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MEMORANDUM FOR: Don Cool, Section Leader Programatic Safety Section Operations Branch FROM:
Leland C. Rouse Chief Fuel Cycle Safety Branch Division of Industrial and Medical Nuclear Safety, NMSS
SUBJECT:
FACILITY RELEASE CRITERIA The input from IMSB on the number of facilities released and the criteria used is provided below. Note that these numbers are for recent releases (last 7-8 years) and does not inc hde facilities that may have been releasJd by the rsgions.
The criteria generally used by IMGB for releasing facilities for unrestricted use are cnntained in two docurr. eats, Theses documents are (1)
- Guidelines for Decontamination c,f Facilities and Equiptaent Prior to Release for Unrestricted Use or Teminatien of Licenses for By-product, Source, or Special Nuclear Material" and (2) Disposal or Or. site Storage of Residual Thorium or Uranium (Either as Natural Ores or Without caughters Present) frem Pest Operetions."
Copies of both are enciesed. The guideltres have been used to relrase on the order of 20 facilities or buildings that processed natural U or Th, Pu, enriched V or e pleted U.
There are also on the order of 10 facilities or buildings that release is pending the confinnatory survey or the removal of residual contamination.
The criteria in the second document has been used to release land or soil on the order of 10 times.
In addition, over 10 requests for release using those criteria are pending.
Occasionally site specific criteria are established such as those in enclosure 3.
. L4-(
Leland C. Rouse, Chief Fuel Cycle Safety Branch Division of Industrial and Medical Nuclear Safety, NMSS
Enclosures:
1 Guidelines for Decontamination...
2 Disposal or Onsite Storage...
3 foil Decontamination Criteria for the Decomissioning of the UNC's Facility Lp-
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i October 5. 1781 SECY-61-!76 ZeWeYR W3 i (information)
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The Comissioners Fmm:
William J. Dircks
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Executiv'e Director for Operaticas
Subject:
DISPOSAL DR ONSITE STORAGE OF RESIDUAL THORI'JM Ok
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URANIUM (EITHER AS NATURAL DRES OR WITHOUT DAUmiTERS PRESE!4T) FROM PAST OPERATICNS Portese:
To infom the Comission of the adoption of a Branch Tecnnical Position for application by the drani'.c l
Fuel Licensing Branch.
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Discussion:
Some of the sites formerly used for processing thorium and uranium are known tocay to be contaminated with resicual radioactive materials.
In many cases, the total amount of contaminated soil is large, but the activity concentrations of radioactive materials present are sufficiently low as to justify their disposal en privately ownec lands or s:srage onsite rauer than transport them offsite to a licensed I
racicactive materials disposal (comercial) site.
In many instances, packaging ano transporting these wastes to a licensee cisposal site would be too costly and not justifiec from the stancooints of risk to the
't puolic health or cost-benefit. Furthermore, because cf the high volume of these wastes, Itmited commercial waste disposal capacity, and restrictions placed on rectiet of long-lived wastes at comercial sites, it is not oresently feasible to cispose of these wastes at comercial low-level waste disposal sites.
Effective January 28, 1981,. NRC regulations in 10 CFR 20 "Stancarcs f:r Protection Against Raciatien" were amencec (45 FR 7;76;-71762) to celete Section 20.204-nnien provicac general authority for disposal of radioactive i
material by burial in soil.
Under the amendec regulations
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ciscose of radioactive materials in nis manner unoer ce licensees must a:cly for and co iain soecific NRC a;creval to provisions of 10.OTR 20.302.
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The Commissioners '
Guidelines ~ for disposal or storage of low activity concentrations of tnorium and uranium or uranium ore bearing wastes on privately owned lands are neeoed to deal with the contaminated site cases wnich are presently pending (Enclosure 1). To this end, the staff has identified five acceptable options for disposal (under the provisions of 10 CFR 20.302) or onsite storage which the staff intends to apply in processing applications.
A summary discussion of these is provided in inclosure 2.
An expanded discussion is contained in Enclosure 4. discusses the technical betes for the derived contentratier limits for each of the four disposal ottices.
The approach used in establishing the concentration limits is consistent with that used in develebing the proposed new Part 61 concerning licensir.g requirements for land ciscosal of radioactive wastes. That proposeo rule is based on two assumptions that a buriel site may some say oe intrucac; anc that buried racietetive materials will not likely present a n'
danger to the public health and safety even if intruded.
In the case of uranium ore residues with caughters present, there will be limited radon emanations; however, witn the burial depths required, resultant surface fluxes will be rear background levels. Accorcingly, tne burial of radioactive materials covered by the Branch Tecnnical Position coes not present a danger to health and safety.
We celieve that the cotions for discosal or storage of thorium er uranium are fully consistent with discosal standares recommencec by IPA. We informally ciscussed the options witn EPA staff members and made some enanges to accommodate $ heir suggestions.
Before approving an soplication to cispose of thorium or uranium unoer cotions, 2, 3, or 4, we will solicit the a
views of appropriate State health officials on a case-by-case basis.
In this connection, we sent the States a copy of the proposed Branch Technical Position. Two States emumented; neitner of wnich were negative.
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The Comnissioners 3-l
< is a Feoerni Register notice which we plan to have published on tnis inatter.
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6v William J. Dircks Executive Director for Operations Inclosuru:
1.
Co!.taminated Site Cases Presently Pending 2.
Sumary of Disposal and Storaga Options 3.
