ML19295A575
| ML19295A575 | |
| Person / Time | |
|---|---|
| Site: | 07109009 |
| Issue date: | 08/27/1980 |
| From: | Kaplan A GENERAL ELECTRIC CO. |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 17272, NUDOCS 8010020127 | |
| Download: ML19295A575 (4) | |
Text
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GEN ER AL h ELECTR :
hUCLEAR ERGY 9
DOC'GTED PkODUCTS DIVISION USHRC
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> ft AINGTON MANUFACTURING CASTLE HAYNE ROAD e P. O. DOX 780 e WILMINGTON, N. C.
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ARTMENT g
\\h DOCKET CLERi< d gust 27, 1980 Nl Director Office of Nuclear 14aterial Safety & Saf eguards g
U.
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Nuclear Regulatory Commission g
Washing ton, D. C.
20555 d
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9 Attention:
Mr. C.
E. MacDonald, Chief 2
U i
Transportation Certification Branch 3
i-IU i
Dear Sir:
o
Reference:
Application Amendment T-18 for NRC Certificate of Compliance USA /9009/B()F With reference to the subject certificate for the FL 10-1 container, Section 12 of that certificate requires that leak tests shall be performed on each containment vessel initially and then once each year following.
We believe that for the uranyl nitrate solution (gadolinia-bearing) for which we use the FL 10-1 to ship this liquid to an of f site vendor for uranium recovery, these yearly leak tests snould not be necessary.
Typically, uranium concentration in these solutions is less than 350 grams per liter and the U-235 concentration less than 15 grams per liter.
Therefore, we are requesting that the inner containers of the FL 10-1 package we use for our shipments of uranyl nitrate solutions meeting the content requirements specified above, be exempted from the annual leak test requirement of Section 12 of that certificate.
Attached for your reference is a copy of the proposed changes to Sections 5 and 12 of the certificate.
Pursuant to 10 CFR 170.31, a General Electric Company check for
$150 is attached for processing this exemption request.
Your prompt consideration of tDis request would be appreciated.
App!! cant..g..hy
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Very truly yours, Check No. 7Pf........
AmounUFee Cctuary. [9.d. h GENERAL ELECTRIC COMPANY Typ oi Fca.. M.%.
Data Check Rce'd.. 9.k[.h....
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Received Dy.....<
A l
rthur L.
Ka31an, Manager ALK : bmw Licensing & Compliance Audits Attachments M/C J25 ggg RCD +
8010020 l23
G E N E R A L () ELECT RIC Director - ONMSS August 27, 1980 ATTACHMENT Two revisions are proposed, as shown on the following two pages, to NRC Certificate of Compliance USA /9009/B()F, to allow shipment low concentration, uranyl nitrate solutions with low-enriched uranium (up to a maximum of 4% enrichment in U-235) in FL 10-1 packages without requiring an annual leak test for the inner con tain er,
o Add a new section 5 (b) (1) (vii) as follows:
" Uranyl nitrate solutions having a concentration of uranium not exceeding 350 grams per liter and not exceeding 4%
enrichment in U-235."
o Add a sentence to Section 12 as follows:
"For shipment of the contents specified in 5(b) (1) (vii), this test shall not be required."
AL Kaplan
- bmw
PROPOSED REVISIUIl a,ge 2 - Certificate flo. 9009 - Revision ilo. 9 - Docket flo. 71-9009
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5.
(a)
(2)
Description (continued)
(threads wrapped with teflon tape) and is protected by a 2-l/2-inch high section 5-inch Schedule 40 pipe welded to the top of the flange. The packaging has a maximum gross weight of 515 lbs.
(3)
Drawings The Model flo. FL 10-1 package is described by International fluclear Company (IllCO) Drawing flo. D50-479-0, Rev. C, and the containment vessel described by IflCO Drawing flo. DSD-480-D, Rev. C.
The containment vessel seal is described by IliC0 Drawing flo. DED-169-B, Rev. 2.
(b) Contents (1) Type and form of material (1) Uranyl nitrate solutions having a concentration of uranium 235 and uranium 233 not exceeding 350 grams per liter and an ll/U-235 atomic ratio r.ot less than 80, provided that the U-233 and plutonium content is not more than 1% of the U-235 content; or (ii) Uranyl nitrate solutions having a combined concentration of uranium 233 and uranium 235 not exceeding 250 grams per liter and an H to fissile material atomic ratio not less than 80 provided (1) the U-233 content is not greater than 20% of the combined U-233;and U-235 content, and (2) the plutonium content is not more than 1% of the combined U-233 or U-235 content; or (iii)
Plutonium nitrate solutions having a concentration not exceeding 250 grams fissile plutonium per liter; or Uranyl sulfate solution (UO S0 ) containing uranium-235; or (iv) 2 (v)
Dry compounds and mixtures of fissile plutonium-uranium-235; or (vi) Mixed U-Pu oxide interspersed with graphite or silicon carbide plus plastic packing material.
.m._.
- (.vii) Uranyl nitrate solutions. having a concentrati.on of uranibm not exceeding 350 grams per liter and not exceeding 4% enricluent in U-235. *
(2) Maximum quantity of material per package Plutonium in excess of twenty (20) curies per package must be in the form of metal, metal alloy, or reactor elements; or must be in accordance with Item 9 below; and:
(i)
For tne contents described in 5(b)(1)(i), (ii), and (iii):
Maximum decay heat load not to exceed 21 watts, and 10.5 liters of solution.
PROPOSED REVISION
PROPOSED REVIS10ll a.ce' 4, Certificate tio. 9009 - Revision !!o.
9-Docket tio. 71-9009 11.
Prior to each shipment of more than Type A quantities of radioactive material, the space between the double 0-ring seal shall be tested at 100 psig and leak dete: tion performed by a method capable of detecting a leak greater than 10 3 ato cc/sec at standard temperature and pressure.
tio package with a detectable leak snall be delivered to a carrier for transport.
12.
In addition to the requirements of Subpart D of 10 CFR 71, a test shall be performed on each conta'inment vessel and associated 1/4-inch SS valve (without its associated pipe cap) initially and once each year at 300 psig and the leak detection perfomed by a metnod capable of detecting a leak greater than 10 6 atm cc/sec at standard temperature and pressure. Any chamber that fails to pass the test shall,be. withdrawn from service and repaired to meet the test. *For shi.proent of c.ontents ipecifi,ed in 5(_b)(j)(yli), this test shall not be required.*
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- 13. The fire resistant phenolic foam shall be in accordance with AEC Materials and Equipment Specification SP-9 or as modified by ORGDP Reports K/TL-729 and X/P-6567S.
- 14. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).
- 15. Expiration date:
August 31, 1983.
REFEREtiCES 1eneral Electric Company application dated March 12, 1973.
Supplernents dated:
April 13,1973; March 21,1974; and April 16, 1979.
4estinghouse Electric Corporation supplements dated:
October 3, 1979; and March 11, 1980.
Sabcock and Wilcox Company supplement dated:
May 14, 1980.
FOR THE U.S. tiUCLEAR REGULATORY COMMISS10tl Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety ate:
PROPOS_ED REVISlotl n"?,3