ML20246P122

Amend 12 to License SNM-33 for C-E,modifying UF6 to U Oxide Process Line

ML20246P122
Person / Time
Site:	07000036
Issue date:	05/10/1989
From:	Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20246P114	List: ML20246P111 ML20246P122 ML20246P129 ML20246P142
References
NUDOCS 8905220091
Download: ML20246P122 (5)

Text

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14RC form 374 g t5 84 U.S. NUCLEAR REcuikTORY COMMISSloN PAGE OF PAGES MATERIALS LICENSE l

Purtuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, g

Code of Federal Regulations, Chapter I, Parts 30,31,32,33,34,35,40 and 70, and in reliance on statements and representations y

g heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, g

i source, and special nuclear material designated below; to use such material for the purpose (s) emd at the place (s) designated below; to l

1 deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Put(s). This l

N license shall be deemed to conlain the conditions,pecified in Section 183 of the Atomic Energy Act of 1954, as amend >J and is I

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

conditions specified below.

l ll Licensee l

g, Combustion Engineering, Inc.

SNM-33

3. License number N

Amendment No. 12

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P. O. Box 107 I

2.

j Hematite, Missouri 63047 December 31, 1989 l

4. Expiration'date 1

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5. Docket or F

70-36 y

y Reference No.

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6. Byproduct, source, and/or

7. Chemical and/or physical

8. Maximum amount that licensee i

,N special nuclear material

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form may possess at any one time I

N under this license U

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!j A.

Uranium enriched"to

.A.

Any, excluding metal-A.

8,000 kilograms y

maximum 5.0 weight powder.,

,f contained U-235 lg g

percent in the U-235 i "'

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isotope 1

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I B.

Uranium, any U-235 B.

Any B.

-350 grams N

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enrichment i

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y C.

Source material C.

Any, excluding metal C.

50,000 kilograms y

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(Uranium and Thorium) powder

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Cobalt-60 D.

Sealed sources

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40 millicuries, lE 5

total I

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Authorized use:

For use in accordance with the statements, representations, and conditions contained in Part I of the licensee's renewal application dated February 26fg' i

1982, and supplements dated July 21, 1982; February 21, 1983.; May 31, 1984; jij i

April 29, June 6, and October 11, 1988; and February 10, 1989; and letters dated f

l February 29, 1984, January 20, 1986, and March 30, 1987.

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10. Authorized place of use:

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

q as described in the referenced license renewal application.

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11. Quarterly inspections by the Supervisor, NLS&A, or his representative shall be E

l preplanned and shall be documented.

Such documentation shall be maintained for l

g 2 years.

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U.S. NUCLE An nEcVLATORY COMMISSloN 2

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i PAGE o,

paces l _ m-sal License number s

I SNM-33, Amendment No.12 l

l MATERIALS LICENSE Docket or Reference number i

SUPPLEMENTARY SHEET g

70-36 y

i NAY 101939 I

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

q 6 months reviewing employee radiation exposure (internal and external) and effluent L

1 release data to determine:

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L if there are any upward trends developing in personnel exposure for identifiable f I

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

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if exposures and releases can be. lowered in accordance with the ALARA commitment; L i

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

l maintained, and inspected.

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13. The licensee shall leak test sealed sources in accordance with the enclosed " License E

I 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 i

be in accordance with the enclosed " Guidelines for Decontamination of Facilities and t:

i Equipment Prior to Release for' Unrestricted Use"or Termination of Licenses for L

i 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 f

l and scrap materials containing uranius enriched in U-235 and/or source material by t!

i incineration.

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

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

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l environmental effects'of, radioactivity on spent limestone rock used as onsite fill g:

y material and to determine'the environmental effects of outdoor storage of the alpha-g g

contaminated material, t

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17. The licensee shall survey spent limestone rock discharge from each HF scrubber N

for beta contamir:ation.

Rock with beta contamination which exceeds five times I

l the background of fresh rock shall not be used for landfill.

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18. Within 60 days of the date of this license renewal, the licensee shall submit to NHSS r N

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

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rock.

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19. The licensee shall decontaminate the two evaporation ponds such that the average f

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

I 250 picocuries of insoluble uranium or 100 picocuries of soluble uranium per dry gram 0

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I of soil.

