ML20210L559
| ML20210L559 | |
| Person / Time | |
|---|---|
| Site: | 07000152 |
| Issue date: | 07/30/1999 |
| From: | Sherr T NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20210L553 | List: |
| References | |
| NUDOCS 9908090167 | |
| Download: ML20210L559 (6) | |
Text
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NRC FORM 374 u.s. NUCLEAR REGULATORY Commission MATERIALS LICENSE Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Code of Federal Regulations, Chapter I, Parts 30,31,32,33,34,35,36,39,40, and 70, and in reliance on statements and representations heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct.
source, and special nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below; to deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations, and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below.
Licensee
- 1. Purdue University
- 3. License Number SNM-142, Renewal
- 2. West Lafayette, Indiana 47907
- 4. Expiration Date August 31,2009
- 5. Docket No.70-152 Reference No.
- 6. Byproduct Source, and/or
- 7. Chemical and/or Physical
- 8. Maximum amount that Licensee Special Nuclear Material Form May Possess at Any One Time Under This License A.
Uranium enriched in A.
SPERT fuel rods, A.* 81,000 grams the U-235 isotope enriched 5 4.8 w/o U-235 B.
Uranium enriched in B.
Fuel rods, B.*
32,000 grams the U-235 isotope enriched 51.3 w/o U-235 C.
Uranium enriched in C.
Solid helices, C.
200 grams the U-235 isotope enriched 5 20 w/o U-235 D.
t Esnium enriched in D.
Solid discs, D.
10 grams the U-235 isotope enriched 5 3 w/o U-235 E.
Uranium enriched in E.
- Samples, E.
10 grams the U-235 isotope enriched 5 20 w/o U-235 F.
Plutonium F.
Encapsulated PuBe F,
80 grams neutron sources G.
Natural Uranium G.
UO pellets clad in G.* 11,760 kilograms U 2
aluminum H.
Natural Uranium H.
Samples, any form H.
10,000 grams U l.
Californium I,
10 doubly I.* 0.002 gram encapsulated sources J,
Uranium 233 J.
Calibration sources J.
0.1 pCl N 9'dOU9d167 990730 PDR ADOCK 07000152 C
u.s. NUCLEAR REGULATORY Commission Page 2 of 2 License Number SNM-142 Renewed MATERIALS LICENSE oocket or Reference Number SUPPLEMENTARY SHEET 70-152 K.
Neptunium 237 K.
Calibration sources K.
100 pCi L.
Plutonium 239 L.
Calibration sources L.
100 pCi M.
Curium 244 M.
Calibration sources M.
100 pCi
- 9.. Authorized use: For use in accordance with statements, representations, and conditions specified in the license application dated May 4,1999.
- 10. Authorized place of use: The licencee's existing Purdue University Campus at West Lafayette, Indiana.
- 11. Notwithstanding Sections 6.0(c) and 9.1(b),of the application dated May 4,1999, the licensee is required to have NRC approval by license amendment before using (e.g., moving) the SPERT fuel rods, fuel rods, californium sources, or natural uraniu' pellets.
m
- 12. Notwithstanding Section 8.5N he application dated May 4,1999, refresher training that covers radiation safety procedures shall be conducted on an annual basis (maximum interval 15 months) for all employees and students who use licensed material.,
- 13. Release of equipment, facilities, or packages to the unrestricted area or to uncontrolled areas onsite shall be in accordance with the attached " Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, Or Special Nuclear Material" dated April 1993.
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- 14. The licensee is hereby exempted from the requirements of'10 CFR 70.24 insofar as the Section applies to the stored materialin the Duncan Annex.
- 15. As it pertains to License SNM-142, the licencee shall fully implement and maintain in effect all provisions of the approved 10 CFR 73.67 physical security plan, including changes and amendments made pursuant to 10 CFR 70.32(e) and 10 CFR 70.34. The approved physical security plan, which was submitted by letter dated May 15,1987, consists of a document containing Safeguards Information entitled, " Security Plan for the Purdue University Reactor, the Fast Breeder Blanket Facility and the Nuclear Fuel Storage Areas," Revision 3, dated May 15,1987."
FOR THE NUCLEAR RE LATORY COMMISSION
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O Ih B! Theodore S. Sherr. Chief Date:
Division of Fuel Cycle Safety and Safeguards Washington, DC 20555
Enclosure:
Guidelines for D: contamination of Facilities and Equipment...dtd 4/93
e GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE, OR SPECIAL NUCLEAR MATERIAL U.S. Nuclear Regulatory Commission Division of Fuel Cycle Safety and Safeguards Washington, DC 20555 April 1993
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TheLinstructions'in this guide, in conjunction ~with Table 1, specify the radionuclides and radiation exposure rate limits which should be used.in decontamination and survey of. surfaces or premises and equipment prior to abandonment or release for unrestricted use. The limits in Table 1 do not apply to premises, equipment, or scrap containing induced radioactivity for which'the. radiological considerations pertinent to their use may be diffsrent.
The release of such facilities or items from regulatory control is considered on a case-by-case basis.
1
'l.
The licensee shall make a reasonable effort to eliminate residual contamination.
2.
Radioactivity on equipment or surfaces shall not be covered by paint, plating, or other covering material unless contamination levels, as determined by a survey and documented, are below the limits-specified in Table 1 prior to the application of the covering. A reasonable effort must be made to minimize the contamination prior to use of any covering.
3.
The radioactivity on the interior surfaces of pipes, drain lines, or i{
ductwork shall be determined by stiing measurements at all traps, and other appropriate access points, prov10 i that contamination at these locations is likely to be representative of cc tamination on the interior of the pipes, drain lines, or ductwork.
Surfaces'of premises, equipment,.or scrap which are likely to be contaminated but are of such size, construction, or location as to make the surface inaccessible for purposes of measurement shall be presumed to be contamP ated in excess of the Ibnits.
i 4.-
Upon request, the Commission may authorize a licensee to relinquish possession or control of promises, equipment, or scrap having surfaces 1
contaminated with materials in excess of the limits specified. This may include, but would not be limited to, special circumstances such
-as-razing of buildings, transfer of premises to another organization continuing work with radioactive materials, or conversion of fac!.lities to a long-term storage or standby status. such requests must:
a'.
Provide detailed, specific information describing the premises, equipment or scrap, radioactive contaminants, and the nature, extent, and degree of residual surface contamination.
b.
Provide a detailed health and safety analysis which reflects that tha residual amounts of materials on surface areas, t
together'with other considerations such as. prospective use of the premises, equipment, or scrap, are unlikely.to result in an unrossonable risk to the health and safety of the public.
. 5.
Prior to release of premises for unrestricted use, the licensee shall make a comprehensive radiation survey which establishes that contamination is within the limits specified in Table 1.
A copy of the survey report shall be filed with the Division of Fuel Cycle Safety and safeguards, U. S. Nuclear Regulatory Commission, Washington, DC 20555, and also the Administrator of the NRC Regional office having jurisdiction. The report should be filed at least 30 days prior to the planned date of abandonment. The survey report shall:
a.
' Identify the promises.
b.
Show that reasonable effort has been made to eliminate residual contamination.
Describe the scope of the survey and general procedures followed.
c.
d.
State the findings of the survey in units specified in the instruction.
Following review of the report, the NRC will consider visiting the facilities to confirm the survey.
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