ML20154D409
| ML20154D409 | |
| Person / Time | |
|---|---|
| Site: | 07001703 |
| Issue date: | 09/30/1998 |
| From: | Emeigh C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20154D403 | List: |
| References | |
| NUDOCS 9810070215 | |
| Download: ML20154D409 (3) | |
Text
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.s U.S. NUCl. EAR REGUI.ATORY COMMISSION l
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 matenal 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 Atoraic 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.' Eastman Kodak Company
- 3. License Number SNM-1513, Renewal
- 2. Kodak Park, Building 320 Rochester, New York 14652-6261 O
bf qrp ration Date September 30,2008 Q'
- 5. Docket yo)No 70-1703 V
Reference' se<
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- 6. Byproduct Source, and/org
.' '7s. Chemical and/or Physical -8? Me.
aximum amount that Licensee Special Nuclear Materiag QF,orm
,g May Possess at Any One Time k
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Undeg This License Uranium enriched to Y
- 4% )iumlaluminutil J
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q JUfan Up to.1,582.6 grams (p (al(uminumalokclad friy
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j ' of U;235 located in 5 93.4% in the U-235 }.-
- QF,;J' Neutron Flux Multiplier isotope g
,, the Cblifornium (p-k W:n s 4,W l {
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' " hy M]g4 Et j'
tements/representati[ons, and conditions spe Fo(r,)use in accordance with 9.
Authorized use:
the licensee's applichtion dated March 23,"1998 arid"ss ~ lement dite'd September 30,1998.
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v Authorized place of use/.:4he licensee's Kodak' Park, Building 82)in Rochester, New Y os,t w 10.
described in the above aphl63 tion.
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v The licensee shall comply with th8$ttacfiedgliceMe '66ndition for Leak Testing Sealed Uranium 11.
Sources," April 1993.
12.
Release of equipment or material for unrestricted use 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," April 1993.
- 13. -
The licensee is hereby exempt from the requirements of 10 CFR 70.24 insofar as this section applies to the materials held under this license.
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4 9810070215 980930 PDR ADOCK 07001703 C
NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE 2 or 2 PAGES License Number SNM-1513 Renewal I
MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 70-1703 I
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l 14.
The licensee shall follow the physical protection plan entitled " Licensee Physical Security Plan for the l
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Protection of Special Nuclear Material of Moderate Strategic Significance," dated February 2,1995 l
(transmitted by letter dated April 4,1995) and as it may be further revised in accordance with the l
provisions of 10 CFR 70.32(e).
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FOR THE NUCLEAR REGULATORY COMMISSION
/()4L!v 1%
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NO By: Charles W. Emeigh. Acting Chief l
Date:
l Division of Fuel Cycle Safety and Safeguards Washington, DC 20555 Attachments: 1. License Condition for Leak Testing..
- 2. Guidelines for Decontamination...
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1 LICENSE CONDITION FOR LEAK TESTING SEALED URANIUM SOURCES APRIL 1993 A.
Each uranium source shall be tested for leakage at intervals not to exceed 6 months.
In the absence of a certificate from a transferor indicating that a test has been made within 6 months prior to the transfer, the sealed source shall not be put into use until tested.
B.
The test shall be capable of detecting the presence of 0.005 microcurie of alpha contamination on the test sample.
The test sample shall be taken from the source or from appropriate accessible surfaces of the device in which the sealed source is permanently or semipermanently mounted or stored. Records of leak test results shall be kept in units of microcuries and maintained for inspection by the Commission.
C.
If the test reveals the presence of 0.005 microcurie or more of removable alpha contamination, the licensee shall immediately withdraw the sealed source from use and shall cause it to be decontaminated and repaired by a person appropriately licensed to make such repairs or to be disposed of in accordance with the Commission's regulations.
Within 5 days after determining that any source has leaked, the licensee shall file a report with the Division of Fuel Cycle Safety and Safeguards, U.S.
Nuclear Regulatory Commission, Washington, DC 20555, describing the source, test results, extent of contamination, apparent or suspected cause of source failure, and the corrective action taken. A copy of the report shall be sent to the Administrator of the nearest NRC Regional Office listed in Appendix D of Title 10, code of Federal Regulations, Part 20.
D.
The periodic leak test required by this condition does not apply to sealed sources that are stored and not being used.
The sources excepted from this test shall be tested for leakage prior to any use or transfer to another person unless they have been leak tested within 6 months prior to the date of use or transfer.
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7 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 Comnission Division of Fuel Cycle Safety and Safeguards Washington, DC 20555 April 1993 l
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'The instructions 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 different.
.The release-of such facilities or items from. regulatory control is considered on a case-by-case basis.
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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 j
covering.
3.
The radioactivity on the interior surfaces of pipes, drain lines, or ductwork shall be determined by making measurements at all traps, and other L
appropriate access points, provided.that contamination at these locations is likely to be representative of contamination on the interior of the pipes, t
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 contaminated in excess of the limits.
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'4.
_Upon request, the Commission 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 l
v ay include, but would not be limited to, special circumstances such l
. " razir:0 of buildings, transfer of premises to another organization continuir4 work with radioactive materials, or conversion of facilities to a long-term storage or standby status.
Such requests l
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 the residual amounts of materials on surface areas, together with other 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.
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. 5.
Prior to release of premises for unrestricted use, the licensee shall make a comprehenrive rr.diation 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 I
shall:
a.
Identify the premises, 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 i
facilities to confirm the survey.
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1 AHLE 1 ACCEPT ABt.E SURFACE CONTAMINATION LLVf LS NUCLIDES*
AVERAGE"'
M A XIMUM* * '
R E MOV ABLE,'
2 2
associated decay products 5,000 dpm o/100 cm 15,000 dpm o/100 cm 1,000 dpm o/100 cro Transuranics, Ra-226, Ra-228, Th-230 Th-228, Pa-231, 100 dom / loo cm 300 dom /100 cm 20 dpm/1GO cm 2
2 2
Ac-227,1-125,1-129 Th-nat, Th-232, Sr-90, 2
2 2
Ra-223, Ra-224, U-232,1-126, 1000dpm/100cm 3000 dpm/100 cm 200 dom /100 cm 1-131,1-133 Beta-gamma emitters (nuclides with decay modes other than j
2 2
2 alpha emission or spontaneous 5000 dpm By/100 cm 15,000 dpm #y/100 cm 1000 dpm By/100 cm fission) except Sr-90 and others noted above.
- Where surface contamination by both alpha-and beta-gamma-emitting nuclides exists, the limits establisled for alpha-and beta-gamma-emitting nuclides should apply independently.
- As used in this table, dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the counts per minute observed by an appropriate detector for background, efficiency, and geometric factors associated with the instrumentation.
' Measurements of average contaminant should not be averaged over more than 1 square meter. For objects of less surface area, the average should be derived for each such object.
2 dThe maximum contamination level applies to an area of not more than 100 cm 2
- The amount of removable radioactive material per 100 cm of surface area should be determined by wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. When removable contamination on objects of less surface area is determined, the pertinent levels should be reduced proportionally and the entire surface should be wiped.
'The average and maximum radiation levels associated with surface contamination resulting from beta-gamma emitters should not exceed 0.2 mrad /hr at ' cm and 1.0 mrad /hr at 1 cm, respectively, measured through not more than 7 milligrams per square centimeter of total absorber.