ML19209A680
| ML19209A680 | |
| Person / Time | |
|---|---|
| Site: | 07109853 |
| Issue date: | 09/01/1979 |
| From: | Jonathan Evans, Mouring R, Shipley W OAK RIDGE NATIONAL LABORATORY |
| To: | |
| Shared Package | |
| ML19209A674 | List: |
| References | |
| 14101, ORNL-ENG-TM-15, NUDOCS 7910050181 | |
| Download: ML19209A680 (75) | |
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en Printed in the United States of America Available from National Technical Information Service f
U.S Department of Commerce j
5285 Port Royal Road, Springfield, Virginia 22161 i
P rice: Printed Copy $6.00, Microfiche $3 00 This report was prepared as an account of work sponsored by an agency of the United States Government Neither the United States Gov ernment nor any agency thereof. nor any cf their employees, contractors. subcontractors, or their employees, makes any warranty, express or imphed, nor assumes any legal 1: ability or responsitahty for any
- rd party's use or the results of such use of any informat:on, apparatus, product or focess disclosed in this report, nor represents that i's use by such third party would not irsfnnge pr:vately owned nghts D
1 1110 002
ORNL/ENG/TM-15 Dist. Category UC-71 Contract No. W-7405-eng-26 ORNL Engineering SAFETY ANALYSIS REPORT FOR PACKAGING:
THE UNIRRADIATED FUEL SHIPPING CONTi.INER
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J. H. Evans W. D. Shipley R. W. Mouring Date Published - September 1979 OAK RIDGE NATIONAL LABORATORY Oak Ridge, Tennessee 37830 operated by UNION CARBIDE CORPORATION for the DEPARTME NT OF ENERGY
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1110 003
CONTENTS Page ABSTRACT I
1.
GENERAL INFORMATION I
1.1 Introduction I
1.2 Package Description.
2 1.2.1 Container description 2
1.2.2 Operational features.
5 1.2.3 Contents 5
2.
STRUCTURAL EVALUATION 6
2.1 Mechanical Properties of Materials 6
2.2 General Standards for All Packages 6
2.2.1 Closure 6
2.2.2 Container lifting device 7
2.2.3 Lid lifting device.
7 2.2.4 Tie-down devices.
8 2.3 Standards for Type B and Large-Quantity Packaging.
3 2.3.1 Load resistance 8
2.3.2 External pressure 10 2.4 Compliance with Standards for Normal Conditions of Transport 10 2.4.1 Heat 11 2.4.2 Cold 12 2.4.3 Pressure.
12 2.4.4 Vibration 12 2.4.5 Water spray 12 2.4.6 Free drop 13 2.4.7 Compression 13 2.4.8 Penetration 13 2.5 Compliance with Standards for hypothetical Accident Conditions.
14 2.5.1 Free drop 14 2.5.2 Puncture.
15 2.5.3 Water immersion 16 3.
THERMAL EVALUATION.
16 3.1 Normal Conditions of Transport 16 3.2 Thermal Accident 18 4.
CONTAINMENT 18 5.
SHIELDING 19 6.
CRITICALITY 19 111
Page 7.
QUALITY ASSURANCE 19 7.1 Fabrication, Inspection, and Acceptance Tests.
19
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7.2 Routine Operating and Inspection Procedures.
20 7.3 Periodic Maintenance and Inspections 20 7.4 Records.
20 REFERENCES 21 Appendix A - FABRICATION DRAWINGS AND DATA SHEETS.
A-1 Appendix B - FUEL ELEMENT DRAWINGS B-1 Appendix C - ROUTINE PACKAGING AND INSPECTION PROCEDURES C-1 Appendix D - PENETRATION TESTS D-1 Appendix E - APPROVAL DOCUMENTS.
E-1 i110 005 iv
LIST OF TABLES Table Page 1.1.
Design summary of t,airradiated fuel containers 4
2.1.
Mechanical properties of container materials 7
A e
4 1110 006 v
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LIST OF FIGURES s
Figure Page 1.1 The unirradiated fuel element shipping container.
3 2.1 Container as a simple beam 9
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1110 007 "i
SAFETY ANALYSIS REPORT FOR PACKAGING:
THE UNIRRADIATED FUEL SHIPPING CONTAINER J. H. Evans W. D. Shipley R. W. Mouring ABSTRACT The Unirradiated Fuel Shipping Container was designed at the Oak Ridge National Laboratory for the transport of unirradiated fuel elements. The container was evaluated analytically to determine its compliance with the applicable regulations governing containers in which radioactive and fissile materials are transported, and the evaluation is the subject of this report. Computational and test pro-cedures were used to determine the structural integrity and thermal behavior of the container relative to the general ste.ndards for normal conditions of transport and the standards for hypothetical accident conditions. Results of the evalua-tion demonstrate that the container is in compliance with the applicable regulations.
1.
GENERAL INFORMATION 1.1 Introduction The Unirradiated Fuel Shipping Container was developed at the Oak Ridge National Laboratory in 1978; three containers of differing dimen-sions were designed.
fhe containers will be fabricated, inspected, and filled with henolic foam in accordance with the drawings in Appendix A.
The primary use of the containers is to ship fuel elements.
The containers provide impact and thermal resistance for the fuel elements during transport for both normal and accident conditions by rail, highway, - c, and water modes. The contents for which the design was evaluatc;
.re outlined in Sect. 1.2.3.
They comply with Department of Energy regulations contained in the Code of Federal Regulations, Title 10, Part 71;l in the AEC Manual Chapter 0529;2 and in all Immediate 1110 008 t
2 Action Directives in effect as of this report date.
The containers also comply with U.S. Department of Transportation regulations published in the Code of Federal Regulations, Title 49, Part 173. 3 Calculations, engineering logic, test results, and documents demonstrating compliance are presented in the following sections of this report.
Copies of the approval documents are reproduced in Appendix E.
1.2 Package Description 1.2.1 Containce descr' -ion The featurcs of the package are illustrated in Fig. 1.1 and listed in Table 1.1; fabrication drawings are in Appendix A.
The container consists of a basket and a cylindrical housing.
Each container has an outside dimension (OD) of 24-1/2 in., except for the National Bureau of Standards container, which has a 26 in. OD.
The basket for the Oak Ridge Research Reactor (ORR), Bulk Shielding Reactor (BSR), and Pool Critical Assembly (PCA) fuel elements is 39-7/8 in., with the overall length of the container being 56-5/8 in.
The basket for the Brc ihaven National Laboratory (BNL) fuel elements is 58-3/4 in., with the overall length of the container being 75-1/2 in.
The basket for the National Bureau of Standards (NBS) fuel elements is 70-5/16 in., with the overall length of the container being 87-1/8 in.
The area betwear the basket and outer housing is filled with phenolic foam. The phenolic foam provides some structural support and is an ef fective thc. mal insulator. Vent holes 3/16 in. in diameter are located in the sides and bottom of the external housing for release of gas pressure that may be generated by decom-position of the phenolic in a fire. After the container is filled with foam, these vent holes are sealed against the weather by two coats of an epoxy paint that does not react with the phenolic foam.
