REMP design and analytical data is performed by RMC and Metrcpolitan Ediscn Company R$+EE professional staff in light of current regulatory trends and operating exoerience. The analytical procedures and quality control methods utilized by RMC(11) meet or exceed the minimum sensitivities required by the Environmental Technical Specifications (1).

Table 1 summarizes infnmation on the Three Mile Island :1uclear Station operational REMP as performed by RMu. Appendix A explains the RMC sample coding system which specifies sample type and relative loct.tions at a glance. Table A-1 gives the pertinent information on individual sampling locations, while Maps A-1, -2 and -3 show their geographic locations.

Exceations The operational REMP was conducted in accordance with the Environmental Technical Specifications for TMI-1(1). Deviations from the program as described in table 3 of these specifications occurred during this period.

Because aquatic plants are very scarce in the vicinity of TMIlS, 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 73,900 cfs was established at Harrisburg for the month of September.

Milk samples were not available at station 5A3 for the months of July, August and September since the single cow at that location was not producing during these months. However, samples were collected and analyzed routinely during those months at station 5B1, only 0.1 mile further frca tne site in the same easterly direction. This second farm (70 cows) adequately covered the need for samples.

Pumo outages resulted in the loss of 5 air particulate and air ;cdine samples.

Flcoding conditions in late September resulted in the loss of 2 additional air particulate and one air iodine samples. Hcwever, the overall air sample recovery rate was greater than 965.

RESULTS Af!D DISCUSSICM The averages and ranges of analytical results are su=arized in tables 2 and 3.

lable 2 is a summary of gross beta, H-3, Sr-89 and Sr-90,1-131 and gama spectrometric results for various samples. Table 3 is a summary of ambient radiation levels as measured by thermoluminescent cosimeters.

Results for each type of sample were grouped according to the analysis perfomed. Means and standard deviations of these results were calculated when applicable. These standard deviations represent sample population variability rather than analytical variability.

For this calculaticn, all resul ts below tne MOL were considered to be at the MCL.

The data for individual samples are presented in tabular form in copendix 3, tables 5-1 through 5-18.

Wi thin t.'.e data tables a 955 ( 2 sigma) confidence interval is suoplied. These intervals represent the range of values into wnich 955 of repeated analyses of the sample would fall.

All results occurring at or below the relevant minimum detectable level were reported as being "less than" the MOL value.

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TAPT.E 2 Stif tt'ARY OF RADIOttt1CLIDF Cot'CEMTRATIOrlS Ill FtNIEOt!PtENTAL sat:PT.TS PRO?1 TMIt*S

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SA f fi'T.f; A t!A T.YSIS sat'P T.C S AI.OVC AVPR/GE TYl>E PI: Tit'O RifED NIATJZED Mph HI!!IMtiM MAXIMtiH i 2 SIGt'76 1"IITS Surface ifator it-3 ( up s t rea r )

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Air Particula tes nota 261 259 1015 99t42 2'1133 I f, Ici/n Gamma 12

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no-7 12 2112 150115 65t44 10 IC1/m Ptn 'id 2

0.1 0.310.2 103 3

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0.2 2.110.5 0.511.1 10-3 [Ci/ra 3 ini- :S 11 (MDI.

4.3to.5 0.012.4 10-? Ici/ra1 10-3 l tr ' [ C i f.a 3 Ru-106 3

0.6 1013 3t5 3

.%-12 5 6

< t t D T, 2.110.7 0.510.6 gri/n 3

cs-117 12 0.110.1 4.310.5 0.011.4 id r.C i /i t co-141 1

(MDL 0.010.3 ItF IC t/'u ca-144 10 0.5 22t2 A, G 17, 9

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!#1/1 Data 24 17 3

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Vegetables K-40 4

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o TATILP 3 Stif'ItARY OF DInFCT ItADI ATIO!! ttFAStl'tE!U'!!TS AT TMI!1S J f!LY I T19tOI)Gil DI:CI:!1n!'It 31, 1975 110. OF SAMPLIllG 17 0 ATIOVE AVE ftAGT' SAtTI.I:

SAttPLUS PI'RIOD MDL MIllIMUM MAXIMU!i 1 2 SIGtA tit!ITS CO!!TitOL f.OCATIOt!S f!on thly TLD 96 6-20-75 96 4.710.8 7.710.2 6.010.4 mrer:/ standard month Do s e !(a t e to 12-24-75 I?!DICAloP f.OCATInt!S

!!onthly TLD 224 6-28-75 224 4.210.2 5.910.2 5.010.4 mren,/ standard month DoSc f(ate to 12-24-75 (O

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faco 'de:r l'onthly v.,,, car s.3 oles,,ere collected at 6 locations en the dates shcwn i~ teLie. ;. Weekly grab samples from stations 1C2, 9A2 and 981 were taken and cor:asited conthly. Samples from staticns 8El,15F1 and 7G1 were ta en en e semi-continuous basis and composited to monthly samples. Ceginning with the ::ovember samples, H-3 analyses were reduced from monthly to c;uarterly. Hence, the tfovember and December samples were composited prior to H-3 analysis in accordance with TMI-1 ETS taole 3.

Each sample was analyzed for H-3 and ga ma emitting nuclides by RMC procedures HXH and TGC, respectively. Samples from 8El,15F1 and 7G1 (drinking water treatment facilities) were also analyzed for Sr-89 and Sr-90. A new upstream sampling location (IC3) was established on Swatara Creek in January 1975 for assessment of any radionuclides which may be added by that tributary. The results therefrom are included in this re po rt.

