ML19339D065
| ML19339D065 | |
| Person / Time | |
|---|---|
| Site: | 07105450 |
| Issue date: | 01/26/1981 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19339D061 | List: |
| References | |
| NUDOCS 8102170186 | |
| Download: ML19339D065 (4) | |
Text
I O
Form NRC418 U.S. NUCLE AR REGULATCRY CoMMISSloN CERTIFICATE OF COMPLIANCE gn C R 71 For Radioactive Materials Packages 1.fal Certificate Numoer 1.Ib) Revision No.
1.(c) Package Identification No.
1.(d) Pages No. 1.(e) Total No. Pages 5450 11 USA /5450/AF 1
4
- 2. PAEAMBLE 2.(a)
This certificate is issued to satisfy Sections 173.393a,173.394,173.395, and 173.396 of the oeoartment of Transportation Hazardous Mater:44s Regulations f49 CFR 170-189 and 14 CFR 103) and Sections 146-19-10a and 146-19-100 of the oepartment of Transoortation oangerous Cargoes Regulations 146 CF R 146-149), as amended.
2.Ib)
The packaging and contents descrioed in item 5 below, meets the safety standards set forth in Suboart C of Title 10. Code of Federal Regulations. Part 71. " Packaging of Radioactive Materiais for Transport and Transportat on of Radioactive Material Under Certain Conditions."
2.fc)
This certificate does not relieve the consigner from compliance arth any requirement of the regulations of the U.S. oepartment of Transportation or other aoolicable regulatory. agencies, including the government of any country througn or into which the package will be transoorted.
- 3. This certif cate is issued on the basis of a safety analysis report of the package design or aposication-3.(a)
Prepared by (Name and address):
3.(b)
Title and identification of report or application:
Westinghouse Electric Corporation Westinghouse Electric Corporation application P.O. Box 355 dated December 17, 1980, as supplemented.
Pittsburgh, PA 15230 3.tc) ooc *et No.
71-5450 4 Co' EDITIONS This certificate is conditional upon the fulfilling of the requirements of Suboart o of Io CFR 71, as applicable, and the conditions specified in item 5 below.
- 5. oescription of Packaging and Autnorized Centents. Model Numoer, Fissile C! ass, other Conditions. and
References:
(a) Packaging (1) Model Nos.:
RCC, RCC-1, RCC-2, RCC-3, and RCC-4.
(2) Description Steel fuel element cradle assembly consisting of a strongback and adjustable fuel element clamping assembly, shock mounted to a 14 gage steel outer container by shear mounts.
Neutron absorber plates are required for the contents as specified. Gross weight for the RCC and RCC-2 is 6,300 lbs.,
RCC-1 and RCC-3 is 7,200 lbs., and RCC-4 is 8,400 lbs.
(3) Drawings The packaging is constructed in accordance with Westinghouse Electric Corporation Drawing Nos.:
1596E24, 1596E25, and 1553E30 for the RCC and RCC-2; 1596E24, 1596E25, and 1553E31 for the RCC-1 and RCC-3; and 1596E22, 1596E23, and 1548E55 for the RCC-4.
810217017%
Page 2 - Certificate No. 5450 - Revision No. 11 - Docket No. 71-5450 5.
(b) Contents (1) Type and form of material (i) Uranium dioxide as zircaloy or stainless steel clad unirradiated fuel elements.
Two (2) neutron absorber plates consisting of 0.19" thick, full length stainless steel containing 1.3% minimum boron or 0.19" thick 0FHC copper are required between fuel elements of the following specifications:
14x14 15x15 14x14 15x15 17x17 16x16 14x14 Zr Zr SST SST Zr Zr Zr Type Clad Clad Clad Clad Clad Clad Clad Pellet diameter (nom), in 0.367 0.367 0.384 0.384 0.308-0.322 0.322 0.3805 Rod diameter (nom), in 0.422 0.422 0.422 0.422 0.360-0.374 0.374 0.44 Maximum fuel length, in 144 144 120 120 168 144 144 Maximum rods /
element 180 204 180 204 264 235 176 Maximum cross
- section, (nom), in sq 7.8
- 8. 4
- 7. 8 8.4
- 8. 4 7.8 7.98 Maximum U-235/
element, kgs 17.7 18.3 18.5 18.7 17.0 (144"L) 16.6 19.0 Maximum U-235 19.8 (168"L) enrichment, w/o 4.0 3.65 4.0 3.65 3.65 4.0 3.85 (ii) Uranium dioxide as zircaloy or stainless steel clad unirradf ated fuel rods of the following specifications:
Type SST Clad Zr Clad Zr, Clad Pellet diameter (nom), in 0.384 0.367 0.322 Rod diameter (nom), in 0.422 0.422 0.374 Fuel length (max), in 144 144 168 Maximum U-235 enrichment, w/o 4.0 4.0 3.65 l
(2) Maximum quantity of material per package (i) For the contents described in 5(b)(1)(1):
Two fuel elements.
(ii) For the contents described in 5(b)(1)(ii):
Two inner containers containing not more than 80 kilograms U-235.
Page 3 - Certificate No. 5450 - Revision No. 11 - Docket No. 71-5450 5.
(c) Fissile Class II and III (1) Minimum transport index to be shown on label for Class II 1.2 (2) Maximum number of packages per shipment for Class III 60 6.
Fuel rods shall be closely packed in the fuel rod container on no more than an equivalent metal-to-metal square lattice.
Partially loaded fuel rod containers shall be fitted with a minimum of three, equally spaced blocks, of which the noncombustible portion of the blocks and the method by which they are secured shall assure that the rods are maintained on no more than an equivalent metal-to-metal square lattice within the fuel rod container.
7.
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 shaathed fuel' assembly.
Alternatively, the fuel assembly may be enclosed in an 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 the entire cross section of the lower end of the assembly is unobstructed. When folding is used, the portion of the shcath 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 to 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.
8.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR $71.12(b).
9.
Expiration date:
January 31, 1986.
1
Page 4 - Certificate No. 5450 - Revision No. 11 - Docket No. 71-5450 I
i REFERENCES Westinghouse Electric Corporation application dated December 17, 1980.
l i
Supplement dated: January 21, 1981.
l FOR THE U.S. NUCLEAR REGULATORY COMMISSION CharlesE.[MacDonald,ChiefY
=
i Transportation Certification Branch i
Division of Fuel Cycle and Material Safety 0 ISSI Date:
1 b
.--m
--_...._,.__m..
-,_.._.-.x-.
..,,,.., - -, -...