The epoxy seals are designed to vent in a fire, since the epoxy pai.it will decompose at temperatures well below 1000*F.
This ability has been demonstrated by Mallet and Newlon on very similar epoxy seals.4 The closure of the basket is afforded by 16-in.-0D, 1/8-in.-thick flanges. Eight 3/8-in. hex-head bolts secure the closure. At the base of the vessel, the inner and outer housings are separated by a cross 1110 009
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The unirradiated fuel element shipping container.
1110 010
Table 1.1.
Design summary of uairradiated fuel containers Inside Maximum Minimum Maximum fuel UCC-ND cavity Element Inside cavity width w.dth U235 -
Container Container Cross weight Container drawing length length cross section element element 7 elements length body OD Base Lid OD loaded type number (in.)
(in.)
(in.)
(in.)
(in.)
(g)
(in.)
(in.)
(in.)
(in.)
(Ib)
ORR X3E-(Oak Ridge 10191-38-3/4 38-3/8 4 x 4 3.397 3.033 370 56-5/8 24-1/2 29 x 29 29 580 National
-002 6
.005
+ 001
+
Laboratory)
-D03 BSR & PCA X3E-g3 (Dak Ridge 10191-34-3/4 38-3/8 4x 4 3.397 2.9#6 370 56 'is 24-1/2 29 x 29 29 580 Estional
-002 6
+ 005
+ 0C9 laboratory)
-003
.010 HFBR X3E-(Brookhaven 10191-57-1/2 57-1/4 4x 4 3.218 2.878 370 75-1/2 24-1/2 29 x 29 29 700 National
-010 &
+.000
+.000 Laboratory)
-011
.005
.005 NBSRR X3E-National 10191-69-3/16 68-51/64 4-1/2 3-13/16 3-1/8 370 87-1/8 26 30-1/2 30-1/2 850 Bureau of
-100 &
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Standards)
-101 4-1/2 30-1/2 emos.*
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5 structure of lumber 5-1/2 in, deep. A foam-filled plug 5-3/4 in. high fits on top of the inner housing and is secured by 6-5/8-in. hex-head bolts with lock washers and nuta.
The materials of construction, as specified on UCC-ND data sheets DS-XEE 1u191-1,2,3, and Rev. 1 are stainless steels and aluminum to AS"" specifications.
The inner container is a basket that is permanently fixed in the top of the outer container by four 2 x 1/2 x =5 in.-long phenolic spacers bolted to the basket and c itainer by eight 1/4-in.-diam bolts with lock washers and nuts.
The bottom of the basket is secured by four threaded rods welded to the bottom of the coatainer. The basket has a capacity of seven fuel elements. Three different containers have been constructed to ship different size fuel elements.
The only difference in the con-tainers will be the overall length, basket length, and basket cross section.
The weights of the baakets are 119, 92, and 66 lb.
The net weights of the packages (cylinder plus basket plus forklifting device) are 500, T, and 450 lb.
Therefore, all calculations will be based on a gross weight of approximately E50 lb.
Compliance or this heavier package with design specifications demonstrates that the lighter packages would be well within design limits.
1.2.2 Operational features The container is specifically designed to house seven fuel elements.
Tnree different containers are available to transport ORNL, NBS, or BNL fuel elements.
1.2.3 Contents The containers are designed to transport seven fresh or unirradiated fuel elements from the fabricator to the applicable reactor site.
These reactors are (1) the ORR, the BSR, and the PCA, located at Oak Ridge, Tennessee; (2) the National Bureau of Standards Research Reactor (NBSRR),
located near Washington, D.C.; and (3) the BNL High-Flux Beam Reactor
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(HFBR), located at Upton, N.Y.
The elements are of similar construction.
0 012
6 They are curved plate with U 0 -Al cores clad with type 6061 aluminum.
3 8 The m: nimum 235U enrichment is 93%. Other characteristics of the elements are listed in Table 1.1, and drawings of the elements are in Appendix B.
2.
STRUCTURAL EVALUATION The package complies with the structural requirements of the regulations.1 The calculational results and engineering logic presented in the following subsections demonstrate enmpliance with these performance criteria. Additional uvaluations considered pertinent to the safety and operability of the package are included. The effects of both normal and specified accident conditions on the structural integrity of the package are considered.
2.1 Mechanical Properties of Materia'.c The values shown in Table 2.1 are conservative, but are typical of container materials.5-7 The static properties shown provide a reasonable approximation of dynamic conditions if care is taken to ensure that the use of static values results in a conservative evaluation.
For most structural materials the static properties are much less than the dynamic properties. Numerous reports substantiate this, including ref. 8.
2.2 General Standards for All Packages The general standards for all packaging cover the chemical and galvanic reactions of,the materials of the package and closure of the package. The containers will be constructed of type 300 stainless steel filled with phenolic foam.
There has been no evidence of any corrosive reactions between these materials and the contents.
2.2.1 Closure The standards specify that the package be equipped with a positive closure that will prevent inadvertent opening.
In this case the lid of 0 0l3
7 Table 2.1 Mechanical properties of container materials
______-_--==-- -
Type 304L Property Symbol stainless steel Carbon steel Yield stress c
(psi) 28,000 30,000 Ultimate tensile o
strength (psi) 75,000 48,000 Modulus of elasti_ity (psi) 28 x 106 29 x 106 Elongation in 2 in. (%)
50 20 Density p
(lb/in.3) 0.290 0.283 Allowable shear
- stress, Imax = c /2 (psi) Y Imax 14,000 15,000 the basket is secured by eight 3/8-in. hex-head bolts with lock washers and nuts and qualifies as a positive closure.
Closure of the outer lid is attained by six 5/8-in. bolts with hex nut and lock washer.
2.2.2 Container lifting device If there is a system of lifting devices that is a structural part of the package, the regulations require that this system be capable of supporting three times the weight of the loaded package <ithout generating stress in any material of the package in excess of its yield strength.
This section is not applicable because there are no lifting devices, an(
the container is designed for forklift handling.
2.2.3 Lid lifting device The lids of the outer housing and basket are of such size and shape as to make hand lifting applicable and to preclude the need for any integral lid lifting device.
Ii10 014
8 2.2.4 Tie-down devices Because these containers have no integral system of tie downs, no calculations as to force-withstanding capacity are required by the general standards.
In transit the containers are secured by the same techniques used for conventional cargo without lifting lugs.
2.3 Standards for Type B and L
,e-Quantity Packaging The structural standards for large-quantity packaging co'er load resistance of the packaging and the external pressure which the package must withstand. Compliance cf the Unirradiated Fuel Shipping Container uith these requirements is discussed in the following subsections.
2.3.1 Load resistance When regarded as a simple beam supported at its ends along any major axis, the container must be able to withstand a static load normal to and uniformly distributed along its length that is equal to five times its fully loaded weight without generating stress in any material in the shield in excess of the yield strength of that material.
The equivalent cross section of the container analyzed in this study is illustrated in Fig. 2.1.
The cross section of the container is composed of the outer 1/8-in.
stainless ateel shell, the phenolic foam, and the 16 gauge stainless steel (GA. SST) basket as shown in Fig. 1.1.
For a thin shell the moment of inertia about its conter is n/2 2
(r,2 z 0)tr,de = nr,3 I=
y dA = 4 o
sin t
where r = radius (in.),
t= thickness (in.).
9 O RN L-DWG 74 - 8 411 R t w = 5 * = 48.7 Poun is per Inch 87 'e in R,="f R, = ]k
= 2121. 5
= 2121.5 (a) SHIELD AS SIMPLE BEAM a
r = 13. 0 in.
o 0
+
l t =.f 25 (b) EQUIVALENT CROSS SECTION OF SHIELD Fig. 2.1.
Container as a simple beam.
A 1110 016
10 Neglecting the effect of the phenolic focs and the basket, the moment of inertia of the container is I = nt(r)3
= n(0.125) (13.0)3
= 862.8 in.4 The maximum bending stress is given by the expression o = Mc/I = 5WLrg/81; so o = (850)(87.125)(13.0)/8(862.8) = 697 psi, where L is the length of the outer housing.
Since this stress is less than the yield stress for either housing material, it is concluded that the container compiles with the simple beam requirement.
2.3.2 External pressure The regulations require that the shipping package be adequate to ensure that the containment vessel will soffer no loss of contents if subjected to 25 psig external pressure. For the purposes of stress calculations, it will be assumed that the foam-filled cavity is at the external pressure. One potential consequence of external pressure is buckling of the cylindrical shells of the shield.
Since the outer shield housing is not airtight, there can be no pressure differential across it.
Since the inner housing (basket) is not scaled, there can be no pressure differential across it.
Therefore, this section is not applicable.
2.4 Compliance with Standards for Normal Conditions of Transport 1
The regulations for normal ccnditions of transport for a single package require that tne effectiveness of the package will not be sub-stantially reduced by the normal conditions of transport, that there will 1110 017
11 be no release of radioactive material from the containment vessel, and that there will be no gases or vapors in the package which could, through any credible increase of pressure or an explosion, significantly reduce the effectiveness of the pac ge.
There is no circulacing coolant other than atmospheric air, and there is no mechanical cooling device required or provided. The container and basket are so designed that the contents will not be vented to the atmosphere under normal conditions of transport.
These conditions include the effects of heat, cold, pressure, free drop, and penetration.
The container should exhibit acceptable performance with respect to all of the normal transport conditions.
2.4.1 Heat The package must be able to withstand direct sunlight at an ambient temperature of 130*F in still air without reducing the effectiveness of the packaging. A simplified one-dimensional heat transfer analysis (Sect. 3.1) was used to compute the steady-state temperature distribution in the package under the specified conditions. The surface temperature under these conditions would be approximately 208*F, and the tempera;ure at the center of the package would be approximately 208 F.
The temperature that would exist in the package will not adversely affect the container. The materials of construction do not suffer signifi-cant loss of physical properties at these temperatures. The maximum 9
service temperature of the phenolic foam is 300 F, which is also well above the temperature encountered.
3 The regulations set forth by the Department of Transportation further stipulate that the temperature of.ay cccessible surface of the fully loaded shipping package shipped by common carrier shall not exceed 122*F when the package is in the shade in still air at an ambient tempera-ture.
For this computation, an ambient temperature of 100 F is assumed, and since the containers have no internal heat load, the temperature of the surface will be 100 F.
I110 018
12 2.4.2 Cold The shipping package must be able to withstand an ambient temperature of -40*F (420'R) in still air in the shade.
Because the containers have no internal heat load, the temperature of the entire package will ba
-40*F, and beenuse the containers are not sealed, no pressure differential will resu3c.
At ~40*F the type 304L stainless steel to be used would not suffer brittle fracture because its transition temperature is considerably lower than -40*F.
In addition, the container closure bolts will be fabricated of stainless steel to avoid the low-temperature-embrittlement problem.
2.4.3 Pressure The regulations for normal conditions of transport specify that tae package be able to withstand a reduction in atmospheric pressure to 0.5 atm (the resulting pressure being 7.35 psia) at the 130*F ambient temperature condition.
Because the basket is not sealed the pressure in the basket will be the same as the atmospheric pressure.
Therefore, this section is not applicable.
2.4.4 Vibration The outer housing of the container is to be 1/8-in. stainless steel with a 26-in. outside diameter (maximum sized -- NBSRR - container);
transport vibrations would not be expected to affect the integri y of the container. The phenolic foam should further isolate the basket agains, vibrations.
The bolts that secure the lids are equipped with lock washers to prevent loosening.
2.4.5 Water spra1 The containers will be fabricated of stainless steel and will not suffer appreciable corrosive damage during the water spray test.
The phenolic foam is also not affected by water spray.
J ii10 019
13 2.4.o Free drop The regulations for normal conditions of transport require that a package weighing less than 10,000 lb be capable of withstanding a free drop through a distance of 4 ft onto a flat, essentially unyielding horizontal surface, striking the surface in a position in which maximum damage is expected to result. Under this impact, there should be no release of package contents (Sect. 2.5.1).
The tests reporcad in these sectior.s are much more severe; therefore, it can be concluded that the package would survive the 4-ft drop without loss of containment or integrity.
2.4.7 Compression It is required that packages weighing less than 10,000 lb be capable of withstaraing a compression load of five times the container weight, or 2 psi distributed uniformly acrose the top and bottom, whichever is greater.2 In this instance, five times the gross weight of 850 lb is somewhat greater than that of the 2-psi condition. The maximum compressive stress in t.ie walls is c = P/A = SW/nDat = (5)(850)/n(25.875)(0.125) = 418 psi, where DO = mean diameter of outer wall (in.),
t = wall thickness (in.).
Thus the package can support five times its weight with relatively low stresses generated in the walls.
2.4.8 Penetration The regulations for normal conditions of transport also stipulate that the package be capable of withstanding the impact of the flat end of a vertical steel cylinder which weighs 13 lb, has a diameter of 1-1/4 in., and is dropped from a height of 4 ft, normally onto the exposed
^
surface of the package that is expected to be the most vulnerable to puncture. This test would not reduce the effectiveness of the container 020
14 and would result in no more than a dent in the surface of the container.
Tests were conducted at ORNL to verify these conclusions (see Appendix D),
2.5 Compliance with Standards for Hypothetical Accident Conditions The standards for the hypothetical accident conditions stipulate that a package used for the shipment of fissile or a large quantity of radioactive material shall be so designed and constructed and its conte 90 limited that if it is subjected to the specified free drop, puncture, thermal, and water immersion (fissile material packages only) conditions, the reduction in containment would not be sufficient to increase the external radiation dose rate to more than 1000 millirems /hr at 3 ft from the outside surface of the package; no radioactive material would be released from the package except for gases containing total radioactivity not to exceed 0.1% of the total radioactivity of the contents of the package; and the contents would remain subcritical.
