ML20137D013
| ML20137D013 | |
| Person / Time | |
|---|---|
| Site: | 07000938 |
| Issue date: | 11/13/1985 |
| From: | Crow W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20137D011 | List: |
| References | |
| NUDOCS 8511260685 | |
| Download: ML20137D013 (3) | |
Text
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3 PAGE OF PACES 1 0. a 4 U.S. NUCt. EAR REGULATORY COMMISSION I
1 MATERIALS LICENSE y
Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93 -438), and Title 10, 1
Code of Federal Regulations, Chapter I, Parts 30,31,32,33,34,35,40 and 70, and in reliance on statements and representations y
1 heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, g
1 source, and special nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below; to l
1 deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This l
I license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is I
subject to all applicable rules, regulations and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any
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1 1. Massachusetts Institute of Technology
- 3. License number SNM-986, as renewed ju
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Nuclear Reactor Laboratory 8
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2.138 Albany Street
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Cambridge, MA 02139
- 4. Expiration date November 30, 1990 y
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1 S. Docket or 70-938 1
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Reference No.
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- 6. Byproduct, source, and/or
- 7. Chemical and/or physical 8., Maximum amount that licensee N
3 special nuclear material form may possess at any one time U
t..sfer this license 1
p A. Uranium enriched to A. Solid (U0 ), clad A. *32,000 grams of U-235 y
1 less than 2.0 wt%
andunclab li l
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in the U-235 isotope.
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1 less than 93 wt%
include material in p
1 in the U-235 isotope -
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3 C. Plutonium C. Pu-Be neutron source C. 197 grams n
3 and Pu-Al neutron i
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1 D. Plutonium D. Solid alpha source; D. 80 u9 B,
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1 E. Plutonium E. Solid, foil E. **172.0 grams b
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F. Natural Uranium F. Solid and solution F. 2515 kilograms l
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l G. Depleted Uranium G. Any G. ***238.2 kilograms p
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H. Any byproduct material H.
Unseparated H. Quantities produced p
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unseparated contained during irradiation f
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- 9000 grams for storage only b
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- for storage only I
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- 58.2 kilograms for storage only i
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NIC Form 374A U.S. NUCLEAR REGULATORY COMMISSION 2
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SNM-986 MATERIALS LICENSE 70-938 k)
SUPPLEMENTARY SHEET l
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Authorized Use.
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For use in accordance with statements, representations, and conditions contained in f
the licensee's revised application dated July 13, 1984.
1 1 10. Authorized Places of Use:
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The MIT Campus, Cambridge, Massachusetts; Bates Linear Accelerator, Middleton, Massachusetts; and the Lincoln Laboratory, Lexington, Massachusetts.
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1 11. This license does not authorize the. insertion of licensed material into a nuclear 1
reactor.
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1 12. The minimum technical qualifications for the position of Radiation Protection Officer s
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shall be a bachelor's degree in science or engineering, completion of a basic g
3 radiation safety course, and at least 2 years of work experience in radiation p
5 protection.
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3 1 13. The licensee shall prepare and follow a descriptive operating procedure in conducting Q
1 all work involving the licensed material. The procedure and its changes shall be j
approved by the Radiation Protection Committee.
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q a 14. The licensee shall conduct quarterly 7 inspections of. radiation safety activities at all 4
a work areas. The inspection shall be conducted in accordance with a written procedure, a
1 and the findings of the inspection with needed corrective actions shall be transmitted g
1 in a timely fashion to the supervisor of the inspected area as well as the Radiation p
j Safety Committee.
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)j 15. The licensee shall provide refresher training to the Health Physics Technicians every 3:
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12 months. The records of the training shall be kept at least 2 years.
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{! 16. Release of equipment or materials for unrestricted use or fro 1
_j areas onsite shall be in accordance with the enclosed Annex A, " Guidelines for i
7 Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or e:
y Termination of Licenses for Byproduct, Source or Special Nuclear Materials," dated p
f July 1982.
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1! 17. The minimum qualifications for the Criticality Officer or for the individual
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1 responsible for the initial nuclear criticality safety analysis, if other than the
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Criticality Officer, shall t'e an accredited college degree in the physical sciences or :Dj 3
engineering plus a minimum of 3 years' applicable nuclear safety experience. The j
nuclear experience shall include 1 year in outside of reactor nuclear criticality j!!
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safety.
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NRC Form 374A U.S. NUCLEAR REGULATcRY COMMISSION 3
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Licznse number l
i MATERIALS LICENSE SNM-986 l
SUPPLEMENTARY SHEET O )
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ja j 70-938 g
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1 1 18. There shall be at least one member of the RSC, other than the Criticality Officer, l
I qualified to evaluate nuclear criticality safety when the initial evaluation under I
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review involving the handling or storage of special nuclear material in the restricted l
j area (e.g., procedure, audit, investigation of unusual event) was prepared by the 3
Criticality Officer. This member shall meet the minimum qualifications of the 1
Criticality Officer.
I 1 19. The licensee shall maintain and fully implement alF provisions of the NRC approved
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Physical Security Plan, including changes made pursuant to the authority of 10 CFR 50.54(p) and 70.32(e). The approved Physical Security Plan is contained in Revision l
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24 to the " Safety Analysis Report for the MIT'Research Reactor (MITR-II), Appendix
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1 13.B," submitted by letter dated August 24, 1981.
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1 FOR THE U.S. NUCLEAR REGULATORY COMMISSION I
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Original Signed By,t l
1 NOV 1319BI W.T.crov g
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By:
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Division of Fuel Cycle and I
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Material Safety, NMSS l
Washington, D.C.
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