Results of H-3 analyses are presented in table B-2 and figure 1.

Concen-trations of F-3 were observed to increase in August, September and October at one or both of the two downstream indicator stations 9A2 and 981. tio increase was observed at these times at station 7G1 (Columbia). These concentrations returned to background levels in the ?!ovember-December ccaposite at all downstream lccaticns. The dose implications of these H-3 levels and a comparison with liquid effluent da5 are discussed ur. der

" Assessment of Impact".

wults of analyses of surface water for Sr-89 and Sr-90 are prescnted in table B-3. These analyses were made cn untreated water from the Brunner Island water treatment facility (8E1), the Steelton municipal water works (15F1) and the Columbia water treatmenc plant (7G1). All Sr-89 concentra-tions were below the MOL (0.3 pCi/1); Sr-90 concentraticns were at or below MDL (1.0 pCi/1) in all of tne samples analyzed.

Garana spectrometric analysis of surface water samples (table B-4) shc.ved that the naturally occurring nuclides K-40 and Be-7 were present at concentrations above their respective MDLs in 2 samples each. The ga=a emitting nuclides Co-60 and I-131 were detected in the surface water sample from station 9A2 during August at concentrations of 2.4 and 50 pCi/l, respectively. Since I-131 was not found in any of the drinking water samples or in any other aquatic pathway, no significant dose can be att-ibuted to this nominal level. The maximum dose implications of the observed Co-60 concentrations are discussed under " Assessment of Impact".

Fish Fish samples were collected at 2 locations each in Juiy and October of this reporting period. Only adult fish were taken for samples.

These were separated into classes of bottom feeder versus predator-game species; fillets were analyzed.

Ga= a spectrometry (TGC) and Sr-89 and Sr-90 analyses (SRB, SRD) were performed on subdivided fish samples.

' results of these analyses are given in table B-5.

Sr-89 was detected

~

.. one of the 9 samples. Sr-90 was detectec in 6 of the 9 samples with the hichest value of 4.2 pCi/Kg detected in the upstream sample (1681).

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detected in The results cr :ne grra analyses are given in table B-7.

The naturally cccurring radi nuclides (K a0, Ra-226 and Th-232) were found in all 6 sediment samples.

In rc:cter, Cs-137 was detected in a sample from Station 11A1 at a leve! of 0.33 pCi/g. This level was greater than 4 times the control staticn v31ue of 0.19 pCi/g but not significantly different from those values observed dering the preoperational period. A number of radienuclides typically found in fallout also were present in detuctable amounts.

Inese included 1b-95, Zr-95, Ru-106, Sb-125 and Ce-144, all of which were present in 20-30'; of the samples. Except for Co-58, all nuclides found were detected in both upstream and downstream samples and no significant variations in concentration were apparent.

Co-58 was cetected in 2 downstream s,amples during July, but not in October.

~

fact that Co-58 was detected in July and not in October, is probably the roult of the September flood which removed the normal sediment loa in this reach of the river. The high'est concentration cbserved in July was 0.47 pCi/g. This, when conpared to upstream values of <0.02 pCi/g and T" Ills dis-charge data, can be attribui.ed to station operaticn. The implicaticns of these Co :3 levels are discussed under " Assessment of Impact".

Atmosoner.ic Environment The atmospheric environment around TMI!S was examined by analyzing air p articulate fi'ters, charcoal cartridges and precipitation. Air particulate samoles were collected at 10 locations with low volume air samplers using Hollingsworth and Voss HV-70 gauze backed filters. At 4 cf these locations, air iodine samples were collected on Cesco "B" charcoal flow through cartridges connected in series following the air particulate filters.

Air volumes sampled were measured with temperature compensated dry gas

.aters and recorded. Both air particulate and air iodine samples were collected weekly.

Precipitation was collected by using a 12 inch diameter funnel draining into a 5 gallon polyethylene bottle. The accumulated samples were collected and ccmcosited for monthly analysis. The amount of precipitation whicn fell during the sampling pericd was measured and recorded.

Air Particulates air particulate samples were analyzed weekly for grcss beta activity by RMC procedure T3D and monthly composites of all indicator and of 'll control samples. sere examined for gam a emitting nuclides by RMC procedure TGC.

30%72 11

Results of the gross beta analyses are listed in table B-8. Gross concentrations of bota emitters in air decreased slightly from July through December.

This decrease was similar to the preoperational trend. The indicator F 4 control monthly averages plotted in figure 2 demonstrate these annual

.nds and show similar behavior at both indicator and control locations.

u Mon.thly gross beta activity in all samples averaged 0.029 pCi/m3.

The gamma spectreretric results on monthly composites 'of air particulate filters are presented in table B-9.

Prominent nuclides found in most samples were naturally occuring Be-7 and the probable fallout nuclides, Ce-144, Cs-137, Zr-95 and fib-95. In addition, Mn-54 and Sb-125 were detected in 3 of 12 and 6 of 12 samples, respectively. The short-lived fallout nuclide Ce-141 was detected in 1 of 12 samples. iio significant differences were observed between indicator and control composites and previously obtained data. Typical MDLs for garra spectrometric analysis of air particulate samples are listed in table B-18.

Air Iodine Gaseous iodine was collected on charcoal cartridges at 4 locations. The resulting samples were analyzed weekly for I-131 by RMC procedure IXB.

Results are listed in table B-10.

