ML20148D351
| ML20148D351 | |
| Person / Time | |
|---|---|
| Issue date: | 08/12/1980 |
| From: | Eadie G NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20148D348 | List: |
| References | |
| CON-FIN-B-2217, REF-WM-40 NUDOCS 8009160479 | |
| Download: ML20148D351 (11) | |
Text
@M Q' 3 UNITED STATES -
0.10WL -- 4 structures I
>0.05WL -- 5 structures'
>0.03WL -- 6 structures
>0.015WL -- 4 structures less than 0.015WL -- 12 structures l
0009160
Also, the Department of Housing and Urban Development (HUD) has become involved in requiring a grab-WL sampling at any structure in Edgemont prior to guarantying federal mortgage monies.
Therefore, in order to full;' assess all possible locations having elevated radiological conditions, the following programs, as shown in Figure 1, shall be conducted in the vicinity of Edgemont, South Dakota:
I.
Grab Working Level Measurenents (HUD/ EPA Protocol)
A grab (i.e., brief sampling time of about 5 minutes or a 10 to 20 liter volume.; sample to determine the radon progeny concentrations (in WL) should be completed using the Thomas method for analysis.
This grab WL sampling shall be conducted based on the hUD/ EPA protocol (see Enclosure 2) in the following manner:
1.
The structure must be in the " closed-up" condition (i.e., all doors and windows shut, and no. air conditioning or heating systems in operation) for at least 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> prior to sample collection.
2.
The grab WL sample shall be collected in the area of longest occupancy, e.g., the bedroom or finished basement area of a residence, or the main working area of a commercial building.
3.
If t% inside grab WL exceeds 0.033 WL, such a structure shall then be resampled.
If upon confirmation of a value in excess of 0.033WL, that structure shall be considered for the engineering assessment.
4.
11 the grab WL is between 0.01 and 0.033WL, a definitive gamma radiatun survey and/or soil sampling programs shall be completed as discussed below.
5.
If the grab WL is less than 0.010WL, the structure shall be cleared and will not require further radiological assessments.
(This is a preliminary value which is to be verified before program implementation.)
II.
Gam a Radiation Measurements A portable gamma survey meter (e.g., micro R meter ) shall be used to complete the gamma radiation measurements both inside and outside of the structure.
This survey meter shall be cross-calibrated with aPressurizedIonizationChamber(PIC)inorderto'providerealistic exposure measurements.
This survey shall be designed to detect the presence of any possible residual radioactive material under, within or around the structure.
A map shall be provided indicating all locations having above background radiation levels.
This survey need only be performed once for each structure.
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I
, 1 III. Long-term Radon Progeny sampling Long-term radon progeny sampling using either the Radon Progeny Integration Sampling Unit (RPISU) or the lleasurement of Daughters
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(MOD) sampling unit may be required in any structure having a grab WL in the range 0.01 to 0.033WL and a radiation survey indicating the presence of residual radioactive material or an exposure rate less than 20 pR/hr above background.
Such long-term rajon progeny samples shall be collected for at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, every other month, for at lease six samples during a yearly cycle.
IV.
Soil Sampling Soil sampling, both surface ~ and at depth, shall be completed at specified locations to detemine the concentrations of uranium decaychainseriesradionuclides(e.g., uranium, radium-226, thorium-230 and lead-210).
The lower limit of detection shall be at least 0.50 pCi/ gram of soil for radium-226 analysis, which may be used to detemine compliance to the regulatory standards.
Bore-hole logging to, determine the pre'sence of radium-226 at depths of up to 8 feet may also be required.
~
V.
Engineering Assessment An engineering assessment shall be completed at each stucture which exr.eeds the EPA's standards for uranium mill tailings cleanup (i.e., as proposed in 40 CFR 192 of an annual average WL greater
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than 0.015, or having. radium in, soil greater than 5 pCi/g, or a gamma radiation exposure rate in excess of background of 0.02 mR/hr). The assessment shall provide a detailed map of all residual radioactive materia 1 deposits and volume estimates.
Such information may be obtained by gamma radiation survey techniques, bore-hole logging techniques, or s. oil sampling and analysis.
