ML19256F025
| ML19256F025 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/06/1979 |
| From: | Battist L, James Buchanan, Congel F Office of Nuclear Reactor Regulation, NRC OFFICE OF STANDARDS DEVELOPMENT |
| To: | |
| Shared Package | |
| ML19210C879 | List: |
| References | |
| NUREG-0558, NUREG-0558-DRFT, NUREG-558, NUREG-558-DRFT, NUDOCS 7911200304 | |
| Download: ML19256F025 (98) | |
Text
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v POPbLATION DOSE AND HEALTH IMPACTOF THE ACCIDENT AT THE THREE MILE ISLAND NUCLEAR STATION Preliminary Estimates Prepared by the Ad Hoc Interagency Dose Assessment Group
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U. S. Nuclear Regulatory Commission 1577 158 7911200 D
NUREG-0475 RADIOLOGICAL ENVIRONMENTAL
=
MONITORING BY NRC LICENSEES FOR RdUTfNE OPERATIONS OF NUCLEAR FACILITIES L
Task Group Report pa nc f.
A I
i Office of Standards Development U.S. Neclear Regulatory Commission 1377 159
.~.
---Branch Technical Position B0ckn rou_n_d P,egulatory Guide 4.8, Environmental Technical Specifications for Nuclear Power Plants', issued for comment in December 1975, is being revised based on comments received.
The Rcdiological Assessment Branch has developed the following Branch Position on the radiological portion of the environ-mental conitoring program.
The position was fornulated by an NRC working group v.hich consicered cercments received af ter the issuance of the Regulatory Guide 4.8.
10 CFR Parts 20 and 50 require that radiological environmental monitoring programs be established to provide data on measuraole levels of radiation and radioactive materials in the site environs.
In addition, Appendix I to 10 CFR Part 50 requires that the relationship between quantities of radio-active material released in effluents durir.g normal operation, including anticicated operational occurrences, and res11 tant radiation doses to in-dividuals fren princioals cathways of exposure be evaluated.
These pro-c:c s snculd be conducted to varify the effect.veness of in plant T.casures u:e; fc' con ccilir.; tre release of radioactive Ta:er.ais.
S u r c e i i l ar.c s should be estsui:sbe: ta icentify changes in the use or u rest:ic ec creas (e. g., fc: a; icultural purposes) to orovice a basis for acci ficatier.s in
- - renitei..; c::;ra s for evalcating deses to inJ: id al s f c;m : r i r.:ipal patt.vays of ex:cstre.
NEC Regulatory Gu:ce 4.1, 'iev 1,
9r:gra.3 for M: n to: ing h_ica:.ivi;) in the Encirons of.uclcar -
tr Plants." arov: cs a
accc ;:ble pasis fe: the desico of prcgrams to T.:.ni; r le.cis of racia-tici anc_recica:;ivi y in the static. ent.: ens.
This pcsition se:3 ferth an exarole of an acceotable T,inir. radiol:gical m:nitoring pro; ram.
Local site characteristics must be exa ined to cete::.iine if path;.ays no covered by this guide may significantly con;cibute to an ir.dividual's casc'and shculd be included in the scmpiin; pecgra?
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m A A.UAL 1377 160
AN ACCEPTABLE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Program Recuirements Environmental samples shall be g lected and analyzed according to Table 1 at locations shown in Figure 1.
Analytical techniques used shall be such that the detection capabilities in Table 2 are achieved.
The results of the radiological environmental monitoring are intended to supplement the results of the radiological effluent monitoring by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measure-nents and modeling of the environmental exposure pathways.
Thus, the specified environmental monitoring program provides measurements of radiation and of radioactive materials in those exposure pathways and for those radio-nuclides which lead to the highest potential radiation exposures of indivi-duals resulting from the station operation.
The initial radiological environ-mental monitoring program should be conducted for the first three, years of commercial operation (or other period corresponding to a maximum burnup in tne initial core cycle).
