ML19249A599
| ML19249A599 | |
| Person / Time | |
|---|---|
| Site: | 07109103 |
| Issue date: | 05/03/1978 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19249A597 | List: |
| References | |
| NUDOCS 7908240035 | |
| Download: ML19249A599 (4) | |
Text
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Frem NRC 618 U.S. NUCLEAR REGULATORY COMMISlON (12 731 CERTIFICATE OF COMPLIANCE
. ' CFR 71 For Radioactive Matarials Packages e
Cartif e umoer 1.(b) R ion No.
1(c) e e f No.
.(d) 1.(e) Total No.
Pz7g fJo.
- 2. PREAMBLE 2.fal This cartificate is iuuad to satisfy Sections 173.333a.173.:394.173.395, ard 173.396 of the Ceoartment of Trantaartstion Har Materials Regulations (49 CFR 170189 and 14 CFR 103) and S.-tisna 146-10-10a and 146-19 10o of the Department of Transportation Cancerous Cargoes Regulations (46 CFR 146-149), as amended.
2.(b)
The packaging and contents described in item s below, meets the safety standsrds set forth in Subpart C of Title 10. Code of Federal Regulations. Part 71. " Packaging of Rm2icactivs Materials for Transpost and Transcortation of Radioactive Matenal Un Certain Conditions.**
2.fc]
This certificate does not relieve the consigner from comeliance with any reauirement of the regulations of the U.S. Departmerit Transcortation or other apolicaola regulatory agencies,includW the governtnant of assy country through or into which the pacu Will be transcorted.
- 3. This :=rtificato is inued on the basis of a safety analysis report of the packMe design or acclicatum-3.(al Prepared by Chme and addressp 3.Ib) Title and identification of reccet or acodication:
!il Industries, Inc.
NL Industries, Inc. application dated P. O. Bor 2046 September 7, 1977, as supplemented.
Wilmington, Delaware 19899 3.fel Docket No.
- 4. CONDITICNS This cartrficate is concitenal upon the fulfi!Iing of the requirements of Subcart D of 10 CFR 71, as applicable, and the cenditions spec in item 5 beicw.
- 5. Description of Pacr. aging ard Autnorizec Centents. Mocal Numoer. Fissile C: ass. Other Conditices, aid Reserence
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(a)
Packaging (1)- Model No.: NLI-6502 (2)
Description A steel, lead, and depleted uranium shielded shipping cask.
Its u
overall dimensions are 33.5 inches in diameter by 130 inches long.
The loaded cask weighs about 45,300 pounds. Tne wall thickness of the cavity and outer shell is 1/2 inch.
The wall thickness of the inner shell is 1 inch.
The main body of the cask is divided into two regions. The inner region, which is a maximum of C-3/4 inches thick, contains uranium shielding angles at the four corners, the remainder of the shielding region is filled with chemical grade lead. The outer (sacrificial) 3-inch thick region is filled with lower melting point 6% antimonial lead.
The cask contains six (6) fusible " weep holes" around the cask at each end.
This 5
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7908240035
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Page 2 - Certificate No. 91C3 - Revision No.1 - Docket No. 71-9103 5.
(a)
(2) Description (Cont'd) sacrificial region also contains 10 layers of 0.018-in terne plate. The main body of the cask is equipped with two (2) lids, one on each end.
The two lids are similar in construction, each being 24.5 inches in diameter and extending 5 inches into tiie cask recess. The lids, like the main cack body, contain an outer sacrifical region (2" thick containing ter> 0.018-in terne discs
'with the remaining volume filled with 6% at timonial lead) and an inner region (4-5/8" thick) containing chemical grade lead. The sacrificial region in each lid is fitted with exterior weep holes.
One lid contains a 1/2-inch drain line and valve.
rhe 6ther lid contains two 1/2-inch lines foSd pressure relief valve with filter and the other line is capped.
The fuel rods are contained within an approximate ll-1/2-inch square by 128-1/2-inch long openwork basket constructed of stainless steel angle and strap.
The basket has a full-length lid a'.ong one side, for horizontal loading, and a lid on one end for vertical unloadi.g. A vertical, stainless steel-clad Boral poison plate divides the basket into two, full-length haives, and two partial polscn plates are incorporated into the sides of the basket.
A metal screen enciesure surrounds the pckage in transport to serve as a sun-shade and prevent inadvertent use of structural parts of the package, other than the tie-cown devices for securing the package to the vehicle during transport.
The cask rests horizontally on its integral supporting structure at each end, and the supporting structure is bolted to a seperate w
structure attached to the deck of the special trailer provided for its use.
(3) Drawings The Model No. NLI-6502 snipping package is const*ucted in accordance National Lead Company Drawings Numbers:
5797-P, Rev. 1 Details-Safety Shield 9 5798-0, Rev. 1 Cask Tie-Down 6502-01, Rev. 5 Basket Details 6502,03, Rev. 4 Latch and Basket Details 6502 '04, Rev. 3 Basket and Lid Assembly 6502-07, Rev. 5 Cask 6502-08, Rev. 4 Lid Assembly and Details
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Page 3 - Certificate No. 9103 - Revision No. 1 - Docket.No. 71-9103 5.
(b) Contents (1) Type and form of material Irradiated NRU-NRX aluminum-uranium alloy fuel rods e'nriched in the U-235 istotepe with the following specifications:
NRU NRX (MKI&I Q Number of elements per rod 12 7
Maximu'm U-235 content per rod 495 550 prior to irradiation, g (1.8 per cm)
(2.6 per em Minimum average burnup, %
45 45 Minimum decay time, days 120 120 (2) Maximum qucntity of material per package The maximum decay heat load per package not to exceed 14,000 Btu /hr, and 20 NRU fuel rods or 28 NRX fuel rods per package.
(c) Fissile Class III Maximum number of packages per shipment One (1)
F Poison inspection and loading of fuel rods shall be subject to the following conditions:
(a)
Poisen inspection and loading of fuel rods in accordance with Section VII-B.2.(S.)(3.) (pp. VII-10 thru VII-il) of the application, and (b) The package shall not be loaded with a mass which exceeds 75% of criticci, determined by extrapolation to zero reciprocal count rate.
7.
Dummy fuel rods consisting of empty aluminum pipes shall be installed in every fuel rod position not occupied with fuel.
8.
The cask cavity shall be dry (no fiee water) when delivered to a carrier for transport.
The cask contin'ts shall be so l'mited under normal conditions of transport 9.
that thh dose rate will not exceed 10 mrem /hr at three (3) feet from the external surface of the cask.
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Page 4 - Certificate No. 9103 - Revision No. 1 - Docket No. 71-9103
- 10. Construction of additional packaging is not authorized.
- 11. Expiration Date: May 31, 1983.
REFERENCES NL Industries, Inc. application dated September 7,1977.
Supplement dated:
May 1, 1978.
FOR THE U.S. NUCLEAR REGULATORY. COMMISSION f
Charles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle and Material Safety 3U Date:
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