ML20236W187
ML20236W187 | |
Person / Time | |
---|---|
Site: | 07000938 |
Issue date: | 12/02/1987 |
From: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
To: | |
Shared Package | |
ML20236W175 | List: |
References | |
NUDOCS 8712070321 | |
Download: ML20236W187 (4) | |
Text
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i ' [ U.S. NUCLE AR REGULATORY COMMISSION N E- OF pCES- : r MATERIAllS LICENSE ' '
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' Pursuant.Io th'e Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93 H438), and Title' 10,1 :
Code of Federal Regulations, Chapter 1, Parts 30,31,132,33,34,35,-40 and 70, and in reliance on statements and representations L heretofore made by the licensee, a license is herebp issued authorizing the licensee to receive', acquire, possess,and transfer. byproduct', =
souice,' and special nucle'ar miterial. designated below; to use such material for the purpose (s) and at the place (s) designated below; to i 0 Edeliver or , transfer such material to persons authorized to receive it in accordance wit,h t_he r'egulations of the applicable Part(s).' This : ;
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Llicense shall be deemed to contain the conditions specified in Section_183 of the' Atomic Energy Act of 1954, as amended, and is-1 <
' subject to all applicable rules, regulations and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any. :
q conditions specified below.
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1q Licensee : e i< <
j a1 MassachusettstInstitute of- 3? License number -
SNM-986' ,
' Technology Amendment 1No.,2.
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77 Massachusetts' Avenue _ : me-Cambridge," Massachusetts 02139 Q (Q,; , l November ~ 30(1990 :
A(4 ,/ 5. Docket or ;
< i Reference.No. 7/yg-938: <
70
- 6. Byproduct, source,and/or special nuclear material A\ 7. Chemical and[or physical
1 b6 Maximum amount that licensee
(/~J. qb form 3Y. psmap possess at any one time :
.f N Splid.(U0 ),-clad'
- A. Uranium enriched to A'.#*32 r} der thislicense less than 2.0 w y nd unclain p' () ,000 grams 'of U-235 ;
1 in the-U-235 is pe glf) s ' .7- 1f
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, .B. Uranium enricheckto -
j BZ o, lid 4 -- B. 450 grams'ofU-235
<93 wt0 in the ,ihl ~;*
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- 1sotope 235JQ hMfj)i nc d {r9.ma e F p , [:
Plutonium 2 eji
- g. Q 9g k@'CD 5 97 grams C.
i[nd"Pu:j T4 :;
h@_ v4 neutron filtfp n~
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D. Plutonium if D. Soli [a1 a source , D .' 80 pg.
E. Plutonium -E. . **172.0 grams E. jjoli1 , fqil'r mir k._f J( _
l F. Natural uranium F. Soli anYso$ution' -F. 2,515'kilogramsJ .
d, G. Depleted uranium G. Any G. ***238.2 kilograms-H. 'Any byproduct material H. Unseparated H. Quantities' produced l .
unseparated contained 'duringLirradiation j d : in any of the above .,
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L i I. U-233 I. **** Solid.- I. **2lmg 4
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? . *9,000 grams for storage only 1'
- for: storage.only: -
- 58.2 kilograms for storage only l **O Information obtained from Mr. R. Masse .
! of_MIT during.a teleconLon' November 10, 1987 ,
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8712070321 B7120209 ADOCK'070 j
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- U.S. NUCLEAR REGULATORY CoMMISSloN
-_--------.__________)I ucense number PAGE OF 3- p,oes-SNM-986 a MATERIALS LICENSE. 1 g,cg,, ,, g,f,,,,c, ,f,eber SUPPLEMENTARY SHEET 70-938 l DEC 0 F 1987-l
- 9. ' Authorized Use: For use in accordance with statements, representations, and '
j conditions contained in the licensee's' revised' application. dated July _ 13, 1984, l I
and November _4,1987. R f, 10. Authorized Places of Use: The MIT Campus, Cambridge, Massachusetts; Bates Linear h Accelerator, Middleton, Massachusetts; and the _ Lincoln Laboratory, Lexington, .
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- l 1 Massachusetts. g .
- 11. This license does not authorize the insertion of licensed material into a nuclear
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I: 1 reactor. I 1 I {
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- 12. The minimum technical qualificatjoqs,'$p tEg[pofitiop of Radiation Protection' I "
N Officer shall be a bache!cr's idegree in scienceNrle*ngineering, completion of a l basic'radiationsafetycoursd[andat-least2yearsdf48rkexperienceinradiation
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protection. ' /* R a
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- 13. The licensee shall prep i's and follow a descriptive operating g rocedure in conducting
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N The procedure ~'Od its changes shall be N N
all work involving the}#)icinsed material.
approvedbytheRadia'tonPfoteitionCommittee' appropriate.
ort, Rea'ctor Safeguards Committee as l j af l %} ,
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- H N 14.ThelicenseeshallconductquartetJyinspdcondbctdI'radiationsafetyactivitiesat all work areas. Tte9 nspectioMshAll be s nMcCordance mith'a written b d procedure, and the}if1'ndingsW f fhhiins'pection'di Mnesded / correch ve actions'shall' 3
be transmitted in aL^f,imelfdashio'nif'bthi stfVe!in'sgectedareaaswell' A
as the Radiation Protectioidcofamit' teem lifioMof'a'feyuardsgommitteeasappropr t
Reattor S [ i l 15. The licensee shall p de es nig he th PtIy cs Technicians'
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every 12 months. The cords"of"tg tr i a i kept aty'least 2; years.
l 5l16.
% Release of equipment or maferials for unrestricted use cleanareasonsiteshallbEinaccordance-withtheenclos Annexor'e(d{ rom contaminated.i A, " Guidelines' fg for Decontamination of Facilitiesg nd Equipment Prior to' Release for Unrestricted-Use or Termination of Licenses for(Byproduct,.Sourbet or Special Nuclear Materials,"
q dated July 1982. 6 M P '
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$. k l r# 17. The minimum qualifications for the Criticality Officer or for the individual . -l N responsible for the initial nuclear criticality safety analysis, if'other than: 1 h the Criticality Officer, shall be an accredited college' degree in the physical gi sciences or engineering plus a minimum of 3 years' applicable nuclear safety D g -
experience. The nuclear experience shall include 1 year in outside-of-reactor N g nuclear criticality safety. N 1 y b o H
- 18. There shall be at least one member of the RSC, other'than the Criticality N
Officer, qualified to evaluate nuclear criticality safety when the initial fg j l evaluation under review involving the handling or storage'of special nuclear g l g material in the restricted area (e.g., procedure, audit,. investigation of W g unusual event) was prepared by the Criticality Officer. This member shall N 3
4 : meet the minimum qualifications of the Criticality Officer. I ,
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I P AM ' ^PAGES' l ucense number i MATERIALS LICENSE .
l iSUPPLEMENTAR'Y SHEET I
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I 19.'The 1.icensee shall maintai.n and fully imp,Jement'all provisions of the NRC l , approved Physical Security Plan,-including changes made pursuant to'the f
, authority of 10 CFR 50.54(p) and 70.32(e). . The approved. Physical Security' Plan-t, j is contained in Revision 24 to'the." Safety Analysis Report for the.MIT Research r i Reactor (MITR-II), Appendix 13.B," submitted by letter dated. August.24,,1981. L I L 1 l-I .
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E i FOR THE NUCLEAR REGULATORY COMMISSION- t I )pP I
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L DEC 0 21987 g g: Lehnd C Rouse j lDate: y ,,
d Division of Industrial and. Medical- t I l . Nuclear Safety L Washington, DC 20555 E I
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