VI.
Remedial Action /Ver.ifi. cation Program Remedial action shall be completed at any location where residual radioactivity has been identified and such material shall be removed and transported to the disposal site. A verification program shall be conducted which will utilize the same screening and measurement 4
i program that was initially used for identifying involved. structures and the verification program shall confirm that the EPA standards are met before any structure is finally clearert in this program..
.t Greg G. Eadie-anium Recovery Licensing Branch ivision of Waste Managment Approved by:
mp
/ Ross A. Scarano, Chief
Enclosures:
1.
Figure 1 2.
Interim HUD/ South Dakota Radiation Survey Protocol 4
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Greater Than or Equal to 0.033 WL I
Greater Than 0.01 WL iRAB SA!4PLES st * "Ofl P ROGE!! Y to less Than 0.033 WL s
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XI AIR F ILTERS IKORKlilG LEVELS) ').01 WL or less2
'llVD/ EPA Protocol Preliminary value to be verified before pr Anomaly may be natural terrestrial radioac The same screening and measurement progran confirm EPA Standards are met before a str
FIGURE 1 REMEDIAL ACTION PROGRAM FOR EDGEMONT, SOUTil DAKOTA
.Nd tvity REMEDIAL ACTION
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VERIFICATION ENGINEERING ASSESSMENT PROGRAM x
4
- GAMMA MAPPING
- SOIL SAMPLING No Residual
- y 90RKING LEVELSJ I
g're
- BORE It0LF,_ LOGGING.
Radioactivityf NO ACTION p
"P er n
0.033 til.
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lESAMPLE INDOOR i
Momay ;)
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lADON DAUGHTERS l0 CONFIRM j
STATE CONSIDERATION Areas Where soll 226Ra, is 5 pC1/g or More Confirmatory Grab I> ample Less Than 0.033 WL T/
COLLECT soll
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CORE EAMPLES iAMMA RADIATION Gansna Dose Rate FOR 22fRA MAPPING SURVEY 20pR/hr or More
- % g Tg#
- e gt' l Areas Where Soll 226g 20 is less Than 5 pCilg.
4 e3 Term Radon' Progeny MAKE LONG-TERM
}Lon 0.0 5 WL or N re INDOOR RADON, PROGENY
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MEASUREMENTS.(RPISUJ 10 REMEDI AL ACTION Long-Term Radon Progeny.
Less Than 0.015 WL Iram implementation.
vity resulting in radiobgical exposure in excess of EPA Standards.
- hat is used for identifying involved structures would be repeated to -
- ture is finally cleared.
.i.
INTERIM HUD/50VIH DAKOTA PADIATION SUREY PR070 COL f
FEBRUARY 1980 4
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CRITERIA Basic-criteria adopted for the South Dakota /HUD radiation level certification program will be drawn from two established sources.
A.
U.S. Surgeon General's Guidelines -for Grand Junction, Colorado, dated July 27, 1970.
B.
U.S. Environmental Protection Agency's F.ec:=er. cations to the State of Florida,. dated June B,1979.
Criteri'a !!
Any weighted. indoor Working Level (WWL) devrmined i:. M sbove 0.02 VL (including background) shall be classif+
- i as exceei't.; that level the Administrator of the EPA has found acceptable ir, terms of the increased long term risk of lung cancer in the exp:se:: ;:p;1Etion.
See Note below.
Criteria #2 If a weighted indoor working leN1 measuremant exceeds 0.0;5 UL, an additional set of measurements shall be made on another dz/ to verify such a reading to determine acceptability of existing resice.:Es.
All measurements taken will be averaged to determine the *,7.-lL.
Hote: When annual average air concentrations of r:dcr. decay products.
are less than 0.02 WL, remedial action reo,uired to re:uce such concentrations to as low as reasonably achievadie levels should be taken.
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METHODOLOGY )
4 (Forexistingresidences)
In. determining acceptability of a residence for federally su:::r:ed financing in Edgemont, South Dahe:a and vicinity, the State wili periors indoor radon daughter measurements in the following manner:
- 1
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Tcr et:h measurement an air sample having a minimum volume of 1.
j 20 li.ters will be drawn through a 25 millimeter Millipore Type AA.
filter having a pore size of 0.80 microns.