The following sections will show compliance with the standards for hypothetical accident conditions.
2.5.1 Free drop The first in the sequence of hypothetical accident conditions to which the container must be subjected is a free drop through a distance of 30 ft onto a flat, essentially unyielding suri ce.
The container must strike the surface in the position expected to cause maximum damage.
A full-scale test model of a fire and impact shield of construction similar to that of the unirradiated shipping container and the ORNL Gas-Cylinder Fire and Impact Shield was designed, fabricated, and tested at the Oak Ridge Gaseous Diffusion Plant as reported by Mallett and Newlon.4 These tests demonstrated compliance with the regulations after being subjected to the regulatory accident.1-3 The fire-resistant phenolic foam insulation used in the test container was the same as that to be used in the subject container.
The volume of determination of the tested shield did not exceed 5% for this package and would indicate no damage to the inner container.
1110 02i
15 4
The drums tested by Mallett and Newlon had locking ring type closures whereas the ORNL gas-cylinder fire and impact shield and the unirradiated fuel shipping containers have a uniform closure design.
The gas-cylinder package utilizes 8-3/8-16 UNC bolts, whereas the unirradiated fuel container has 6-5/8-11 UNC bolts.
The Mallett and Newlon closure utilized a single 3/8-16 UNC bolt in the locking ring closure.'
The flanged and bolted closure employed on the containers is designed to reduce the possibility of loss of lid in the event of an impact such as a 30-ft free-fall.
Note that the closuca is not sealed and does not form part of either the primary or secondary containment.
To comply with regulations the lid need only remain in place in order to maintain thermal (fire) protection.
Closure flanges and bolts are fabricated from ductile materials that would deform locally near the point of impact, if subjected to a free-fall.
We acknowledge that failure of the fastener directly at the impact paint is possible, though not probable.
Such a failure would not change the magnitude of permanent deformation of the container from the model tested at ORGDP.4 2.5.2 Puncture The second in the sequence of hypothetical accident conditions to which the package must be subjected is a free drop through a distance of 40 in. to strike, in a position in which maximum damage is expected, the top end of a vertical, cylindrical mild-steel bar mounted on an essentially unyielding horizontal surface. The mild-steel bar shall be 6 in, in diameter, with the top horizontal and its edge rounded to a radius of not more than 1/4 in., and of such length that it will cause maximum damage to the container but not less than 8 in. long.
The long axis of this bar shall be normal to the surface of the container upon it pac t.
4 In their report on a similar package, Mallett and Newlon presented the results of a puncture test.
Their container was dropped on its side
~
and was indented about 1.25 in without rupture of the wall.
Because of the similar design, it is concluded that the subject shield would behave in a like fashion and that no rupture would occur.
Ii10 022
16 2.5.3 Water immersion The final condition in the specified hypothetical accident is immersion in water to a depth of 3 ft for a period of 24 hr.
The container is not sealed, so the container cavity would be completely filled with water. The primary containment (aluminum clad fuel) would not be breached as a result of any of the accident conditions; hence the unirradiated fissile material wouli.iot be in contact with the vater, and no radioactive material would be transferred to the water. The fully loaded container filled with water and fully reflected by water remains suberitical.10 The phenolic foam of the container does not degrade upon water immersion; thus the criticality ca'.culations are valid during the entire time of the immersion test.
3.
THERMAL EVALUATION The package must remain effective after exposure to severe thermal environments. Applicable normal and accident environments are specified i
in the regulations -3 and are diecussed below. Analytical evaluations
~
and tests have been utilized to demonstrate the ability of the package to remain effective after exposure to the specified environments.
3.1 Norral Conditions of Transport The package must be able to withstand direct sunlight at an ambient temperature of 130*F in still air without reducing the effectiveness of ll the packaging. A simplified one-dimensional heat transfer analysis was used to compute the steady-state temperature distribution in the package under the specified conditions.
To determine the temperature of the outside surface of the container, an expression that includes convective and radiative heat transfer effects 12 is used. The expression is of the form 99 + " ' '
1110 023 c
q = h A ( s - T ) + 0.173 E A [(T + 460)/(100)]4 12 cc a
s
- [(T, + 460)/(100)]4 (1)
17 where q = convective heat flow (Btu /hr),
g = r diative heat flow (Btu /hr),
r h = convcetive heat transfer coefficient 12 = 0.19(T
-T) s a
Btu /hr ft2,op, A = convective heat transfer area = 52.1 ft2, T = surface tempecature (*F),
s T,= ambient temperature, 130 F, radiative heat transfer area = A (ft2),
A
=
c = endasivity of the painted shield surface (ref. 12., Table 5.2),
12 (%0.6).
F12 = gray body shape factor The heat load q on the package is only the solar heat load.
Because of the cyclic nature of solar heat load and the large time constant associated with containers of this type, the solar heat load per unit area can be approximated by numerically integrating the area under a normal incident solar energy curve (Fig. 5.3 in ref. 12) and is equal to 144 Btu /ft2.hr.
(This average solar heat flux is the same as was used in an example problem on p.
.43 in ref. 12.) The solar contribution ir the only heat load in this calculation, and the exposed surf ace area will be conservatively calculated as the convective heat transfer area, including the top and sides but not the bottom:
A = nr2 + 2nr1
= n(15.25)2 + (2) (n) (13.0) (82. 875) 7530 in.2 = 52.1 ft2,
=
The solar heat load is q = (144)(52.1) = 7500 Btu /hr.
s 1110 024
18 The net heat load at the surface is q = 7500 Btu /hr.
The surface heat transfer equation [Eq. (1)] was solved via an iterative process to determine the surface temperature T c rresponding s
to q = 7500 Btu /hr.
In this case T 206*F.
s Since there is no internal heat load, the maximum temperature of the container is the same as at the surface, 208*F.
3.2 Thermal Accident The third in the sequence of hypothetical accident conditions specified by the regulation to which the package must be subjected is exposure for 30 min within a source of radiant heat having a temperature of 1475'F and an emissivity coefficient of 0.9.
For calculation purposes the surface of the package is assumed to have an absorption coefficient of 0.8.
The package shall not be cooled artifically until 3 hr after tne test period has ended, unless ic can be shown that the temperature on the inside of the package has began to fall in less than 3 hr.
Similar packages with the same fire-resistant foam insulation, as reported by Mallett and Newlon," were tested according to the above requirements. The complete results indicate that at no point in the package inner liner will the temperature reach 200*F.
It is concluded, therefore, that the fuel shipping container will not exceed 200*F under the same conditions.
4.
