ML20042A023
| ML20042A023 | |
| Person / Time | |
|---|---|
| Site: | 07109103 |
| Issue date: | 03/10/1982 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20042A022 | List: |
| References | |
| NUDOCS 8203220567 | |
| Download: ML20042A023 (4) | |
Text
Fod NRC418 U.S. NUCLEAR REGULATORY COMMISSloN
[,gfi2 CERTIFICATE OF COMPLIANCE gR7 Fcr Radioactive Materials Packages 1.h) Certificate Number 1.(b) Revision No.
1.(c)USA /9103/B( pion No.
1 4
Package Identific 1.(d) Pages No. 1.(e) Total No. Pages
)F 9103 2
- 2. PRE AMBLE 2.f a) This certificate is issued to satisfy Sections 173.393a,173.394,173.395, and 173.396 of the Department of Transportation Hazardous Materials Regulations (49 CFR 170189 and 14 CFR 103) and Sections 14"r-19-10a and 146-19-100 of the Department of Transportation Dangerous Cargoes Regulations (46 CFR 146-149), as amended.
2.(b)
The packaging and contents described in item S below, meett the safety standards set forth in Subpart C of Title 10, Coos of Federal Regulations, Part 71, " Packaging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certain Conditions.**
2.(c)
This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other applicable regulatory agencies, including the government of any country through or into which the package will be transported.
- 3. This cartificate is issued on the basis of a saf ty analysis report of the package design or application-3 3.(a)
Prepared by (Name and address):
3.(b)
Title and identification of report or application:
NL Industries, Inc.
NL Industries, Inc. application dated P. O. Box 2046 September 7, 1977, as supplemented.
Wilmington, DE 19899 3.(c)
Docket No.
- 4. CONDITIONS TNa certificate is conditional upon the fulfilling of the requirements of Subpart D of 10 CFR 71, as applicable, and the conditions specified in item 5 below.
- 5. Description of Packaging and Authorized Contents, Model Number, Fissile Class, Other Conditions, and
References:
(a)
Packaging (1) Model No.: NLI-6502 (2) Description A steel, lead, and depleted uranium shielded shipping cask.
Its overall dimensions are 33.5 inches in diameter by 130 inches long. The l
loaded cask weighs about 45,300 pounds. The wall thickness of the cavity and cuter 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 regior.3. The inner region, which is a maximum of 5-3/4 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 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 the cask recess. The lids, like the main cask body, contain an outer sacrifical region (2" thick containing ten 0.018-in terne discs with the remaining volume filled with 6% antimonial 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.
8203220567 820310 PDR ADOCK 07109103 C
Page 2 - Certificate No. 9103 - Revision No. 2 - Docket No. 71-9103 E.
(a)
(2) Description (Cont'd)
One lid contains a 1/2-inch drain line and valve.
The other lid contains two,1/2-inch lines for a pressure relief valve with filter and the other line is capped.
The fuel rods are contained within an approximate 11-1/2-inch square by 128-1/2-inch long openwork basket constructed of stainless steel l
angle and strap. The basket has a full-length lid along one side, for horizontal loading, and a lid on one end for vertical unloading. A l
l vertical, stainless steel-clad Boral pcison plate divides the basket into two, full-length halves, and two partial poison plates are incorporated into the sides of the basket.
A metal screen enclosure surrounds the package in transport a serve as a sun-shade and prevent inadvertent use of structural parts of the package, other than the tie-down devices for securing the package to the vehicle during transport.
The cask rests horizontally on its integral sepporting structure at each end, and the supporting structure is bolted to a separate structure attached to the deck of the special trailer provided for its use.
(3) Drawings The Model No. NLI-6502 shipping package is constructed in accordance National Lead Company Drawing Nos.:
5797-P, Rev. 1 Details-Safety Shield 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 l
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P'ge 3 - Certificate No. 9103'- Revision No. 2 - Docket No. 71-9103 a
5.
(b) Contents (1) Type and form of material Irradiated NRU-NRX aluminum-uranium alloy fuel rods enriched in the U-235 istotope with the following specifications:
NRU NRX (MKI&IV)
Number of elements per rod 12 7
Maximum U-235 conte'nt per rod 495 550 prior to irradiation, g (1.8 per cm)
(2.0 per cm)
Minimum average burnup, %
45 45 Minimum decay time, days 120 120 (2) Maximum quantity 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) 6.
Poison inspection and loading of fuel rods must be subject to the following conditions:
(a)
Poison inspection and loading of fuel rods in accordance with Section VII-B.2.(B.)(3.) (pp. VII-10 thru VII-ll) of the application, and (b) The package must not be leaded with a mass which exceeds 75% of critical, l
determined by extrapolation to zero reciprocal count rate.
7.
Dumy fuel rods consisting of empty aluminum pipes must be installed in every fuel rod position not occupied with fuel.
8.
The cask cavity must be dry (no free water) when delivered to a carrier for transport.
9.
Additional contents in accordance with Nuclear Assurance Corporation application dated February 17, 1982. Fuel rods must be contained within a fuel basket to minimize damage to the rods during normal conditions of transport.
- 10. The cask contents must be so limited under normal conditions of transport that the dose rate will.not exceed 10 mrem /hr at three (3) feet from the external surface of the cask.
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9 Page 4 - Certificate No. 9103 - Revision No. 2 - Docket No. 71-9103
- 11. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).
- 12. 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 COP 91ISSION W.
^Th Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety Date:
MAR 101982 I
(
of U.S. Nuclear Regulatory Commission Transportation Certification Branch Model No. NLI-6502 Docket No. 71-9103 By application dated February 17, 1982, Nuclear Assurance Corporation i
requested additional contents in the Model No. NLI-5602 package.
1 The applicant requests shipment of four (4) irradiated fuel rods containing, prior to irradiation, 203 grams U-235 and allowed to decay for at least one (1) year. The rods will be positioned within a fuel basket to minimize damage to the rods during normal conditions of transport as discussed with R. H. Odegaarden and C. R. Johnson of Nuclear Assurance Corporation on March 4, 1981. The possible noble gas release would be l
much less than the limit of Part 71 under accident conditions of transport.
Nuclear criticality safety has been adequately addressed by the applicant.
M[
Charles E. MacDonald, Chief Transportation Certification Branch l
Division of Fuel Cycle and Material Safety, NMSS Date:
MAR 1 0 yggg
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