ML20206B362

Amend 11 to License SNM-33 for C-E,authorizing Use of U,Thorium & Co-60 at Stated Location & Requiring Preplanning & Maint of Documentation for Quarterly Insps by Nls&A

ML20206B362
Person / Time
Site:	07000036
Issue date:	11/07/1988
From:	Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20206B352	List: ML20206B346 ML20206B362 ML20206B370 ML20206B375
References
NUDOCS 8811150424
Download: ML20206B362 (5)

Text

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I NRC Form 374 1

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U.S. NUCL E A'1 R E!ULATOY COMMISSl* N gj MATERIALS LICENSE

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l Pursuant to the Atomic Energy Act of 1954, as ameed, the Energy Reorganization Act of 1 Code of Federal Regulations, Chapter I, Pat's 30,31,32,33,34,3S,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, ;p source, and special nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below; to ll deliver or transfer su:h material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This

.I fl license shall be deemed to contain the conditions specified in Section 183 of the Atomic En I

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

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Combustion Engineering, Inc.

3. IAense number SNM-33 I

j'I Amendment No. 11 I

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P. O. Box 107

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4. Eiptritidadde December 31, 1989 n

1 Hematite, Missouri 63047 I

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5. Docket or 3 A 70-36

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7. Chemical and/or physical

8. Maximum amount that licensee t

I special nuclear material form i.may possess at any one time

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',Wnder this license A.

Uranium enriche'd' to Ab'Any, excluding metal (

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8,000 kilograms

,p maximum 5.0 weight 7 powder a

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contained U-235

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percent in the y* 235

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Uranium, any U-235 B., Any r

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Source materia 1 M C.~.' 50,000 kilograms

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40 millicuries, p

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Cobalt-60 1

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4 Authorized Use:

For use in accorbance with the sistements, representations, and l

conditions contained in Part I of theGicehsee's renewal application dated February 26. P f

1982, and supplements dated July 21, 1982; February 21, 1983; May 31, 1984; l

V April 29 June 6, and October 11, 1988; and letters dated February 29, 1984, y

aj January 20, 1986, and March 30, 1987.

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10. Authorized Place of lise:

The licensee's existing facilities in Hematite, Missouri, h

as described in the referenced license renewal application.

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11. Quarterly inspections by the Supervisor, N1.S&A, or his representative shall be l

N preplanned and shall be documented.

Such documentation shall be maintained for p

i Ni 2 years.

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,,oe races Licen,e nurnber l

Stif t-33 Amendment flo.11 j

MATERIALS LICENSE SUPPLEMENTARY SHEET Il 70-36 g

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12. A written report shall be made by the NLS&A Supervisor to the Plant Manager every

!pI 6 months reviewing employee radiation exposure (internal and external) and effluent j'

'l release data to detemine-l; a.

if there are any upward trends developing in personnel exposure for identifiable g

categories of workers, types of operations, or in effluent releases;

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if exposures and releases can be lowered in.accordance with the ALARA cocr11trent; i J

and

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'I if equipment for effluent and exposure control is Ning properly used, c.

s maintained, and inspected.

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13. The licensee shall leak test sealed sources in accordance with the enclosed "License Condition For Leak Testing Sealed Byproduct Material., Sources."/

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14. Release of eqt f pment and material from the plant site or to clean areas onsite shall I

be in accordance with the enclosed "Guidelines (for Decontamination of Facilities and jb Equipment Prior to Release for Unrestricted Use or Temination of Licenses for 8

Byproduct Source;,or Special Nuclear Material," dated August 1987 j!

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

p and scrap materials containing uraniurs enriched in U-235 and/or source material by

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i incineration.

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16. Within 60 days of the date of thts license' renewal ithe licensee shall submit to the l

NRC a description of a' proposed monitoring program to determine the quantity and p

environmental effects of radioactivity on spent ilmestone-rock used as onsite fill lp I,

j material and to detemine the environmental effects of; outdoor storage of the alpha-contaminated material.

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17. The licensee shall survey spent liu: stone rock discharge from each HF scrubber

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i for beta contamination.

Rock with beta contamination which exceeds five times the background of fresh rock shall not be used for landfill.

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i 18. Within 60 days of the date of this license renewal, the licensee shall submit to NMSS P i

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

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ll L 19. The licensee shall decontac11nate the two evaporation ponds such that the average

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residual contamination in each pond does not exceed the appropriate limit of either i

250 picocuries of insoluble uranium or 100 picoeuries of soluble uranium per dry gram j

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of soil. The Tc.99 concentrations in a corrposite sample for each pond shall be detemined.

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ll U.S. NUCL E A1 R E CULATGY COMMISSION w

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MATERIALS LICENSE 3

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SUPPLEMENTARY SHEET NOV 7 1988 I

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20. a.

If the radioactivity in plant gaseous effluents exceeds 105 mci per calendar J

ouarter, the licensee shall, within 30 days, prepare and submit to the

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j;g Comission a report which identifies the cause for exceeding the limit and the corrective actions to be taken by the licensee to reduce the release rates.

If the parameters important to a dose assessment change, a report shall be

,e submitted within 30 days which describes the changes in an estimate of the resultant change in dose commitment.3 parameters and includes,ej b.