All results were less than the respective MDLs which were of the order of 0.01 pCi/m3.

precipitation l'onthly precipitation samples were analyzed for gross beta activity by RMC procedure TBA. ln: RMC analytical procedures HXH and TGC were utilized for the analysis of H-3 and gama emitting nuclides, respectively, quarterly composites of precipitation from each station. Concentrations of Sr-89 and Sr-90 (RMC procedures SRC, SRA) were determined in semi-annual composites from each :tation. The results of gross beta activity measurements in precipitation samples are presented in table B-11.

The data for this period ranged from 3.3 to

pCi/l while averaging 5.7 pCi/l. The wet desposition of beta activity averaged 0.6 nCi/m2, ranging from 0.2 to 1.7 nCi/m2. fio sicnificant differences betsuen indicator and control locations were observed.

The results of analyses of quarterly composites of precipitation for ii-3 and gamma emitting nuclides are presented in table B-12.

Tri tium concentrations averaged 87 pCi/l slichtly lower than pre-operational levels. The gama emitting nuclides Be-7 and Zr-?!b-95 were the only ones detected in precipitation. The cbserved levels of these nuclides iere similar at both indicator and control locations. Typical MDLs for gama spectrometric analyses of precipitation are listed in table B-18.

Semi-annual comcosites of precipitation samples from each station were analyzed for Sr-89 and Sr-90 and the results are presented in table B-13.

Of the 4 samples analyzed, Sr-89 and Sr-90 were belcw FDL in all.

Terrestrial Environment Tha terrestrial environment around TMII;S was examined by analyzing ples of milk frca 6 locations on a monthly basis and green leafy 30 273 12

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vegetables on an annual basis. Two gallon milk samples were collected and shipped fresh to RMC. Each sample '.las analyzed for I-131 using RMC reocedure IXD. Quarterly composites frca each station were analyzed Sr-89 (SRC) and Sr-90 (SRA).

Green leafy vegetables (cabbage) were taken in July at 4 stations. Each sample was analyzed for gamma emitters by RMC procedure TGC.

The results of I-131 analyses are presented in table B-14.

Mone of the 27 milk samples analyzed showed 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-89 was not detected while Sr-90 was detected in 9.

Results from indicator stations were similar to those from the control station and all results were similar to preoperational levels.

Tne results of gamma spectrometric analysis of green leafy vegetable samples (table B-16) showed detectable levels of natural K-40 only. No other gamma emitters were detected.

Direct Radiation The arbient radiation levels in the area of Three Mile Island Muclear Station were determined with energy compensated calcium sulfate (Tm) thermoluminescent dosimeters. A total of 80 monthly TLD packets (4 TLDs each) were placed at 21 locations around TMIMS. The results of the TLD measurements are presented in table B-13.

All TLD results presented in this report have been normalized to a standard month (30.4 days) to eliminate the differences in exposure periods. The resulting e rate was similar to preoperational levels averaging 5.3 mrad / standard mon th.

The projected annual dose computed from results for this reporting period is 64 mrads, or 54 mrem assuming a quality factor of 1.

An annual dose equivalent of 82 mrem was computed for the Harrisburg area and published by the EPA (12). 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 radiatior dose rates for indicator and control stations are plotted in figure 3.

No trends in ambient gamma radiation levels as a result of TMI-1 operations are apparent from this graph.

ASSESSMENT _O_F IMPACT The gaseous and liquid effluent streams from TMI-1 were continously sampled and/or monitored for the presence of radioactive materials by Patropolitan Edison Ccmpany. The REMP was designed and conducted in a manner to pennit identificaticn of the radionuclides actually released from the station.

Of the radioactive caterials released from TMI-1 to the environs, only H-3, Co-50, and I-131 in surface water and Co-58 in sediment showed a statistically significant contribution from iMI-1. Those samples showing concentrations statistically different from preoperacional or trol station values are listed in table 4.

Thus, the only pathways

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October it-3 3490!96 pC i/!

-1 Ganrra Au.r us t Co-60 2.410.4 pC1/1

!!11-3h I-131 50i9.4 gci/1 r:nta-30 9'll August 11 - 3 2720!al pC1/1 tiq P-7 Oc ptemlier

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for potential exposure of individuals or of a segment of the population to radicactive materials frca station operation is frca consumption of river water or frca shoreline deposits. Table 5 compares TV.I"5 discharge data for H-3 and Cc-58 with mean river flow. Since the H-3, Co-60, and I-131 were not detected in any other aquatic pathways (e.g. fish or sediment) except surface water, no sicnificant dose can be atrributed to these other potential pathways.

Untreated river water is monitored as part of tne TMIMS REMP at 2 locations (Brunner Island, eel, and Columbia, 7G1) in the downstream vicinity whicn At no time use treated river water continuously for human consumption.

during the reporting period did H-3 or I-131 levels at these stations differ statistically from those at the upstream station.

It can then be concluded that these H-3 and I-131 levels did not result in a significant dose to man.

On one cccasion during the reporting period (July) Co-60 was detected at a concentraticn of 2.1 pCi/l in untreated drinking water frca station eel.

The maximum dose which could be attributed to this level is 0.005 mrem to the GI tract or 0.0006 mrem to the total body frca consumption of this un-treated water for one month.

In addition, a similarly small dose (0.08 mrem) could have been received from standing 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> on the sediment in which 0.47 pCi/g of Co-58 was detected during July. These dose calculaticns were performed using the basic equations employed in ', LASH-1258(15).

These insignificant doses are the maxima which could be attributed to the radic-nuclides released to the Susquehanna River by TMI-1.

