ML19276G215
| ML19276G215 | |
| Person / Time | |
|---|---|
| Site: | 07104986 |
| Issue date: | 04/26/1979 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19276G213 | List: |
| References | |
| NUDOCS 7905240020 | |
| Download: ML19276G215 (6) | |
Text
.
Form NRC-618 U.S. NUCLEAR REGULATORY COMMISSICN M 2-73)
CERTIFICATE OF COMPT.!ANCE 10 CFR 71 For Radioactive Materials Pacxages io o.
1.(d ) ages No. 1.(e) Totg No. Page-1.f a) f cate Number 1.(b) Revision No.
1.lc) P q tg
- 2. PREAMBLE 2.(a)
This certificate is issued to satisfy Sections 173.333a,173.394,173.395. and 173.336 of the Ceoartment of Transoortation Hazardou Materials Regulations (49 CFR 170189 and 14 CFR 103) and Sections 146-19-wa and 146-19-100 of the Copartment of Transportation Congerous Cargoes Regulations (46 CFR 146-149). as amended.
2.(b)
The packaging and contents described in item 5 below, meets the safety standards set forth in Subpart C of Title 10. Code of Feceral Regulat:ons. Part 71, " Packaging of Radioactive Materials for Transpstt and Transoortation of Radicactive Material Unaer Certain Conditions."
2.(c)
This certificate does not relieve the consignor from compliance with any recuirement of the regulations of the U.S. Ceoartment of Transportation or other applicable regulatory agencies, including the government of any country througn or into wnich the package will be transcorted.
- 3. This certificate is issued on the basis of a safety analysis report of the package design or acolicatiord-3.la)
Prepared by (Name and address):
3.(b)
Tide a identificatto of recort or acc General Electric Company General Tlectric tampany appI'catiollon dated 1ca P.O. Box 780 December 20, 1976, as supplemented.
Wilmington, N.C.
28401 3.re) oocket No.
71-4986 4 CONOtTIONS This certificate is conditional upon the fulfilling of the requirements of Suboart O of 10 CFR 71, as applicable, and the conditions specified in item S below.
- 5. Description of Sckaging and Authorized Contents, Model Number, Fissile C! ass, Cther Conditions, ard
References:
(a) Packaging (1) Models Nos.:
RA-1, RA-2, RA-3, and RA-J (2) Description A fuel assembly and fuel rod shipping container. Packagings are right rectangular boxes consisting of an outer container of wooden construction and a metal inner container separated by cushioning material.
The metal inner container is 11-1/2 inches by 18 inches by 174 inches long for the Mcdel RA-1, and 179 inches long for the RA-2, RA-3, and RA-J and ir positioned within an all wood or a fiberglass coated wood on aluminium outer container approximately 32 inches by 33 inches by 207 inches long.
An optional outer container for the RA-3 is of all wood construction, and is approximately 30 inches by 31 inches by 207 inches long.
Cushioning is provided between the inner and outer containers by phenolic impregnated honeycomb and ethafoam, or equivalent.
Closure is accomplished by bolts, latches, or equivalent. A pressure relief (breather) valve is provided on the inner container, and is set for 0.5 psi differ-ential. The total weight of the packaging and contents is 2800 pounds.
79052400 0 4.
Page 3 - Certificate No. 4986 - Revision No. 4 - Docket No. 71-4986 5.
(a) Packaging (continued)
(3)(iii) Drawings (continued) thera-3outercontaineriscon$tructedinaccordance with GE Drawing No. 829E209, Revision 0, 3, 4, or any of the GE Drawings Nos. listed in Section (iv) below.
(iv) The RA-1, 2, or 3 outer containers may be constructed in accor' dance with the following GE Drawings Nos.:
761E529, Revision 2 731E283, Revision 0, 1, 2, 3, or 4 (v) The RA-J inner container is contructed in accordance with GE Drawing No. RAJI-1, Revision 0.
(vi) The RA-J outer container is constructed in accordance with GE Drawing No. RAJ0-1, Revision 0.
(4) Product Container Five-inch, Schedule 40, Type 304 (or equivalent) stainless steel, pipe fitted with screw type or flange closure.
Container shall be vented in the event it contains materials which decompose at less than 1475"F.
(b) Contents
'l ) Type and form of material (1) UO fuel assemblies with a maximum average U-235 enrich-2 ment of 3.2% by weight. Assembly rods are clad with a minimum 0.032 inch thickness of zircaloy and a maximum fuel pellet outside diameter of 0.410 inch.
Each assembly, made up of a maximum 8 x 8 square array of fuel rods, shall have a maximum fuel length of 174 inches with a maximum fuel cross-sectional area of 25 square inches.
(ii) UO fuel assemblies with a maximum average U-235 enrich-2 ment of 3.2% by weight.
Assembly rods are clad-with a minimum 0.034 inch thickness of zircaloy and a maximum fuel pellet outside diameter of 0.416 inch.
Each assembly, made up of a maximum 8 x 8 square array of fuel rods, shall have a maximum fuel length of 174 inches with a maximum cross-sect".onal area of 25 square inches.
Page 4 - Certificate No. 4986 - Revision No. 4 - Docket No. 71-4986 5.
(b) Contents (continued)
(1) Type and form of material (continued)
(iii) 00 fuel assemblies with a maxim)um average U-235 enrich-2 ment of 2.7% by weight. Assembly rods are clad with a minimum 0.032 inch thickness of zircaloy and a maximum fuel pellet outside diameter of 0.490 inch.
Each assembly, made up of a maximum 7 x 7 square array of fuel rods, shall have a maximum fuel length of 174 inches with a maximum cross-sectional area of 25 square inches.
