ML20248B489

Amend 13 to License SNM-33 for C-E,authorizing Use of 8,000 Kg Contained U-235,350 G U W/Any U-235 enrichment,50,000 Kg U & Thorium & 40 Mci Co-60 Sealed Sources for Uses Indicated

ML20248B489
Person / Time
Site:	07000036
Issue date:	07/28/1989
From:	Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20248B435	List: ML20248B430 ML20248B489 ML20248B521
References
NUDOCS 8908090244
Download: ML20248B489 (5)

Text

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NIC Form 374 M 84) -

- U.s. NUCLEAR GE!ULATcRY CoMMisSicN PACE 1 OF 5 PAGES l MATERIALS UCENSE Pursuant to.the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, l)

I Code of Federal Regulations, Chapter I, Parts 30,31,32,33,34,35,40 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, g l -l L '

l source, and special nuclear material designated below.; to use such material for the purpose (s) and at the place (s) designated below;to y deliver or transfer'such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This 1 license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is il

. subject to all applicable rules, regulations and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any lI I

, conditions specified below.

I il Licensee il 11 i 1, Combustion Engineering, Inc. . SNM-33 lig

3. License number Amendment No. 13 .gI lg 2' P. O. Box 107 y '- 'l

' Hematite, Missouri 63047 ,ff' '

4'. EipiratiorUate Deceder 31, 1989

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, .,; 5. Docket or ys 70-36 g u1 Reference No. ~

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6. Byproduct, source, and/or ) 7. Chemical and/or physical < By Maximum amount that licensee ,1 special nuclear material ,

form ytnay possess at any one time l

{I id .. under this license I A. .Uraniumenriched[to

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maximum 5.0 weight 1f'.NAny,excludingnedeF M

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A. 8,000 kilograms contained U-235 j '

y percent in the U-235 f @ $ powder e ;, - p isotope w

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F. . Uranium, any U-235 44 B.;Mnpx 3..

R,' 8.2 350 grams Vd enrichment '$yQ j . M[lf Et

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C. Source material / exc ing metal Cp 50,00n kilograms (Uranium and Thorium) ,liCg{;Any; . 1

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'/ 3, D. Cobalt-60 D. Sealed sources *1 .@ D. 40 millicuries, I

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9. Authorized use: Forusein/accordance with the statements, representations, and g conditions contained in Part I bf the-licensesjs renewal application dated 3 February 26, 1982, and supplements da'ted Ju19 21, 1982; February 21, 1983; I May 31, 1984; April 29, June 6, and October 11, 1988; and February 10, and 1 March 22, 1989; and letters dated February 29, 1984, January 20, 1986, and March 30, 1987. l '

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10. Authorized place of use: The licensee's existing facilities in Hematite, Missouri, g as described in the referenced license renewal application. I I

11. Quarterly inspections by the Supervisor, NLS&A, or his representative shall be I preplanned and shall be d)cumented. Such documentation shall be maintained for 2 years. l g

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MATERIALS LICENSE gg-33 Amendment No. 13 SUPPLEMENTARY SHEET " ***""

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JUL 2 8 Bb9 I

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12.release A written report shall be made by the NLS&A Superviso 1

F data to determine: l8 I

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if there are any upward trends developing in personnel exposure for identifiable categories of workers, types of operations, or in effluent releases; l

b. j lli if exposures and and releases can be lowered in accordance with the ALARA Il com I

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if equipment maintained, andfor effluent and exposure control' is being properly used, inspected.~ I f

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13.Condition The licensee shallSealed For Leak Testing leak'Byproduct test sealedMaterial sources Sources? in accordance with j l the

14. Release of equipment and material-from the plant siteLor to clean areas onsite shall be in accordance Equipment Byproduct, withfor Prior to Release ~

the enclosed Unrestricted Use '.'Guidefines or Termination for Decontamination of Licenses for f

R o Source,' or Special Nuclear Material," dated August 1987. &

15. Pursuant to 10 CFR 20.302,.the licensee is authorized to treat waste c

fb and scrap materials containing. uranium enriched in' U-235 and/or source material by incineration.

