ML19338D898
| ML19338D898 | |
| Person / Time | |
|---|---|
| Site: | 07104986 |
| Issue date: | 09/02/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19338D895 | List: |
| References | |
| NUDOCS 8009240132 | |
| Download: ML19338D898 (6) | |
Text
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Form NRC-618 U.S. NUCLEAR REGULATORY COMMISSION
- 02 3) 3ep CERTIFICATE OF COMPLIANCE For Radioactive Materials Packages 1.(
- tificate Number 1.(b) Rev ion No.
1.(
a a d t fi ion No.
1.
) Pages No. 1.(e) otal No. Pages
- 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 5 belov.. 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.(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 povernment 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.la)
Prepared by (Name and address):
3.(b)
Title and identification of report or' application:
General Electric Company General electric Coinpany application dated P.O. Box 780 December 20, 1976, as supplemented.
Wilmington, NC 28401 b
~
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 sxcified in item 5 below.
- s. Description of Fackaging and Authorized Contents, Moce! Number. Fissile Class, Other Conditions, and
References:
(a) Packaging (1) Model 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 con-struction and a metal inner container separated by cushioning material.
The metal inner containet 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 a fiber-glass coated 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-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.
8809240 / 3,R
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Page 2 - Certificate No. 4986 - Revision N]. 8 - Docket No. 71-4986 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 886D364, Revision 2 or 3 112C3309, Revision 2 The RA-1 outer container is construr.ted in accordance with GE Orawing No. 718E688, Revision 2 or any of tne GE Drawings listed in Section (iv) below.
(ii) The RA-2 inner container is constructed in accordance with the following GE Drawing Nos.:
731E291, Revision 1 or 2 161F329, Revision 0 9210446, Revision 0 9210447, 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 128D5212, Revision 0 or 1 12805177, Revision ~0, 2, 3, or B 12805178, Revision 1 or 2 117C3979, Revision 2, 3, or 4 159C5411, Revision 2 159C5372, Revision A 159C5373, Revision A q v{
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Page'3'- Certificate No..4986 Revision'No. 8 - Docket No. 71-4986 S.
(a) Packaging (continued)
(3)(111). 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.
(iv) LThe RA-1, 2, or 3 outer containers may be constructed in accordance with the following GE Drawing 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 contain's materials which decompose at less than 1475 F.
(b) Contents (1) Type-and form of material (i) UO2. fuel assemblies with a maximum average U-235 enrichment 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)
U0 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) U0 fuel. assemblies with a maximum average U-235 enrichment of 2.7%
2 by weight.
Assembly rods are clad with a minimum 0.032 inch thickness of-zircaloy and a maximum fuel pellet outside diameter-of ~0.490 inch. -Each assembly, made up of a maximum 7 x 7 square array of fuel roos,'shall have a maximum fuel length of 174 inches with a maximum cross-sectional area of 25 square inches.
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Pdge!4 Certificate No. 4986 - Revision No. 8 - Docket No. 71-4986 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 fuel tross 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 weight.
2 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).
(vi) Pu0 -UO fuel rods with a maximum Pu0 concentration not exceeding 2
2 2
8.0% by weight in natural or depleted U0.
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 maxi' mum length of 174 inches.
The clad rods shall be bundled (contained) in the product containers dascribed 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 Pu0 concentration in natural or depleted uranium exceeds 4.0% by 2
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 Pu0 concentration and the maximum Pu-239 concentration in total 2
The Pu0 -UO 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 Total Pu Where Pu0 Concentration Does Not Exceed 2
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
.l.0 0.56 0.28 J
f.
_._..mm_
.Ab
- Page 5 - Certificate No. 4986 - Revision No. 8 - Docket No. 71-4986 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
6 w/o 7 w/o 8 w/o 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 (2) Maximum quantity of material per package (i) For the contents described in 5(b)(1)(i), 5(b)(1)(fi), 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 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):
0.9 m
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Page 6 - Certificate No. 4986 - Revision No. 8 - Docket No. 71-4986 6.
Each fuel assembly shall be unsheathed or shall be enclosed in an unsealed, polyethylenQ 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 cut 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 cubicacentimeter averaged over the 2
assembly.
7.
In lieu of the product container specified in 5(a)(4), except for UO fuel rods 2
with U-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 strappings at two or more locations) with a maximum cross sectional area of 20.0 square inches.
The total breaking strength of the strapping shall be 30 times the weight of the bound rods.
s.
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 971.12(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 R#O&pC Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety SEP 0 21980 Date:
.-