ML19320C204
| ML19320C204 | |
| Person / Time | |
|---|---|
| Site: | 07104986 |
| Issue date: | 07/07/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19320C201 | List: |
| References | |
| NUDOCS 8007160412 | |
| Download: ML19320C204 (6) | |
Text
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. U.S. NUCLEAR REGULA. TORY CoMMIS$loN u2 31 CERTIFICATE OF COMPLIANCE 3o g q 7, For Radioactive Materials Packages 1.(2) Certificate Number 1.lb) Revision No.
1.(c) Pack ge Identification No.
1.(d) Pages No. 1.le) Total No. Pages 4996 6
USA /4986/3( TF 1
6
- 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 Transoortation Hazardous Materiais 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 Regutetions (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
, Federal Regulations. Part 71," Packaging of Radioactive Materiais for Transport and Transportet%n of Radioactive Material Under Certain Conditions.**
2.(c)
This certificate does not relieve the consi;nor from compliar:ce with any requirement of the regulations of the U.S. Department of Transoortation 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 s"ety analysis report of the package design or applicatiost-3.la)
Prepared by (Name and address):
3.fb)
Title and identification of report or' application:
Genert.1 Electric Company General Electric Company application dated P.O. Box 7s0 December 20, 1976, as supplemented.
Wilmington, NC 28401 3.(c) oocket No.
7] 4ggg 4 CCNDITloNS This certificate is conditional upon the fulfilhng 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 Contr9ts, Model Numoer, Fissile Class. other Conditions, and
References:
(a) Packaging s
(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 can-
'struction and a metal inner container separated by cushioning material.
1 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 a fiber-glass coateJ wood on aluminium outer container approximately 32 inches by 33 inches-by 207 inches long.
An optional oute'r container for the Model No. RA-3 is of all wood construction,;ind is approximately 30 inches by.31 inches by 207 inches long. CusW iing is provided between the inner and outer containers by ph< aic impr.egnated honey-comb and ethafoam, or equivalent.
Closure '. accomplished by bolts, latches, or equivalent.
A pressure relief u reather) 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.
8007160 L \\*'
O
.s
, ~
Page 2 - Certificate No. 4986 - Revision No. 6 - Docket No. 71-4888 5.
(a) Packaging (continued)
(3) Crawings (i) The RA-1 inr.er container is constructed in accordance with the following GE Drawing Nos.:
71CE684, Revision 2 148F938, Revision 2 8860364, Revision 2 or 3 ll2C3309, 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 a.ccordance'with the following GE Drawing Nos.:
731E291, Revision 1 or 2 161F329, Revision 0 9210446, Revision 0 921D447, Revision O' The RA-2 outer container is constructed in accordance with ar.y of the GE Dr, wing listed in Section (iv) below.
(iii) The RA-3 inner container of all welded construction is constructed i.in accordance with the following GE Drawing Nos.:
73iE674, Revision 1, 2, 3, or 4 161F329, Revision 0, 2, or 3 921D446,_ Revision 0, 1, 2, 3, or 4 ll7C3979, Rrrision 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
~4 s
2 e
v-Page 3 - Certificate No. 4986 - Revision No. 6 - 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.
(iv) The 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 contrected in accordance with GE Drawing No. RAJI-1, Revision O.
(vi) The RA-J outer container is constructed in a'ccordance 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) Typ ( and form of material (i) UO fuel assemblies with a aaximum average U-235 enricnment of 3.2%
2 by weight.
Assembly rods are clad with a minimum 0.032 inch thickness of zircaloy and a maximum fuci pellet outside diameter of 0.410 inch.
Each assembly, mace 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 assemo;ies with a maximum average U-235 enrichment of 3.2%
2 by weight.
Assembly rods are clad with e minimum 0.034 inch thickness of zircaloy and a maximum fuel pellet outside diameter of 0.416 inch.
Each asser.bly, 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 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.
e-P' age'4 - Certificate No. 4986 - Revision No. 6 - 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 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 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 i.qch.
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 Pu02 concentration not exceeding 2
2 8.0% by weight io natural or depleted U0.
Rods are clad with a 2
minimum 0.030-i.1ch 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
'sPu02 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 -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 1.0 0.56 0.28
~_
e Page 5 - Certificate No. 4986 - Revision No. 6 - Docket No. 71-4888 5.
(b) Contents (continued)
(1)
(vi) Type and form of material (continued)
Maxin.cm 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_y/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)(ii), and 5(b)(1)(iii):
Two (2) fuel assemblies.
(ii) For the contents describr.d 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 Cisss I and II (1) Class I For the contents soecified 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 S(b)(1)(i),
to be shown label 5(b)(1)(ii), and o' 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
.,9 a
Page 6 - Certificate No. 4986 - Revision No. 6 - 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 folded or taped in any manner that would prevent the flow of liquids into or out of the sheathed fuel assembly.
Polyethylene shipping shins may be inserted between rods within the fuel assemblies up to a maximum of 0.20 g H O equivalent per cubic centimeter 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 strapping shall be 30 times the weight of the bound rods.
8.
The maximum spacing between adjacent rods withir 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 571.12(b).
10.
Expiration date:
October 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
.S.
NUCLEAR REGULATORY COMMISSION W~
QCharlesE.Maconald, Chief 4
J Transportation Certification Branch Division of Fuel Cycle and Material Safety
~ Date:
Jul. 0 7 1980 1
,