Following this period, program changes may be proposed based on operational experience.
The specified detection capabilities are state-of-the-art for routine environmental measurements in industriai laboratories.
The LLDs far I 101 in water, milk and other food procucts correspond to one quarter of the Appendix I (10 CFR Part 50) cesign oojective cose equivalent of 15 mrem /yr for atmospheric released and 10 mrem /yr for liquid releases to the most sensitive organ anc age group.
They are based on the assumptions given in Regulatory Guide 1.109, Rev 1.
Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons.
If specimens are unobtainaole due to sampling equipment malfunction, every effort shall be made to ccmplete corrective action prior to the end of the next sampling period.
All deviations from the sampling schedule shall be documented in the annual report.
The laboratories of the licensee and licensee's contractors which perform analyses shall participate in the Environmental Protection Agency's (EPA's)
Environmental Radioactivity Laboratory Intercomparisons Studies (Crosscheck)
Program or equivalent program.
This participation shall include all of the
-^ It may be necessary to require special studies on a case-by-case and site specific basis to establish the relationship between quantities of radioactive material released in effluents, the concentrations in environmental media, and the resultant doses for icportant pathways.
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determinations (sample medium-radionuclide combination) that are offered by EPA and that also are included in the monitoring program.
The results of analysis of these crosscheck samples shall be included in the annual report.
If the results of a determination in the EPA crosscheck program (or equivalent program) are outside the specified control limits, the laboratory shall investigate the cause of the problem and take steps to correct it.
The results of this investigation and corrective action shall be included in the araual report.
The requirement for the participation in the EPA crosstneck program, or similar program, is based on the need for independent checks on the precision and accuracy of the measurements of. radioactive material in environmental sample matrices as part of the quality assurance program for environmental monitoring in orcer to demonstrate that the results are reasonably valid.
A census shall be conducted annually during the growing season to determine the location of the nearest milk animal and nearest garden greater than 50 sq. meters (500 sq. ft.) producing broad leaf vegetation in each of the 16 ceteorological sectors within a distance of 8 km (5 miles).2 For elevated releases as defined in Regulatory Guide 1.111, Rev. 1.. the census shall also identify the locations of all milk animals, and gardens greater than 50 sq. meters procucing croad leaf vegetation out to a distance of 5 km. (3 miles) for each radial sector.
If it is learned from this census that the milk animals or gardens are pre-sent at a location whicn yielcs a calculated thyroid dose greater tnan tnose previously sampled, or if the census results in changes in tne location usea in the radioactive effluent technical specifications for dose calculations, a written report shall be submitted to the Director of Operating Reactors, NRR (with a copy to the Director of the NRC Regional Office) within 30 days identifying the new location (distance and direction).
Milk animal or garden locations resulting in higher calculated doses shall be added to the surveillance program as soon as practicable.
The sampling location having the lowest calculated dose may then be dropped from the surveillance program at the end of the grazing or growing season during which the census was conducted.
Any location from which milk can no longer be obtained may be dropped from the surveillance program after zBroad leaf vegetation sampling may be performed at the site boundary in a sector with the highest D/Q in lieu of the garden census.
D**D
]D ]1 b eJL so 1377 162
notifying the NRC in writing that they are no longer obtainable at that location.
The results of the land-use census shall be reported in the annual report.
The cen$us of milk animals and gardens producing broad leaf vegetation is based on the requirement in Appendix I of 10 CFR Part 50 to " Identify changes in the use of unrestricted areas (e.g., for agricultural purposes) to permit modifications in monitoring programs for evaluating doses to individuals from principal pathways of exposure." The consumption of milk from animals grazing on contaminated pasture and of leafy vegetation con-taminated by airborne radiciodine is a major potential source of exposure.
Samples from milk animals are considered a better indicator of radiciodine in the environment than vegetation.
If the census reveals milk animals are not present or are unavailable for sampling, then vegetation must be sampled.
