ML20137B207

Amend 1 to SNM-1373 for Idaho State University

ML20137B207
Person / Time
Site:	07001374
Issue date:	03/17/1997
From:	Weber M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20137B205	List: ML20137B199 ML20137B207 ML20137B214
References
NUDOCS 9703210216
Download: ML20137B207 (7)

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U.S. NUCLE AR REGULAToCY COMMIS$50N t l l (l MATERIALS I.ICENSE g'g

'p' ll i ursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Lawj 93-4 p!

d Cede of Federal Regulanons Chapter I, Parts 30,31,32,33,34,35,39,40 and 70, and in reliance on statements and representations heretofore y d made by the licensee, a license is hereby issued authoruing the licensee to receive. acquire, possev 'nd transfer byproduct. source, and special l I 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 k to persons authorved to receive it in accordance with the regulations of the applicable Pan (s). This license shall be deemed to contain the conditions g ! spcified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations and orders of the N

{ Regulatory Commission now or hereafter in effect and to any conditions specified below. p di 0 ,

f Licensee I{

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1. Idaho State University 3. License number SNM-1373. Amendment 1 1 L I I:

g 2. Pocatello. Idaho 83?no-0009 'I!

N 4. Expiration date October 31, 1997 t l fi I 1

5. Docket or I ll 70-1374 q Reference No y l 1

I; 6. Byproduct, source, and/or

7. Chemical and/or physical 8. Maximum amount that hcensee ) l

! special nuclear material form may possess at any one time f i fI under this license

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I A. Uranium enriched in A. Clad uranium- A. 1511 grams U-235 ji '

I the U-235 isotope aluminum fuel plates I

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g B. Uranium enriched in B. Uranium-aluminum B. 1 gram U-235 !g i i the U-235 isotope foils and ;E 1 fission counters ;E ill lE Plutonium C. Encapsulated Pu-Be C. 20 grams Pu

[ C. neutron sources {j j i l

9. Authorized use: The materials specified above shall be used in accordance with the lEr l I statements, representations, and conditions specified in the application dated [

l March 13, 1991; supplements dated June 8, July 1, and July 13, 1992; and letter y dated January 31, 1997.

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d l 10. Authorized place of use: The materials specified in Conditions 6. A and B above lp g- shall be used in the Lillibridge Engineering Laboratory at Idaho State University. E l The materials specified in Condition 6.C above shall be used in the til11 bridge ;E ,

1 Engineering Laboratory when the subcritical assembly is in operation and shall be l stored in a neutron howitzer in a vault in the Physical Science Building basement at A{ l l other times. p' I 11 . The Reactor Safety Committee shall review all new activities and procedures and any i

changes to the plans and procedures for the usage of licensed materials prior to

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< q A 1 l I 12. The Radiation Safety Officer shall be responsible for ensuring periodical performance l

' of instrument calibrations, radiation surveys, and leak tests c'id reviewing radiation l

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l exposure records. {[J I

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I l - j 9703210216 970317 I' ADOCK 0700 4 DR E______________-________._________._______________

1_utw w w w wouusustuuuumundsusumuni = w = s = w w w 6 w w w mg NR FORM 374A U.S. NUCLEAQ REGULATORY COMMISSION 2 PAGE OF 2 PAGES g License Number

, g SNM-1373 Amendment 1 g

a. MATEi!!ALS LICENSE Ixxtei or Reference Number g SUPPLEMENTARY SHEET 70-1374 4 g-N N R E N s N N N N N E N N

W 13. The licensee shall comply with the attached " License Condition For Leak Testing g N Sealed Plutonium Sources," August 1987. g E E N 14. Release of equipment or materials for unrestricted use or from contaminated to clean g N areas onsite shall be in accordance with the attached " Guidelines for Decontamination a N of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of g h Licenses for Byproduct, Source, or Special Nuclear Materials," August 1987. g N q u 15. The licensee shall calibrate all radiation detection' instruments used in connection g N' with this license prior to each use, unless the instrument has been calibrated within g W the 6 months preceding such use. g N g g 16. The licensee shall review emergency procedures; conduct drills;'and maintain, y p inspect, and test all emergency equipment, including the communication and alarm y y systems; on a periodic schedule consistent with good industry practice, but at least y 4 g once a year. g M N N <

a N N N g N N N . N N N N N N N i N E N N N N N N N N FOR THE NUCLEAR REGULATORY C0milSSION l

N N NYWUA l N Date:

• By: Michael F. Weber U N Division of Fuel Cycle Safety E N and Safeguards a N Washington, DC 20555 N N 5 N Attachments: 8 E 1. License Condition for Leak Testing ... 8 N 2. Guidelines for Decontamination ... E N N N R ,

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l LICENSE CONDITION FOR LEAK TESTING SEALED PLUTONIUM SOURCES AllGl'ST 1987 i

A.