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16. Within 60 days of the date of this' license renewal,.the licensee shall submit to the NRC a description of a proposed monitoring program to determine the quantityl and environmental effects of radioactivity on' spent limestone rock used as onsite fill iy matorial contaminated andmaterial.

to determine 1the environmental effects of, outdoor storage of the alpha-e C ln

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87.Thelicenseeshallsurveyspent"1kmestonerockdisdhargefromeachHFscrubber for beta contamination.

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i the background of fresh rock shall not be used for landfill. Rock with beta! contami l l

18.Within60daysofthedateofthislicenserenewal,thelicenseeshallsubmittoNMSS! /

a plan, including schedule, for the disposal of alpha-contaminated spent limestone rock.

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19. The licensee shall decontaminate the two evaporation ponds such thct jaNthe avera residual contamination in each pond does not exceed the appropriate limit of either,Rl, 250 of soil.picocuries of insoluble uranium or 100 picocuries of soluble uranium per dry gra i determined.The Tc-99 concentrations in a composite sample for each pond shall be

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pu m mm mmm = = = m m m == = === ====== ======= -- = = = = = = m= ===== = = = ==g l kxc rore 27dA U.S. NUCLEA2 REcuLATcMY CoMMIS$13N PAoE 3 or 5 P Aq q.s l l - @e4 Ucense number l SNM-33 Amendment No. 13 l ~

MATERIALS LICENSE "*'*'*"*

SUPPL EMENTARY SHEET I 70-36 t C

JUL 2 8'1989 L

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20. a. If the radioactivity in plant gaseous effluents exceeds 150 pCi per calendar D quarter, the licensee shall, within 30 days, prepare and submit to the k Commission a report which identifies the cause for exceeding the limit and r de corrective actions to be taken by the licensee to reduce the release rates.

i 'i the parameters important to a dose assessment change, a report shall be  !

I submitted within 30 days which describes the changes in yparameters and includes an estimate of the resultant change in dose commitment I

l l b. In the event that the calculated dose?to'any member of the public in any =

l consecutive 12 month period.is about'to exceed:the limits specified 'n 40 'FR  :

l 190.10, the licensee shall,take immediate step'sfto reduce emissions so as io  ;

I comply with 40 CFR 190.10. As provided in 40 CFR 190.11, the licensee mau  :

I petition the Nuclear < Regulatory Commission for a variance from the requirements  :

I of 40 CFR 190.10. J 1f a petition for a variance is anticipated the licensec shall l submit the request'at least 90 days prior to exceeding the limits specified in r L

40 CFR 190.10. y

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I' 21. The licensee sha111 maintain and ' execute the responss;measuresfof his Radiological .;

I Contingency Plan submitted to, the: Commission by letter dated facember 28, 1987._ The i-i l

licensee shall also1 maintain implementing procedures for his Radiological Contingency

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E Plan as necessary;to implement:thefian. ~ The;1ic.ensee shall make no change in his

[L Radiological Contingency; Plan that-would decreaseithe response effectiveness of the Pian without prior'Commis'sion approval 'astevidenced by a license amendment. The f;

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[l I, licensee .aay nake changes?to his Radiological Contingency Plan without prior k I

Commission approvalrif the changes doinot! decrease the respons'e effectiveness of the  :

l Plan. The licensee ~sh'all furnish the Chief', Fuel Cycle Safety Brancn, Division of j l [

Industrial and Medicalc Nuclear Safety., NMSS; U. .SJ N.s.iear? Regulatory Commission, l [: Washington, DC 20555, 'a; report containing'a. description of'each change within l JW

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[ 6 months ifter the change'.#is,made. i l_ , r s _

U 22. At the end of the plant life, the. licensee shall2decontamia te the facilities and [

I site in accordance with the general; decommissioning plan suomitted in the enclosure to the letter dated January 12, 1979, so that these facilities and grounds can be  %[

released to unrestricted use. The financial commitment to assure that funds will be C available for decommissioning in the letter dated March 8, 1979, is hereby p incorporated as a condition of the license.

