ML19269E861
| ML19269E861 | |
| Person / Time | |
|---|---|
| Site: | 07000687 |
| Issue date: | 03/26/1979 |
| From: | Crow W, Delaney J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML19269E857 | List: |
| References | |
| NUDOCS 7906290738 | |
| Download: ML19269E861 (2) | |
Text
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f UNITED STATES y%~
NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20555 (7d
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Docket No.:
70-687 Applicant:
Union Carbide Corporation (UCC)
Facility:
Corporate Research Laboratory
Subject:
LICENSE AMENDMENT APPLICATIONS DATED DECEMBER 28, 1977, WITH SUPPLEMENTS DATED MAY 3, AND OCTOBER 13, 1978.
Background
The December 28, 1977, application requested that (a) the quantity of special nuclear material in a single hot cell be increased from 650 grams to 2650 grams and, (b) that the possession limit of U-235 under the license be increased from 4600 grams U-235 to 3000 grams of unirradiated U-235 and 10,000 grams of irradiated U-235. The May 3, and October 13, 1970, supple-ments provided supporting data for the increased mass limits in hot cells.
i A license amendment was issued on October 30, 1978, approving the increased l
quantities in hot cells.
The 13 kilogram mass limit, however, was not approved at that time because the licensee did not meet the requirements for physical protection of licensed activities for the higher U-235 posses-sion limit as required by 10 CFR 70.53.
f Discussion By letter cated January 30, 1979, Union Carbide Corporation was advised that an exemption from the requirements of 10 CFR 73.50 had been granted and that the UCC Materials and Pla:.t Protection Amendment MPP-3 had been amended by adding Section 9 (a ccpy of which is attached) which contains the conditions of the exemption.
Nuclear Safety Although the total mass of U-235 which the licensee may possess is being i
increased there is no change in the safe parameters discussed in the previously referenced SER of October 30, 1978.
Howeser, at the request of Mr. Jerry Roth, I&E, Region I, and with the concurrence of Mr. Mark Voth, UCC, I have added License Condition No. 17 as follows:
17.
The licensee shall empty and clean the unsafe geometry container in the waste storage laboratory after each batch of not more than 350 grams of U-235 have been processed through the plating laboratory and shall maintain records showng that the container has been emptied after each 350 gram batch is processed.
2142 057 7906290 7 3 7 c
Docket No.:
70-687 Radiation Safety and Environmental The change in possession limit does not affect the currently approved radiation safety procedures nor the environmental considerations.
Recommendation On the basis of the above, I re ommend that the license be ameaded as requested by the licensee.
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J. C. Delaney s
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Approved:
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W. T. Crow l
2142 058
I J 3 SC-FS :RRR 70-5C7 Union Carbide Corporation Sterling Ferect Research Ccr.ter ATT." :
Mr. i' arcus h. Vcth Manager, fluclear Opera:icas F,. u. ac x x.,,
n Tuxece,:;ew York 10937 Gentlemen:
Reference is mace to your letter cf,;cverber 10,.1975 re;arding a re:;uest for exemption frc: 10 CFP 73.50 for cer:ain special nuclear caterial under License !;o. S';M-539. Le F. ve eter.ir.ed that an exerttien c the rec;uirements of 10 CFR-72.E0 as per ains to irradiate.1 tarce: caterial is autheri:ed :y lay.<, will nc encar.ger life or property or the ccmr.cn cefense an: securi y, an:. is other-t 1
wise in tne public interest.
Accordingly, we are hereby atending ':aterials anc Piar.t Frotection 4
Amencment !:FP-3 to your License I;c.
S... -529 cy addir.; Section 9 as set forth in the encicsure to this ie;;er, effective irrediately.
Sincerely,
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g-Rober: F. Eurnett, l'i recto r Divist:r of Safegu;rcs Enciesure:
As state:.
P00ROR8NAL D E3 m'
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Enclosure A Section 9 Materiais and Plant Prctection Amenc ent MPP-3 to License No. SNM-539-9.0 The licensee shall comply with the following provisions.
9.1 The combined amount of uranium-235 pcssessed under License Nos. E-81 and SNM-539 which is contained in uranium enriched to 20 percent or more in the U-235 isctope and which is not irradiated shall be less than 5,000 grams.
9.2 The licensee is not required to include uranium-235 contained in irradiated target material in calculations of the 5~,000 gram thresh.
cid for application of 10 CFR 73.50 provided that the hot cells are protected within a protected area so that irradiated target material located there is afforded the same protecticn measures,as given to irradiated fuel elements in the reactor building under the licensee's approved reactor security plan, and I
(a) locks and alarms which annunciate upon unauthorized use when the area is unoccupied are provided to ei-ther the hot cell manipula-tors or hot cell doors (b) any irradiated target material loca ed in the transfer channel or reactor pool is in a container which has an external radia-tion dose rate of 100 rem at 3 feet frca its surfaces without intervening shielding and equiprent for hancling such contair.ers is provided with iocks and alarms which annunciate upon un-authorized use when the area is unoccupied.
)DDRORGNAL 2142 060
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