ML19329F875
| ML19329F875 | |
| Person / Time | |
|---|---|
| Site: | 07105450 |
| Issue date: | 06/27/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19329F870 | List: |
| References | |
| NUDOCS 8007110290 | |
| Download: ML19329F875 (5) | |
Text
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. Form NRC418 U.S. NUCLE AR REGULATORY CoMMISsiCN I[ 10 C R 71 U
CERTIFICATE Or COMPLIANCE For Radioactive Materials Packages 1.lal Certificate Number 1.(b) Revision No.
1.(c) 5450 9
USA /5d*50/AF 1.[d), Pages No. 1 (e) Total No. Pages Packa identification No.
5
- 2. PN E AMBt.E 2.la)
This certsficate is issued to satisfy Sectior's 173.393a.173.394.173.325, and 173.396 of the Cepartment of Transportation Hazardous Materials Regulations (49 CFR 170189 and 14 CFR 103) and sections 146-19-104 and 146-19-100 of the Department of Transportation oangerous Cargoes Regulations (46 CFR 146-149), as amended.
2.tbl The packaging and contents described in item 5 below meets the safety standards set forth in Subpart C of Title 10. Code of "scerel Regulations. Part 71. "Pacraging 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. Cepartment of Transportation or other apolicsole 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 analysrs report of the paczage design or application-3.lal Prepared by (Name and address):
3.tb)
Title and identification of repor or apolication:
Westinghouse Electric Corporation Westinghouse Electric Corporation application P.O. Box 355 dated July 13, 1973, as supplemented Pittsburgh, PA 15230 3.(c) oockei No.
- 4. CONDITIONS Th;2 certificate is conditional upon the fulfilling of the requirements of Swepart o of 10 CFR 71. as applicable, and the conditions specified
(
in item 5 below.
- s. Cescription of Fackaging and Autnerimod Contents uocei Numoer. Fissise C: ass otner Conditiens and
References:
(a) Packaging (1) hodel 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.
(3) Drawings Cantainers constructed in accordance eith Westinghouse Electric Corporation Crawing Nos.: EDSK319401F, EDSK319402F, EDSK323133B, 684J580, for the RCC; 541F351, 684J861, 684J898, for the RCC-1; 684J963, 541F614 and EDSK3231338 for the RCC-2; 1215E34,1213E59,1215E60,1464F14 for the RCC-3; and 1596E22,1596E23 and 1548E55 for the RCC-4.
(4)
Fuel rod container reinforced 13-gage steel box constructed in accordance with Westinghouse Electric Corporation Drawing No. C56J0055.
a
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800 7110 M
-e Page 2 - Certificate No. 5450 - Revision No. 9 - Docket No. 71-5450 t!E:l 5.
(b) Contents (1) Type and form of material (i)
Uranium dioxide as zircaloy or stainless steel clad unirradiated fuel elements of the following specifications:
15 x 15 14 x 14 14 x 14 15 x 15 Tyge Zr Clad Zr Clad SST Clad SST Clad Pelletdiameter(nom),in 0.367 0.367 0.384 0.384 Rod diameter (nom), in 0.422 0.422 0.422 0.422 Maximum fuel length, in 144 144 120 122 Maximum rods / element 204 180 180 204 Maximum cross section (Nom),
in sq 8.4 7.3 7.8 8.4 Maximum U-235/elesient, kgs 15 16 18 20 Maximum U-235/ enrichment, w/o 3.2 3.7 3.9 3.7 a
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ill{h~l b
Elib 2-(ii) 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" g
thick 0FHC copper are required between fuel elements of the following o
speci fica tions:
2 0o 14x14 15x15 14x14 15x15 17x17 llxil 16x16 14x14 1
Zr Zr SST SST Zr SST Zr Zr Type Clad Clad Clad Clad Clad Clad Clad Clad Pellet diameter (nom), in 0.367 0.367 0.384 0.384 0.308-0.322 0.503 0.322 0.3805 E
Rod diameter (nom), in 0.422 0.422 0.422 0.422 0.360-0.374 0.567 0.374 0.44 e
Maximum fuel length, in 144 144 120 120 168 65.7 144 144
- o Maximum rods / element 180 204 180 204 264*
117 235 176
'E Maximum cross secti..o 2
(nom), in sq
!7.8 8.4 7.8 8.4 8.4 8.7 7.8 7.98 8
Maximum U-235/ element, i
ks 17 18 18.5 20.5 16.25(144"L)9.3 14.5 19.0 6
9
~
Maximum U-235 enrich-19.0 (168"L) ment,w/o 3.85 3.59 4.0 4.0 3.5 4.3 3.5 3.85 7
8
- Guide thimbles to be as shown in Figure 1 of application dated February 5,1974 for the fe 3.5 w/o enriched U02 fuel and Figure 1 of application dated June 29, 1978 for the 3.25 fuel.
w/o enriched UO2 M
k' 8
e O
Page 4 - Certificate No. 5450 - Revision No. 9 - Docket No. 71-5450 5.
(b) Contents (continued)
(1) Type and form of material (continued)
(iii)
Uranium dioxide as zircaloy or stainless steel clad unirradiated fuel rods of the following specifications:
h SST Clad Zr Clad Zr Clad Pelletdiameter(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 3.9 3.7 3.5 (2) Maximum quantity of material per package (i) For the contents described in 5(b)(1)(i) or (5)(b)(1)(ii):
Two fuel elemen'ts.
(ii) For the contents described in 5(b)(1)(iii):
Two inner containers described in 5(a)(4) containing not more than w
80 kilograms U-235.
(c) Fissile Class II and III (1) Minimum transport index to be shown on label for Class II 1.5 (2) Maximum number of packages per shipment for Class III 60 6.
Fuel rods snall 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 rection of the lower end of the assembly is unobstructed. When folding is used, the portion of the sheath that I
gy
Page 5 - Certificate No. 5450 - Revision No. 9 - Docket No. 71-5450 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 for-ned 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 971.12(b).
9.
Expiration date: October 31, 1980.
REFERENCES Westinghouse Electric Corporation application dated July 13, 1973.
Supplements dated:
February 5,1974; March 19,1975; April 27 and June 4,1976; August 2, 1977; June 29, 1978; and October 22,1979(WRD-LS&S-859).
For the 11 x 11 SS Clad Fuel Elements Described in 5_(b)(1)(ii) and Limited _in 5(b)(2)(i)
Energy Research and Development Administration, Richland Operations Office, application dated July 16, 1976.
For the Model No. RCC-4 Packaging Westinghouse Electric Corporation supplement dated April 2,1980.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION dA 4#ADA Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety JUN 2 71980 De l
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