ML19260E089
| ML19260E089 | |
| Person / Time | |
|---|---|
| Site: | 07109069 |
| Issue date: | 02/04/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19260E087 | List: |
| References | |
| NUDOCS 8002130329 | |
| Download: ML19260E089 (4) | |
Text
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Form NRC418 U.S. NUCLE AR REGui.ATORY COMMISSION CERTIFICATE OF COMPLIANCE 10 CFR 71 For Radioactive Materials Packages 1.fal Certifica mber 1.(b) Re sion No.
1.lc) d f ca n No.
1.(d) P es No. 1.(e) T tal No. Pages
- 2. PREAMB LE 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 170189 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.lb)
The packaging and contents described in item 5 below, meets the safety standards set forth in Subpart C of Title 10. Code of Federal Regulations, Part 71, ** Packaging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certain Conditions.**
2.fc)
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 applicatiort-3.(a)
Prepared by (Name and address):
3.(b)
Title and identification of report or application:
Westinghouse Electric Corporation Westinghouse Electric Corportation application Box 356 dated April 27, 1976, as supplemented.
Pittsburgh, Pennsylvania 15230 3.(c)
Docket No.
7] _qqp;q 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 stem 5 below.
- 5. Description of Packaging and Authorized Contents. Model Number. Fissile Class. Other Conditions, and
References:
(a) Packaging (1) Model No.: M0-1 (2) Description Steel overpack consisting of a 12 gauge outer shell (45" x 47" x 206")
and a 10 gauge inner shell (max. 37" x 37" x 186"). The volume between the shells is filled with a shock-and-thermal-insulating material consisting of rigid polyurethane foam. The upper and lower sections cf the overpack are secured by 12 ratchet binders and 12 high strength 6/8" latch pins. The fuel assemblies are held in place within the overpack by a strongback and adjustable clamping assembly (shock mounted).
Neutron absorber plates are located between the fuel assemblies. The package is equipped with lifting, tiedown and pressure relief devices.
Gross weignt of the package is 8600 pounds.
(3) Drawing The packaging is constructed in accordance with Westinghouse Electric Corportation Di awing No.1581F50, sheets 1 and 2, Rev.1.
Fuel rod container is constructed in accordance with Wesinghouse Electric Corporation Drawing No. C5650D55.
b
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Page 2 - Certificate No. 9069 - Revision No. 3 - Docket No. 71-9069 5.
(b) Contents (1) Type and form and maximum quantity of material per package.
PWR fuel assembly with the following (i) Unirradiated UO2 - Pu02 maximum active dimensions and maximum compositions:
Cladding material Zr Envelope, in 7.784 x 7.784 Enrichment pug 2 in Pu02 plus UO, w/o
- (a) 2 Pu0 fissile in pug, w/o
- (b) 2 2
UO fissile in UO, w/o 0.71 2
2 Fissile, kg 16.6 Fuel length, in 144 Decay heat load, watts /pkg 400
- For three plutonium isotopic cases:
Case 1, the Pu02 enrichment (a) is 6.0 w/o; fissile Pu0 (b) is 71 w/o.
2 Case 2, the Pu02 enrichment (a) is 4.4 w/o; fissile Pu0 (b) is 81 w/o.
2 Case 3, the Pu02 enrichment (a) is 3.03 w/o; fissile Pu0 (b) is 85 w/o.
2 (ii) Mixed Pu0 in natural U02 as pressed sintered pellets 2
fully clad in leak-tight zircaloy of minimum 0.024" thick-ness as fuel rods of the following specifications:
Type Pellet diameter (Nom), in 0.365 Rod diameter (Nom), in 0.422 Fuel length (Nom), in 120 to 144 Pu0 in Pu02 plus UO, w/o 6.0 2
2 Pu0 fissile in Pu0, w/o 85 2
2 UO fissile in UO, w/o 0.71 2
2 (2) Maximum quantity of material per package.
(i) For the contents described in 5(b)(1)(i)
Two fuel assemblies.
(ii) For the content described in 5(b)(1)(ii)
Not more than 94 kilograms Pu contained within the fuel rod container described in 5(a)(3).
Page 3 - Certificate No. 9069 - Revision No. 3 - Docket No. 71-9069 (c) Fissile Class II and III (1) Minimum transport index to be shown on label for Class II 1.6 (2) Maximum number of packages per shipment for Class III 62 6.
Two (2) neutron absorber plates consisting of 0.19" thick, full length, stainless steel containing 1.3 percent minimum boron or 0.19" thick 0FHC copper shall be installed between the active area of the fuel assemblies.
7.
Fuel rods shall be closely packed in the fuel rod container on no more than an equivalent metal-to-metcl 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.
8.
Each fuel assembly shall be unsheathed or shall be enclosed in an unsealed, poly-ethylene sheath whica 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 folder back to assure that the entire cross section of the lower end of the assembly is unobstructed. When the 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 slip 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 percent 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.
9.
The package authorized by this certificate is hereby approve-for use under the general license provisions of Paragraph 71.12(b) of 10 CFR Port 71.
10.
Expiration date: October 31, f981.
Page 4 - Certificate No. 9069 - Revision No. 3 Docket No. 71-9069 REFERENCES Westinghouse Electric Corporation application dated April 27, 1976.
Nuclear Packaging, Inc. supplements dated: March 18, August 13, and September 21, 1976.
. Westinghouse Electric Corporation supplements dated: February 11, and April 11, 1977; and January 9 and January 11, 1980.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION fW Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety Date:
G
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