ML20154B801
| ML20154B801 | |
| Person / Time | |
|---|---|
| Site: | 07000152 |
| Issue date: | 05/06/1988 |
| From: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20154B767 | List: |
| References | |
| NUDOCS 8805170312 | |
| Download: ML20154B801 (3) | |
Text
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U.S. NUCLE AR REGULATORY COMMISSION
._ O F PAGgs g
MATERIALS LICENSE j
! Pursuant to the Atomic Energy Act of 1954. as amended, the Energy Reorganization Act of 1974 (Public Law 93 -438). and Title 10, I
i Code of Federal Regulations. Chapter I Parts 30,31. 32,33,34,35,40 and 70 and in reliance on statements and representations heretofore made by the licensee, a license is hereby issued authorizing the licensee to receise, acquire, possess, and transfer byproduct.
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- source, and special nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below;to J deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the appheable Part(s). This 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 i
subject to all applicable rules, regulations and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below.
y Licensee N
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t lI-Purdue University SNM-142, f
- 3. License number Amendment No. 1
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2.
i West Lafayette, Indiana 47907 I
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- 4. Expiration date June 30, 1992 I
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- 5. Duket or g-Reference No.70-152 p.
k; 6. Byproduct, source, and/or
- 7. Chemical and/or physical
- 8. Maximum amount that licensee F.
special nuclear material form may possess at any one time I
i under this license l
6 k
+
i A.
Uranium enriched in A.
SPERT fuel rods, A.
81,000 grams y
the U-235 isotope enriched 5 4.8 w/o U-235 g
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B.
Uranium enriched in B.
Fuel rods, enriched B.
32,000 grams l
h the U-235 isotope 1 1.3 w/o U-235 g
C.
Uranium enriched in C.
Solid helices, C.
200 grams p
i the U-235 isotope enriched < 20 w/o p
U-235 W
t
(*
0.
Uranium enriched in D.
Solid discs, D.
10 grams
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the U-235 isotope enriched 1 3 w/o U-235 g.
t E.
Plutonium E.
Encapsulated PuBe E.
80 grams Pu t
f4 neutron sources D.
k F.
Plutonium F.
Waste as metal, salts F.
1 gram k
and solution l.
G.
Natural Uranium G.
U03 pellets clad in G.
11,760 kilo-p aluminum grams U t
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V H.
Californium H.
Up to 10 doubly H.
0.007 gram Cf
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encapsulated sources y
V I. Uranium 233 I.
Plated source I.
0.01 pCi U-233
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- 1 g
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N'IC Form 374 A u.S. NUCLE AR REGuLAToaY CoMMisStoN l 3
PAGE 2
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ocenu number SNM-142, Amendment No. 1 MATERIALS LICENSE SUPPLEMENTARY SHEET li
- p 1'
.N 1
R I
J. Neptunium 237 J. Plated source J. 100 pCi lN (0.014 gram)
- v. Plated source K. 100 pCi l
fK. Plutonium 238 l'
(0.58 pg) i i
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L. Thorium 230 L. Plated source L. 100 pCi
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(0.5 mg) j M. Plated source M. 100 pCi
)
fM. Actinium 227 1
(0.14 pg) p n!
1:
N. Curium 244 N. Plated source N. 100 pCi
{f9.
(0.12 pg)
Authorized use:
For receipt, possession, and use in accordance with the j
statements, representations, and conditions specified in the licensee's y
3) application dated September 17, 1986, and addenda cated August 12, 1981 g
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(page 5 part a).
F 1
R E
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- 10. Authorized place of use:
The materials specified in A through N above f
shall be used in locations specified in the application dated September 17, f
g 1986.
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- 11. Refresher seminars which cover radiation safety procedures shall be conducted K
1.
on an annual basis (maximum interval 15 months) for all employees and/or W
I students who use radioactive material.
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F l;12.Ifpersonalclothingand/orskincontaminationlevelsareabovebackground, f
q persons shall not exit an area without approval of the Radiological Control p-q:
Officer.
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h 1 13. Release of equipment or material from Purdue University for unrestricted E-I use shall be in accordance with the enclosed "Guidelines for Decontamination f
l of facilities and Equipment Prior to Release for Unrestricted Use or
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l Termination of Licenses for Byproduct, Source, or Special Nuclear Material" g
q q
May 1987.
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V i 14. Storage of U0, fuel rods in the Duncan Annex Storage Facility and the F88F i
shall be in accordance with representations for Duncan Annex, page 5, of
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l the Addenda enclosed with the licensee's letter dated August 12, 1981.
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E q.
- 15. The Fast Breeder Blanket Facility shall not be operated with a measured
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4' normal operation k-eff greater than 0.45.
In addition, the fuel loading P
1 shall be limited such that the calculated k-eff would not exceed 0.75 if
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the F88F were accider, tally flooded with water.
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PAGE o,
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- ucense number
- l MATERIALS LICENSE
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SUPPLEMENTARY SHEET I
I il
- f 1
- I 1
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- 16. Fuel shall be transferred in 8-inch diameter cylinders.
Fuel haadling
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procedures shall be carried out in such a way that no more than one B!
3 loaded cylinder will be in the storage area, in transport, or in the FBBF E-f; f
at the same time.
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- 17. The licensee is hereby exempted from the requirements of 10 CFR 70.24 g
1 insofar as the section applies to the stored material in the Duncan Annex I
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and the Pharmacy Building.
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3:
I 18. As it pertains to License SNM-142, the licensee shall fully implement and maintain in f f
effect all provisions of the approved 10 CFR 73.67 physical security plan, including g
changes and amendments made pursuant to 10 CFR 70.32(e) and 10 CFR 70.34.
The 1!
approved physical security plan, which was submitted by letter dated May 15, 1987, 1;
consists of a document containing Safeguards Information entitled, "Security Plan h
1 for the Purdue University Reactor, the Fast Breeder Blanket Facility and the Nuclear 0
f
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Fuel Storage Areas," Revision 3, dated May 15, 1987."
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i FOR THE NUCLEAR REGULATORY COMMISSION P
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l Origina!S@ed 4 Bl Date: l?AY 6 1988 By:
Leland C. Rouse 1
Division of Industrial ana Medical Nuclear Safety f
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