(iv) U0 fuel rods with a maximum U-235 enrichment of 5.0% by 2
weight.
Rods are clad with zircaloy, incaloy, inconel, or stainless steel such that the ratio of clad to fuel cross sectional area be at least 0.26, and a maximum fuel pellet outside diameter of 0.508 inch.
Each rod shall have a maximum length of 174 inches. The clad rods shall be bundled (contained) in the product container described in 5(a)(4).
(v) UO fuel rods with a maximum U-235 enrichment of 6.5% by 2
weight.
Rods are clad with zircaloy, incaloy, inconel or stainless steel such that the ratio of clad to fuel cross sectional area be at least 0.26, and a maximum fuel pellet outside diameter of 0.508 inch.
Each rod shall have a maximum length of 174 inches. The clad rods shall be bandled (contained) in the product container described in 5(a)(4).
(vi) Pu0 -UO fuel rods with a maximum Pu02 concentration not 2
2 exceeding 8.0% by weight in natural or depleted UO -
2 Rods are clad with a minimum 0.030-inch thickness of zircaloy and a maximum fuel diameter of 0.508 inch.
Each rod shall have a maximum length of 174 inches. The clad rods shall be bundled (contained) in the product containers described in 5(a)(4). Of the total plutonium, the maximum mass ratio of Pu-241 to Pu-240 shall not in natural or depleted exceed unity (1) when the Pu02 uranium is 4.0% by weight or less. Where the Pu02 concentration in natural or depleted t-anium exceeds 4.0%
by weight, the maximum mass ratios of Pu-241 to Pu-240 shall not exceed the values specified in the table provided as determined from the PuC2 concentration and the maximum Pu-239 concentration in total plutonium.
Page 5 - Certificate No. 4986 - Revision No. 4 - Docket No. 71-4986 5.
(b) Contents (continued)
(1)
(vi) Type and form of material Maximum w/o Pu-239 Maximum Ratio of w/o Pu-241 to w/o Pu-240 Concentration Does Not Exceed in Total Pu Where Pu02 6 w/o 7 w/o 8 w/o 50 1.0 0.68 0.42 52 1.0 0.68 0.42 55 1.0 0.68 0.38 57 1.0 0.66 0.36 59 1.0 0.66 0.36 60 1.0 0.64 0.36 61 1.0 0.64 0.34 62 1.0 0.62 0.34 63 1.0 0.62 0.32 64 1.0 0.60 0.32 65 1.0 0.60 0.30 66 1.0 0.58 0.30 67 1.0 0.58 0.28 68 1.0 0.56 0.28 69 1.0 0.54 0.26 70 1.0 0.54 0.26 71 0.88 0.52 0.24 72 0.88 0.50 0.22 73 0.88 0.48 0.22 74 0.88 0.46 0.20 75 0.88 0.44 0.20 76 0.88 0.42 0.18 77 0.88 0.40 0.16 78 0.88 0.38 0.14 79 0.88 0.36 0.12 80 0.88 0.34 0.10 81 0.76 0.32 0.08 82 0.76 0.28 0.06 83 0.76 0.26 0.04 84 0.76 0.22 0.02 85 0.76 0.20 0.00
Page 6 - Certificate No. 4986 - Revision No. 4 - Docket 'fo. 71-4986 5.
(b) Contents (continued)
(2) Maximum quantity of material per package (i) For the contents described in 5'(b)(1)(i), 5(b)(1)(ii),
and 5(b)(1)(iii):
Two (2) fuel assemblies.
(ii) For the contents described in 5(b)(1)(iv),
5(b)(1)(v), and 5(b)(1)(vi):
Two (2) fuel bundles.
(A bundle is defined as an arrangement of rods which are either contained witnin a product container or strapped together.)
(c) Fissile Class I and II (1) Class I For the contents specified in 5(b)(1); and contained within the packaging described in 5(a)(3)(i),5(a)(3)(ii),
5(a)(3)(iii), and 5(a)(3)(iv).
(2) Minimum transport For the contents specified in index to be shown 5(b)(1)(i),5(b)(1)(ii),and on label for Class II 5(b)(1)(iii); and contained within the packaging described in 5(a)(3)(v) and 5(a)(3)(vi):
0.9 6.
Each fuel assembly 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.
Polyethylene shipping shims may be inserted between rods within the fuel assemblies up to a maximum of 0.20 g H 0 equivalent per cubic centimeter 2
averaged over the assembly.
7.
In lieu of the product container specified in 5(a)(4), except for UO2 fuel rods with U-235 enrichment greater than 3.2% and for rods described in 5(b)(1)(v) and 5(b)(1)(vi), the clad rod shall be bundled (bound with steel strappings at two or more locations with a maximum cross
Page 7 - Certificate No. 4986 - Revision No. 4 - Docket No. 71-4986 7.
(Continued) sectional area of 20.0 square inches. The total breaking strength of the strapping shall be 30 times the weight of the boDnd rods.
8.
The maximum spacing between adjacent rods within the bundle shall be 0.012 inch. The spacing shall be maintained by the product container wall, metal strappings or peripheral metallic dunnage with a melting point greater than 1475 F within the bundle.
9.
The package authorized by this certificate is hereby authorized for use under the general license provisions of 10 CFR 5 71.12(b).
10.
Expiration date: March 31,1980.
REFERENCES General Electric Company application dated December 20, 1976.
Supplements dated: March 15,1978; and January 5,1979.
Exxon Nuclear Company letter dated May 30, 1978.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION t
(W Charles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle and Material Safety APR 2 61979 Date: