ML19345G755
| ML19345G755 | |
| Person / Time | |
|---|---|
| Site: | 07105450 |
| Issue date: | 04/15/1981 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19345G750 | List: |
| References | |
| NUDOCS 8104220222 | |
| Download: ML19345G755 (4) | |
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Form NAC418 U.s. NUCLEAR REGULATORY CoMMisstoN U
CERTIFICATE OF COMPLIANCE M CFR 71 For Radioactive Materials Packages 1.(a) Certificate 1.(b) R n No.
1.(c) d t f cation No.
1 (d) Pages No. 1.te) Total No. Pages
- 2. PRE AM8LE 2.fa)
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 Sect ans 146-19-10a and 146-19-100 of the Decertment of Transportation oangerous Cargoes Regulations (46 CFR 146-149), as amended.
2.(b)
The packaging and contents described in item 5 below, meets the safety standards set forth in subpart C of Title 10. Code of Federal Aegulations. Part 71. ** Packaging of Radioactive Materials for Transport and Transportation of Radioactive Matenal Under Certain Conditions.
2.(c)
This certificate does not relieve the consignor from comohance with any recuirement of the regulations of the U.s. oeoartment of Transportation or otner applicable regulatory agencies, including the government of any country ~hrough 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 aoolication-3.(a)
Prepared by (Name and address):
3.(b)
Title and identification of report or apotication:
Westinghouse Electric Corporation Westinghouse Electric Corporation application P.O. Box 355 dated Decemcer 17, 1980, as supplemented.
Pittsburgh, PA 15230 71-5450 3.(c)
Docnet No.
4.
CONOITIONS This certificate is conoitionai upon the fulfiiling of the seawirements of Succart 3 of *O CFR 71, as asolicac e, and the concit.ons specified in item s below.
- 5. Gescnotion of Pacmaging and Authonzed Contents. Mooel Numoer. Fissile Class, otner Conostions. 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 i,
RCC-2; 1596E24, 1596E25, and 1553E31 for the RCC-1 and RCC-3; and i
1596E22, 1596E23, and 1548E55 for the RCC-4.
(4) Fuel rod container reinforced 13 gage steel box constructed in 1
accordance with Westinghouse Electric Corporation Drawing No. C56J0055.
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810.422022.2.
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Page 2 - Certificate No. 5450 - P.evision No.13 - Docket No. 71-5450 5.
(b) Contents (1) Type and form of material (i) Uranium dioxide as zircaloy or stainless steel clad unitradiated 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 0.344-l (nom), in 0.367 0.367 0.384 0.384 0.308-0.322 0.322 0.3805 Rod diameter 0.400-l (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 Mr.aimum 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 unitradiated 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 3
Fuel length (max), in 144 144 168 Maximum U-235 enrichment, w/o 4.0 4.0 3.65 (2) Maximum quantity of material per package (1) For the contents described in 5(b)(1)(i):
Two fuel elements.
(ii) For the contents described in 5(b)(1)(ii):
Two inner containers containing not more than 80 kilograms U-235.
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Page 3 - Certificate No. 5450 - Revision No. 13 - 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 i
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 sheathed 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 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 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 lice.nse provisions of 10 CFR 571.12(b).
9.
Expiration date: January 31, 1986.
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Page 4 - Certificate No. 5450 - Revision No. 13 - Docket No. 71-5450 REFERENCES Westinghouse Electric Corporation application dated December 17, 1980.
Supplement dated:
January 21, 1981.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION f)A&
Charles E. MacDonald, Chief Transportation Certification Branch l
Division of Fuel Cycle and Material Safety Date:
I 0 IS3I 4
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