ML19289E736
| ML19289E736 | |
| Person / Time | |
|---|---|
| Site: | 07109009 |
| Issue date: | 05/04/1979 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19289E732 | List: |
| References | |
| NUDOCS 7905290046 | |
| Download: ML19289E736 (4) | |
Text
,
Form NRC418 U.S. NUCLEAR REGuLATCRY CoVVISSICN 8
to CfR M CERTIFICATE OF COMPL!ANCE For Radioactive Materials Packages 1.fa) Certificate Numter 1.(b) Revision No.
1 (c) Package Ident fication No.
1 (d) Pages No. 1.fe) Total No. Paq.
ongg 1
ifc a /cnno /n ( TF 1
4
- 2. PREAMBLE 2.(a)
This certificate is issued to satisfy Sections 1732334,173.394.173235, and 173236 of the Oeoartrnent of Transportation Wazarde Materiais Regulations (49 CFR 170169 and 14 CFR 103) and Sections 146-19-10a and 146-19-100 of the Ceoartment cf Transportation Cancerous Cargoes Regulations (48 CFR 146-149), as amended.
2.(b)
The packaging and contents described La item 5 below, meets the safery standards set forth in Sueoart C of Titte 10, code of Federal Regulatens, Pwt 71," Packaging of Radioactive Materials fer Transoort and Transocrtation of Radioactive Matenal Under Cartain Conditions.
2.(c)
This certificate does not relieve the consignor from comodiance with any reouirement of the regulations of the U.S. Oeoartment of Transoortation or otner aceticaele regulatory agencies, incluaing the government of any country througn or into which tt'e paczage will be transoorted.
- 3. This certificate is issued on tf e basis of a safety analysis report of the package design or apodication-3.(a)
Prepared by plame and address):
3.lb)
Title and identification of report or acclicaticn:
General Electric Company General Electric Company application dated P.O. Box 780 March 12, 1973, as supplemented.
Wilmington, North Carolina 28401 3.te) cocket No. 71-9009 4 CCNCITIO NS This certifieste le conditional upon the fulfilling of the requirements of Subcart O of 10 CFR 71, as acodicscle, and the conditions scocified b item $ below.
- 5. Cescriptions Of Packaging and Authorized Centents, Model Nurncer, Fissile C! ass, Cther Conditions, and
References:
(a) Packaging (1) Model No.: FL 10-1 (2) Description Two 16-gage 55-gallon drums welded 'end to end, approxima'.ely 68 inches long and 22-1/2 inches in diameter. The outer drum closure shall be accomplished by at least 'a 12-gage bolt-locking ring with drop-forged lugs, one of which is threaded to receive at least 5/8-inch diameter bolt and, lock nut. The pressure vessel support mechanism consists of wood supports, steel inner sleeve and nut ring to receive the containment vessel, and fire resistant phenolic foam, formed in place in accordance with AEC Materia?s and Equipment Specificatic.; SP-9 to an average finished dens.4ty of at least 8 pounds per cubic foot for the main body and 10 pounds per cubic foot for the cap.
Gas relief holes shall be provided in the outer steel drum.
The containment vessel is a 304L stainless steel 5-inch schedule 4_0 pipe, approximately 53-1/2 inches long, with a 304L stainless
. itt el T/2-inch thick welded bottom plate and a 304L stainless steel 300 pound slipon flange and Blind flange which is fastened by eight 3/4-inch steel bolts. The flange closure is gasketed by s
two flouroelastomer 0-rings with a pressure tap between the two
/
0-rings grooves. During shipment, the 0-ring groove pressure tap 790529004a 2043 27'8 amu.
f
Page 2 - Certificate No. 9009 - Revision No. 3 - Dccket No. 71-9009 5.(a)(2) Description (continued) is sealed with a pipe plug with threads wrapped in teflon tape. A 1/4-inch stainless steel valve is screwed into the blind flange of the containment vessel. The valve is sealed by a pipe cap (threads wrapped with teflon tape) and is protected by a 2-1/2-inch high section 5-inch Schedule 40 pipe welded to the top of the flange. The packaging has a maximum gross weight of 500 lbs.
(3) Drawings The FL 10-1 package is described by International Nuclear Company (INC0) Drawing No. DSD-479-D, Rev. C, and the containment vessel described by INC0 Drawing clo. DSD-480-0, Rev. C.
The containment vessel seal is described by INC0 Drawing No. DED-169-B, Rev. 2.
(b) Contents (1)
Type and form of material (i) Uranyl nitrate solutions having a concentration of uranium 235 and uranium 233 not exceedirm 350 grams per liter and an H/U-235 atomic ratio not less than 80, provided that the U-233 and plutonium content is i
not more than 1% of the U-235 content; or (ii) Uranyl nitrate solutions having a combined concen-tration 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 comLined 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 50u) containing uranium-235; (iv) 2 or (v) Dry compounds and mixtures of fissile plutonium-uranium-235.
z0h_ 279 h
Page 3 - Certificate No. 9009 - Revision No. 3 - Docket No. 71-9009 5.(b) Contents (continued)
(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 the 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.
(ii)
For the contents described in 5(b)(1)(iv):
Maximum decay heat load not to exceed 18 watts and 950 grams t'ssile material.
(iii) For the contents described in 5(b)(1)(v):
Maximum decay heat load not to exceed 30 watts, and 4.5 kilograms fissile material.
(c) Fissile Class I
6.
The solution contents of the package call be contained with a bottle having one of the following specifications:
(i) Siit vent polyethylene bottle per CAPE-ll70-37, (ii) Duo-vent polyethylene bottle per Nuclear Fuel Services, Inc.,
Specification U-l and Drawing No. 5B-U-740, or (iii) Steinless steel bottle as shown on General Electric Company Drawings Nos. FRO-140 and FR0-140A.
7.
The polyethylene bottles may be packaged within the metal inner container described by Chester-Jensen Company, Inc., Draw'ngs Nos.1092M-1,1093M-1,1095M-1 and 1096M-1, Issue 1, dated April 26, 1971.
8.
The packaging for the polyethylene bottles shall include a flexibile restraining device (such as recommended in ARH-1819 " Vibration Testing of L-3 and L-10 Shipping Containers") placed between the cap assembly of the polyethylene bottle and the closure flange of the pressure vessel to assure that the polyethylene bottle will vibrate at the same frequency as the pressure vessel during transport.
20A5 280 m
Page 4 - Certificate No. 9009 - Revision No. 3 - Docket No. 71-9009 9.
Dry compounds and mixtures which shall be packaged within sealed metal cans or DOT specification 2R containers (49 CFR 5178.34); and placed within an inner container constructed and leak tested as specified on General Electric Illustration AFL 1105.
- 10. Appropriate steps shall be taken to assure that from the time of sealing to the time of delivery to the consignee, the pressure in the containment vessel will not exceed 40 psig.
- 11. Prior to each shipment of more than Type A cuantities of radioactive material, the double 0-ring seal shall be tested at 100 psig and leak detection performed by a method capable of detecting a leak greater than 10 3 atm cc/sec at standard temperature and pressure. No package with a detectable leak shall be delivered to a carrier for transport.
12.
In addition to the requirements of Subpart D or 10 CFR 71, a test shall be performed on each containment 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 performed by a method 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.
- 13. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).
14.
Expiration date: August 31, 1983.
REFERENCES General Electric Company application dated March 12, 1973.
Supplements dated: April 13, 1973; March 21, 1974; and April 16, 1979.
l FOR THE U.S. NUCLEAR REGULATORY COMMISSION d& A f/dr! Ej Charles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle and Material Safety Da te:
2043 281
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