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23. The licensee shall continue the soil sampling program for the spent limestone fill [ l I areas, as described in the letter dated February 29, 1984, until discontinuance is ,

I authorized ty the Commission. l l

F 1 L b The report or petition should be submitted to the Director, Office of Nuclear l f i Material Safety and Safeguards, with a copy to the. Regional Administrator, k l Region III.  %

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,wr,cyg,gn3743 U.S. NUCLEA3 RE!ULATERY COMMISSloN g (5 asl- ,

PAGE 4 OF 5 paars I License number I l MATERIALS LICENSE SNM-33 Amendment No. 13 l

SUPPLEMENTARY SHEET

• * ' * * " " l 70-36 l g

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JUL 2 61383 l

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24. The monitoring program for the spod limestone shall includa: 1 I

a.

l Continuous air sampling at the center of, and approximately 1 meter above, the l

uncovered spent limestone piles for a minimum 2 year period. The weekly samples a l maybecompositedandanalyzedforurgiumactivityonaquarterlybasis. The I t

. lower limit of detection shall be 10 pCi/mi, or I i i

b. Measurement of the uranium activity on the surface of the spent limestone.

Prior to conducting such a program, the licensee shall submit the sampling l g

g and analytical program to the NRC for approval f g l . '

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l 25. Processing of UF in 10 ton. cylinders is not authorized. .,

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26. The 10-ton UF6cylindersshallbeequippedwithvalveproEetstors.

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i 27. The concrete pad for3torage 'of.UFg cylinders and thelsurrounding area shall be

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i sloped or graded so that any spilled combustible fluids would not be confined to I the storage area. !~ ^ i l

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l l 28.Nocombustiblesshailbestored'ont.heconcretepad.

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! 29. A C0 2 fire extinguisher shall be readily;availiable.near the storage pad.

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I 30. In addition to the controis-in Section Ifof, the enclosure to tt'e letter dated i March 30, 1987, l shall be either sekled; in sealed overpacks, or in sealed vehicles,UF 6 \ cylinders llI i ', . ., 1/

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31. Notwithstanding the st'atement in Section.4.2.3 of the application, the i

i k-effective of a unit or an-array of units all not exceed 0.95 unless flI specifically authorized by# the license. W

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, 32. Nuclear criticality safety evaluations ~ perfomed by the licensee in accordance with sp 4

g Section 2.7, Part I of the application, shall be based on assumptions of optimum '

i moderation and reflection of individual safe units and of arrays.

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I 33. Nuclear criticality safety evaluations involving k-effective calculations performed by a Nuclear Criticality Specialist shall be independently reviewd and approved by l y

i an individual having, as a minimum, the qualifications of a Nuclear Criticality l Specialist. l

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1--------------------------- ------=-------------------g NIc rtem 374A U.S. NUCLEAR RE!ULATORY COMMISSION PAGE 5 op 5 I PAGES

[ W 8dl , License number I

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. MATERIALS LICENSE S E-33 Amendment No. 13

' , Docket or Reference number l SUPPLEMENTARY SHEET 70-36 g l

WL 2 81989 I l

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I l l l l 34. For uranium entiched to more than 4.1 W o U-235, the licensee shall limit the I L agglomeration / granulation process, each agglomerated powder storage location, and the pellet pressing operating to safe mass units as specified in Table 4.2.4, Ig!

Part I of the application.

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FOR THE NUCLEAR REGULATORY COMMISSION I-4 I

! $*Yh,p( p #M*lsened Br l

Date: f '

By: Leland C. Rouse Division of Industrial and Medical lI i

Nuclear Safety, NMSS

Washington, DC 20555 {

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