ML20195D748

Amend 10 to License SNM-33,authorizing Use of 8,000 Kg U Enriched to Max 5.0% in U-235 at Listed Address

ML20195D748
Person / Time
Site:	07000036
Issue date:	10/31/1988
From:	Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20195D724	List: ML20195D721 ML20195D748 ML20195D782 ML20195D788 ML20195D803
References
NUDOCS 8811070129
Download: ML20195D748 (5)

Text

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U,S. NUCLE AR RECULATO3Y Comett$60N

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] Code of Federal Regulations, Chapter I, Parts 30,31. 32,33,34,35,40 and 70 Pursuant io the Atomic Energy Act of 1954, as amended, the Energy Reorganisation Act of 1974 (Public Law 93 -438), and Title 10, l

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)) heretofore made by the licensee, a license is hereby issued authorizing the licensee to r

] source, and special nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below:to -

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I, deliver or transfer such material to persons authorized to reccive it in accordance with the regulations of the applicable Part(s). This 3

I heense shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and k i

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f subject to all applicable rules, regulations and orders of the Nuclear Regulatory Commission now or hereafter in effe

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[l condition: specifled below.

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Cerbustion Engineering, Inc.

SNM-33

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Ameneent No. 10 y

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P. O. Box 107

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Hematite, Missouri 63047

4. Ey'estion date Cerember 31,_1986 j

5. Docket or

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Reference No.

70-36

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6. B)produet, source, and/or

7. Chemical and/or physleal

8. Maximum amount that licensee I,

speena.1 nuclear material form may possess at any one time f

under this hcense f

A.

Uranium enriched to A.

Any, excluding metal A.

8,000 kilograms maximum 5.0 weight powder contained U-235 f

r percent in the U-235 l'

isotope I

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Uranium, any U-235 E.

Any B.

350 grams enrichment

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Source material C.

Any, excluding metal C.

50,000 kilograms 1

(Uranium and Thorium) powder 1,

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Cobalt 60 D.

Sealed sources D.

40 millicuries, j

total

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Authorized Use: For use in accordance with the statements, representations, and J'

conditions contained in Part ! of the licensee's renewal application dated February 26,:

1 1987, and supplements dated July 21, 1982; February 21, 1983; Pay 31, 1964; I

April 29. June 6, and October 11,19tt; and letters dated February 29, 1964, f

January 20, 1966, and March 30, 1987.

[' 10. Authorized Place of Use:

The licensee's existing facilities in Fematite, Missouri, l

as described in the referenced license renewal application.

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lle Quarterly inspections by the Supervisor, bl.S&A or his represt.ntative shall be I

preplanned and shall be documented.

Such documentation shall be maintained for l

2 years.

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Lxena 6mber i

f MATERIALS LICENSE SNM-33. Amendment No. 10 f

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SUPPLEMENTARY SHEET f

I' 70-36 l

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

6 months r wiewing employee radiation exposure (internal and external) and effluent 1l l

release data to cetermine:

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

categories of workers, types of operations, or in effluent releasest l!

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if exposures and releases can be lowered in accordance with the ALARA comitment; ;

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if equipment for effluent and exposure control is being properiy used.

i maintained, and inspected.

f13.Thelicenseeshallleaktestsealedsourcesinaccordancewitt.theenclosed"License 3,

Condition For Leak Testing Sealed Byproduct Material Sources."

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14. Release of equipment and material from the plant site or to clean areas onsite shall be in accordance with the enclosed "Guidelines for Decontamination of Facilities and i

3 Equipment Prior to Release for Unrestricted Use or Termination of Licenses for i

1 Byproduct Source, or Special Nuclear Material," dated August 1987.

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

and scrap naterials containing uranius enriched in U-235 and/or scurce material by incineration.

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16. Within 60 days of the date of this license renewal, the licensee shall submit to the 1

NRC a description of a prcposed monitoring program to determine the quantity and 1

environmental effects of radioactivity on spent limestone rock used as onsite fill 1

material and to determine the envirerrental effects of outdeer storage of the alpha.

j contaminated material.

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17. The licensee shall survey spant limestene rock discharge fron each hF scrubber 1

for beta contamination.

Rock with beta contamination which exceeds five times 1

the background of fresh rock shall ret be used for landfill.

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16. Within 60 days of the date of this license renewal, the licensee shall submit to NHS$ 5 j

a plan, including schedule, for the disposal of alpha centamir.ated spent limestone 1

rock.

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19. The licensee shall decontam% ate the two evaporation pends such that the average I

residual contamination in each pond dees not exceed the appropriate limit of either j

250 picccuries of insoluble uranium or 100 picoeuries of soluble uranium per dry gram of soil.

The Tc 99 concentrations in a composite sample for each pond shall be 3

1 cetermined.

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NATERIALS LICENSE Duket or Reference number ll

$UPPLEMENTARY SHEET 70-36 1

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20. a.