CONIAINMENT It is required -3 thet packages maintain containment of their radio-1 active contents during normal and specified accident conditions.
The containment boundaries and capabilities of the fuel shipping container are outlined below.
In this package, the fuel element cladding constitutes the primary containment of the nuclear material. The basket lid and outside housing lid will provide further containment of the fuel unirradiated elements.
025
19 5.
SHIELDING This section is not applicable, since the container will not be used to transport irradiated fuel elements.
6.
CRITICALITY The container loaded with any of the five types of fuel 1.
'ed in Table 1.1 may be used as a Fissile Class I package.10 10 The analyses conservatively assumed that the package contained nine fuel elements in 3 x 3 square matrix instead of the proposed seven in a trianguler matrix.
It was also assumed that the principal damage to the package as a result of package test requirements (10-CRF-71, Energy) was that resulting from a fire. Tests 4,13 with the borated phenolic foam insulation indicated a char depth of from 2 to 2.5 in. may be expected.
The damage package evaluations were performed for a charred depth of 3 in.
The absence of water from the inner container results in a very low K.,
less than 0.2.
Water in the inner container, or fuel element baskets, results in a K. no greater than 0.9.
7.
QUALITY ASSURANCE l
The regulctions require packaging to be designed, fabricated, and operated in conformar with an established formal quality assurance pro-2 gram.
Compliance with this requirement is discussed in the following subsections.
7.1 Fabrication, Inspection, and Acceptance Tests The fabrication, inspection, and acceptance tests are specified on the drawings X3E10191-002, X3E10191-003, X3E10191-010, X3E10191-011, X3E10191-100, X3E10191-101, and data sheets DS-XDE--10191-1, DS-XDE-10191-2, and DS-XDE-10191-3.
The welds will be made and inspected according to the data sheets. The ferrous materials to be used in the container are specified on the data sheets to ASTM standards. The phenolic foam will h
20 be poured as specified on the data sheets and job specification JS-31536-1, Rev. 1, dated March 28, 1968, Fire Resistant Phenolic Foam.
Acceptance criteria are specified on the data sheets. Dimension inspection and inspection of finishes shall be performed per the data sheet to ensure that they are within the specified tolerances. A certificate of com-pliance with the drawings and data she4ts will be issued to the owner.
7.2 Routine Operating and Inspection Procedures The ORNL Operations Division has established routine operating and inspection procedures and standard check lists to ensure that all ship-ments are safe, comply with the regulations,1-3 and comply with all ORNL procedures and regulations. Copies of the procedures and the check-lists are presented in Appendix C.
7.3 Periodic Maintenance and Inspections Prior to each shipm nt, routine inspections are performed with the owners' procedures and check lists. The ORNL procedures are presented in Appendix C as an example. Maintenance is required cnly when routine inspections indicate damage.
There are t.o time-d: gradable padding materials used in the construction of the containers except for gaskets, padding, and cement used in the construction of containers.
Any damage or degradation to these would be detected during routine inspection and replacement effected.
7.4 Records It is the responsibility of the owner to assume that his containers are fabricated to the specifications on the drawings and data sheets.
In addition, the owner shall maintain f abrication and inspection records in an auditable form for the life of tne container.
4 1110 027 9
21 REFERENCES 1.
Code of Federal Regulations, Title 10, Part 71, " Transport of Licensed Materials;" see also Fed. Regist. 31, 9941-49 (July 1966).
2.
b.S. Atomic Energy Commission, "afety Standards for the Packaging of Fissile or Other Radioactive Materials," AEC manual, vol. 0000, General Administration:
Part 0500, Health and Safety, chap. 0529 (Jt.ne 16,1973).
3.
Code of Federal Regulations, Title 49, Part 173, " Transportation;"
see also Fed. Regist. 33, 14920-31 (October 1968).
4.
A. J. Mallett and C. E. Newlon, Protective Shipping Packages for B-and 12-Inch Diameter UF C linders, ORGDP K-1714 (April 196~).
F 6
5.
The International Nickel Company, Properties of Some Metals and Alloys, A-297 (1971).
6.
1974 Annual Book of ASTM Standards, ? art 3, Steel - Sheet, Strip, dire.
7.
1974 Annual Book of ASTM Standards, Part 5, Steel - Bars, Forgings.
8.
D. S. Clark, The Influence of Impact Velocity on the Tensile Charac-teristics of Some Aircraft Metals and Alloys, NACA TN-868 (October
~
1942).
9.
R. D. Seagren, Oak Ridge National Laboratory Returnable Type B Gas Shipping Package, ORNL/TM-3544 (October 1971).
10.
J. T. Thomas, Nuclear Criticality Safety Assessment of ORR, NBS, and HFBR Fuel Element Shipping Package, ORNL/CSD/TM-77 (January 1979).
11.
F. Kreith, Principles of Heat Transfer, International Textbook.
Scranton, Pa., 1965.
12.
L. B. Shappert, Cask Designer's Guide, ORNL/NSIC-68 (February 1970).
13.
A. J. Mallett and C. E. Newlon, "New End-Loading Shipping Container for Unirradiated Fuel Assemblies," Proceedings of Second International Symposiwn on Packaging and Transportation of Radioactive Materials, con 681001 USAEC, 1968.
1110 028
APPENDIX A Fabrication Drawings and Data Sheets 1110 029
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P00RDEINAL h
^
^
DATA SHEET oS-xoiT0ili-i
'T "I'i6 79 i
uNloN C ARBIDE CORPOR ATioN 1
3 NUCLEAR olVistoN emocwan o e,
,m e r a L 6 s o.*
o An nicoE, TN
- P A0uC AM, "
EJN 10191 emact vi r u s
> =os s c e no.
ase o==o ORR Unirradiated Fuel Element Shipping Container
- a. v.1c.
.m o...
.c.~v EQJf AMEN T Fabrication Notes for Dwgs. X3E-10191-002, Rev. A and X3E-10191-003, Rev. A 1.
Functional Acceptance Criterion Ifie fuel element barket assembly (Part Number 2) will be acceptable if, when assembled and centered in th shipping container body (Part Number 8) an inspection bar 315/1611/16 inches wuare and a straightness of 1/32 in. over its full length of 40 in. can be freely inserted and withdrawn from each and every one of the 7 fuel cavities. The inspection bar may have a maximum corner radius of 0.125 1.015 in.
2.
Fuel Element Basket Assembly Fabrication The fuel element basket assembly (Part Number 2) may be fabricated by a combination of formed (bent) shapes and welded joirts at the fabricator's option. The seams shall be joined by welds of 1/2 in lcag or. 4 in. centers or equal. The functional acceptance criterion shall be per note 1.
3.
Suggested Fuel Basket Assembly Procedure A.
Cross timbers (Part Number 14) installed in the shipoing container body (Part Number 8).
3.
The threaded rods, nuts and lockwashers (P.irt Numbers 8F, 5 and 6) installed and tightened on the fuel basket assemb'y bottom plate (Fort Number 28).