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CONCLUSIONS-n The preo;eraticnal Radiological Environmental Fonitoring program (REM?)

conducted by Ry.C and t.:etropolitan Edison Company was continued as the after TMI-1 initial criticality on June 5,1974.

opera tional prograt, The REM? (from July 1 through December 31,1975) described in this re;crt was conducted according to the Environmental Technical Specifications for TMIMS which permitted the objectives of the program to be met. Additional l

sampling and analyses beyond those required by the Technical Speci fications were performed. All results therefrom were reviewed by RI'C and Metropolitan Edisen to assess all possible environmental pathways.

Although other possible dose pathways to man were considered in the environs of the TMINS site, tritium, Co-60, I-131 and Co-58 were the only radionuclides of TMINS origin detected above background levels with only Co-58 and Co-60 potentially contributing to dose. The radiation dose to people from ambient garna radiation, as measured by thermoluminescent dosimeters, averaged 5.3 mren/ month and showed no evidence of a Ti1 INS contribution during this operaticnal period of TMI-1. The radiation dose to people in the TMINS environs is compared with the exposure from other artificial and natural sources in the following table:

Source of Excosure Annual Ccse in mren Medical 72(14)

Ambient Gamma (TLD) 64 Radionuclides in body (primarily K-40) 18(14)

Global fallout 4(14)

TMINS (Co-58 in sediment,

< 0.1 Co-60 in water)

Even tnough the TMI-1 contribution to population exposure is very small (approximately 0.15 of that from other sources), the TMINS has a continuing program to improve operatir.g techniques and to maintain equipment directed toward reducing releases of radioactive' materials to the environment.

Therefore, it can be concluded that operation of TMI-1 did not significantly alter the radiological characteristics of the TM1GS environs. The radienuclides and radiation levels observed were prir.cipally due to natural radioactivity and global fallout.

30 OSO 19

REFERETICES (1)

Metropolitan Edison Company.

"Three Mile Island nuclear Station-Technical Specifications." Appendix S. DPR 50, 1972.

(2)

Radiation Management Corporation.

"Three Mile Island Nuciear Generating Station-Preoperational Radiological Environmental Monito rino Program". RMC-TR-75-17,1975.

(3)

Radiation Management Corporation.

"Three Mile Island iluclear Station-Radiological Environmental Monitoring Program-First Operational Period." RMC-TR-75-02, 1975.

(4)

Radiation Management Corporation.

"Three Mile Island Nuclear Station-1975 Semi-annual Report". RMC-TR 13, 19 7 5.

(5)

United States Department of the Interior-Geological Survey.

" Water Resources Data for Pennsylvania, Part-1." 1973 (6)

Radiation Management Corporation.

"Three Mile Island Huclear Generating Station-Agricultural Land Use Survey". RMC-TR-75-1, 1975.

(7)

Matropolitan Edison Ccmpany.

" Environmental Report, Operating License Stage-Three Mile Island Nuclear Station Unit 1 and Unit 2", 1971.

(8)

United States Atomic Energy Commission.

" Final Environmental Statement-Thrce Mile Island Nuclear Generating Station Units 1 and 2". Docket Nos. 50-289 and 50-320,1972.

(9)

Metropolitan Edison Company, Jersey Central Power and Light Company, Pennsylvania Electric Company. " Final Safet Analysis Report, Three Mile Island Nuulear Station-Unit 2".

Docket Nc 90-320, 1974 (10)

Metropolitan Edison Company, Jersey Central Power and Light Company, Pennsylvania Electric Company. " Environmental Report Supplement II, Three Mile Island Nuclear Station." Docket f;o.

50-320, February 1975.

(11)

Radiation Management Corporation " Analytical ar.d Quality Control Program. " RNC-TM-75-3,1975.

(12)

Donald T. Oakley, " Natural Radiation Exposure in the United States," U.S. Environmental Protection Agency, ORP/SID 72-1, June 1972.

30 281 20

REFERE:lCES (Cont.)

(13)

S. E. Thompscn, C. A. Burton, D. J. Quinn and T. C..ig, "Concen-tration Factors of Cher.lical Ele. Tents in Aquatic Organisms."

UCRL-50564 (Rev. 1), October 1972.

(14)

"The Effects on Populations of Exposure tu tow Levels of Ionizing Radiation" (BEIR REPORT). flational Academy of Sciences,1972.

(15)

United States Atomic Energy Com.ission.

" Final Environmental Statement-ALAP UASH-1253," 1972.

dyJ - a pp' r

^*

21

APPEilDIX A a0 283 22

M ENJI/ r Samaling Locations Samole Identi fic3 tion RMC identifies samples by a three part code. The first two letters are the power station identification code, in this case TM.

The next one to three letters are for the media sampled.

AI

= Air Icdine FPL = Green Leafy AP

= Air Particulates Vegetables x1F = Fish ID

= Immersion Dose (TLD)

AQP = Aquatic Dlants M

= Milk AOS = Sedimant RW

= Precipitation E

= Soil SW

= Surface '.later The last four sy-bols are a location code based on direction and distance from the site. Of the last four symbols, the first two 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=NNE, 3=NE, 4=ENE, 5=E, e tc.

The next cigit is a letter which rep asents the radial distance from the plant:

5 = On-site location E = 4-5 miles off-site A = 0-1 miles off-site F = 5-10 m#les off-site E = 1-2 miles off-site G = 10-20 ailes off-site C = 2-3 miles off-site H = > 20 miles off-site D = 3-4 miles off-site The last number is the station numerical designation within each sector and zone; e.g. 1, 2,...

TN location portions of these codes (i.e.151, 3A1, etc.) are shown in the attached table along with more detailed information and a map coordinate number used to indicate the sampling locations. This sample identification systen is used to desicnate the individual samples in the analytical result tables, Appendix B.

