ML20052B535
| ML20052B535 | |
| Person / Time | |
|---|---|
| Site: | 07105450 |
| Issue date: | 04/12/1982 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20052B532 | List: |
| References | |
| NUDOCS 8205030235 | |
| Download: ML20052B535 (5) | |
Text
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{ s Form NRC-618 U.S. NUCLEAR REGULATORY COMMISSION l1 CERTIFICATE OF COMPLIANCE
,g CFR 71 Fct Radioactive M;terials Psck ges 1.h) Certificate Number 1.(b) vision No.
1.(c) Package Identification No.
1.(d) Pages No. 1.(e) Total No. Pages 5450 USA /5450/AF 1
4
- 2. PRE AMBLE 2.(a)
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 Sections 146-19-10a 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 S below, meets the safety standards set forth in Subpart C of Title 10, Code of Federal Regula* ions, Part 71, ** Packaging of Radioactive Materials f,a 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. Department of Transportation or other applicable 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 analysis report of the package design or application-3 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 December 17, 1980, as supplemtated.
Pittsburgh, PA 15230 3.(c)
Docket No.
- 4. CONDITIONS This certificate is conditional upon the fulfilling of the requirements of Subpart D of 10 CFR 71, as applicable, and the conditions specified in item 5 below.
- 5. Description of Packaging and Authorized Contents, Model Number, 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-3; 1596E24,1596E25, and 1553E31 for the RCC-1 and RCC-2; 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.
820.s030235 l
/
Page 2 - Certificate No. 5450 - Revis~ ion No. 15 - Docket No. 71-5450 5.
(b) Contents (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 17x17 16x16 14x14 Zr Zr SST SST Zr Zr Zr Zr Type.
Clad Clad Clad Clad Clad Clad Clad Clad Pellet diameter 0.344-(nom),in 0.367 0.367 0.384 0.384 0.308 0.320 0.322 0.3805 Rod diameter 0.400-(nom),in 0.422 0.422 0.422 0.422 0.360 0.374 0.374 0.44 Maximum fuel length, in 144 144 120 120 168 168 144 144 Maximum rods /
element 180 204 180 204 264 264 235 176 Maximum cross
- section, (nom),in~sq 7.8 8.4 7.8 8.4 8.4 8.4 7.8 7.98 Maximum L1-235/
element, kgs 17.7 18.3 18.5 18.7 16.95 17,1 16.6 19.0 (144"L) (144"L) 19.8 20.0 (168"L) (168"L)
Maximum U-235 enrichment,w/o 4.0 3.65 4.0 3.65 3.65 3.70 4.0 3.85 (ii) Uranium dioxide as zircaloy clad unirradiated fuel elements contained within the Model No. RCC-4 packaging. Two (2) neutron absorber plates consisting of 0.19" thick carbon steel are required between fuel elements of the following specifications.
17 x 17 M
ZR Clad Pellet diameter, in.
0.308 - 0.322 Rod diameter, in.
0.360 - 0.374 Maximum fuel length, in.
168 Maximum rods / element 264 Maximum cross section, (nom),in.sq.
8.4 Maximum U-235/ element, kgs.
19.3 Maximum U-235 enrichment, w/o 3.55
Page 3 - Certificate No. 5450 - Revision No. 15 - Docket No. 71-5450 (iii) Uranium dioxide as zircaloy or stainless steel clad unirradiated fuel rods of the following specifications:
Type SST Clad Zr Clad
-Zr Clad Pelletdiameter(nom),in
,1.384 0.367 0.322 Roddiameter(nom),in U.422 0.422 0.374 Fuel length (max), in 144 144 1 68 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) and 5(b)(1)(ii):
i Two fuel elements.
(ii) For the contents described in 5(b)(1)(iii):
Two inner containers containing not more than 80 kilograms U-235.
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 or 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 assenbly shall be unsheathed or shall be enclosed in an unsealed, polyethylene 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.
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Page 4 - Certificate No. 5450 - Revision No. 15 - Docket No. 71-5450 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.
REFERENCES Westinghouse Electric Corporation application dated December 17, 1980.
Supplements dated:
January 21 and September 4, 1981; and March 8, 1982.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION
[
Charles E. MacDonald, Chiof Transportation Certification Branch Division of Fuel Cycle and Material Safety 0 02 Date:
e (Y
s 0
U.S. Nuclear Regulatory Commission i
Transportation Certification Branch Approval Record Model No. RCC-Series Docket No. 71-5450 By application dated March 8, 1982, Westinghouse Electric Corporation requested revised contents for the Model No. RCC-Series package to permit the shipment of a 17x17 PWR fuel assembly with the following characteristics and delimiting parameters:
17x17 Type ZR Clad Pellet diameter, in 0.322 Rod diameter, in 0.374 Maximum fuel length, in 168 Maximum rods / element 264 Maximum cross-section (nom),insq 8.4 Maximum U-235/ element, kgs 17.1 (144"L) 20.0 (168"L)
Maximum U-235 enrichment, w/o 3.70 The applicant performed a 3D-KEN 0 Monte Carlo (19 neutron group cross-section set) calculation for the subject fuel assembly in the Model No.
RCC-Series container under accident conditions with copper as the absorbing plate. The average k for 2 crushed containers (total of 4 assembliesascloseaspossible*Nthabsorberinplace)wascalculated to be 0.946,+0.0043.
The staff has checked the detailed modelling of the submitted calculation and concurs that the geometry and material are represented accurately for the accident condition postulated.
Additionally, number densities, thickness, and fissionable mass limits were verified using all the data supplied as input to the calculation.
Since the methodology used by the applicant has previously successfully calculated a list set of critical benchmark experiments and for the above noted reasons on the accurate KEN 0 calculation, the staff reconnends approval in using the copper absorber plates in the Model No. RCC-Series for the 17x17 fuel assembly.
(,'
Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS IS02 Date:
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