The 50 sq. meter garden, consicering 20% used for growing broad leaf vege-tation (i.e., similar to lettuce and cabbage), and a vegetation yield of 2
2 kg/m, will produce the 26 kg/yr assumed in Regulatory Guide 1.109, Rev 1., for child consumption of leafy vegetation.
The option to consider the garden to be broad leaf vegetation at the site boundary in a sector with the highest D/Q should oe conservative and that location may be used to calculate coses due to radioactive effluent releases in place of the actual locations which would be determined by the census.
This option does not appiy to plan.s with elevated releases as defined in Regulatory Guide 1.111, Rav. 1.
Reoortino Recuirement A.
Annual Environmental Operating Report, Part B, Radiological.
A report on the radiological environmental surveillance program for the previous calendar year shall be submitted to the Director of the NRC Regional Office (with a copy to the Director, Office of Nuclear Reactor Regu}ation) as a separate document by May 1 of each year.
The period of the first report shall begin with the date of initial criticality.
The reports shall include a s,ummarv (format of Table 3,
interpretations, and stst':ti:C m.C _J.::f'5f the resu radiological environmental surveillance activities for the report
' P.J period, including a comparisen with operational controis, preoperat anal studies (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the station operation on the environment.
In the event that some results are not available the report shall be submitted noting the explaining the reasons for the missing results.
The missing data shall be submitted as soon as possible in a supple-mentary report.
Dd**D *3DTlb 1377 163 M
The reports shall also include the following:
a summary description of the radiological environmental monitoring programjfecluding ;smp ?ag
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- aMh-s-air.p re i.yp e, s ue and phy h : 3 ractr':t N d w h r W e type, s' " : p r ;p ete t. 6 ir.e u m, aus'.fuca+-mete, W sasuring
<eqd4; c-t used; a map of all sampling locations keyed to a table giving distances and directions from one reactor; the results of land use censuses; and the results of licensee participation in the Environmental Protection Agency's Environmental Radioactivity Laboratory Intercom-parisons Studies (Crosscheck) Program.
B.
Nonroutine Radiological Environmental Operating Reports "If a confirmed 3 measured radionuclide concentration in an environ-mental sampling medium averaged over any quarter samoling period exceeds the reporting level given in Table 4, a written report shall be submitted to the Director of the NRC Regional Office (with a copy to the Director, Office of Nuclear Reactor Regulation) within 30 days from the end of the quarter.
If it can be demonstrated that the level is not a result of plant effluents (i.e., by comparison with control station or preoperational data) a report need not be submitted, but shall be discussed in tne annual report.
When more than one of the radionuclides in Table 4 are detected in the medium, the reporting level shall have been exceeded if:
concentration (1) concentration (2)
~~
7 3
reporting level (1) report;ng level (2)
If radionuclides other than those in Table 4 are detected and are due frcm plant effluents, a reporting level is exceeced if the potential annual cose to an individual is ecual to or greater than the design objective doses of 10 CFR Part 50, Appendix I.
This report shall includa an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the anomalous result.
"A confirmatory reanalysis of the original, a duplicate, or a new sample may be desirable, as appropriate.
The results of the confirmatory analysis shall be completed at the earliest time consistent with the analysis, but in any case within 30 day 5.
1377 164
=
I Alll E 1 OPERAT10tlAL RADIOLOGICAL ENVIR0tillEllTAL t10NITORING PROGRAM a
Exposure Pathway t{ umber of Samples Sampling and Type and. Frequency and/or Sample and Locations Collection Frequency" and Analysis AIRBORilE Radioiodine and Samples frem 3 offsite locations (in Radioiodine Cannister:
Particulates different sectoPs) of the highest analyze weekly for calculated annual average ground-I-131 level D/Q.