Calculation of Allowable Concentrations for Four Disposal Options
- t.. Feceral gjster Notice I
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Contaminated Site Cases Presently Pencin; 1111 Disposal or Storage Oction that Nov Aeoly Stepan Chemical Company 2,3' Maywood, New Jersey (Trorium ore residues)
Kerr-McGee Corocration 5
Wes: Chicego, 1111nois (Thorium ore residues)
Mc3ean Chemical C: meany 4
Newburg Meignts, Chio (Ceple::: uranium; Amax Cor: oration 4 or 5 Darkersourg, 'nes Virginia (Thorium oxice mixec witn :irconium)
Cotter Corporation (former owner) 5 Lat:y Avenue St. Louis, Missouri (Uranium resicues)
Velsicol Chemical lf:rmerly Michigan Chemical:
A
$. L:uis, MiCniyan (Uranium, :ncrium an: racium cre wastes Ex:eo ':r a 'tw no: scots :nt:.111 neeg :: se remov,3 < rem
.x, site :ne ::ntjss. nation on a: joining croperty west of Hignway i7 accears ;c fali un:er cotions 2 or 3.
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SUMMARY
OF DISPOSAL AND STORAGE OPTIONS The following is a suonary of the disposal and storage options which staff intenes to apply, The maximum concentrations permitted under each disposal option are tabulated on the last page of this enclosure.
1.
Disposal of acceptably low concentrations (which meet EPA cleanup -
standards) of natural thorium, depleted or enriched uranium, and uranium ores with no restriction on burial method, 1
The concentrations specified for this option are believed acceptably low without rastricting the method of burial.
It is expected, however,
tha currently licensed operations will be conducted in such a manner i
as to minimize the possibility of soil contamination end when such occurs the contamination will be reduced to levels as low i
as reasonably achievable.
2.
Disposal.of certain low concentrations of natural thorium and capleted or enriched uranium (with no daugnters present) when burito unoer prescribed conditions with no land use restrictions anc no continuing NRC licensing of the material.
Uncer this option, burial will be pemitted only if it can be demon-
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strated '. hat the buried materials will be stabilized in place and not i
be transported away from the site. Acceptability of the site for disposal will depend on topographical, geological, nydrological and meteorological enaracteristics of the site. At a minimum, burial depth will be at least four feet below the surface.
3.
Disposal of low concentrations of natural uranium' ores with daughters in ecuilibrium, when buried uncer prescribed conditions in areas :oned for industrial use, and tne recorded title documents are einended to state that the specified land contains buriec radioactive materials' and are concitioned in the manner acceptaDie uncer state law to impose a ;ovenant running with the land snat the specified lano may not be used for resicential Duilding.
(There is no continuing NRC licensing of the material.)
Oisposal will be approved if the burial triteria outlined in option 2 (including burial at a minimum of four feet) are met. Under this option, no residential building would be permitted over land where natural uranium ore residues have been buried.
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?A uh, d3g 2-4 Disposti of land-use-limited concentrations of natural thorium, natural uranium anc cepleted or enrichec arsnium when buried uncer prescribed concitions in areas zoned for incustrial use and the recorced title cocuments are amenoec to state that the lano contains buried radioactive materials, and are conditioned in the manner reovired by state law to impose a covenant running with the land that the land (1) may not be excavated below stated Sepths in specified areas unless cleared by appropriate health authorities. (2) may not be used for residential or incustrial building, and (3) may not be used for agricultural purposes.
(There is no continuing NRC licensing of the disposal site.)
Criteria for disposal under these conditions is predicated upon the is given in land documents of recorc not to excavate bel in specified arteh of land without clearance by health authorities; not to i
construct residential or industrial builcings en the site; and not to use specifiec areas of lanc for agricultural purposes.
In aceition to meeting tne Ourial criteria in cetten 2, *ecorcec title cocuments novid be inended to impose inese land use f>estrictions.
1 5.
5:: rage of If censec concentrations of thorium and uranium onsite pending the availacility of an a:propriate dispesal site.
khen concentrations exceed those specified in option 4, long term disposal otner tnan at a licensed cisposal site will not normally oe a viaole option under tne previsions of 10 CFR 20.302.
In such cases, the taorium and uranium may oe :ermittee to be stored onsite under an NRC license until a suitaoie metnod of cis:esal is founc. 'icense concitions will recuire that raciati:n costs not exceec those s:ecifiec in 'O CFR Part 20 and be main-tainec as low as reasenely achievaole.
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SUMMARY
OF MAXIMUM 00NCINTRATIONS PERMIT *IO 'JNDER DISPOSAL OPTIONS Discosal Cotions
( C1/gm) 0 0
Kind of Material 1
2 3
4 Natural Thorium (Th-232 + Th-228) 10 50 500 with daughters present and in equilibrium Natural Uranium (U-238 + U-234) 10 40 200 with daughters present and in equi 11trium Depleted Uranium o Soluble 35 100 1000 o Insoluble 35 300 3000 Enriched Uranium o Soluble 30 100
!000 o Insoluble 30 250 2500 a Based on EPA cleanup stancares.
b Concentrations based on limiting individual soses to 170 mrom/yr.
- Concentration basec on Ifmiting ecuivalen exoosure to 0.02 working level or less, Concentrations based on limiting indivi:ual coses to 500 mrem /yr c
and, in case of natural uranium, limiting exposure to 0.02 working level or less.
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ny-CALC"LATION OF ALLOWABLE CONCINTRATICNS FOR FOLR 0 Sp05AL CpTICNS 1
Introcuttien The following sections provice dose calculations for establishing limiting concentrations of thorium and uranium for dispcsal under four disposal options. The dose tabulation includes various significant pathways to man resulting from the burial cf racicactive wastes containing natural thorium, natural uranium, enriched uranium, or dep'ieted uranium. With these tables, the concentration limit of,a radionuclide or mixture of radionuclides in various types of wastes to be disposed of by these options can be calculated. Tables 7 ano 8 sumarize the concentration limits of some typical wastes for each cotion of disposal. Concentration limits involving t
other mixtures of these radionuclides can be calculated by the use of these tables.
Racicactive Characteristics cf the Nuclices A.
Thorium The natural thorium decay chain and the characteristics Of each nucliot are summarized in Table 1.
The parent Th-232 generally exists in nature with its caugnters whicn are in radioactive equilibrium with the parent. Howeve". in some types of waste such as from processing of thortum cre the puri#ied metal (Th-232 and Th-228) is removec as the procuct and the caugnter procucts can be various wastes. Therefore.
it is iaiocriant t: unoerstano the history of the operation anc how the wastes are generatec.