NO^?SA 23

= = _

TA T'I.E A-1 PtJ)IOIDGICAT. Tf r/I nom?tr?! TAT. MOfiT"'O't !!!G Pl:(VM,*J f SM1PLTt?C LOCATI O!!S TJ hr' ATI Of f itAP ro!)l:

!!O.

DESCill PTIOt!*

1:;2 2

0.4 niles 17 of sita 2S2

.t

0. 7 miles t!!!r: of sito on light pole in middle of !! orth Eric1ce 21, 3 5

0.7 miles t.*!E of nite 1 eside gua rd house at t! ort.h Gate 4S2 7

0. 3 miles Film of site on top of dike, East Fence SS3 9

0.2 miles M of site on top of dite, East Pence t.;l 10 0.5 niles SSF of site at South n' eat her Sta tion 931 12 0.4 miles S of site at South Deach of Three Mile Island llSI 14 0.1 miles St!of site, west of Mechanical Praf t Towers on dike.

1492' 16

0. 4 mile s tit't ? o*

u i t e a t. Shelly's Island picnic arua N

16S1 17

0. 2 miles !!!'il of site at gate in fence on vest side of Three Mile Island t-1A2 19 0.7 niles ti of site at north tip of Three Mile Island 4A1 21 0.5 miles Ptir of sito on Taurel Rd., tie t. Td. Pole # 6 6 ft-OL SA1 22 0.4 miles n of site on north side of Observation Center Duildir; 5A3 2'1 0.9 milus n of site on !!oover Parm 97.2 27 0.5 miles S of site l>cl ow Discharoe Pipe 11A1 29 0.2 niles Su of site ori t>i schurge Pipe 10Al 31 0.4 miles tim? of site on 1:ohr Island an1 33 1.1 miles I: tin of site, west of Gringrich Road 5til 34 1.0 mile n of site on Peck Road V

%J CD Cn

TAftf.E A-1 (Cont.)

R ADI O f DG IP A T. 17!VI Rot IME tiTAT. MO PI ITO R I llG PROG TtA?1 eat"PT.IPIG LOP 3.TIOl10 f.OCATIO!!

ttAP CODE

!!O.

DI:SC*tI PTIOt!*

711 1 37 1.6 miles Sr of site on eart side of Conewago Crock 9161 30 1.5 mileu S of sitn, above York Itaven nc.m lon1 41 1.1 miles S3tt of site on south beach of Shelly's Island 1201 42 1.6 milen 1 St? of site adjacent to rishing Creek 1 6111 30 1.1 miles ilt:tf of site belou rail Island ICl 43 2.6 miles ti of site at Middletoun Substation 14C2 45 2.7 niles trilU of site near Intersection of Routes 262 and 392 0111 45a

'.1 miles SSI: of site at nrunner Island

'O 11'1 47 6 miles !! of site a t liiumrels town Substation on Fiddler's Elbow P.oad U1 IP2 40 9 miles il of site on tinion fMposite Doad, west of !!oornersto'in SFl 49 9 niles C of site on Past Ridqo and Greentree Roads 7P1 51 9'milen SI' of site e t Drager Farn of f Engle's Tollgate Road 15"1 53 0.7 uiten titt of aita at Steel ton ttunicipal 1:a ter t!or1.s 4G1 54 10 miles EtP: of sitt " ' w a - Pe t. Ed. Pole fJ1313 7G1 55 15 niles SF of uito at Columbia t?ater Treatment Plant 9G1 56 13 nile 5 of site in tie t.

Ed. York T,oad Dispatch S ta tion 15G1 5f1 15 miles tit. of site a t I?e s t Pairview Substation 5ttl 60 80 miles T. of site on Rtic roof in Philadelphia VC 5!!2 61 30 mil'

~

site on lute roof in Philadelphia

All d istances are mea sure<,

goint that is midway betueen the Peactor 2) nulldings of I' nits One and nuo O

1 2

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g Location of Operational Rcdicic; cal Envirc.r.antal

?:c nitoring Sta tions.ithin The Site :cendries rW..) - O gy*9 e., u (

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1* : A F P R.10 MILES

iap A-3 THREE '1:LE I S L'.'!D

UCLE'J STATIO:'

Locaticr. Cf Oper atic nal Radic'ccica] E n f i r c r r.e n t a l

lanitoring Stations Greater Th.in 5 :".ile s frcr the Site 23 a0 289..

APPEllDIX B

>O ~. 90 0

23

_ APPENDIX B Data Tables Appendix B is a preseritation of the results of the TMINS Radiological Environmental Monitoring Program.

TABLE JUMBER TITLE PAGE AQUATIC ENVIRONMENT B-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 C.1nking Water 34 3-4 Concentrations of Gamma Emitters in Surface Water 35 B-5 Concentrations of Sr-89 and Sr-90 and Gamma Emitters in Fish 36 B-6 Concentrations of Sr-89 and Sr-90 in Sediment 37 S-/

Concentrations of Gamma Emitters in Sediment.

38 ATMOSPHERIC ENVIRONM.ENT B-8 Concentrations of Beta Emitters in Air Particulates.

39 3-9 Concentrations of Gamma Emitters in Air Particulates 43 3-10 Concentrations of I-131 in Filtered Air 44 3-11 Concentrations and Ceposition of Beta Emitters in Precipitation.

46 3-12 Concentration; of Tritium and Gamma Emitters in Precipitaticr.