In the event that the calculated dose to any marber of the public in any consecutive 12-month period is about to exceed the. limits specified in 40 CFR 190.10, the licensee shall take imediate steps to reduce emissions so as to

)l comply with 40 CFR_190.10. As provided in 40 CFR 190.11, the licensee may lu petition the Nuclear, Regulatory Comission for a variance from the requirements t@

of 40 CFR 190.10. 'If a petition for a variance is anticipated the licensee shall j submit the request at'least 90 days prior to exceeding the111mits specified in j

40 CFR 190.10. ( y

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21. The licensee shall maintain and execute the response measures of his Radiological Contingency Plan submitted to the: Commission. by letter dated Decerber 28, 1987. The

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licensee shall also maintain irpleoenting procedures for his Radiclogical Contingency j Plan as necessary;to implement the Plan.,,The. licensee sM11 make no change in his ip Radiological Contingency Plan that would? decrease the response effectiveness of the

,p Plan without prior Comission approval' as evidenced by a-license amendment. The licensee may make changes to his Radiological Contingency Plan without prior l

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Comission approval if the changes do not decrease the response effectiveness of the j i

Plan.

The licensee shall furnish the Chief Fuel Cycle Safety Branch, Division of i

n Industrial and Medical Nuclear Safety, MMSS, U. S.' Nuclear Regulatory Comission.

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Washington, DC 20555 a report containing a description of each change within

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6 months after the change is!made.

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22.Attheendoftheplantlife,th'e'1denseeshAlldhcontaminatethefacilitiesand

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I site in accordance with the general decomissioning plan submitted in the enclosure p

to the letter dated January 12, 1979, so that these facilities and grounds can be

p released to unrestricted use. The financial comitment to assure that funds will be l

available for decomissioning in the letter dated March 8,1979, is hereby I

,l incorporated as a condition of tht license,

j e 23. The licensee shall continue the soil sampling program for the spent limestone fill q

areas, as described in the letter dated February 29, 1984, until discontinuance is lp il authorized by the Comission.

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[' I. The report or petition should be submitted to the Director, Office of Nuclear s

Material Safety and Safeguards, with a copy to the Regional Administrator, p

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Region !!!.

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C e,msnA U.S. NUCLEA2 CE2ULATORY COMMIS$mN 4e 5

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l MATERIALS LICENSE Stift-33 Amendnent flo. 11 il

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SUPPLEMENTARY SHEET

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24. The monitoring program for the spent lim stone shall include:

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Continuous air sampling at the center of, and approximately 1 meter a':,ve, the i

uncovered spent limestone piles for a minimum 2-year period. Tha,eekly samples lg i

may be composited and analyzed for urgium activity on a o".nerly basis. The ll 1

lower limit of detection shall be 10-mci /ml,or I

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Measuremert of the uranium activity on the-surface of the spent limestone.

Prior to conducting such a - srogram, the licensee shall submit the sampling lg j

and analytical program;to tW NRC for approval'.h i

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in10toncylindersisnotauthorized.G3

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25. Processino of UF 7

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27. The concrete pad for storage of UFg cylinders and the ~ surrounding area shall be I

sloped or graded so.that any spilled cottbustible fluids would not be confined to jb

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the storage area.

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) 28. No combustibles shall be stored on the concr'ete pad.

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fire extinguisher shi.ll be readilylavailable near the storage pad.

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30. In addition to the controls in'Sectiori !!of de enclosure to the letter dated f;>

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March 30,1987, UF, cylinders which are in transport and containing UF h*'I8 6

1 shall be either seMled, jn sealed overpacks ;or ip;itealed. vehicles.

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q 31. Notwithstanding the statement in Section 4.2.3 of the application, the

k. effective of a unit or an Array of units shall nut exceed 0.95 unless specifically authorized by the license.

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}[ 32. Nuclear criticality safety evaluations perfonned by th 1

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Section 2.7, Par! I of the application, shall be based on assumptions of optimum lt lj moderation and reflection of individual safe units and of arrays.

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fl 33. Nuclear criticality safety evaluations involving k. effective calcula 3

by a Nuclear Criticality Specialist shall be independently reviewed and approved by j

0 an individual having, as a minimum, the qualifications of a Nuclear Criticality 1,l Specialist.

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_-----------------------------------------------m===9 l, N C Form 374 A U.S. NUCLE AR CEiULATCRY COMMISSION rau 5 or 5 rAors - N I

85' " 3 Lkenee number N

l MATERIALS LICENSE SNf1-33 Amendment flo 11 f

I SUPPLEMENTARY SHEET I

g 70-36 S

I NOV 7 1988 I

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34 For uranium enriched to more than 4.1 w/o U-235, the licensee shall limit the l

agglomeration / granulation process, each agglomerated powder storage location, and ji i

the pellet pressing operating to safe mass units as specified in Tab' 4.2.4,

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Part I of the application.

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35. Deleted.

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I FOR THE NUCLEAR REGULATORY COPNIS$10N j

g.Y J ll OrpalSigned b It Date:

By:

Leland C. Rouse I

Division of Industrial and P'edical lI, Nuclear Safety, NMSS k

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s Washington, DC 20555 l8 p

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