ML19338F700
| ML19338F700 | |
| Person / Time | |
|---|---|
| Site: | 07105450 |
| Issue date: | 10/14/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19338F696 | List: |
| References | |
| NUDOCS 8010270075 | |
| Download: ML19338F700 (5) | |
Text
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=
, 8:re-.9C M3 U.S. NUCLE AR REGULATCRY CoMMISSICN
(
thf CERTIFICATE OF COMPLIANCE 71 For Radioactive Materials Pacsages 1Ja! Certificate Number 1.(b) 5450 RevEn No.
i 1.tc) Packsee Icentification No.
1.(d), Pages No. 1.(e) Total P.?
- ?' '
USA /5450/AF 3
5
- 2. PREAYELE 2.(a)
Tnis certifica:e is issued to satisfy Sections 173.393a.173.394.173.395, and 173.396 of the Cepartment cf Transecriation Hazardous Materials Regulations (49 CFR 170189 and 14 CFR 1031 and Sections 146-19-10a and 146-19-100 of the Cepartment of Transportation cangerous Cargoes Regulations (46 CFR 146-149), as amended.
2.(b)
The packagica and contents described in item $ below, meets the safety standards set forth in Subpart C of Title 10. Code of Federal Regulations. Fort 71," Packaging of Racioactive Materials for Transport and Transportation of Radioactive Yaterial Under Certain Conditions.
2de)
This cartificate does not relieve the consignor from ecmoliance with atly requirement of the regulations of the U.S. Department of Transportation or otner applicable regulatory agencies, including the government of any country through or into which the package will be transported.
- 3. TNs certificate is issued on the basis of a safety analysis report of the package des;gn or aoolication-3Jal Preoared by F.*ar.e and address):
3.(b)
Title and identification of report or aoptication:
destinghouse Electric Corporation Westinghouse Electric Corporation application P.O. Box 355 dated July 13, 1973, as supplemented Pi!;.; burgh, PA 15230 3.tc) occ=et No.
71-5450 4 CC'JOlitCNS This certdicate is conditional uoan the fulfilling of the requirements of Subpart D of 10 CFR 71, as a plicable, and the conditions specified f
in item 5 below.
- 5. Cescriotion of Packaging and Authorized Contents. Model Number, Fissile Cass. Other Conditions, and
References:
(a) Packaging (1) itodel Mos.: 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 Containers constructed in accordance with Westinghouse Electric Corporation Orawing 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.
8910270 07 5
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Pa a 2 - Certificate No. 5450 - Revision No.10 - Docke ::c. 71-5450 5.
(b) Contents-(1) Type and form of material (i) Uranium dioxide as zircaloy or stainless steel clad unieradiated fuel elements of the following specifications:
15 x 15 14 x 14 14 x 14 15 x 15 Tyce Zr Clad Zr Clad SS7 Clad SST Clad Pellet diameter (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 7.8 7.8 8.4 Maximum U-235/ element, kgs 15 16 18 20 Maximum U-235/ enrichment, w/o 3.2 3.7 3.9 3.7 s.
4 i
n
iY
':l (ii) Uranium dioxide as zircaloy or stainless steel clad uriirradiated fuel elements.
Two (2) neutron ab,orber pla tes consisting of 0.19" thick, n
full length stainless steel containing 1.3% miniinum boron or 0.19" g
thick 0FilC copper are required between fuel ele sents of the following a
speci fica tions:
3 0a 14x14 15x15 14x14 15x15 17x17 11x11 16x16 14x14 f.
.lyp.e Clad Clad Clad Clad Clad Clad Clad Clad Pei1et diameter (nom), in 0.367 0.367 0.384 0.384 0.308-0.322 0.503 0.322 0.3805 8
thni diameter (noni), in 0.422 0.422 0.422 0.422 0.360-0.374 0.567 0.374 0.44 i
fiaximuni fuel length, in 144 144 120 12Cr 168 65.7 144 144
- o Maximuni rods / element 180 204 180 204 264*
117 235 176 2
tiaximum cross section, C
(nom), in sq
'7.8 8.4 7.8 8.4 8.4 8.7 7.8 7.98 8
Maximuni U-235/ element.
[
kys 17 18 18.5 20.5 16.25(144"L) 9.3 14.5 19.0 liaximuni U-235 enrich-19.0 (168"L) i ment, w/o 3.85 3.59 4.0 4.0 3.5 4.3 3.5 3.85 7
8' cGuide thimbles to be as shown in Figure 1 of application dated February 5,1974 for the 3.6 w/o enriched UO. fuel and Figure 1 of application dated June 29, 1978 for the 3.25 7.
2 w/o enriched 00 fuel.
2 M
0 0
8 L-.D M
F3 M
GD g
M b
Page 4 - Certificate No. 5450 - Revision No.10 - Docket No. 71-5450 5.
(b) Contents (continued)
(1) Type and form of material (continued)
(iii)
Uranium dioxide as :ircaloy or stainless steel clad unirradiated fuel rods of the following specifications:
Type SST Clad Zr Clad Zr Clad Pelletdiameter(nom),in 0.384 0.367 0.322 Roddiameter(nom),in 0.422 0.422 0.374 Fuel length (max), in 144 144 168 l
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 elements.
(ii) For the contents described in 5(b)si)(iii):
I g
Two inner containers described ir 5(a)(4) containing not more than 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 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 l
be fitted with a minimum of three, equally spaced blocks, of which the noncombustible i
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, l
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 tne assemoly is unobstructed. When folding is used, the portion of the sheath that
page 5 - Certificate !!o. 5450 - Revision No.10 - 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 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 !i71.12(b).
9.
Expiration date:
January 31, 1981.
REFERENCES Westinghcuse 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).
I 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, Richlar.) Operations Office, application dated July 16, 1976.
For the "cdel No. RCC-4 Packaging Westinghouse Electric Corporation supplement dated April 2,1980.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION Y)
Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and 00T 1 1 1990 Material safety Date: