ML19294B598
| ML19294B598 | |
| Person / Time | |
|---|---|
| Site: | 07105450 |
| Issue date: | 02/14/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19294B590 | List: |
| References | |
| NUDOCS 8003050125 | |
| Download: ML19294B598 (6) | |
Text
.
Form NRC418 U.S. NUCLEAR REGULATORY COMMISSION 10 C)7 '
CERTIFICATE OF COMPLCANCE U
R 71 For Radioactive Materials Packagws 1.(a) Certificate Number 1.(b) Revision No.
1.(c) Package Identification No.
1.(d) Pages No. 1.(e) Total No. Pages 54S0 7
USA /5450/B( )F 1
6
- 2. PREAMBLE 2.(a)
This cartificate 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 Sections 146-19-10s and 146--19-100 of the Department of Transportation Dangerous Cargoes Regulations (46 CFR 146-149), as amended.
2.(b)
The packaging and contents described in item 5 below, meets the safety standartis set forth in Eubpart C of Tit:e 10 Code of Fedeval Regulations, Part 71, ** Packaging of Radioactive Materials for Transport and Transportation of Radioactive
- Material Under Certein Conditions."
2.(c)
This certificato does not relieve the consignor from compliance with any requirement of the regulation' of the U.S. Department of Transportation or other applicable regulatory agencies, including the government of any country thruggh 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 application-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 July 13, 1973, as supplemented Pittsburgh, PA 15230 3.(c)
Docket No.
- 4. CONDITIONS This certificate is conditional upon the fulfilling cf the requirements of Subpart D of 10 CFR 71, as applicable, and the conditions specified in h -m 5 below.
- 5. Description of Packaging and Authorized Contents, Model Nurnber, Fissile Class, Otrer Conditions, ard
References:
(a) Packaging (1) Model Nos.: RCC, RCC-1, RCC-2, and RCC-3.
(2) Description Steel fuel element cradle assembly consistug of a strongback and adjustable fuel element clamping assembly, shock mounted to a 14-gage steel outer container by shear r.ounts.
Neutron absorber plates are required for the contents as specified.
(3) Drawings Containers constructed in accordance with Westinghouse Electric Corporation Drawings Nos. EDSK319401F, EDSK319402F, EDSK323133B, 6d4J580, for the RCt., 541F351, 684J861, 684J898, for the RCC-1, and 684J963, 541F614 and EDSK323133B for the RCC-2, and 1215E34, 1213E59,1215E60,1464F14 for the RCC-3.
(4) Fuel rod container reinforced 13-gage steel box approximately 9"x9"x160" constructed in accordance with Westinghouse Electric Corporation Drawing No. C5650055.
8003050[
Page 2 - Certificate No. 5450 - Refision No. 7 - Docket No. 71-5450 6.
(b) Contents t
(1) Type and form of material (1) 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 Type Zr Clad Zr Clad SST 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-236/ enrichment, w/o 3.2 3.7 3.9 3.7
2'
"?
u e
9, (ii) Uranium dioxide as zircaloy or stainless steel' clad unirradiated fuel Et elements. Two (2) neutron absorber plates consisting of 0.19" thick.
t full length stainless steel containing I.3% minimum boron or 0.19" O
thick 0FHC copper are required between fuel elements of the following g
specifications:
z 14x14 15x15 14x14 15x15 17x17 lix11 16x16 14x14
((
C-Zr Zr SST SST Zr SST Zr Zr Tyge Clad Clad Clad Clad Clad Clad Clad Clad 5'
Pellet diameter (Nom), in 0.367 0.367 0.384 0.384 0.308-0.322 0.503 0.322 0.3805 li Rod diameter (Nom), in 0.422 0.422 0.422 0.422 0.360-0.374 0.567 0.374 0.44 YL Maximum Fuel Length, in 144 144 120 120 144 65.7 144 144 g
Maximum Rods / element 180 204 180 204 264*
117 235 176
=
P Maximum Cross Section, (Nom),in,sq 7.8 d.4 7.8 8.4 8.4 8.7 7.8 7.98 sa Maximum U-235/ element, kgs 17 18 18.5 20.5 16.25 9.3 14.5 19.0 a
Maximum U-235 enrich-8 ment,w/o 3.85 3.59 4.0 4.0 3.5 4.3 3.5 3.85
((
5
- Guide thimbles to be as shown in Figure 1 of application dated February 5,1974 for the fuel and Figure 1 of application dated June 29, 1978 for the 3.25 2f 3.6 w/o enriched UO2 fuel.
6, w/o enriched U02 Q
e
Page 4 - Certificate No. 545; Revision No. 7 - 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:
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 144 144 144 Maximum U-235 enrichment, w/o 3.9 3.7 3.5 (iv) Mixed Pu02 in natural UO2 as pressed sintered pellets fully clad in leak-tight zircaloy of minimum 0.018" thickness as fuel rods which are assembled into 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. full length 0FHC copper are required between fuel elements of the following specifications:
Type 14 x 14 Pelletdiameter(Hom),in 0.367 Rod diameter (Nom), in 0.429 Maximum Fuel Length, in 120 Maximum Rods / element 180 Maximum Cross Section (Nom), in.sq.
7.8 Maximum Pu/ elements, kgs 14.5 Maximum Pu fissile / element, w/o 3.31 (v) Mixed Pu0 in natural UO2 as pressed sintered pellets fully clad in 2
leak-tight zirceloy of minimum 0.018" thickness as fuel rods of the ~
following specifications:
T,y.pe, Pellet diameter (Nom), in 0.367 Rod diameter (Nom), in 0.422 Fuel length (Nom), in 120 to 144 Highest w/o Pu fissile (Nom) w/o 3.6 (2) Maximum quantity of material per package (1) 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)(1)(iii):
T.o inner containers described in 5(a)(4) containing not more than 66 kilograms U-235.
Page 5 - Certificate No. 5450 - Revision No. 7 - Docket No. 71-5450 5.
(b) Contents (Continued)
(iii) For the contents described in 5(b)(1)(iv):
Two fuel elements.
(iv) For the contents described in 5(b)(1)(v):
Two inner containers described in 5(a)(4) containing not more than 66 kilograms Pu.
.t (c) Fissile Class II and III (1) Minimum tran: port 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 w!,ich 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 sheatn 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 sneath along its full length. At the bottom end of the fuel assembly, the bag will-be cut off cr folded back to assure that the entire cross section of the lower end of tne 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 sneath 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 'o 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 chat formed by the top of tne 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: July 31,1980.
Page 6 - Certificate No. 5450 - Revision No. 7 - Docket No. 71-5450 REFERENCES Westinghouse Electric Corporation application dated July 13, 1973.
Supplements cated February 5,1974; Harch 19,1975; April 27 and June 4,1976; August 2,1977; June 29,1978; and October 22,.1979 (WRD-LS&S-859).
Energy Research and Development Administration, Richland Operations Office, application dated July 16, 1976 required only for the use of the package for the shipment of the 11 x 11 SST clad fuel elements described in 5(b)(1)(ii) and limited in 6(b)(2)(.1).
FOR THE U.S. NUCLEAR REGULATORY COMMISSION N5 Charles E. MacDona d, Chie Transportation Certification Branch Division of Fuel Cycle and Material Safety FEB 141980 Date:
,