1 sample from the vicinity of a Continuous sampler Particulate Sampler:
community having the highest operation with sample Gross beta radio-calculated annual average ground-collection weekly or activity folloging level D/Q.
as required by dust filter change, composite loading, whichever is (by locagion) for gamma more frequent" isotopic quarterly 1 sample from a control location 15-30 km (10-20 miles) distant and d
in the least prevalent wind direction I
DIRECT RADIATIOi1 2 or more dosimeters or one in-11onthly or quarterly Gamma dose monthly or strument for measuring and record-quarterly ing dose rate continuously to he placed at each of the same loca-tions as for air particulates, and at each of three additional offsite locations (different sectors) or highest calculated annual average ground-level X/Q.
LN N
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TAlli.E 1 (Continued)
I Exposure Pathway flumber of Samples"'
Sampiing and Type and Frequency and/or Sample and Locations Collection Frequency of Analysis WATERBORilE Surface 9 1 sample upstream Composite sample Gamma isotopic analysis 1 sample downstream one-month period 'yer monthly.
Composite for h
tritium analyses quarterly Ground Samplesfrom1or2sourgesonly Quarterly Gamma isotopic and if likely to be affected tritium analysis quarterly Drinking 1 sample of each of 1 to 3 of Composite sample I-131 analysis on each the nearest water supplies which over two-week period; composite when the dose could be atfected by its if I-131 anlysis is calculated for the con-discharge performed, monthly sumption of the water composite otherwise is greateg than 1 mrem per year.
Composite for Gross l1 and gamma isotopic analyses n'onthly.
Compo-site for tritium analysis quarterly 1 sample from a control location Sediment from I sample from downstream area Semiannually Gamma isotopic analyses Shoreline with existing or potential semiannually recreational value It4GESTI0tl Milk Samples from milking animals Semimonthly when ani-Gamma isotopic and I-131 in 3 locations within 5 km mals are on pasture, analysis semimonthly when distant having the highest dose monthly at other times animals are on pasture; U
potential.
If there are none, monthly at other times.
[
- then, 1 sample from milking animals in each of 3 areas between 5 to 8 km distant where doses are calculated to be greater than 1 mrem per year
TABLE 1 (Continued)
Exposure Pathway flumber of Samples Sampling and k Type end Frequency and/or Sample and Locations Collection Frequency
_ of Analysis a
Mil k (cc.nt'd) 1 sample from milking animals at a control location (15-30 km distant and in the least prevalent wind directioq)
Fi.h and 1 sample of each commercially and Sample in season, or Gamma isotopic Invertebrates recreationally important species semiannually.if they are analysis on edible in vicinity of discharge point not seasonal portions 1 sample of same species in areas not influenced by plant discharge Food Products 1 sample of each principal class At time of harvest)
Gamma isotopic of food products from any area analysis on edible which is irrigated by water in portion.
1-131 which liquid plant wastes have analysis on broad been discharged leaf vegetation 3 samples of broad leaf vegetation Monthly when available grown nearest offsite locations of hi hest calculated annual 0
average ground-level D/Q if milk sampling is not performed 1 sample of each of the similar Monthly when available vegetation grown 15-30 km distant in the least prevalent wind direction if milk sampling is not performed u
N N
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MJ TABLE 1 (Continued) 6._3 "The number, media, frequency and location of sampling may vary from site to site.
It is recognized that, at times, EEL.)
it may not be possible or practical to obtain samples of the media of choice at the most desired lo' cation or time.
In these instances suitable alternative media and locations may be chosen for the particular pathway in. question bd and submitted for acceptance.
Actual locations (distance and direction) from the site shall be provided.
Refer y
to Regulatory Guide 4.1, " Programs for Monitoring Radioactivity in the Environs of thiclear Power Plants."
bParticulate sample filters should be analyzed for gross beta 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and b thoron dau0hter decay.
If gross beta activity in air or water is greater than ten times the4mean of control samples for any medium, gamma isotopic analysis shou'Id be performed on the individual samples.
y'd }
CCamma isotopic analy:is means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility, d The purpose of this sample is to obtain background information.
If it is not practical to establish control loce tions in accordance with the distance and wind direction criteria, other sites which provide valid background data may be substituted.
" Canisters for the collection of radioiodine in air are subject to channeling.
These devices should be carefully checked before operation in the field or several should be maunted in series to prevent loss of iodine, fRegulatory Guide 4.13 provides minimum acceptable performance crite-ia for thermoluminescence dosimetry (TLD) systems used for environmental monitoring.
One or more instruments, such as a pressurized ion chamber, for measur-ing and recording dose rate continuously may be used in place of, or in addition to, inte0 rating dosimeters.
For the purposes of this table, a thermoluminescent dosimeter may be considered to be one chip, and two or more chips in a packet may be considered as two or more dosimeters.
9The " upstream sample" should be taken at a distance beyond significant influence of the discharge.
The "down-stream" sample should be taken in an area beyond but near the mixing zone.
"Upstreau" samples in an estuary must be taken far enough upstream to beyond the plant influence.
hCenerally, salt water is not sampled except when the receiving water is utilized for recreational activities.
i Composite samples should be collected with equipment (or equivalcnt) which is capable of collecting an aliquot at time intervals which are very short (e.g., hourly) relative to the compositing period (e.g., monthly).
5Groundwater samples should be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge propert.ies are suitable for contamination.
- The dose shall be calculated for the maximum organ and age group, using the methodology contained in Regulatory b Guide 1.109, Rev.
1.,
and the actual parameters particule to the site.
Nj w If harvest occurs more than once a year, sampling should be performed during each discrete harvest.
If harvest occurs continuously, sampling should be monthly.
Attention should be paid to including samples of tuborous and root food products.
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TABIE 2 Detection Capabilities for Environmental Sample Analysis Lower Limit of Detect. ion (LLD)U
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Airborne Particulate Water or Gas fish fli l k Food Products Sediment 3
Anaysis (pCi/1)
(pCi/m )
(pCi/kg, wet)
(pCi/1)
(pCi/kg, wet)
(pCi/kg, dry) gross beta hc
-2 1
10 3
11
.-330 54ttn 15 130 g
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3 59Fe 30 260
(<
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65 M
Zn 30 260 95 G
Z r-fib 10' /5 131; Od '
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d a
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-2 Cs 1 x 10 130 15
'80[ '
150 O
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TABLE 2 NOTES
" Acceptable detection capabilities for thermoluminescent dosimeters used for environmental measurements. are given in Regulatory Guide 4.13.
bTable 2 indicates acceptable detection capabilities for radioactive materials in environmental samples.
These detection capabilities are tabulated in terms of the lower limits of detection (LLDs).
The LLD is defined, for purposes of this guide, as the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95?; probability with only 5?; probability of falsely con-cluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
4.66 s b LLD =
E V 2.22 exp(-M )
Y where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume) s is the standard deviation of the background counting rate or cf bthe counting rate of a blank sample as appropriate (as counts per minute)
E is the counting efficiency (as counts per disintegration)
V is the sample size (in units of mass or voluce) 2.22 is the number of disintegrations per minute per picocurie Y is the fractional radiochemical yield (when applicable)
A is the radioactive decay constant for the particular radionuclide At is the elasped time between sample collection (or end of the sample collection period) and time of counting The value of S used in the calculation of the LLD for a particular measure-s ment system sh3uld be based on the actual cbserved variance of the back-ground counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicated variance.
In calculating the LLD for a radionuclide determined by garma-ray spectrometry, the backgrounri should include the typical contributions of other radionuclides normally present in the samples (e.g., potassium-40 in milk samples).
Typical values of E, V, Y and at should be used in the calculation.
1377 171
It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement.*
CLLD for drinking water.
d 131 LDs. for I in water, milk and other food products correspond to one-
, uarter of the Appendix I.(10 CFR Part 50) design objective dose-equidiel
,/of 15' arem/ year for!,atmo, spheric'. releases and 10 mr,er6/yr for\\ liquid release)t
/
s to ithe'most sensitive organ and age group using therasssumptions-giIen in l
Re'
~ gulatorv Guide 1.109', Rev. 1.
i
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6 LLD for leafy vegetables.
