ML19329A030
| ML19329A030 | |
| Person / Time | |
|---|---|
| Site: | 07104986 |
| Issue date: | 07/21/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19326E251 | List: |
| References | |
| NUDOCS 8007280720 | |
| Download: ML19329A030 (6) | |
Text
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Ftrm NRC418 U.S. NUCLEAR. REGULATORY COMMISSION II CERTIFICATE OF COMPLIANCE to C R 71 For Radicactive Materials Packages 1.! I snificata Number 1.tb) Rev ion No.
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d fi n No.
1.
) Pages No. 1.(e) otal No. Pages
- 2. PREAMBLE 2.ta) This certificate is issued to satisfy Sections 173.39 a.173.394.173.39s, and 173.396 of the Department of Transportat".on Haasnsous Materials Regulations (49 CFR 170189 and 14 CFR 103) and Sections 146-19-10s and 146-19--100 of the Department of Transportatio.: Dangerous Cargoes Regulations (46 CFR 146-149), as amended.
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lib) The anckaging and contents descrioed in item 5 be6cw meets the safety standards set forth in Suboart C of"Inle 10. Code of
, Federal Regulations. Part 71.** Packaging of Radioac0ve Materials for Transport and Transoortation of Radioactive Material Under,
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l.* $ b.52. ~~:k.i '
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This certificat's does not relieve the consignor from complier.i;e with any'recuirement of the regulations of the U.S. Department of ~ ~
Transoortation or other apolicable regulatory agencies, including the government of any country through or into which the package -.
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will be transported...
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- 3. This certificate is issued'on the basis of a safety analysis reoort of the package design or application-
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' 3.(a)
Propered by yame and address):
3 tbl Title and identification of report or' application:
General Electric Company General Electric Comp &ny application dated P.O.. Box 780 December 20, 1975, as suppleniented.
Wilmington, NC 28401
/1"49bb 3.(c)
Docket No.
'4 CONDITIONS This cartificate is a-31itional upon the fulfilling of the requirements of Surpart D o' to CFR 71, as applicable, and the conditions sos.:fied in item 5 below.
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- 5. Description of Packaging and Authorized Contents. Model Numoer, Fissile Cass, Otner Conditions, ard
References:
(a) Packaging (1) Model Nos.:
RA-l', 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 con-struction 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 Model No. RA-1, and 179 inches long for the Model Nos.
RA-2, RA-3', and RA-J and is positioned within an all wood or i fiber-glass co'ated wood on aluminium outer container approximately 32 inches by 33 inches by 207 inches long.
An optional outer container for the Model No. 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 honey-comb and ethafoam, or equivalent.
Closure is, accomplished by bolts, latches, or equivalent. A pressure relief (breather) valve is pro-
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vided on the inner container, and is set for 0.5 psi differential.
The total weight of the packaging and contents is 2,800 pounds.
soonso72o 1
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Page 2 - Certificate No. 4986 - Revision No. 7 - Docket No. 71-4888 5.
(a) Packaging (continued)
(3) Drawings (i) The RA-1 inner container is constructed in accordance with the following GE Drawing Nos.:
718E684,~ Revision 2 148F938, Revision 2 8860364, Revision 2 or 3 112C3309, Revision 2 The RA-1 outer container is constructed in accordance with GE Drawing No. 718E688, Revision 2 or any of the GE Drawings listed in Section (iv) below.
(ii) The RA-2 inner container is constructed in accordance with the following '2s Drawing Nos.:
731E291, Revision 1 or 2 161F329, Revision 0 921D446, Revision 0 921DA47, Revision 0 The RA-2 outer container is constructed in accordance with any of the GE Drawing listed in Section (iv) below.
(iii) The RA-3 inner container of all welded construction is constructed in accordance with the following GE Drawing Nos.:
731E674, Revision 1, 2, 3, or 4 161F329, Revision 0, 2, or 3 9210446, Revision 0, 1, 2, 3, or 4 ll7C3979, Revision 0, 1, or 2 The RA-3 inner container of welded and riveted construction is constructed in accordance with the following GE Drawing Nos.:
731E674, Revision 5 or 6 12805211, Revision 1 or 2 12805212, Revision 0 or 1 12805177, Revision 0, 2, 3, or B 12805178, Revision 1 or 2 ll7C3979, Revision 2, 3, or 4 159C5411, Revision 2 159C5372, Revision A 159C5373, Revision A i
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Page 3 - Certificate No. 4986 - Revision No. 7 - Docket No. 71-4888 5.
(a) Packaging (continued)
(3)(iii) Drawings (continued)
The RA-3 outer container is constructed in accordance with GE Drawing No. 829E209, Revision 0, 3, 4, or any of the GE Drawing Nos. listed in Section (iv) below.
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(iv) The RA-1, 2, or 3 outer containers may be constructed in accordance with the following GE Drawing Nos.:
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761E529, Revision 2
-f 731E283, Revisien 0, 1, 2, 3, or 4
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(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 (1) Type and form of material (i) UO fuel assemblies with a maximum average U-235 enrichment of 3.2%
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 enrichment of 3.2%
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-sectional area of 25 square inches.
(iii) UO fuel assemblies with a maximum average U-235 enrichment of 2.7%
2 by weight. Assembly rods are clad with a minimum 0.032 i'nch 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.
Page 4 - Certificate No. 4986 - Revision No. 7 - Docket No. 71-4888 5.
(b) Contents (continued)
(1) (vi) Type and form of material (continued)
(iv) U0 fuel rods with a maximum U-235 enrichment of 5.0% by weight.
2 Rods are clad with zircaloy, incaloy, inconel, or stainless steel such that the ratio of clad to fJel Cross sectional area be at least 0.26, and a maximum fuel pellet outside diameter of 0.508 inch.
Each rod shall have a maxinum length of 174 inches. The clad rods shall be bundled (contained) in the product container described in 5(a)(4).
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fuel rods with a maximum U-235 enrichment of 6.5% by weight.
(v) UO2 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 langth of 174. inches.
The clad rods shall be bundled (contained) in the product container described in 5(a)(4).
fuel rods with a maximum Pu02 concentration not exceeding (vi) Pu0 -UO2 2
8.0% by weight in natural or depleted UO.
Rods are clad with a 2
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 exceed unity (1) when the Pu02 in natural or depleted uranium is 4.0% by weight or less. Where the Pu02 concentration in natural or depleted uranium 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 Pu02 concentration and the maximum Pu-239 concentration in total plutonium. The Pu0 -U0 fuel rods shall be unpressurized (atm pressure).
2 2
Maximum w/o Pu-239 Maximum Ratio of w/o Pu-241 to w/o Pu-240 Concentration Does Not Exceed 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
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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
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Page 5 - Certificate No. 4986 - Revision No. 7 - Docket No. Ti-4888 5.
(b) Contents (continued)
(1) (vi) Type and form of material (continued)
Maximum w/o Pu-239 Maximum Ratio of w/o Pu-241 to w/o Pu-240 Total Pu Where Pu0 Concentration Does Not Exceed 2
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6 w/o 7 w/o 8 w/o
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69 1.0 0.54 0.26
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70 --
1.0 0.54 0.26 71 :-
0.88 0.52 0.24 72 0.88 0.50 0.22
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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 (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(bT(1)(v), and 5(b)(1)(vi):
Two (2) fuel bundles.
(A bundle is defined as an arrangement of rods which are either c d ained within 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 5(b)(1)(i),
to be shown label 5(b)(1)(ii), and on 5(b)(1)(iii); and contained for Class II within the packaging described in 5(a)(3)(v) and 5(a)(3)(vi):
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r Page 6 - Certificate No. 4986 - Revision No. 7 - Docket No. 71-4888 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 f:lded 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 averaged over the 2
assembly.
7.
In lieu of the product container specified in 5(a)(4), except for UO2 fuel rods with (J-235 enrichment greater than 3.2% and for rods described in 5(b)(1)(v) and 5(b)(1)(vi), the clad rods shall be bundled (bound with steel strappi..gs at two or more locations with a maximum cross strapping shall be 30 times the weight of the bound 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 wa.ll, 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 $71.12(b).
10.
Expiration date:
January 31, 1981.
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 Charles t.
acDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety Date:
M 21 E
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