C.
The fuel element basket assembly (Part Numcer 2) lowered into the shipping container body (Part Number 8) with the threaded rods (Part Number 8F) passing through the holes in the shipping container's bottom plate (Part Number 8C).
D.
The phenolic spacers (Part Number 10) will be installed between the fuel
~lement basket upper plate (Part Number 2C) and the clip (Part Number 8E) on the inner surface of the container. The boles in the phenolic spacers will be adjusted to locate the fuel element basket in the center of the container body within 11/16 in.
E.
The threaded rod (Part Number 8F) at the bottom of the container body will be tensioned through the channel fi ture (see Dwg. X3E-10191-101) by applying x
a 10 ft/lb torque. The threaded rods will be tack-welded, the channel fixture removed, the welds completed and finally the excess rods will be removed and the bottom plate ground smooth.
4.
Welds A.
Welding and Inspection of Weld Joining Stainless Steel to Stainless Steel All welds shall be performed according to the provisions of a qualified orocedure and in accordance with the weld symbols on tFe fabrication drawings.
Fumish the fono*ing manufactueer's NUMBER OF COPIES TYPE GF OATA NUMBER OF CoPl".s data a avant ties indicatej W 'Bds A opeo val Cet tified (CONTINUED)
_w 'B os Appioval Cert + ed I. outhne dimentonal drawings
- 6. Test & Inrect9n Reports 2 operstm & Performarxe data
- 7. Materials Certification
- 3. Literature & Parts hst 3
- 4. operating & Ma.nt. Instructicos 9.
- 5. Installation Insti.,ctions t
10.
p m E *,A R E.) BY
- ' VEDBV P8'
^t A
Gi se E E%
PROJEC1 E N G R, W A nd A G E R - ~
_t N
M
=
6M 1110 036
A-10 DS-XDE-10191-1, Rev. 1*
Page 2 of 3 The fabricator shall qualify all welding procedures used in accordance with Section IX of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code. A 100% visual inspection is required for all welds and the welds shall comply with paragraph 8.15 of AWS Dl.1-1975. Visible defects such as cracks, pinholes, incomplete fusion, cold laps, porosity and under cuts shall be removed and repaired by grinding, or by grinding and reweldt 'g.
The repaired weld shall meet the quality requirements of the original weld. Written inspection reports are not required.
B.
Welding and Inspection of Weld Joining Carbon Steel to Stainless Steel Tfie welding process is DC Gas tungsten-arc, argon shielded. The filler material shall be ERNICR-3 (Inconel 82T). The preheat temperature shall be 60-300 F.
A 100% visual inspection is required for all welds and the welds shall comply with par. graph 8.15 of AWS Dl.1-1975.
Visible defects such as cracks, pinholes, incomplete fusion, cold laps, porosity and undercuts shall be removed and repaired by grinding, or by grinding and rewelding. The repaired weld shall meet the quality requirements of the original weld. Written inspection reports are not required.
5.
Materials A.
Lumber shall be douglas fir or southern pine, with moisture content 18% or less, No. 2 or better grade. The plywood may be any grade.
B.
Stainless sheet per ASTM A240 or A167, type 304 or 347 hot finished and annealed.
C.
Sta%1ess plate per ASTM A240, type 304 or 304L or 347 hot rolled.
D.
Aluminum sheet AA2024-T4 or 6061-T6 ASTM B209.
E.
Steel bar and structural shapes, type 304L or 347, ASTM 276 or A479, hot rolled, annealed and pickled.
F.
Screw, alloy steel ASTM A449, SAE 5,105,000 psi min. tensile.
G.
Hut, stainless steel type 303, ASTM A194, Grade 8F.
H.
Sheet, phenolic laminated brown or natural fire weave continuous filament wovenglass, fabric laminate melamine resin base nema Grade GB-112M.
I.
Sheet neoprene, 50 to 60 durometer hardness.
J.
Screw, stainless steel, any 300 series.
K.
Carbon steel plate per ASTM A-516 grade 60 hot rollu. and annealed.
6.
Foam Filling Toam filling shall be fire resistant phenolic foam and w4ter proofed per job specification JS-31536-1 and as follows.
A.
Fill the top section by foaming in one pour into top shell (container lid) and using a mold of specified finished shape. Weight of foam filling shall be 21/2 lt, t 10%.
B.
Fill the bottom section between the fuel element basket and container body in two approximately equal weight pours with the exposed finish surface being shaped by foaming into a mold. Weight of finished foam filling the bottom section shall be 35 lb i 10%. Materials may be substituted per K/TL-729. Evaluation of Materials in Fire-Resistant Phenolic Foam, C. E. Daugherty, G. E. Harris and R. R. Wright, March 1, 1978.
JS-31536-1 K/TL-729 Origi....
Sestitute Material 2 Union Carbide Corporation (UCC) V-6663 Material 6 Owens-Corning Fiberglas No. 833 Material 4 P0-2685 Eastman Material 5 Technical Grade Oxalic Acid, H C 0 224 1110 037
A-ll DS-XDE-10'91-1, Rev. 1*
Page 3 of 3 7.
Dimensi t inspectic ana 'nspection of Finishes All dime sian:, a-gles and finishes shall be sEoii inspected to insure they 7
are wi.
n tha specified toleiance. A certification of compliance with the d-awings
- ata sheets will be issued by the fabricator to the owner.
- General revisions to reflect the rep! -ment of carbon steel components with stain-less steel components:
(1) Item 4, welding change to carbon steel to stainlee-steel welding requirement.
(2) Item 5, deletion of cirbon steel specification ano addition of stainless steel specifications.
(3) Deletion of painting requirements.
I.4) Item 6, addition to foam filling requirements.
4 e
E001ORSIEL e
DATA SHEET DS -X DE-10191 -2 1*
l-16-79 o... _......
..._ o...
pass or a s ow.s
..o. = o UNtoN CARBIDE CoRPOR AT!oN 1
3 huCLE Alt olvistoN emocwano e, mov au no e.
c an ni cos, v..cu c a. a v EJN 10191
- *o s 4 C e
,*,LE P a OJ E C, so o 5 s e on w 0 HFBR Unirradiated Fuel Element Shipping Container ios,,a ev.u...
6...
E QUIPME N Y Fabrication Notes for Dwgs. X3E-10191-010, Rev. A and X3E-10191-Oll, Rev. A 1.
Functional Acceptance Criterion The fuel element basket assembly (Part Number 2) will be acceptable if, when assembled and centered in the shipping container body (Part Number 8) an inspection bar 315/1611/16 inches square and a straightness of 1/32 in, over its full length of 40 in. can be freely inserted and withdrawn from each and every one of the 7 fuel cavities. The inspection bar may have a maximum corner radius of 0.125 1.015 in.
2.
