ML20153B677

License SNM-1373 for Idaho State Univ,Renewed

ML20153B677
Person / Time
Site:	07001374
Issue date:	09/16/1998
From:	Emeigh C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20153B668	List: ML20153B664 ML20153B677 ML20153B681
References
NUDOCS 9809230216
Download: ML20153B677 (2)

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U.S. NL.'CLFAR REGtJLATORY COMMISSION MATERIALS LICENSE l Pursuant to the Atomic Energy, A.:t 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 rehance 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 rpecial 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 tc 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 specined below.

Licensee

1. Idaho State University 3. License Number SNM-1373, Renewal

2. Pocatello, Idaho S3209-0009 4. Expiration Date September 30,2008

5. Docket No. 70-1374

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6. Byproduct Source, and'or s iChemical and/or Physical NO 3 8. Maximum amount that Licensee Special Nuclear Material N Form i May Possess at Any One Time t

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A. - Uranium enriched to A. ;150 Clad uraniurn , 'A. 1511 grams U-235

-s 20 wt% in the U-235 - . aluminum fuel plates isotope  !

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B. Uranium enriched to W ;B. 74 Ulai)ium-aluminum. . B'. 1 gram U-235

< 93 wt% in the U-235 G T ; foils and one; isotope 59 ~ fission'600nterj C[

9, Q v y h) f Authorized use: For use in"accordance with the statements, representations, and conditions specified in the application dated July 24' 1998. ,

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10. Authorized place of use: The Lillibridge Engineering Laboratory Building and three Accelerator Center facilities at Idaho State University, Pocatello, Idaho.

9 9809230216 980916 I PM ADOCK 07001374, C PM L

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NRd FOR.\l 374A [f.S. Nt' CLEAR REGt'ISIORY CO)l\llSSION PAGE 2 or 2 PAGES License Number

SNM-1373 MATERIALS LICENSE Met or Reference Nurnber SUPPLEMENTARY SilEET 70-1374 Renewal

11. Release of equipment or materials for unrestricted use, or from contaminated to clean 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 Materials," April 1993.

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'~ M M k,SM E,f , 1 Date: (Ill6 Y By: _ Charles W Emeighlgting Chief  ;

Division of Fuel Cyc!e Safety and Safeguards Washington, DC 20555 ,

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Attachments:

1. Guidelines for Decontamination . .

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GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE i

. OR TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE, OR SPECIAL NUCLEAR MATERIAL e

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f U.S. Nuclear Regulatory Commission Division of Fuel cycle Safety and Safeguards Washington, DC 20555 .

April 1993 b /

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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 1 decontamination and survey of surfaces or premises and equipment prior to l abandonment or release for unrestricted use. The limits in Table 1 do not i apply to premises, equipment, or scrap containing induced radioactivity for )

which the radiological considerations pertinent to their use may be different. 1 The release of such facilities or items from regulatory control is considered I on a case-by-case basis. I l

1. The licensee shall make a reasonable effort to eliminate residual l contamination.

2. Radioactivity on equipmen' or surfaces shall not be covered by paint, I plating, or other covering material unless contamination levels, as determined by a survey and documented, are below the limits specified in Table 1 pric *n 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 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 limita 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 i facilities to a long-term storage or standby status. Such requests must: j

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 I I

the premises, equipment, or scrap, are unlikely to result in an unreasonable risk to the health and safety of the public. l 1

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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 Safety and Safeguards, U. S. Nuclear Regulatory Commission, Washington, DC 20555, and also the Administrator of the NRC Regional i 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.

Following review of the report, the hRC will consider visiting the j facilities to confirm the survey.

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ACCEP1 ABt.E SUHFACE CONTAMINATION LEVELS i

NUCLIDES* AVER AGE * " MAXIMUM **'

R EM O VABLE* * ',

U nat. U-235 U-238, and associated decay products 5.000 dom o/100 cm' 15,000 dpm o/100 cm2 1,000 dpm o/100 cm 2 Transuranics, Ra-226, Ra-228, i T h-230, Th-228, Pa-231, 100 dpm/100 cm2 300 dom /100 cm2 20 dpm/100 cm 2 Ac-227,1-125,1-129 Th-nat, Th-232, Sr-90, Ra-223, Ra-224, U-232,1-126, 1000 dom /100cm' .3000 dpm/100 cm2 200 dpm/100 cm 2 1-131,1-133

- Beta-gamma emitters (nuclides with decay modes other than i alpha emission or spontaneous 5000 dpm Br/100 cm 2 15,000 dpm By/100 cm2 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 established 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.

"The maximum contamination level applies to an area of not more than 100 cm'.

• The amount of removable radioactive material per 100 cm2 of surface area should be determined by wiping that area with dry filter or sof t absorbent paper, applying moderate pressure, and assessing the amount of radioactive materiai 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. ,

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'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 i absorber.

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