47 3-13 Cc-rectrations of Sr-89 and Sr-90 in Precipitation 43 TERRESTRIAL ENVIRONMENT 3-14 Cancentrations of I-131 in Milk 49 C

i Concentrations of Sr-89 and Sr-90 in Milk.

50 P-16 Concentrations of Gamma Emitters in Green Leafy Vegetables 51 a, - can4 t)*)

m. v 1 30

J APPEi! DIX B Data Tables (Co t.)

TABLE ilUM3ER TITLE PAGE DIRECT RADIATI0il B-17 TLD Dose Rate 52 MIrlIMUM DETECTASLE LEVELS B-13 Typical MDLs for Gama Spectrometry 53 CO.I CEriSUS B-19 Distribution of Milk Cows '.lithin Five Miles of TMIflS 54 kb 31

TABLP B-1 SAP'PLIt!G PPR100S FOR StJRPACP. UATP,R ThttPLUS STATIOt! !!O.

JtiL Aln SEP OCT ty"?

n.C 171-SU-1 C3

7-05-75 0-02-75 9-06-75 10-04-75 11-Of-75 12-03-75 h

to to to to to-to 7-?6-75 8-10-75 9-27-75 11-01-75 11-26-75 12-11-75 Tri-SU-15P 1 6-29-75 7-27-75 8-31-75 9-30-75 11-02-75 12-03-75 to to to to to to 7-26-75 8-10-75 9-29-75 11-01-75 11-26-75 12-31-75 1N-SU-9A2 7-05-75 n-02-75 9-00-75 10-0d-75 11-06-75 12-03-75 to to to to to to 7-26-75 0-30-75 9-27-75 11-01-75 11-26-75 I?-31-75

,o ra Tit-SU-9nl 7-05-75 0-C2-75 9-0C-75 10-04-75 11-0e-75 12-03-75 to to to to to to

". - 2 C -7 5 R-30-75 9-20-75 11-01-75 11-2f-75 12-31-75 "11-S U-9 t:1*

6-20-75 7-?6-75 0-30-75 9-29-75 11-01-75 11-2r-75 to to to to to to 7-26-75 n-30-75 9-29-75 11-01-75 11-26-75 12-11-75 T!t-SU-7Cl 6-23-75 7-26-75 8-30-75 9-26-75 10-25-75 12-03-75 to to to to to to 7-26-75 0-30-75 P-2r-75 10-25-75 12-03-75**

12-31-75 t1ananenent nudit sampl es Con.posite sampler inoperative; composite of weekly grab.

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'"A PL C t'- i CO!!CI'f!TI!ATIOflS OF S11-fl 9 NID SR-90 If1 i111TRPATED DRIf f!'I t1G WATER Results in Ifnits of pri/l STATIOf! 110.

STAitT DATE S'lO P DNE S R-fl 9 SR-90 Tit-SW-15 P1 6-29-75 9-29-75

< 0. 2

<0.2 9-30-75 32-33-75

< 0. f1 0.4io.4 Tri-SW-!T E l

6-28-75 9-23-75

<0.1

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<0.7

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<0.8

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TAB LI' It-5 lilCf7!TRATIO?!S OF SR-0 9 A!!D SR-9 0 Af f D GAMtm I?11TTT'RS Iti PISil Results iri tinits of pci/Pg i 2 signa SAMPLItM STATIO!! !!O.

sat 1 PLT' TYPU*

MO!!T!!

SR-09 S R-9 0 1:-40**

CS-137**

!!PSTitFAtt S AF1P L1'S

'I*1-AOP-16 f t 1 Catfinh July

~3.0 3.4 !2.0 35001350

'11 7 11roen Itullhead Tri-AOP-16ill S.

t'outh Ilans July

<4.1 5.0 1.4 37001370 3210 R oc); Hass

'171-AOF - 16 B 1 RocP. Dans October

< 5. 6 3.912.6 46001460 3 r1 16 Tri-AOP-16 n l Catfish October

< R.0 4.914.6 32001320 1210 u

On DO!I!!ST!!! M* SAf'PL1'S Tif-Ao!'- 9n 2 Ca t fi sh July

<4.5

<3.2 31001319 1010 S.

Pfooth Dass

""M-Aor-o n 2 nock 11 ass July

<7.5 3.913.4 61001610 29111 T!'- AOP.- 9 S 2 catfinh October

<6.4

< 5. 7 37001370 1110

'IT1-AOP-9 3 2 S.

Plouth Hass Octolier

<7.7 1714 36001360 21!9 Rock l'ish Potton f eeders - ca tfish, brown ball head; predator / game - small mouth bass, rock bass All other qarrna emitters (PDL W

C C:

M

l TA97,P P-6 COf!CFi1TRATIOt!S OP PR-30 A' f D GR-9 0 I?! SEDI'1EtiT Re sul t s in 11ni ts of pC i /g (<l r y) ! ? s ig rra STATIOIT !!O.

SAMi'T,Ir1G DATI:

SR-80 SR 60 I

l T!1-AOS-]A?

7-30-15 O.2

<0.1

]0-27-75

<0.07

<0.06 Tri-Ans on1 7-30-75

<0.2 0.310.1 Tit-AOS-3 l Al 7-30-75

<0.2

<0.1 10-23-75

<0.1

<0.1 Tr f-AO r;-l l A2 10-23-75

<0.1 0.03 0.03 l

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C C

r M

C c:

-e A. M V

V V V V V V c,

V C

s e4 e4 b

C bZ e4 W

6 4

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mb H

C C.

