ML19351G300
| ML19351G300 | |
| Person / Time | |
|---|---|
| Site: | 07105450 |
| Issue date: | 01/29/1981 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19351G295 | List: |
| References | |
| NUDOCS 8102230464 | |
| Download: ML19351G300 (4) | |
Text
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Form NRC418 U.S. NUCLE AR REGUt.AToRY CoMMISStoN U
CERTIFICATE OF COMPLIANCE lo CFR 71 For Radioactive Materiais Packages 1.(a) Certificate Numcor 1.(b) Revision No.
1(c) Package Identification No.
1.[d) Pages No. 1.(e) Total No. Pages O
M US?./SiSC/fr 1
4
- 2. PREAMBLE 2.(a)
This certificate is issued to satisfy Sections 173.393a.173.394,173.395, and 173.396 of the Departrnent of Transcortation Hazardous Materials Regulations (49 CFR 17o.189 and 14 CFR 103) and sections 146-19-loa and 146-19-100 of the Department of Transportation Dangerous Cargoes Regulations (46 CFR 146-149). as amended.
2.(b)
The packaging and contents oescribed in hem 5 below, meets the safety standards set forth in Suboert C of Title to. Code of Federal Regulations. Part 71. ** Packaging of Radioactive Materiais for Transport and Trans ortation of Radioactive Meterial Under Cer.ain Conditons.
2.(c)
This artificate does not relieve the consignor from compliance wrth any requiremerrt of the regulations of tfie U.S. Department of Transportation or other apoticable reguistory agencies, enduding the government of any country through or into which the nar==a=
will be trensoorted.
- 3. Thes certificate is issued on the basis of a safety analysis report of the package desagn or apodicaren-3 (a) Prepared by (Name and address):
3.(b)
Title and identafication of report or spotication:
Westinghouse Electric Corporation Westinghouse Electric Corporation application P.O. Box 355 dated December 17, 1980, as supolemented.
Pittsburgh, PA 15230 71-5450 3.(c)
Docket No.
- 4. CONDITIONS This certificate is conditonal upon the fulfilling of the reauirements of Subpart D of to CFR 71, as apoticable, and the conditons specified in item S below.
- 5. Description of Packaging and Autnorized Contents. Model Nurnber. Fissile Class. 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. l (4) Fuel rod container reinforced 13 gage steel box constructed in accordance with Westinghouse Electric Corporation Drawing No. C56J0055.
8102300 lk
Page 2 - Certificate No. 5450 - Revision No. 12 - Docket No. 71-5450 5.
(b) Contents i
(1) Type and form of material (1) 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 M
Clad Clad Clad Clad Clad Clad __
Clad Pellet diameter (nom),in 0.367 0.367 0.334 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. 4 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 Maximem 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 :ods of the following specifications:
T SST Clad Zr Clad Zr Clad m
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 (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. 12 - 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 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 license provisions of 10 CFR 571.12(b).
9.
Expiration date:
January 31, 1986.
~
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Page 4 - Certificate No. 5450 - Revision No. 12 - 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 Q )k CharlesE.MacDonald[ Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety JAN 2 91981 Date:
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