As shown in Taole 1. Th-232 anc its caughters consist of alona, beta, and gama emitters. The alona emitters will constitute a significant patnway f:r cese to man througn innalation ano ingestion. The critical organs in tne inhalation and ingestion patnways are the lung and the l
done decencing on the solubility classificati:n of the nuclice. The gama emitters will contribute external raciation (wnole-bocy) dose to man. Therefore, the patnways for cose to man to be consicered for l
natural incrium are cirect raciation, innalation and ingestion.
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'l Table 1 Thorium Chain 1
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. Principal Radiations (MeV)a
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- Isoteo, T1/2 Dauchter Alena-6 eta-raama-10 Th-232 1.40!x10 y Ra-228 4.00 Ra-22S 5.75y Ac-228 0.01 0 Ac-228 6.13h Th-228 0.376-0.915 Th-228 1.9131y Ra-224 5.40 0.002 Ra-224 3.66d Rn-220 5.67 0.009 l
l Rn-220 55.5s Po-216 6.29 Po-215 0.15s Pb-212 6.78 i
Pb-212 10.6ah 31-212 0.100 0.117 1
I Bi-212 60.55m T1-208 6.04(25.93%)
0.003 i
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( 64.07% )
0.71 7 0.281 1'
T1-208 3.07m Pb-208 0.561 2.37 Po-212 3.05x10' s Pb-208 8.78 (Stable) 1-a l
iranenes <1 not included.
Average enery.
C Total Enery emitted per disintegration.
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Urar.ium The uranium chains including U-238 and U-235 are given in Tables 2 and 3.
For uranium that has been processee through the milling operation, the only nuclides of importance in the dose calculations are U-238 and U-23a. The. buildup of daughters in the separated uranium is not imoortant, i.e., neither the Th-220 nor the Ra-226 could reach 10% of equilibrium with the separated uranium until greater than 10,000 years. The.U-234 usually stays in ecuilibrium with the U-238 parent with the +quilibrium between U-238 and Pa-234 reached in a matter of months.
In normal processing of uranium ore, the process separates both the Th-230 anc Ra-226 to the same stream of waste; then both nuclides are in secular equilibrium.
If in the case of uranium resioues Th-220 and Ra-226 are not in ecuilibrium, particularly if the Th-230 is much higher than Ra-226, a potential source of Ra-226 contamination may exist as radium builes uo te ecuilibrium with the Th-230.
In this case, the primary con-siceration must ce given to exposure from racionuclices other than U-238 anc U-234 In seme tyees of operations, other metals are extracted and uranium ore is left in the waste stream as byoroducts.
- n these cases all uranium daughter reducts must de considered.
The parent U-236 occurs to the extent of only about 0.7% in natural uranium and the chain is generally unimcortant comparec with tne U-238 chain. However, in the early years of the Mannattan Project 'nuen of.
- ne ore was very high grace sitchblence or carnetite ore. After the uranium was seoarated anc Ra-226 extracted from the wastes, the Ac-227~
and Pa-231 nuclices remained in the waste stream. These constitute
!lo a significant'scurce of contamination.
As shown in Tables 2 and 3, radionuclides in the uranium decay chains emit alpna, beta anc gamma radia: Ton. The sa:nways for dose to man are from cirect raciation, innalation and ingestion. The critical organs are the wnole bocy, the bone and tne lung, i
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. Principal Radiations (MeV)"
Isotope 1/2 Daughter A1cha" 5 eta
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U-238 4.468x10' Th-234 4.20 "h-234 24.10d Pa-234 0.044 0.008 Pa-234 1.17m U-234 0.82 0.011 e
U-234 2.445x10 y Th-230 4.76 Th-230 7.7x10 1 Ra-226 4.66 l..
Ra-226 1600y Rn-222 4.77 0.006 Rn-222 3.8235c Po-218 5.49
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E Pb-214
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81-214 0.22 0.23-o t
31-214 19.9m Po-214 0.63 2.03 Po-214 1.64x10'#s Pb-210 7.69 Pb-210 22.3y Bi-210 0.007 0.002 31-210 5.012 d Po-210 0.39 1
Po-210 138.378d Pb-206 5.31 (Stable) a3 ranches <1'. not included DAverage ecnergy.
Ciotal energy emittec per cisintegration.
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1 Actinium Chain
. Principal Radiations (MeV)"
Isotone 1/2 Dauchter Aiona-Eeta' Gama-0 U-235 7.1x10 y Th-231 4.28 0.140 I
Th-231' 25.525 Pa-231 0.078 0.017
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Ac-227 4.92 0.030 i
Ac-227 21.773y Fr-223 4.19(1.38%)
Th-227
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0.01 0 Th-227 1B.715c Ra-223 5.57 0.010 Fr-223 21.5m Ra-223 0.345 0.051 Ra-223 11.434c Rn-219 0.087 Rn-219 3.96s Pe-215
- il 0.054 Po-215 1 '. 7 B0 x10 ~ 3 s
Pb-211 7.39 l
0.453 0.050
. 4 Pb-211 36.1m 31-211 1
31-211 2.13m 71-207 6.55 0.043 T1-207 4.77m Pb-207 3.293 0.002 (Staele)
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7etal energy emittec :er cisintegration.
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~III Dose Calculation The following Tables 4-6 susmarize the organ doses for various pathways to man based on unit concentration of each nuclide as shown in Tables 1-3.
All internal doses listed in the tables are 50-year dose comitments; that is, the total dose ar individual will receive from one year of intake integrated over the next 50 years of his life. For those materials that either have short radioactive half-lives or are eliminated rapidly from the body, essentially all the dose is received in the same year'that the radionuclide entered the body, and the annual dose rate is about tne same as the 50-year dose comi,tment. All external doses are given as annual dose rates.