C H

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ce C

C C

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CM

+i

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U C

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10 wJ

TABLE P-8 COT'Cl31 Tit ATIO!!S OF PITA E!1ITTI:RS It! AIR PARTICtlLATI'S Restilts in Ifnits of 10--3 pCi/m 1 2 sigma 3

STATIO!! I?O.

STN<T S10P D AT1' D A Tr' Tit-AP-lPl Tot-AP-SP1

'IM-AP-7 P 1 "N-AP-9P1 Ttt AP-15G1 6-28-75 7-05-75 63i8 61 7 MS*

4416 51 7 7-05-75 7-12-75 4517 4616 11 S

4416 5517 7-12-75 7-19-75 26 6 3716 1:S

32i6 18i4 7-19-75 7-26-15 21 t5 2216

<10 21is 2415 7-26-75 0-02-75 34r7 3617 30!6 34i6 4217 C-02-75 e-04-7 5 2516 3317 2616 2016 3517 c,

u2 e-09-75 n-16-75 3617 4217 4617 4117 5019 8-16-75 3-23-75 2716 2716 32t6 2616 15i5 3-23-75 0-30-75 2616 1916 2716 2816 2216 0-30-75 9-On-75 1015 2217 13t3 2016 1815 h

9-06-75 o-13-75 2616 itS

2]i6 17 5 22!G 9-13-75 9-20-75 1514 7215 la 5 18!4 1214 0-20-75

^- 2 7-7 5 06t39 2015 1114 1815 1715 9-27-75 10-04-75 2315 2515 1715 2415 1825

!!o sample, ]>wp inoperative C"e t

Q c

CD

1 G

5 4

1 5

6 6

5 7

6 5

5 6

6 6

2 P

1 1

A 2

1 7

7 9

8 6

5 9

7 1

1 1

6 2

3 2

1 1

1, 4

2 2

1 2

2 2

2 t'T S

UTAL l

t C

J C

a 9

0 6

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5 6

6 4

7 5

5 5

7 1

0 5

5 1

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P 1

1 1

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1 t

1 1

1 R

i A

6 9

6 2

2 6

7 3

4 4

0 2

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2 T

t I

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'm i

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4 6

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8 5

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1 1

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1 i

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0 0

7 7

7 4

2 5

7 2

7 7

0 T ~

1 3

2 9

2 1

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8 1

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0 0

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t 1

1 T

t 1

D F

t f

E A

o or L

T I

s T

T I

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t A

1 T

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P F

in C

S 8

6 6

6 5

8 6

s 6

6 6

5 6

5 2

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1 1

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1 t

1 1

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7 8

8 5

7 7

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i I

s T

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I D

l

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P I

4 C'

6 G

5 4

7 6

6 6

6 5

6 6

6 3

C P

i 1

1 1

1 A

4 2

9 5

3 8

8 4

9 3

6 3

6 8

2 2

1 1

2 1

2 2

2 1

2 2

1 2

t iT 5

5 5

7 7

7 PP 1

8 5

1 6

3 0

6 3

1 7

4 1

OT 2

1 2

0 0

1 2

2 0

0 1

2 3

A m' D 0

0 0

1 1

1 2

2 2

1 1

1 2

1 1

1 5

5 5

?

7 7

7 n

T C

t

'A 4

1 3

5 1

6 3

0 6

3 0

7 4

A nM 0

1 1

2 0

0 1

2 2

0 1

1 2

n f D e

0 0

1 1

1 2

2 2

2 vA 1

1 1

1 3

1 1

Ja C

CCb C

f3 l3l l

l i

l

TAP T.E B-6 (Con t. )

cot!CPflTRATIOtIS OF P.19A IMITTERS Ill AIR PARTICill.ATPS 8

Re stilt s in Unit.5 of 10 pCi/m 12 s bJina STATIOrt !!O.

START STOP DATI:

DATP Tit-AP-lS2 T' t-AP-2 S 3

'm-AP P Sl Tf *- AP-5Al T"-AP-?2III A'.' " ' I T" 6-20-75 7-05-75 6117 56 7 5317 50i9 6118 5(11?

7-05-75 7-12-75 1614 6218 46i7 4216 2717 4 ? i: "

7-12-75 7-19-75 3516 33 6 1814 3216 3017 2' !14 7-]9-75 7 75 11 4 2016 26i5 04136 12 6 2714' 7-26-75 C-02-75 1615 3213 42114 3917 351C 3?il5 8-02-75 0-09-75 3116 2618 3016 90142 2716 3ri45 P-09-75 8-16-75 3416 2117 3016 3417 4417 3ri? 7 e-16-75 0-23-75 2a 6 2117

-30i7 26i6 3016 26t'0 0-23-75 e-30-75 1415 2617 1916 90 42 20 6 30 t.t 3 n-20-75 9-o r-7 5 2115 20i4 2416 1014 2015 1910 9-06-75 9-13-75 1615 2015 20 6 1915 2215 20fr 9-13-75 0-20-75 80136 86!29 2015 60136 2015 4]i6 9-20-75 9-27-75 1615 20i6 1716 16i4 1514 25150 9-27-75 10-04-75 11 S

l'S

15t4 1915 22t7 2017

(~

!!o sample, purp inoperative C3 CJ C

DJ

f TABLM E-R (Co n t. )

t I

COMCrttTRATIntfS OF PPTA TMIT'!TRS It! A7.R PARTICtfLATUS Results in Units of 10~3 pCi/ :i' i 2 sigma STATIOFI !!O.