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

l determined.

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PAGE 3 og

&84 Lic;nse number I

MATERIALS LICENSE

[ k Amy,ndm nt No. 12 l

SUPPLEMENTARY SHEET 70-36 MAY 101989 l

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20. a.

If the radioactivity in plant gaseous effluents exceeds 105 pCi per calendar N

quarter, the licensee shall, within 30 days, prepare and submit to the E

Commission a report which identifies the cause for exceeding the limit and I

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

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

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

y an estimate of the resultant change in dose commitment i

I b.

In the event that the calculated dose to any member of the public in any I

consecutive 12-month period is'about to exceed the limits specified in 40 CFR l

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

comply with 40 CFR 190.10.

As provided in 40 CFR'190.11, the licensee may p

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

of 40 CFR 190.10.

If a petition for a variance is anticipated the licensee shall I submit the request at least 90 days prior to exceeding the limits specified in l

40 CFR 190.10.

21. The licensee shall maintain'an'd' execute the response measures of his Radiological h

(ontingency Plan submitted to the Commission byeletter dated December 28, 1987.

The N

1 licensee shall also maintain implementing procedures for his Radiological Contingency B

jlg Plan as necessary to implement the Plan.

The licensee shall make no change in his Radiological Contingency Plan that would' decrease the response effectiveness of the Plan without prior Commission approval as evidenced by a license amendment.

The licensee may make changes to his Radiological' Contingency Plan without prior l5, l

Commission approval if the changes do!not decrease the response effectiveness of the R

Plan.

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

Industrial and Medical Nuclear Safety, NMSS, U. S. Nuclear Regulatory Commission, j

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

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6 months after the change is made.

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22. At the end of the plant life, the licensee shall-decontaminate the facilities and P

site in accordance with the general decommissioning plan submitted in the enclosure f

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

released to unrestricted use.

The financial commitment to assure that funds will be y

available for decommissioning in the letter dated March 8, 1979, is hereby b

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

4 areas, as described in the letter dated February 29, 1984, until discontinuance is y

authorized by the Commission.

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The report or petition should be submitted to the Director, Office of Nuclear l

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

1 Region III.

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NRC Farm 374A U.S. NUCLEAR REoVLAToRY COMMISStoN f4 6

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PAGES l

toe 43 Lic;nse number l

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MATERIALS LICENSE SNM-33, Amendment No. 12 l

SUPPLEMENTARY SHEET 03 l

MAY 101989 l

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

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ilg Continuous air sampling at the center of, and approximately 1 meter above, the a.

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uncovered spent limestone piles for a minimum 2 year period.

The weekly samples maybecompositedandanalyzedforurgiumactivityonaquarterlybasis.

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lower limit of detection shall be 10 pCi/ml, or p

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

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

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and analytical program to the NRC for approval.

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

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26. The 10-ton UF cylinders shall be equipped with valve protectors.

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27. The concrete pad for storage 'f UF cylinders and the surrounding area shall be o

g sloped or graded so that any_ spillhd combustible fluids would not be confined to H

the storage area.

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28. No combustibles shall be stored on the concrete pad.

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29. A CO 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 B

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

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shall be either sekled, in sealed overpacks, or in sealed vehicles.

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

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

specifically authorized by the license.

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32. Nuclear criticality safety evaluations performed by the licensee in accordance with y

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

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

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33. Nuclear criticality safety evaluations involving k-effective calculations performed N

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

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

l Specialist.

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NRC' Form 374 A U.S. NUCLEAR REoVLATcRY COMMISSION 5

5 PAGE oP PAGES l

(5 84)

Licens tumber N

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MATERIALS LICENSE SNM-33, Amendment No.12 l

Docket or Reference number SUPPLEMENTARY SHEET g

70-36 l

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34.

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

agglomeration / granulation process, each agglomerated powder storage location, and l

j the pellet pressing operating to safe mass units as specified in Table 4.2.4, y

Part I of the application.

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35.

Deleted.

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FOR THE NUCLEAR REGULATORY COMMISSION I

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e (MvglSigned f5r j

Date:

AIAY 10 Mi By:

Leland C. Rouse q

Division of Industrial and Medical j(h l

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Nuclear Safety, NMSS G

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Washington, DC 20555 ul+< pr'"

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