ML19260A986
| ML19260A986 | |
| Person / Time | |
|---|---|
| Site: | 07105395 |
| Issue date: | 11/26/1979 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19260A983 | List: |
| References | |
| NUDOCS 7912060222 | |
| Download: ML19260A986 (4) | |
Text
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Form NRC418 U.S. NUCt. EAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE 10 C R 71 For Radioactive Materials Packages 1.(a) Certificate Number 1.(b) Revision No.
1.(c) Package Identification No.
1.(d) Pages No. 1.(e) Total No. Pages 6395 4
Il9 A / 5105 /R ( IF 1
a
- 2. PREAMBLE 2.ta)
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 170-189 and 14 CFR 103) and Sections 146-19-10a and ?46-19-100 of the Department of Transportation Dangerous Cargoes Regulations (46 CFR 146--149), as amendsd.
2.(b)
Se packaging and contents described in item 5 below, meets the safety starviards set forth in Subpart C of Title 10, Code of Federal Regulations, Part 71," Packaging of Radioactive Materiait for Tran xrt 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 certificate is issued on the basis of a safety analysis report of the package design or application-3.(a)
Prepared by (Name and address):
3.(b)
Title and identification of report or application:
Westinghouse Electric Corporation Westinghouse Electric Corporation's P. 0. Box 355 application dated October, 17, 1973.
Pittsburgn, PA 15230 3.(c)
Docket No.71-5395 4.
CONDITIONS Th!: certificate is canditional upon the fulfilling of the renuirements of Subrart O of 10 CFR 71, as applicable, and the conditions specified in item 5 below.
- 5. Oncription of Packaging and Authorized Contents, Model Number, Fissile Class, Other Conditions, and Reft.rences:
(a)
Packaging (1) Model No.:
CC (2)
Description The CC packaging consists of a steel fuel element cradle assembly with strongback and fuel f lement clamping assembly, shock mounted to a 14-gage steel outer container by shear mounts. The maximum weight of the packaging and contents is 5,500 pounds.
(3)
Drawings The CC container is constructed in accordance with the Champion Company's Drawings Nos. 10410,10536,10538, and 10541.
The steel box mounting assembly in accordance with Drawing No. SKA-219, Rev.2.
(4) Fuel rod container Reinforced 13-gage steel box approximately 7" x 7" x 110" constructed in accordance with Westinghouse Electric Company Drawing No. C8830214.
1520 009 7912060
Page 2 - Certificate No. 5395 - Revision No. 4 - Docket No. 7 - 5395 5.
(b) Contents (1) Type and form of material (i) Uranium dioxide as stainless steel clad unirradiated fuel assemblies of the following specifications:
14 x 14 15 x 15 14 x 14 Pellet diameter (Nom) 0.317" 0.355" 0.313" Rod diameter (Nom) 0.341" 0.385" 0.341" Maximun Fuel Length 105" 106" 90" Maximum Rods / element 173 208 173 Lattice Pitch (Nom) 0.453"
- 0. 51 3 "
0.453" Maximum Cross Section (Nom) 6.284"sq 7.635"sq 6.284"sq Maximum U-235/ element 10 kgs 14.25kgs 10 kgs Maximum U-235 enrichment 4.1 w/o 4.5 w/o 4.5 w/o (ii)
Mixed Pu0
- in natural or depleted UO2 as pressed sintered pellets 2
fully clad in leak-tight stainless steel of minimum 0.015" thickness as fuel rods which are assembled into fuel assemblies of the following specifications:
Type 15 x 15 Pellet diameter (Nom) 0.355" Rod diameter (Nom) 0.385" Maximum Fuel Length 106" Maximum Rods / element 208 Lattice Pitch (Nom) 0.51 3" Maximum Cross Section (Nom) 7.695" sq Maximum Pu fissile / element 15 kgs in UO / element 8.1 w/o Maximum Pu0 2
2 (iii) Uranium dioxide containing uranium up to 4 w/o enrichment in the U-235 isotope as stainless steel clad fuel rods of nominal diameter of 0.385".
Mixed Pu0
- in natural or depleted UO2 as pressed sintered pellets (iv) 2 fully clad in ' sk-tight stainless steel of minimum 0.015" thickness as fuel rcds of nominal diameter of 0.385" and containing up to 8 w/o total Pu0 in UO -
2 2
"Pu must contain a minimum of 17.2 w/o Pu-240.
Page 3 Certificate No. 5395 - Revision No. 4 - Docket No. 71-5395 5.
(b) Contents (continued)
(2) Maximum quantity of material per package (i) For the contents described in 5(b) (1)(i):
Two fuel assemblies containing not more than 28.5 kilograms U-235.
(ii) For the contents described in 5(b)(1)(ii):
Two fuel assemblies containing not more than 30 kilograms Pu fissile.
(iii) For the contents described 5(b)(1)(iii):
Two (2) inu.r containers descrbed in 5(a)(4) containing not more than forty-one (41) kilograms U-235.
(iv) For the contents described in 5(b)(1)(iv):
Two (2) inner containers described in 5(a)(4) containing not more than eighty-three (83) kilograms fissile content.
(c)
Fissile Class II and III (1) Minimum transport index to be show~n on label for Class II 1.5 (2) Maximum number of packages per shipment for Class III 60 6.
Each fuel assembly shall be unsheathed or shall be enclosed in an unsealed, poly-ethylene sheath which will not extend beyond the ends of the fuel assembly. The ends of the sheath shall not be folded or taped in any manner that would prevent the flow of liquids into or out of the sheathed fuel a'embly.
Alternatively, the fuel assembly may be enclosed in en elongated plastic bag or sheath along its full length. At the bottom end of the fuel assembly, the bag will be cut off or folded back to assure that ne entire cross section of the lower end of the assembly is unobstructed. When folding is used, the portion of the sheath that is folded back will be cinched with tape near its end to hold it in place, and the length will be such that when the assembly is loaded in the packaging, the folded sheath will be clamped in place in at least two grid locations. The top end of the bag may be gathered together and taped closed.
However, the top end then will be slit on all four sides. The slits will run perpendicular tc the axis of the assembly and will extend the inner distance between the top nozzle pads and spring clamps (approximately 60% of the length of each side.) The slits will be made in a plane near that formed by the top of the pads and clamps.
7.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).
1520 0!i
Page 4 - Certificate No. 5395, Rev. 4 - Docket No. 71-5395 8.
Expiration date: March 31, it'80.
REFERENCE Westinghouse Electric Corporation application dated October 17, 1979.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION t.U $$
%f/
Churles E. MacDonald, Chief Trat:sportation Certification Branch Division of Fuel Cycle and fiattrial Safety Date:
NOV 2 61979 1520 012