The factors for converting internal exposure to dose (dose conversion l
factors) were determined using ICRP-2 anc other reco imolementee by recent models (Task Group Lung Model)gnized values and u,
for the lung and GI l - ^
tract. The dose conversion factors used for external radiation cose determination are given in CRNL-4992. The dose conversion factor for innalation of racon anc its caughters are derived from ne SE*R report.
IV Derivec Maximum allowable Concentration for Various Disposal Ootions Tables 7 and 8 sumarize the maximum allowable concentration for the disposal of various types of wastes. Concentrations cerived in cotion 1 are residues l
of cleanup. concentrations which can be disposed of in any manner. The concentra-l' tions cerived in eption 2 are such that under the worst moces of execsure
-inclucing all significant pathways, the maximum indivicual dose would not C
exce'ec 170 mrem /yr to any critical organ. In option 3. the most significant l
pathway is from the innalation of radon and its caugnter procucts. With an average concentration of 20 pCi Ra-225 per gm of waste, it'is estimated I
tnat an indiviaual could be exposed to en average of 0.0a Worxing Level I
(WL) from inhalation of raden instde structures ouilt on contaminated land.
This exposure is juoged to be too hign for resicential use of the curial site.
(Ccmpare w1:n 0.033 WL-10 CFR 20; 0.005-0.02 WL-EPA Florica Shospnate Gui cance. ) Comercial use of the site is allowaole because the exposure time to racon is expected to be less tnan 50% of continuous exposure and l
consecuently no indivicual will likely be exposeo to an average of 0.5 WLM.
The concentrations of uranium, depleted uranium anc natural tnorium derived in option A-are higner by aporeximately a factor of 10 since a limited exposure from an intrucer (assuming aeout 30% of full exposure used in cation 2) is i'
assumed anc a maximum indivicual dose of 500 mrem /yr to a critical organ is-assumed. ~ce the case of natural uranium the concentration cerived in option a is higner ey a f actor of 5.
The concentration is based on a limitec execsure such that no indivicual will se exoosec to a racon cose in excess of 0.5 WLM assuming a maximum exposure time of 2.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (i.e.10%) a cay. This is ecuivalent to continuous execsure to 0.02 WL.
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Figures are based on a unit concentra of 1 pCf/g for each radionocifde in soll Whole body dose Whole body dose lfhole body dose Raellossucl ides (mres/yr)
Ra if eenecildes (mres/yr)
Radionucildes (aree/yr)
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U-235 4.4E-1 Th-232 t h-2.14 2.50-2 1h-231
- 1. 9t -1 Ra-228 Pa-234m 1.9E-2 Pa-231 2.?L-1 Ac-228 1.30-0 Il-234 Ac-221 Th-228 Th-230 1h-227 4.1E-1 Ra-224 Ra-226 1.40-2 Ra-223 3.8E-1 Ra-220 Ha-222 Ra-219 1.1 E-. I Pb-212 3.0E-1 Po-218 Ph-211 9.4E-2 81-212 2.3E-1 Pb-214 4.11t-1 til-211 9.40-2 11-208 5.5E-0 H1-214 2.flE-U I1-201 Po-Zli Ph-210 3.4t-2 141-210 Po-210
- Assinned structieral shielding factor of 0.5 'aeul 001 occupancy.
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(c) Insignificant casupared with other nacildes.
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Table Sa Dese Comitments(a) From Inhalation of Resuspended Raalonuences' From contaminateo 5cii Figures are based on a unit concentration of 1 pCi/g of each radionuclide in soil.
(Clearance rate class Y; particle size (AMAD) = 1 um) 4' i
Raetonuence Dose comit:nen:
3 (arem)(f)
Lung \\ss done Worting Levei ur_anium series 4
ICI U-238 6.1E-1 5.2E-3 Th-234 Id)
Pa-234a U-234 S.9E-1 5.SE-3 Th-230 6.7E-1 2.4E-1 I
Ra-225 7.2E-2 'I 3.5E-2 po-218 pp-214
- 31-214 po-214 I
Pb-210 7.9E-3 'I 3.1E-2 L
31-210 L
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'a)Fif y-year dose comitment for one year Of intake.
l I?) Assumed resuspension factor Ex10-9' m '; maximum soil censity of 2.5 g/::
l BC*. oc:Upancy. This resuscension factor may be :enservative. These factors should be basec on particle si:e and :ensities associatec with specific sites.
t I:) Read as 6.1x10'1
',. I:nsignificant c:mpared with other nuclides.
U')Ra-225 and 3b-210 are classified as W compounds; 3o-210 is :lassified as W
- m:ounc.
t.r.
Based on quality factor of 20 for alpna particles.
- Dulmonary lung
" *ne average Wort ing Level (WL) is :alculated on :ne easis of 25 WLM/ year ;er WL i:entinuous ex:osure) and a cose conversion fac.:e :f 5 rem per working level This mean level of ex osure cerivec fr:m racon insice a structure ouilt men:n.
on contamina:ec wastes : uid ee off significantly cepending en :ne incut carametert use, suen as tne ventilation rate, type of floor, et:.. wni:n are cepencent on tne strue ur,a1 :esign cf ne builcing.
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Table Sa (Cont ~C)
Racienue n ce
,00se Commitment (arem)
Lung zone Actinium 5eries U-235 6.2E-1 5.3E-3 Th-231 Pa-231 7.6E-1 7.0E-1 Ac-227 1.3E-0 3.9E Th-227 B.BE-2 2.9E-4 Ra-223 5.9E-2 7.0E-4 Rn-219 po-215 p3-211 31-211 T1-207 Thorium Series l
Th-232 5.8E-1 2.5E-1 Ra-228.
