ML20245H750
| ML20245H750 | |
| Person / Time | |
|---|---|
| Site: | 07001068 |
| Issue date: | 06/23/1989 |
| From: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20245H722 | List: |
| References | |
| NUDOCS 8906300078 | |
| Download: ML20245H750 (1) | |
Text
_ _ _ _ _ _. _ _ _,
' CC Form 374 '
OF 1-
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U.S. NUCLEAR REGULATORY COMMISSION PAGE I
PACES MATERIALS LICENSE f'
Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, f
Code of Federal Regulations, Chapter I, Parts 30,31,32,33,34,35,40 and 70, and in reliance on statements and representations g
heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct,
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1 source, and special nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below; to r
deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This
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1 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 E
conditions specified below.
Licensee I
University of Florida L
1.
- 3. ucense numbe' SNM-1050, as renewed f
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2.
Gains.sville, Florida 32611 9 r% r'i
- 4. Eipiration date June 30, 1994 E;
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5.- Docket er "1 s\\70-1068 E.
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- 6. Byproduct, source, and/or
.L 7, Chemical and/or physical L8 Maximum amount thatlicensee N
g special nuclear material form
- }may possess at any one time
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.under this license m
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C Uranium enriched up to s.$CladUO[fdel(elements 1190 kg of U-235 b,
4.96w/oU-235q
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- s For' possession:anf use in a%( / g,
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- 9. Authorized use:
ccordance with the statements, representations, anOconditions specif fidiid ithe; licensee's application dated c
E March 1, 1989.
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'10. Authorized place of use:
Nuc ear:Research Field Building as specified in the application' dated'Harchi1>,11989.g~ l}'
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- 11. The licensee shall deconi;aininate facilit"iesfsurfaces, anOquipment in accordance with the enclosed " Guidelines)for Decontamination of Factlities and Equipment Prior to Release for Unrestricted Use on Termination of Licenses for Byproduct, Source,' or i
j Special Nuclear Material, " August"198L 4 g, P l
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- 12. The licensee is hereby exempted from the requirements of 10 CFR 70.24, insofar as
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this requirement applies to materials possessed under this license under normal storage conditions.
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,13. Notwithstanding the retention limit specified in Section 2.8 of the application, i
i the licensee shall maintain records of surveys and personnel exposures in
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accordance with 10 CFR 20.401.
E FOR THE NUCLEAR REGULATORY COMMISSION F
8906300078 89o623
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- Date
JUN 2 31989 r
By:
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Leland C. Rouse i
Ny((/k Washington, DC 20555 L
htg Division of Industrial and l -
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Medical Nuclear Safety i
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Enclosure:
As stated
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l GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE, OR SPECIAL NUCLEAR MATERIAL
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l U.S. Nuclear Regulatory Comission l
Division of Industrial and j
Medical Nuclear Safety l
Washington, DC~ 20555 1
i August 1987 l
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l The instructions in this guide, in conjunction with Table 1, specify the radionuclides and radiation exposure rate limits which should be used in I
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 different.
The release of such facilities or items from regulatory control is considered l
on a case-by-case basis.
1.
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 l
ductwork shall be determined by making measurements at all traps, and other appropriate access points, provided that contamination at these locations is likely to be representative of contamination on the interior i
of the pipes, drain lines, or ductwork. Surfaces of premises, equipment, j
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 contaminated in excess of the limits.
4.
Upon request, the Connission may authorize a licensee to relinquish possession or control of premises, equipment, or scrap having surfaces 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 l
with radioactive materials, or conversion of facilities to a long-term storege or standby status. Such requests must:
a.
Provide detailed, specific infonnation describing the premises, equipment or scrap, radioactive contaminants, and the nature, axtent, and degree of residual surface contamination.
b.
Provide a detailed health and safety analysis which reflects that the residual amounts of materials on surface areas, together with other i
considerations such as prospective use of the premises, equipment, or scrap, are unlikely to result in an unreasonable risk to the health and safety of the public.
l
J 5.
Prior to release of premises for unrestricted use, the licensee shall i
cake a comprehensive radiation survey which establishes that contamination i
is.within the limits specified in Table 1.
A copy of.the survey report shall be filed with the Division of Industrial and Medical Nuclear Safety, 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 premises.
b.
Show that reasonable effort has been made to eliminate residual contamination.
c.
Describe the scope of the survey and general procedures followed.
I d.
State the findings of the survey in units specified in the instruction.
d Following review of the report, the NRC will consider visiting the facilities to confirm the survey.
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