If the radioactivity in plant gaseous effluents exceeds 105 mC1 per calendar i

quarter, the liGinsee sFall, within 30 days, prepare and submit to the I

Comissicn a report which identifies the cause for exceeding the lifwit and l

the corrective acticns to be taken by the licensee to reduce the release rates.

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

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submitted within 30 days which describes the changes in parameters and includes 3

an estimate of the resultant change in dose comitment l

ll b.

In the event that the calculate <f dose to any nwaber of the public in any 4

censecutive 12-month period is about to exceed the limits specified in 40 CFR I,

190.10, the licensee shall take immediate steps to reduce emissions so as to

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comply with 40 CFR 190.10. As provided in 40 CFR 190.11, the Itcensee may i

petition the Nuclear Regulatory Comission for a variance from the requirments L

t of 40 CFR 190.10.

If a petition for a variance is anticipateo the licensee shall i

1, submit the request at least 90 days prior to exceeding the limits specified in 1

40 CFR 190.10.

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21. The licensee shall maintain and execute the response measures of his Radiological j

Contingency Plan submitted to the Comission by letter dated December 28, 1987.

The licensee shall also raintain irplementin Plan as riecessary to implement the Plan.g procedures for his Radiological Contingency 1

The licensee shall make no change in his 1

1 Radiological Contingency Plan that would decrease the response effectiveness of the l

Plan without prior Comission approval as evidenced by a license amendment.

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licensee may make changes to his Radiolcgical Contingency Plan without prior 3

Comission approval if the changes do not decrease tha response effectiveress of the 3

Plan. The licensee shall furnish the Chief Fuel Cycle Safety Branch, Division of 1

Industrial and Medical Nuclear Safety, hMSS, U. S. Nuclear Regulatory Comission, 1

Washington, DC 20555, a report containing a description of each change within 1

6 months after the change is made.

j 22. At the end of the plant life, the licensee shall decontaninate the facilities and 3

site ir iccordance witn the general decomissioning plan submitted in the enclosure a

to the letter dated January 12, 1975, so that these facilities and grounds can be 1

released to unrestricted use.

1he financial comitment to assure that funds will be 1

availab17 for decomissioning in the letter dated March 8,1979, is hereby j

incorporated as a condition of the license.

j 23. The licensee shall certinue the soil sampling progr.

for the spent litrestone fill a

areas, as described in the letter dated February 29, 1984, urtil discontinuance is I

authorizeo by the Cctrission.

1 1lI The report or petition should be submitted to the Directcr. Office of Nuclear l

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

a Region III, 4

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f MATERIALS LICENSE sNM-33, Amendment N. 10 I

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24. The monitoring program for the spent limestone shall include:

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

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uncovered spent limestone piles for a minimum 2-year period.

The weekly sampics ilf l

i maybeccepositedandanalyzedforurgiumactivityonaquarterlybasis.

The 1cwer limit of detection shall be 10' eCi/ml, or i

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

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

ij and analytical pregram to tie NRC for approval.

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25. Processing cf UF in 10-ton cylinders is not authorized.

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26. The 10-ton UF6 cylinders shall be equipped with valve protecto'rs.

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( 27. The cor. crete pad for storage of UFslopedorgradedsothatanyspillhdccmbustibleflu l

cylinders and the surrounding area shall be j

the storage area, i

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1 St. No combustibles shall be stored on the concrete pad.

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29. A CO2 fire extinguisher shall be readily available near the storage pad.

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30. In addition to the controls in Section I of the enclosure to the letter dated t

i March 30, 1987 UF,. cylinders which are in transport and containing UF heels i

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shall be either sex 1ed, in sealed overpacks, or in sealed vehicles.

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

1 k-effective of a unit or an array of units shall not exceed 0.95 unless g

i specifica11) authorized by the license, g

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32. Nuclear criticality safety evaluations performed by the licensee in accordance v',th i

1 Section 2.7. Part I of the application, shall be based on assumptiens of optimum i

1 moderation and reflection cf individual safe units and of arrays.

l j 33. Nuclear criticality safety evaluations insolving k-effective calculations performed r

i by a Nuclear Criticality Sp2cialist shall be independently reviewed and approved by 1

1 an individual having as a minimum, the qualifications of a Nuclear Criticality i

1 Specialist.

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'II ll 34. For uranium enriched to more thar. 4.1 w/o U-235, the licensee shall limit the I

l ll agglomeration /granulatten process, each agglomerated powder storage location, and I

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ll the pellet pressing cperating to safe mass units as specified in Tt.ble 4.2.4 Part I of tie application.

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FOR THE NUCLEAR REGULATORY COMMISSION l

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OCT 31 1933 1 Date:

By:

Leland C. Rouse i

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DTVTsion of Industrial and Medical

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fN d' e Nucletar Safety, NMSS I

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