5.2E-3 2.1E-2 Ac-22S l
Th-228 9.2E-1 2.3E-2 Ra-224 i
Rn-220 L
p3-212 31 212 71-208 9
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Table Eb Dose Commitments From Innalation of Resusoended Racionuclides From Contaminated Soil Figures are based on a unit concentration of 1 pC1/g of each radionuclide in soil (clearance rate class W; particle size (AMAD) = 1.n) 1 Racionuclice Dose commitment (mrem)
- t.u n g sone acrxing :.evei Uranium series U.238 6.3E-2 1.!E-2 Th-234 Pa.234a U 234 7.0E-2 1.7E-2 Th-230 6.9E-2 5.0E-1
'Ra-225 7.2E-2 3.SE-2 Po-21S Pb-214 31-214 Po.214 1-
?b-210 7.9E.3 3.1I.2 i
91 210 l
Po.210 1.3E-3
- 5..:E.3 Rn 222
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Racionuclice Dose Comm1: ment (mrem)
Lung none Actinium Series U-Z35 6.4E.2 1.5E-2' Th.231 Pa.231 1.6E-0 Ac-227 7.4E-2 1.1E.0 Th-227 6.8E-2 2.5E-3 Ra-223 5.9E-2 7.0E.4 An-219 Po-215 Pb-211 31-211
. s. - 2 e.,,
Thordum Series Th-232 5.0E-2 6.2E-1 Ra-228 6.1E-3 2.1E.2 Ac-228 Th-225 1.3E-1 1.3E.1-Ra-22:
An-220
- b-212 31-212 71 208-O
- I s
4
.E
. g, Q
. ~.
Table Sc Dose Comitments from Inhalation of Resuspended Raatenucitoes from contaminateo soil Figures are based on a unit concentration of 1 pCi/g of sach radionuclide in soil.
(Clearance rate class w
Y 0; particle size (AMAD= 1 um))
Racionucisce pose conrritment (mrem)
Lune 5ent Working Level sranium 5eries U-238 1.1E-3 5.0E-2 4n-234
?a-234a U-234 1.2E-3 5.6E-2 ih-230 6.?E-2 6.0E-1 Ra-225 7.2E-2 3.6E-2 Do-218 Pb-21a 3i-214 Pc-21a
.b-211 7.9E-3 3.1E.2
?
ei-210 -
?0-210 1.3E-3 1.9E.3 Rn-222
.002 I
C.
I' "
M.
2(a*?
Table 5e teont ci Racionuclide Rose commitment (metm)
Lung g
AC*inium Series U-235 1.1E-3 5.0E-2 Th-231 Pa-231 7.4E-2 1.6E-0 Ac-227 1.1E-1 1.1E-0 Th-227 S.SE-2 2.5E -
Ra-223 5.9E-2 7.0E-4 Rn-219 Do-215 Pb-211 31-211 T1-207 1
e Note:
Thorium comoeunes are classified as Y and W compouncs.
7 1
i e
l t
\\
4
- ?. ' "
s.
iable6 Unse Econettment ResisitTng(~from Iny'stion(a)
(we etatIon bee ~inllO
~
of Radionici iles FrneN6AINI6ited soll.
Figures based on a sanf t concentration of I pCf /g of each enecilde in the soll (the f f rst 15 cm of s ll) o lione Dose Bone dose Bone Dose Radionuclides (mrem) _
Radionuclides (mrem)
Radlonescildes (ares)
Ilrantum Series Actinlaan Series lhorium Leries i
(1-23tt 1.0E-0 H-235 1.8E-0 Th-232 5.0E-1 1 h-2.14 Th-231 Ra-228 5.4E-0' Pa-234 Pa-231 1.4Ei1 Ac-228 H-214 2.0E-0 Ac-227 8.1E-0 Th-228 1.1E-1 ih-230 1.2E-0 th-221 Ra-224 Ma-226 1.1E-0 Ra-223
~
Po-218 Pb-212 Pb-2il B1-212 Ph-214 111-211 TI-20fl Hi-214 Il-201 Po-214 Ph-210 8.0E-0 Hi-210 Po-210 3.30-2 t
i I*I lt is assessed that an individual would raise 60% of his own food on the heertal site.
The staff helleves this to be a conservative assianytfon since it Is highly inillkely'that an tsullvidisal would raise this asusunt of his own food on a hurial site.
e 6
3
.~
,.g
- ._.s.,
n.g y
y __ _ _,. _. _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _, _ _ _ _
_,.__g.____
. +~ g. :
4
~
r Tahle 7 Simmary of RadioinTcildF concentrations I iWasteillnil FVW16ss Ifisposal~Qtlidiis Type of Wastes option i Whole!ptions 2 and 3 O
~
O lihole-Body ~ption 4 hic-Boili ~-~l~emg
-Hone B6dy liesg~~
Bonc IIeng Bone (10:er/hr)
~~
---' HixtiiiGii,AnsiTable t5,icentraT1on Git 17gm1
' -(Imrad) (3 mrad). (1/ Harem)
(110 mrem) (170eren) (500 mrem)
(500eren) (500eren)
- 1. Hepleted uranium
- a. Insolidsle 35 300 3,000
- h. Soluble 35 100 1,000
- 2. I nriched uranium
~
d.
I fiSUIlelsle 30 250 2,500
- h. Soluble 30 100 1,000
- 3. Natieral thorlism (Th-232, Th-22H)
(inclueles all daughters) i-a. Iris olieb le 10 50 500
- b. Soluble 10 50 500
- 4. Nateis al us asilienii (11-238,11-234)
(inclueles all daughters)
~40{4 2tN)(3)
- 4. IfisoInible 10())
- h. Soluble 40 200.
(
lhe resteheal clearstep concentration for natural israsilesimi is liased twi that set ley I'PA (46 lR 2556-2563) for radium 226 and Its decay poducts.
(2) Indoor radon expostere. ls estimated to be about 0.04 WI. for contisusness' exposure; land restriction for residential tese is resguired.
I3I
- s.
Radiism concentration is based on a ilmited exposure such that no individual ult'l be exposed to a radesse do of u.5 in M assimilng a sinaxImism exposure time of 2.4'hoters a ' day. 'This is espotvalent to centisinous espostare les.07 W1..-
g
-.. =
-.~
- - _ - _ - - - - _ - _ = - -
W
'^
e.
n ~
+
N.
l l
Table 8 Maximum Allowable Concentration in Waste for Cotions 1, 2, 3 and A Tyce of Wastes Maximum Allowable concentration (DCi/g)
C::1on i cc: ion 2 6 3 Option 4 1.
- a. Insoluble 25 300 3,000 5
- d. Soluole 35 100 1,000 2.
Snriened Uranium (U-238, U-225,.U-234) i
, a. Insoluole 30 250 2,500
- c. Solunie-30 100 1,000 3.
Natural 'Jranium (U-238, U-234)
- 3. :nsoluole 10 40 200
- c. Soluole 10 10 200 4.
Natural Therium (Th-232, Th-223)
- a. *nsoluole 10 50 500
- c. Soluole 10 50 500 g
4
s,.
c 4
y NUCLEAR REGULATCP,Y COMMISSION N
~
ev DISPOSAL OR ONSITE STORAGE OF THORIUM
~
OR "RANIUM WASTES F:.CM PAsi OptgA;;c3g
'EENCY:
'4uclear' Regula* cry :mmission (NRC)
- . w,.4 :
Discussion cf 0;;iens.fer NRC AFDroval of ADD 11 cations for Disposal or Onsite Storage of Therium or Uranium Wastes.
- nterim Use anc Public Coment
SUMMARY
This notice ciscusses five optiens for NRC accroval Of Cis:Csal
- nsite s; rage of norium or uranium was;es fr:m cas nucitar :Derati:ns,
- P
're :::icns are ::ntaire: in a Branen Te:nnical 3:si-i:n for acminis rati n
- y One Uranium Fuel Licensing Branch, Division of Fuel Cycle an: Materda;
'Sa'e:y, Office Of Nuc'. ear 9aterial Safety anc Safeguarcs,
.a. u :
. mments en :ne ::: ions for cisposal er Onsite s:Orage of :n=rium
. Or uranium are enc:urage:. Suen ::=ents will te : nsiderec in any su:se:uen: revisi:n Of :ne Branch Tecnni:31 ?:siti:n.
- ments art :ue FOR ACO:T:0NAL :NFO M T:CN ;;NTAt;:
at:n 3. Page, ;hief, Uranium Fue:
.i:ensing Brenen, Civision Of Fuei /:le an: Material Safety, affdce of Nuclear Vateriai Safe:y anc Safeguarcs, Wasnirg::n, ;,;, 23535,
- ele:none 301 27 23 9,
' iC :3ys af ar :c:licati:n In:I:sure 4 6
j
^
~
"S.-...
.2 SUPPLEMENTARY lNFORMAT!CN:
Intrecuction Some of :ne sites fomerly used for processing therium and-uranium are known today to be contaminated with residual radioactive materials. Some are currently covered by NRC licenses. Others were ence licensed, but the licenses te Possess and use material have expired.
!n many cases, the total amount of ceritaminated soil is large, but the activity concentra:icns of racicactive materiais are believec suf'iciently low to justify their :isposal on Ori'/a:ely owned lancs :r storage Onsite rather : nan their transper: to a licensec radioactive ma arials disposai (:cmercial) site.
n nany instances packaging anc transcerting these aastes to a license disposal site woulc te ::o c:stly anc nc: justifie: fe m the stanc;oints of risk to :ne puclic netith or cost-senefit.
Furthermere, :ecause :f :ne :c:si volume Of these wastes, limite:
comercial waste disposal :apacity, anc restrictions placed :n recei : Of 1:ng-lived wastes at c mmer:ial sites, it is ne:
presently feasible to dispose of these aastes at c:mercial low-level waste dis:csal sites.
Effective January 29,1981,1RC *egulati:ns in 13 CFR 20 "5:ancar:s f:r Dr::ec: ton Agains: :adiatien, aere amen:ec (45 FR 71751-71752) o celete Sec-ien 20.3Ca wnich crovice:
generai autnerity f:r cis;csai of racioective materiais :y curial in s:il. Once- :ne amencec regula:d:ns, licensees l
JW 4
c.
3 mus: apely f:r an: c:tain spect*ic 1RC a:er: val to dispose :f racica::ive mater ais in :nis manner uncer the orovisions of 10 CFR 20.302. A case-by-case review was believed neogeo to assure that burial of radioactive wastes woulo not present an unreasenacle health ha:ard at some future cate.
The deleted pr:vist'ons of Secti.on 20.30t. previously pemitted turial of up to 100 milli:uries of thorium or natural uranium at any one time, with a yearly limitati n :f '.2 eurials for eacn ty:e :f material at ea:n site. The Only' dis:esal standar:s s:e:1#ie: aere (l'; turial at a minimum ce::n of feur feet, and (2) suc:essive Ourials se:arate: by at leas six feet. Thus a
- 11 cf 1.2 :gries of these materials were ;ermi :eg :: te-dis:ese of each. year by burial'in a 12 foe by 18 foc: er larger :::: :f grounc.
Uncer :ne amea.:e regulaticns. 't is incumter.: On an accid ant wne wants :: tury ract:a::ive wastes :: :emens rate that local lan: turia; is referacle to ::ner dis:osal alternatives. The eva'.uation of :ne a:clication : axes in:0 ac::un: :ne foilcwing information:
'y;es in: :Lantities f material :: te turies 3ackaging :f weste
m.:
- fk
.[
- ll
,h
't Ql
". l Burial lobation Characteristics of burial site Depth of burial-Access restrictions to disposal site
- Radiation safety procedures during disposal operations Recordkeeping Local burial restrictions. if any For applications involving discosal of soils c:ntaminatec with
' low level concentrations of therium anc aranium (other than concentratiens not exceeding EPA cleanuo s andarcs), the matters of principal importance are:
3 Concentrations of thorium anc uranium (either in secular t
l_
equilibrium with their daugnters or wi*hout daughters Dresent)
V:lume of c:ntaminated soil C:s:s for offsite and ensite isposal
-- Availability of effsite burial space Disposal site characteristics Oepth Of burial and accessibility of buried wastes.
u L
State and local govermnent views l'. ' Bran'en Technical Pesition
~here are five ac:ectable op-ions for disposal or ensi e s:Orage of thorium anc uranium contaminatec wastes. Amplications for cis:esal Or s : rage will be approved if the gui:elines dis:assec 4
under any :::i:n are met. A::li:ations f:r c:ner me:nces Of
. v.~
~
g.
t 4
4 cisposal may be submitted and these will be evaluated :n their own meri*s.
i.
Disposal of acceptably low concentrations (which meet EPA clearee stancards) cf natural thorium with daughters in secular epilibrium, depleted or enriched uranium, and uranium cres vith daughters in secular equilibrium with no i
restriction on burial methoc, L
Under this cption, the concentrations.of naturai hord um and depleted or enriched uranium wastes are set sufficiently low that no memcer of ne wblic is expected te receive a raciation'cose comi: ment from the disposed materials in excess of 1 millirad per year :: the lung er 3 millirads I
per year c the tone from innalation and ingestion, uncer any foreseeable use cf the material or property. These raciatien dose guidelines were recomended by the Environmental Pr tection agency (EPA) for protection a
against transuranium elements present in the e'nvircnmen:
as a result of unplanned centamination (42 FR 60956-50959).
- n accition, tne concentrations are sufficiently low so L
that no incivicual may receive an external cose in excess 1.
Of 10 microrcentgens per hcur above backgrounc. This is c:meatible wi:n guidelines EPA preocsec as cleanuo stancards f:r inactive uranium Drec'essing sdtes (26 FR 2556-2563).
f
1 Q
.n g.
6-For natural uranium ores having daughters in equilibrium, the concentration limit is equal to that set by the EPA (46 FR 2556-2563) forracium-226(i.e.,5pCi/gm, including background) and its decay products.
The' concentrations specified below are believed appropriate to apply.
It-is expected, however, that currently licensed i
operations wil.1 be conducted in such a manner as to minimize t
the possibility of soil contamination and when such eccurs 1
the contamination will be reouced to levels as low as I
reasonably achievable.
Kind of ' Material Ccncentratien(PCi/gm)
Natural thorium (Th-232 plus Th-222) if all daughters are I-p t.-ent and in ecuilibrium 10 g
Deplete: Uranium 25 Enrienec Uranie.
30 Natural Uranium Ores (U-238 plus 'J-234) 10 if all daughters are present and in ecuilibrium
% e analysis u:en which the Branch Technical Pesition is based is availatie for ins:ecti:n at tne 00 mission's Puolic Doc =ent Roem at 1717 H St., N.W., Washinct:n, 0.0.
.m-
?
.:jm.;;c.
p
-7 The concentrations s;e #fito uncer h's option may be
- mpare: with naturally occurr<ng :horium and uranium cre
- ncentrations of 1.3 PCi/gm in igneous rock anc uranium k
concentrations of 120 pCi/gm in Florida phospnate rock anc' 50-80 pCi/gm in Tennessee bituminous shale.
C ncentration limits for natural therium end natural-uranium ore wastes :entaining daughters not at secular ecuilibriulm can be calculated on a case-by-case casis using ':ne acclicable iso::cic activities data.
2.
Oisposai of :ertain 1:w :encentratiens of na ural :ncrium with caugnters 'in secular e:uilibrium and de;ietec Or enrichec uranium with no taughters :resen: wnen buriec uncer
- rescribed c
- ncitions with no subsecuent'lanc use aestrictions an: nc :entinuing-NRC it ensing :f ne materdal.
Uncer :nis eptien ne :encentra:f ons f natural :ncrium and uranium are se:'sufficiently 1:w so :na: no memcer Of the
- u
- 1': will receive a raciati:n ::se exceecing :nese 'scussed under option 1 when :ne wastes are bur ec in'an a:pr:ved manner d
a sent intrusion into the burial.grouncs. "his ::: ion will i
recuire esta:lishing crescribec ::n:itiens f:r dis:csal in
- ne l' cense, sucn as de:th an: :'s ritu:'On f aterdai, to minimi:e the likelince: Of ir:rusten.
Eurdai wi'.1 se :ermit ec Only 'f it :an be cemenstra ed tha: the turie:.a erdals wili te s a:ili:e: in : lace and ne: :e rans:cr e: away ' :n te si e.
a
- - " " ~
~
me-71 7g
. +.
'"i i
7 qf y
-_I =
Acceptability of the site for discesai will depene on
- cograchical, geological, hycrolegical anc meteorological characteristics of the site, At a minimum, burial depth will be at least.four feet below the' surface.
In the event that there is an intrusien into the burial ground, no member.of the public will likely receive a dose in excess of 170 millirems to a critical organ. An average dose not exceeding 170 millirens.tc the whole body for all memoers of a general population is recantencec by international and national r
-acia tion ' ex:er bocies :c limit peculation.d:ses. With 1.
i respect ic limiting coses :: indivicual bocy organs, the c:ncentra:icns are sufficiently low that no incivicual will
\\
1 receive a dose in excess of 170 miliirems to any Organ from exposure :s natural :horium, depletec uranium er enriched l;
1 1
The average activity c:ncentra:icn of radicactive material
- nat may be buriec under this option in the :sse :f r.aturai thorium (Th-232 31us Th-22?) is 50 :Ci/;m,
'# all daughters are present and in equilibrium; for enriened uranium it is 100 DC1/gm if the uranium is solutie and 250 PCi/gm if fasciusie; for ceointec uranium it is 100 'pci/;m if the uranium-is sciuble and 200 pct /gm if insclucie.
'4atural uranium cres ::ntaining racium 225 and its daughters are not inciucec under this cetten, because of possible rac:n 222 emanations anc esui: ant nigner
- nan acca::able ex:csure Of incivi:uals in :r'vate esicences d' neuses aere buil: Over buriec materiais.
