ML20236W187

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Amend 2 to License SNM-986 for Mit,Authorizing Possession of 2 Mg U-233 for Storage by Adding Conditions 6.I,7.I,8.I & Revising Condition 9 to Incorporate 871104 Application
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)
v • d • e


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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: <

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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 :

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  • 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 -

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<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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NRC Form 374A -

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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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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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  1. 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.

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% 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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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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