After an.apprcpriate
- l period of decay, the filter will be counted for alpha activity The radon daughter concentration in
- j vi:5 a scintillation counter.
Working Levels (WL) will.be calculated and recorded.
~
A H;use' Closed Reading (HCR) shall be made in a ground. floor or 2.
re:m af ter the residence has been sealed for a minimum basemen:
period of three (3) hours.
Sealed means that all. windows, doors, ar.d :: side vents are closed. To make the measurement, The State Officer will enter the residence, opening the entry dcor only to that equipment and stcff may enter.
Jf the HCR exceeds the exter.:
0.02 UL, then a House Open Reading (HOR) will be taken.
The House Open Reading will be made in the same location where the 3.
The HDR will be made while the room is being venti-HCR was taken.
a n:rmal level using available doors, windows, fans, etc.,
la:ed a:
that supply fresh outside air.
Such ventilation shall be in use for.
a minimum of 15 minutes before the HOR is taken.
Weich:ine procedure:
-.Each reading (HCR and HOR) will receive the following weighting:
7/12 HCR + 5/12 HOR = WWk The L".0. shall then be used to certify P. given resident's' acceptability In the Edgemont area for fur:her federal financing consideration.
seven months are chosen a.1 precluding the use of outside ventilation due tc inclement weather.
The weighted indoor working level procedure may be bypassed by making a " house closed reading" to maximize conditions (worst case) to deter-4.
cine acceptability directly if the working level determination falls 1
below 0.02 WL.
An alternate method of determining acceptability of a residence is th2 use of data acquired by measurement with a Radon Indoor Progeny.
[
5.
Integrating Sampling Unit (RIP 15U).
RIP 150 dcta wi)1 be derived RI?35U data acquired in f r:m a minimum sampling time of 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />.
~
the period between November 15 and April I ctn be substituted for RIP 15U data acquired between June I and September 30 can the HCR.
be substituted for the HOR.
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(ForUndevelopedYacantLand)
Future raciatien exposures in~ structures built on a given' tract of,
land can be influenced by certain conditions.
Thesi. can be.largely.
characterized by answering the followir.g questions.
1.
Is the land mineralizid with geological formations.that contain '
uranium, decay chain elements in varying amounts.?
~ 2.
Is.the.under1fing'geolocy.ssificier.ily disturbed by fiact0 ring, tunneling cr;other perturbations -which:can enhince radon seepage t
and diffusign.to the ground's surface?
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Has the inv.: icv-d tra': of land b6pn reclaid.ed,' graded 'or previously -
2.
impacted wit 6'decesits of phosphate end/or copper slag. that contains-uranium decay,cnain elemer.,ts in va~ryinc amounts?
4.
Will the buiidi:.j materials usid in's'ubsequen't,' construction of-a structure c6 a ';iven ract' cf vacant land contain a sufficiently low enoucn level of uranium decay chain elements?
(Normally, this is-tne case if non-wasts. materials are used 'in fabric'ation of building 'miterial s,. ).
-In deter:fr.krig ac:'dptabilit[of i'given tr'adi of land for its utili-
- aticr. as a federai',y fir. anted _ project site in Edgemont, South Dakota -
and vicinity, the State wi]) handle each evaluation znd certification on a casa by case basis, Tr.is is d. t to the complex,ity of. par,ay.eters. t. hat.need i
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2 to be considered 'in the process.
Methods that can' be employed by the State to perform these evalua-tions will normally include:
1.
gamma scintillometer grid surveys; 2.
surface ' soli s;mpiing and ground coring for radironalytical deter-r.a nations ;
charconi chnister or scinti11ation cell renitoring of radon diffusion 3.
and seepage to ground surfaces; 2.
use ci aerial r6dicmatric or other radioanalytical data to determine existing back;round gamma radia: ion.
Sae Figures 1 and 2 for clarifying data, definitions and depictions concerning this protocol.
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