ML20213H181

Renewed License SNM-1513,authorizing Use of 1,582.6 G U-235 for Conditions Specified in 870310 Application

ML20213H181
Person / Time
Site:	07001703
Issue date:	05/13/1987
From:	Bidinger G NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20213H158	List: ML20213H156 ML20213H181 ML20213H189
References
NUDOCS 8705190187
Download: ML20213H181 (3)

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L l wnC rorm 373 PAGE 1

OF 2

man PACES g U.S. NUCLEAR REGULATcRY COMMISSION I

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, l Cods of Federal Regulations, Chapter I, Parts 30,31,32,33,34,35,40 and 70, and in reliance on statements and representations l

l hsretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, I source, and special nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below; to I deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable 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 subject to all applicable rules, regulations and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any l conditions specified below.

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1. Eastman Kodak Company 3. License number SNM-1513, renewed I

Health and Environment Laboratories Kodak Park, Building 320 1 l 2. Rochester, New York 14650 3 -

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l h hbg 2 lEpNti e May 31, 1992 j j

5. Docket or i ,N)P0-1703 l l y Reference No. .  !

l 6. Byproduct, source,and/or 7. Chemical and/or physical U Maximum amount thatlicensee i special nuclear material _

form '

ay possess at any one time .

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% der thislicense v

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w O 1 Uranium enriched to I hr i mig m I Up 1,582.6 grams I <

N 93.4% in the U-235 p Isotope

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of E:235 located in th'e Californium N

u Ne bon Flux l l 9 M% plier.(CFX) i i 0 h ~

,N, rep,reke'ntations,and i

9. Authorized Use: For\Nein eco ance ti t t i conditions specified ifthe l'icenue' ' Eli i ated MaMh 10, 1987.  !

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l 10. Authorized Place of Use: licensee's esearchLaboyAt@oriesBuildingNo.8? l g in Rochester, New York, as cribed in the above app 1rc& tion. i

11. Notwithstanding Section 2.2 of t ahikk i

a. The Chairman of the Radiation Protection Consnittee shall have at least l 5 years experience in management including 2 years working with ionizing l l

radiation, j i i i b. The Radiation Safety Officer shall have at least 2 years work experience ;i i in health physics. j i  ?

l 12. The licensee shall establish, maintain, and follow written procedures for carrying out the health physics activities. The procedures shall be approved f

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i by the Radiation Safety Officer. ]

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8705190187 870513  !

l PDR ADOCK 07001703

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p--n- -----------------n --na-w--Emax&wn--n-n------wn--q l NRC Form 374A U.S. NUCLEAR KEGULATORY COMMISSION , 7 g g i License number i I

! MATERIALS LICENSE N

N SUPPLEMENTARY SHEET * * "*'*"" IO 703 I I i I I I i N

l 13. The RS0 shall conduct quarterly inspections of radiation safety at all work areas. The inspection shall be conducted in accordance with a written procedure, I

l I and the findings of the inspection with needed corrective actions shall be u transmitted to the supervisor of the inspected area and the Radiation Protection H l Committee.

lI 14. Notwithstanding the retraining in Section 3.5 of the application, the retraining of operators in radiation safety and safe operations of CFX shall be performed at ih W

l intervals not to exceed 14 months. E' I i l 15. Release of equipment or material or n eshriL(te fuse shall be in accordance with E l y the enclosed Annex A, "GuideJipe econtamin tio'n Md Use or Termination /of Facilities and Equipment offlicenses T

for Byproduct,

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g Prior to Release for Unrestr49 [

( Source, or Special Nucle aterial," May 1987. *A  !!

16. Notwithstanding the sta ment on wipe testing in Section 5. 3 Page 11, of the I application, the lice 6s e ij[ah comply with the enclosed 1tEnel)'B, " License Condition

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l for Leak Testing Se Uranic' rces," May 1987 [

17.Thelicenseeshallhohductmon.b abovethecavityoutpdeBuild) i h p1 ury ej$, of the ensure control room and the h) radiation levels fW N

(grgdjlev l' l are within regulat p limi l 18.Manipulationofthe@umi elw) s h W 'e die'notauthorized. ,

n li 5 19.Thelicenseeshalln(Mposses hmat. "'al other than the h

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N 1,582.6gcontainedU-J35ati i N]fcensdM i (/)

20. The licensee is hereby pt from the( hedenf! f 10 0.24 (d) insofar as j the section applies to ma rial held r!n ils license. I H 3 h  !

Enclosures:

An A

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R l 4 l 1 i FOR THE U. S. NUCLEAR REGULATORY COMMISSION l N i I

W y Original Signed By:

1 4 MAY 1319F By: George H. Bidinger l

i l Date:

i Division of Fuel Cycle, Medical, i Academic, and Commercial Use Safety, NMSS Washington, DC 20555 l l

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ANNEX A 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 Comission Division of Fuel Cycle, Medical, Academic, and Comercial Use Safety Washington, DC 20555 May 1987 l

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The instructions in this cuide, 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 I censidered on a case-by-case.

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 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 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 a of measurement shall be presumed to be contaminated in excess of..the limits.

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 may ]

include, but would not be limited to, special circumstances such as razing of buildings, transfer to premises to another organization continuing work with radioactive materials, or conversation of facilities to a long-term l 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.

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! b. Provide a detailed health and safety analysis which reflects that the Q

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 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, Medical, Academic, and Comercial Use 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.

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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.c TABLE 1 e- ,

c -r ACCEPTABLE SURFACE CONTAMINATION LEVELS ,

MAXIMUMbdf REMOVABLEbef NUCLIDESa AVERAGEbcf U-nat, U-235, U-238, and 2 15,005 dpm a/100 cm2 1,000 dpm a/100 cm2 associated decay products 5,000 dpn o/100 cm .

Transuranics Ra-226. Ra-228 300 dpm/100 cm.2 20 dpm/100 cm2 Th-230. Th-228. Pa-231, 100 dpm/100 cm2

, Ac-227. I-125, I-129 ,

l' Th-nat, Th-232, Sr-90, I

200 dpm/100 cm2 1000.dpm/100 cm2 3000 dpm/100 cm2

! Ra-223, Ra-224. U-232, I-126, 1-131,'l-133

! Beta-gamma emitters (nuclides with decay modes other than 15,000 dpm sy/100 cm2 1000 dpm sy/100 cm2

' alpha emission or spontaneous 5000 dpm sy/100 cm2

l. fission)exceptSr-90and .

others noted above.

aWhere surface contamination by both alpha- and beta-gamma-emitting nuclides exists, the limits established for alpha- and beta-gamma-emitting nuclides should apply independently.

bA s used in f S table, dpm (disintegrations per minute) means the rate of emission by radioactive material as detemined by correcting the counts per c mute 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 i square meter. For objects of less surface area,'the~ average should be derived for each such object. ,

.d The maximum contamination level applies to an area of not more than 100 cm2

! 'The amount of removable radioactive material. per 100 cm 2 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. .

f The average and maximum radiation levcis associated with. surface contamination resulting from beta-gamma emitters should not exceed 0.2 mrad /hr at I cm and 1.0 mrad /hr at 1 cm respectively, measured through not more than 7 milligrams per square centimeter of total absorber. . .

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l ANNEX B l LICENSE CONDITION FOR LEAK TESTING l

SEALED URANIUM SOURCES MAY 1987 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.

i 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.,

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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, Medical, Academic, and Commercial Use Safety, U.S. Nuclear Regulatory Commission, Washington, DC 20555, describing the source, the test results, the extent of contamination, the 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 l 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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