Eacn plutonium source shall be tested for leakage at intervals not to exceed 6 months. 1 In the absence of a certificate from a transferer indicating that a test has been made within 6 months prior to the transfer, the seeled source shall 'ot be put into use until tested.

B. The test shall be capable of detecting tbc 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 semipermarently 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 'of in accordance with the Commission's regulations. Within 5 days after determining that ary source has leaked, the licensee shall file a report with the Division of Industrial and Medical Nuclear Safety U.S. Nuclear

.Pegulatory Commission, Washington, DC 20555, describing the source, test results, extent of contamination - apparent or suspected cause of source failure, and corrective Action taken. A copy of the repcrt shall be sent to the Administrater 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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P GUIDELINES FOR DECONTAMINATION OF FACILITIE PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE, OR SPECIAL NUCLEAR MATERIAL 1

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l U.S. Nuclear Regulatory Commission Division of Industrial and Medical Nuclear Safety Washington, DC 20555 August 1987 a

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l The instructions in this guide, in conjunction with Table 1, specify the i radionuclides and radiation exposure rate limits which should be used in 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 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 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 Ifmits. !

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 of premises to another organization continuing work with radioactive materials, or conversion of facilities to a long-term storage or standby status. Such requests must:

a. Provide detailed, specific infonnation describing the premises, equipment or scrap, radioactive contaminants, and the nature, extent, and degree of residual surface contamination.

l b. Provide &< detailed health and safety analysis which reflects that the residual amounts of materials on surface areas, together with other r

' 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 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. i The survey report shall:  ;

a. Identify the premises.

b. Show that reasonable effort has been made to eliminate residual l contamination. 1

c. Describe the scope of the survey and general procedures followed.

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d. State the findings of the survey in units specified in the instruction.

Following review of the report, the NRC will consider visiting the l facilities to confirm the survey. l

TABLE 1 ACCEPTABLE SURFACE CONTAMINATION LEVELS AVERAGEbcf fM11MUMbdf kEMOVABLEbef NUCLIDE5a ,

-nat. U-235. U-238, and ssociated decay products 5.000 dpa e/100 cm2 15.000 dpa e/100 cm2 1.000 dpm ./100 c 2

• l ransuranics. Ra-226. Ra-228 2 300 dps/100 cm2 20 dpe/100 cm2 h-230, th-228. Pa-231 (100dpe/100cm c-227. 1-125. 1-129 .

h-nat. Th-232. Sr-90, 1000 dpe/100 cm2 3000 dpm/100 cm2 200 dpa/100 cm2 a-223. Ra-224. U-232. 1-126, -

-131. 1-133 eta-garna etaitters (nuclides 4th decay modes other than 5000 dpa sy/100 cm2 15.000 dpa sy/100 c.2 1000 dpa sy/100 c 2 Ipha emission or spontaneous ission) except Sr-90 and .

thers noted above.

Where surface contamination by both alpha- and beta-gasma-emitting nucildes exists, the limits established for alpha- and beta-gasuna-emitting nuclides should apply independently.

As used in this table, dpa (disintegrations per minute) means the rate of emission by radioactive material as determined b co i counts per minute observed by an appropriate detector for background, efficiency, and geometric factors associated with the in na on.

Measurements of average contaminant should not be averaged over more than i square meter. For objects of Iess surface area. the ave. age ,

should be derived for each such object.

The maximum contamination level applies to an area of not more than 100 cm2, 2

The amount of removable radioactive material per 100 cm of surface area should be determined by wiping that area with dry filter or sof 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-gasuna emitters should not exceed I cm and 1.0 mrad /hr at I cm. respectively, measured through not more than 7 milligrams per square centimeter of 0.2 mrad /hr at total absorber. .

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