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/
a
- For a more complete discussion of the LLD, and other detection limits, see the following:
(1)
HASL Procedures Manual, HASL-300 (revised annually).
(2)
Currie, L.
A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968).
(3) Hartwell, J.
K., " Detection Limits for Radioisotopic Counting Techniques," Atlantic Richfield Hanford Company Report ARH-2537 (June 22, 1972).
1377 172
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TAHiE 3
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EtNIR0f1MEilTAL RADIOLOGICAL 110tliIORIf1G PROGRAtt A!1tlVAL SUMf1ARY 6
3 flame of Facility
_ _ Docket tio.
33 0) location of Facility Reporting Period ~
bs c3 (County, State)
W D
Medium or Type and Lower Limit All Indicator Location with lii hest Controllocatfons Number of 3
0 L cation Annual flean flean (f) fionroutine b Pathway Sampled Total fiumber of Mean (f)g Mean (f)t, Range Reported a
(Unit of of Analyses Detection flame Measurement)
Performed (LLD)
Range Distance &
Range Measurements Direction Air Particu 3) lates (pCi/m Gross p 416 0.01 0.08(200/312) Middletown 0.10 (5/52) 0/08 (8/104) 1 (0.05-2.0)
S miles 340 (0.08-2.0)
(0.05-1.40) y-Spec. 32 137 0.01 0.05 (4/24)
Smithville 0.08 (2/4)
<LLD 4
cS (0.03-0.13) 2.5 miles 160 (0.03-2.0) 131 0.07 0.03 (2/24)
Podunk 0.05 (2/4) 0.02 (2/4) 1 g
(0.01-0.08) 4.0 miles 270 (0.01-0.08)
Fish pCi/kg (wet weight) y-Spec. 8 u
137 130
<LLD
<LLD 90 (1/4) 0 Cs y
N 134 130 GLD
<LLD
<LLD 0
Cs
[
60 130 120 (3/4)
River flile 35 See Column 4
<LLD 0
Co u
(90-200)
D See Table 3, note b.
bilean and range based upon detectable measurements only.
Fraction of detectable measurements at specified locations is indicated in parentheses.
(f) c!ote:
The example data are provided for illustrative purposes only.
t
Y (L _.3 TAllt.E 4 O
Me)
REPORTIllG LEVELS FOR fl0llR0lHIllE OPLRATIllG REPORTS k
U Reporting level (RL) g Broad Leaf g
Water Airborne Particulate Fish Milk Vegetati6n Analysis (pCi/l) or Gases (pCi/m )
(pCi/Kg, wet)
(pCi/1)
(pCi/Kg, wet)
M 3
N A
4 h
11-3
/ x 10 3
4 Mn-54 1 x 10 3 x 10 2
4 Fe-59 4 x 10 1 x 10 4
3
, Co-58 1 x 10 3 x 10 2
4 Co-60 3 x 10 1 x 10 2
4 Zn-65 3 x 10 2 x 10 2
Z r-lib-95 4 x 10 2
I-131 2
- 0. 9 '
3 1 x 10 3
3 Cs-134 30 10 1 x 10 60 1 x 10 3
3 Cs-137 50 20 2 x 10 70 2 x 10 2
2 b)
Ba-La-140 2 x 10 3 x 10
,.. s c -
s s
j ).<. e w
f / )',.
n,,,j..
I ' 'l-h o a f:. '
x..
.p I_..
w.
N (l ) Je h I ('* vj>an :.] a,,.' ci!a ea.y./. (Tv
~
~
N
Figure 1 (This figure shall be of a suitable scale to show the distance and direction of each monitoring station.
A key shall be provided to indicate what is sampled at each location.)
1377 175
.