< +
e
c.
7 7
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(
- c. : ; '
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t
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1 9
.I d
3.
Oisposai of icw concentrations of natural uranium cres, wi r.
ali caugn:ers in ecuilibrium, wnen turied uncer prescrised
- enditions_ in areas :enec for industrial use and the recor:ed title documents are amended to state that the specified land centains buried radicactive materials and are conditione: in a manner acceptable uncer state law to impose a c venant running with the -land': hat the specified land may not be used for' resicential builcing.
(There is no continuing NRC licensing of the material.)
Oispesai wili :e a:or:ved if :ne Ourial :riteria Outline: in 0;; ion 2 (in:'.ucing burial 4: a minimum of a feet) are met.
L Oepencing u:en local soil :hara:: eristics, burials a: :e::ns greater : nan a fee: may te required.
!n order to assure-J Protec:icn agains racen_222 eleases (caugn:er.in :e:ay
- nain of uranium 238 an: uranium 234', i: is necessary na: the ree:r:ed title :ccuments :e amen:e: to s a:e in' :ne permanen-i lanc re:Or:s :na: no resi:entiai :uilding snculd :e permitte:
over s:ecifie: areas of lan: wnere nc ural uranium Ore resicues (U-238 plus U-234) in :encentraticns ex:se:ing 10 :Ci/;m has 1
L teen buriec.
'ncustrial builcing is ac:e::atie s 1:ng as -he l-i concentra:icn of curied ma ertai : es s.c: exceed 40 :Ci/gm :f uranium
'.i.e., Ra-225 snail'not excee: 20 pC1/gm}.
4 Ois: sal Of land-use-limitec ::ncentra:1cns Of na: ural :ncrium er natural ;ranium. with :augr.ters i, se:ular e:uilibrium an:
cepie e: Or enti:ne: uranium i-heu :augn:ers :resen: 'anen 4
y 4
,q/p
/
[?
BR
.s,c.
' " ' ~
i bi buried under prescribed conditions in areas-Zoned fer indurerial use and the recorded title documents 'are amended Oc 1
state that the land contains buried radioactive material and are conditioned in a manner acceptable under state law to impose a covenant running w'f *.h land that the land (1) may not-be-excavated below <tated depths in specified areas of ~ land unless cleared o;- ippropriate health authorities (2) may not be used for residential or industrial structures over specified areas where radioactive materials in cencentrations-higner than specified in -options 2 and 3 are buried, anc (3) may.
not be used for agricultural purposes in the specifiec areas.
(There is no continuing NRC licensing cf the disposal site.)
Uncer inis cetion, conditions of burial will be such that no member cf the public will receive radiation deses in excess cf these discussec under option i absent intrusien into the i
burial grounc.
Criteria fcr cisposai under these concitions p+
is precicated uten the assum: tion that intentional intrusien E
is less likely to occur if a warning is given in land-cocuments of record no: to excavate below burial depths in specifiec areas of land without clearance by health authcrities;-
not to construct resicential er industrial building on the site; anc ne: :: use specified areas of land for agricultural zurcoses.
i Because cf :nis, we believe it appropria:e to apely a maximum-critical organ ex:csure limit :f 500 mil'.irems ser year to :norium l
l L
4 I
i
. - - ~
cy;~
i
~i e
l; n
RA g.
m g'
1
[
y_.
11
^
i; l-anc uranium buried uncer this restrictiun insteac of ; 0 millirems. ~
as used in ::: tens 2 ano 2.
- n acci:icn, any exposure to suc.5-L materiais is likely to de more transient than assumed (essentially! continual exposure) under those options. These two:
facters c:mbine to increase the activity concentration limits calculated under Oction 2 by about 10. Thus,'the average concentration that may be buried under this cotion for~ horium (Th-222 plus Th-228) is 500 ;Ci/gm if all daugn:ers are : resent anc in e uilibrium; for entienec uranium it is 1000 pCi/Sm if the uranium is soluele and 2500 :C1/gm if insoluble; anc for ceoieted.
uranium it is 1000 ;Ci/Sm if the uranium is solu:le and 2000 ;Ci/;m if insciable.
Wi:n res:ee: :: na: ural uranium with daughters resent and in e:uilibrium, the :encentration tnat may be burie: uncer :his ption is 200 :Ci/gm Of J-223 ?ius U-224, i.e., 100 :Ci/;m Ea-II5.
This ::n=entrati:n is based en a limi:e: ex:esure Of 2.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> :er day :: limi: :he rac:n cse :L less : nan i
- 5 working level men:5 (WLM) wnien is e:uivalen: ::
c:ntinucus exposure :: 0.C2 worxing level (WL}. Cepending-
- cn 10
- 31 soil enaracterdstics, buriais at ces
- hs greater
- nan a feet ?.ay :e ecu4re:.
5.
5::rrge Of '.t:ense: ::ncen:ra:i:ns f :P.:rium anc uranium
- nsite :ened.ng :ne availability f an a:preerdate :is:csa; si a.
t
.2
r 3,
.]
= = -
. e :L y. ;
esp)y
' ~ *
- sg)
J:
. 4.m
- pg,
.I l.
in-12 -
I When concentrations exceec those specified in option 4,-long l
term disposal other-than at a license disposal s*te will not
~
normally be a viable option under the provisions of 10 CFR 20.302.
In such cases, the thorium and uranium may be pemitted to be stored onsite under an NRC license until i
a' suitable method of disposal is found.. License conditions i
will require that radiation doses not exceed those specified in 10 CFR Part' 20 and be maintained as low as consenably achievable.
i Before-aporoving an a;olica:icn to dispose of thorium or uranium I
s..
under options'2,-2, er 4, NRC will solicit the view of aper:oriate State health off4cals within the State ie. whien
- ne dis;osal would be made.
3ated:
l' b
l.
Richard E. Canningham Cirecter, Divisien of Fuel Cycle anc Material Safety Of# ice of Nuclear Material Safety i
and Safeguards L
+.
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