Fuel Element Basket Assembly Fabrication The fuel element basket assembly (Part Number 2) may be fabricated by a combination of formed (bent) shapes and welded joints at the fabricator's option. The seams shall be joined by welds of 1/2 in. long on 4 in centers or equal. The functional acreptance criterion shall be per note 1.
3.
Suggested Fuel Basket Assembly Procedure A.
Cross timbers (Part Number 14) installed in the shinping container body (Part Number 8).
B.
The threaded rods, viuts and lockwashers (Part Numbers 8F, 5 and 6) installed
^
and tightened on the fuel basket assembly bottom plate (Part Number 28).
C.
The fuel element basket assembly (Part Number 2) lowered into the shipping container body (Part Number 8) with the threaded rods (Pa.-t Number 8F) passing through the holes in the shipping container's bottom plate ' Dart Number 8C)
D.
The phenolic spacers (Part Number 10) will be installed between the fuel element basket upper plate (Part Number 2C) and the clip (Part Number 6E) on the inner surface of the container. The holes in the phenolic spacers will be adjusted to locate the fuel element basket in the center of the container body within 11/16 in.
E.
The threaded rod (Part Number 8F) at the bottom of the container body will be tensioned through the channel fixture (see Dwg. X3E-10191-101) by applying a 10 f t/lb torque. The threaded rods will be tack-welded, the channel fixture removed, the welds completed and finally the excess rods will be removed and the bottom plate ground smocth.
4.
Welds A.
Welding and Inspection of Weld Joininq Stainless Steel to Stainless Steel All welds shall be performed according to the provisions of a qualified procedure _and in a_qcordance with the weld symbols on the fabrication drawings.
Fuen.sn tB* 'co sa m g s n iuhtturer's N!MBE R OF cGPIES TYPE OF DATA NUVBER OF COPits CMa n hait t es micateJ W 'tk J1 A C Po val Cer t< fe ed
' con TINUE Di W Scs A woral Ce.taed 1 outMea tw on.i f ee.."gl e.
Test & lesrecten Repo !s 2 of t. *+ 0 t 4 Vc h " W e d it,4
- 7. %skf a stl Cettif tCJ!ron LUtv atee 4 Pa ts,in g.
- 4. Occ atra & Mant. Instruct.ons o.
- 5. Inwlity int uct'o'n j
10.
az aavao ev paw F. se Gm E t a '
PRJJECTCreGk. >WANAw(R
_P afsu> bcaukhse w. AAPe'ubm
=
1110 039
A-13 DS-XDE-10191-2, Rev.1*
Page 2 of 3 The fabricator shall qualify all welding procedures used in accordance with Section IX of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code. A 100% visual inspection is required for all welds and the welds shall comply with paragraph 8.15 of NS Dl.1-1975. Visible defects such as cracks, pinholes, iacomplete fusion, cold laps, porosity and under cuts shall be remove 1 and repaired by grinding, or by grinding and rewelding. The repaired weld shall meet the quality requirements of the original weld. Written inspection reports are not required.
B.
Welding and Inspection of Weld Joining Carbon Steel to Stt 'nless Steel The welding process is DC Gas tungsten-arc, argon shielded. The filler material shall be ERNICR-3 (Inconel 82T). The preheat temperature shall be 60-300 F.
A 100% visual inspection is required for all welds and the welds shall comply with paragraph 8.15 of AWS Dl.1-1975.
Visible defects such as cracks, pinholes, incomplete fusion, cold laps, norosity e d undercuts shall be removed and repaired by grinding, or by grinding and rewelding. The repaired weld shall meet the quality requirements of the original weld. Written inspection reports are not required.
5.
Materials A.
Lumber shall be douglas fir or southern pine, with moisture content 18% or less, No. 2 or better grade. The plywood may be any grade.
B.
Stainless sheet per ASTM A240 or A167, typ3 304 or 347 hot finished and annealed.
C.
Stainless plate per ASTM A240, type 304 or 30^L or 347 hot rolled.
D.
Aluminum sheet, AA2024-T4 or 6061-T6 ASTM B209.
E.
Steel bar and structural shapes, type 304L or 347, ASTM 276 or A479, hot rolled, annealed and pickled.
~. Screw, alloy steel ASTM A449, SAE 5,105,000 psi min. tensile.
G.
Nut, stainless steel type 303, ASTM A194, Grade 8F.
H.
Sheet, phenolic laminated brown or natural fine weave continuous filament wovenglass, fabric laminate relamine resin base nema Grade GB-112M.
I.
Sheet necprene, 50 to 60 durometer hardness.
J.
Screw, stainless steel, any 300 series.
K.
Carbon steel plate per ASTM A-516 grade 60 hot rolled and annealed.
6.
Foam Filling foam filling shall be fire resistant phennlic foam and water proofed per job specification JS-31536-1 and as follows.
A.
Fill the top section by foaming in one cour into top shell (container lid).
and using a mold of specified finished shape. Weight of foam filling shall be 21/2 lb t 10%.
B.
Fill the bottom section between the fuel element basket and container body in two approximately eoual weight pours with the exposed finish surface being shaped by foaming into a mold. Weight of finished foam filling the bottom section shall be 45 lb ! 10%. Materials may be substituted per K/TL-729, Evaluation of "aterials in fire-Resistant Phenolic Foam, C.E. Daugherty, G. E. Harris, and R.R. Wright, March 1, 1978 JS-31536-1 K/TL-729 Original Substitute Material 2 Union Carbide Corporation (UCC) V-6663 Material 6 Owens-Corning Fiberglas No. 833 Material 4 P0-2685 Eastman 1
Material 5 Technical Grade Oxalic Acid, H C 0 224 1110 040
A-14 DS-XDE-10191-2, r.ev.1*
Page 3 of 3 7.
Dimensional Inspection and Inspection of Finishes alt dimensions, angles and finishes shall be shop inspected to insure they are within the specified tolerance. A certification of compliance with the drcwings and data sheets will.be issued by the fabricator to the owner.
- General revisions to reflect the replacement of carbon steel components with stain-less steel components:
(1) Item 4, welding change to carbon steel to stainless steel welding requirement.
(2) Item 5, deletion of carbon steel specification and addition of stainless steel specifications.
(3) Deletion of pt.nting requirements.
(4) Item 6, addition to foam filling requirements.
1110 041
hh mS i o...... -o -
....o...
DATA SHEET DS-X DE-10191 -3 1*
l-16-79 union cARSIDE CoRPoR ATloN 1
3 NUCLEAR DIVistoN maccvaso av ins t.66 s o e v
~
O AK sti OG E. Tot = P ADU C AH. R Y UN ldM P
arosac t vi s ta paos.cr wo-aae on a o NBSRR Unirradiated Fuel Element Shipping Container
,o.
,,es.
.v. w..
.u.~1 E QWl'UE N T Fabrication Notes for Dwgs. X3E-10191-100, Rev. A and X3E-lC191-101, Rev. A 1.