STA f t*

STOP DA'll:

DATC T!1-AP-lS2 Ttt-AP-2S 3 T!!-AP-CSl

'nt-AP-5 A l TM-AP-12nl AVI:i'I.cn 10-04-75 10-11-75 73139 25116 1915 94!37 2(15 3515 10-11-75 30-13-75 22i4 21t6 2516 19 14 1715 2.7i10 10- 1 f1- / 5 10-25-75 1514 2416 1315 2616 2215 22110 10-25-75 13-01-75 90140 84152 771:4 10 4 16i5 41i?6 11-01-75 11-06-75 33110 2019 22 7 1417 2217 721]?

3i-06-75 11-13-75 1314 1216 1715 1319 23!6 171r 9

N 11-13-75 11-20-75 2615 94150 14t4 2215 2615 72i*7 13-20-75 31-2C-75 2010 2617 2215 90142 2216 301'2 31-26-75 12-03-75 tis

16iG 85!30 2115 1715 3715 l?-03-75 12-10-75 1717 T5**

11i4

<3**

Ifi5 2 n ? l r.

12-10-75 12-17-75 2015 15130 1015 10 14 2415

'a':

12-17-75 12-24-75 1J15 2113 1716 2616 2616 211:

12-24-75 12-30-75 16_5 3217 1415

<4**

1315

] Sit AvrnAGn 30i46 32148 20137 29159 25 21 2912e C'

fio sarole, pump inoperativo C;

Iwcult not included in average; sample vol ure in question CO I

CO CJ i

Q C

(N N

M A

m N.

1 1

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C J

b d

C C

c' CM t.

f 'r f:

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+i

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C C

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C G

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l TANT.E P-10 cot!CEt'TRATIOriS OF I-131 It! PIT.TERED AIit 3

Pasults* in tinits of 3 ff' pCi/m STA RT STOP STATIOil 110.

DASU DATE Tit-AI-IS2 Tf1-AI-3S1 Tit-AI.5Al T:1-AI-15G1 6-2 C -7 5 7-05-75

<a

<0

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<R 7-05-75 7-12-75

<a

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<3

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<7 7-19-75 7-26-75

<8

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<9

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<n

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< 10 R-09-75 U-17-75

< 10

<10

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3-;e-75 7-27-75

< 11

<5

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<3 n-23-75 8-30-75

<8

<9

<7

<7 9-30-75 9-06-75

<7

<7 9-06-75 9-13-75

<7

<3

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<7 9-13-75 9-20-75

<7

'10

<3

<7 9-20-75 9-27-75

< 10

<10

<7

<8 9-27-75 10 - 0 <1 - 7 5 I:S**

<7

<7 Resultn corrected for decay to uampling stop date

!!o sampic, pinne inoperativo O 'e L^l

1 G

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to to to to STATIOt! !!O.

7-26-75 3-30-75 10-04-75 12-24-75 AvrRAcr CONTROL LOC %TIOMS Tit-In-Ir1 6.010.6 6.210.2 6.410.3 6.210.3 6.210.3 Ttt-ID-7P1 7.210.2 7.710.2 7.410.4 7.AiO.2 7.410.4 T;t-In-4G1 5.5 0.2 5.010.3 5.710.0 5.010.3 5.710.3

- '-I n- 0C 1 5.710.1 6.210.7 6.210.4 6.010.7 6.0!O.5 T"-ID-15G1 5.410.2 5.010.3 5.610.5 5.7io.2

5. 610. /.

T 1-ID-5111 5.510.4 5.1 0.4 4.7t0.0 5.?!0.4 5.]!O.7 I!!DICATOR LOCATInt!S TM-ID-IS2 4.010.4 5.210.6 5.410.3 5.510.5 5,310.5 Tit-ID-2S2 4.7to.4 4.410.2 4.710.4 4.010.5 4. r.+ n. 3 Tt'-ID-4 S 1 5.0t0,5 5.210.4 5.d10.2 5,310.3 5.?t6.3

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!1-ID-14C2 4.310.4 5.110.5 4.7tl.1 Tit-ID-2 6S1 5.2!n.2 5.5 0.1 5.4t0.3 5.820.3 5.510.5

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Y AVERAGP 5.211.4 5.4t1.5 5.311.4 5.511.4

5. 3 +.1. e k.

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DIS" IIP.U"'IO!! OP !!II.I'I5!C COPS 1?Ia'?:I!! PIVE ??II.ES CP T? tit!S PA!1r!

PA D!1

?!t'?!D ER FA fet l' Anti titIt'PI'R DI P.FCTIO!!

DISTA!!CE OF cot?S DIRI:CTIOtt DISTAt!CE O F C ot'S 3.1 70 ESr 3.8 45 4.9 1

ESE 4.3 23

!!E 2.3 17 ESE 4.5 34

!!E 4.4 45 SI:

1.4 43

!!P 4.1 85 SF 4.0 4P E!!P 1.0 35 SP 4.1 69 T.71E 2.5 1

SU 4.7 40 Et1C 4.2 36 SF 4.8 10 E!!E 4.4 80 S$ti 4.9 20 8

Et!E 4.5 40 St' 4.7 1

E!!r 4.0 63 HS11 4.0 2

0 0.0 2

USt1 4.4 1

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2.7 25 E

3.5 20 inn!

2.9 6

PSP

2. 3 29

!!!31 3.1 5

PSP 3.1 1

1G?!?

3.6 35 ESP 3.2 34 13!!!

4.2 1

ESP 3.6 33 CC Total flu @cr of Pa rms.

35

'rotal tiuniser of Milk Coirs 1095 Uu Cfl

ML19206A219

Text

SUMMARY

SUMMARY

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