Functional Acceptance Criterion The fuel element basket assembly (Part Number 2) will be acceptable if, when assembled and centered in the shipping container body (Part Number 8) an inspection bar 4 7/16!1/16 inches squere and a straightness of 1/32 %. over its full length of 70 in. can be freely inserted and withdrawn from each and every one of the 7 fuel cavities. The inspection bar may have a maximum corner radius of 0.125 1.015 in.
2.
Fuel Element Basket Assembly Fabrication The fuel element basket assembly TfRIiumber 2) may be fabricated by a combination of formed (bent) shapes and welded joints at the fabricator's option. The seams shall be joined by welds of 1/2 in, long on 4 in. centers or equal. The functional acceptance criterlon shall be per note 1.
3.
Suggested Fuel Basket Assembly P>ocedure A.
Cross timbers (Pert Number l*) installed in the shipping container body (Part Number 8).
B.
The threaded rods, nuts and lockwashers (Part Numbers 8F, 5 and 6) installed and tightened on the fuel basket assembly bottom plate (Part Number 2B).
4 C.
The fuel element basket assembly (Part Number 2) lowered into the shipping container body' (Part Number 8) with the threaded rods (Part Number 8F) passing through the holes in the shipping container's bottom plate (Part Number 8C).
D.
The phenolic spacers (Part Number 10) will be installed between the fuel element basket upper plate (Part Number 2C) and the clip (Part Number 8E) on the inner surface of the container. The holes in the phenolic spacers will be adjusted to locate the fuel element basket in the center of the cor.tainer body within 11/16 in.
E.
The threaded rod (Part Number 8F) at the bottom of the container body will be ten 3ioned through the channel fixture (see Dwg. X3E-10191-101) by applying a 10 ft/lb torque. The threaded rods will be tack-welded, the channel fixture removed, the welds complcted and finally the excess rods will be removed and the bottom plate ground smooth.
4.
Welds A.
. Welding and Inspection of Weld Joining Stainless Steel to Stain ess Steel l
Tl welds shall be performed according to the provisions of a qualified Dros.tdure and in accordance with the weld symbols on the fabrication drawinas.
F u<ni sn tee folic *in g -anu f ac tur et's NUMBE R OF COPIES TYPE of DATA NUMBER of COPIES dna e i cuant t es indtcited W 'B 1s Arpeovat Cer tM ed icon TIN U E Dt w %ds Aarc at CertMed oat 7e ec'siona S* rp
- 6. Test & Inspectron Rercuts 2 ocm t o, g rec m se cata L Wienat= ceitification o
3 IJte'3'.,ve & PJ ts itV 11 4 ocerating & Maint. InstNctions 9.
- s. Installat'on instwetions P Ett g
P ROJ EC 1 E N dDi _ _ A3TR' j a ss C yj AN, A p qo v t O B y
.P jt E 'e pa re E t p P
U. /f$h$Ot L 0 & ^/$
Nf/f
&Kh
~..,
s i
.e3 g3 yy, Ii10 QQ
A-16 DS-XDE-10191-3, Rev. 1*
Page 2 of 3 The fabricator shall qualify all welding procedures used in accordance with Section IX of the American Society of Mechanical Engineers (ASME) Boiler and P. essure Vessel Code. A 100% visual inspection is required for all welds and such as cracks, pinholes, incomplete' fusion, cold laps, porosity and under cuts shall be removed and repaired by grinding, or by grinding and reweldir;. The repaired weld shall meet the quality requirements of the original weld. Written inspection reports are not required.
B.
Welding and Inspection of Weld Joining Carbon Steel to Stainless Steel The welding process is DC Gas tungsten-arc, argon shielded. The filler material shall be ERNICR-3 (Inconel 82T). The preheat temperature shall be 60-300'F.
A 100% visual inspection is required for all velds and the welds shall comply with paragraph 8.15 of AWS Dl.1-1975. Visible defects such as cracks, pinholes, incomplete fusion, cold laps, porosity and undercuts shall be removed and repaired by griming, or by grinding and rewelding. The repaired weld shall meet the quality requirertents of the original weld. Written inspection reports are not required.
5.
Materials A.
Lumber shall be douglas fir or southern pine, with morsture content 18% or less, No. 2 or better grade. The plywood may be any grade.
B.
Stainless sheet per ASTM A240 or A167, type 304 or 304L or 347 hot rolled.
C.
Stainless plate per ASTM A240, type 304 or 347 hot rolled.
D.
Aluminum sheet, AA2024-T4 or 6061-T6 ASTM B209.
E.
Steel Bar and structural shapes, type 304L or 347, AST, 276 or A479, hot rolled and pickled.
F.
Screw, alloy steel ASTM A449, SAE 5, 105,000 psi min. tensile.
G.
Nut, stainless steel type 303, ASTM AlC4, Grade 8F.
H.
Sheet, phenolic laminated brown or natural fine wesve continuous filament wovenglass, fabric laminate melamine resin base nema Grade GB-112M.
I.
Screw, stainless steel, any 300 series.
J.
Sheet neoprene, 50 to 60 durometer hardness.
K.
Carbon steel plate per ASTM A-516 grade 60 hot rolled and annealed.
6.
Foam Filling Foam filling shall be fire resistant phenolic foam and water proofed per job specification JS-31536-1 and as follows.
A.
Fill the top section by foaming in one pour into top shell (container lid) and using a mold of specified finished shape. Weight of foam filling shall be 2 1/2 lb 110%.
B.
Fill the bottom section between the fuel element basket and container body in two approximately equal weight pours with the exposed finish surface being shaped by foaming into a mold. Weight of finished foam filling the bottom section shall be 60 lb 110%. Materials may be substityted per K/TL-729. Evaluation uf Material in Fire Resistant Phenolic Foam, C. E. Daugherty, G. E. Harris, and R. R. Wright, Ma. -
1, 1978.
JS-31536-1 K/TL-729 Original Substitute Material 2 Union Carbide Corporation (UCC) V-6663 Material 6 Owens-Corning Fiberglas No. 833 Material 4 P0-2685 Eastman Material 5 Techanical Grade Oxalic Acid, H C 0224 1110 043
A-17 DS-XDE-10191-3. Rev.1*
Page 3 of 3 7.
Dimensional Inspection and Inspection of Finishes All dimensions, angles and finishes shall be shop inspected to insure they are within the specified tolerance.
A certifi ation of compliance with the c
drawings and data sheets will be issued by f.ne fabricator to the owner.
- General revisions to reflect the replacement of carbon steel components with stain-less steel components:
(1) Item 4, welding change to carbon steel to stainless steel welding requirement.
(2) Item 5, deletion of carbon steel specification and addition of stainless steel specifications.
(3) Deletion of painting requirements.
(4) Item 6, addition to foam filling requirements.
O e
e 1110 044
A-18 JOB
_ g,;.,* cAvioN STANDARD REFERENCE iHF03MATiON UNION CARBlDE CORPOR#. TION JS-31526-1 Rev. 1 NUCLEAR Dm3]oN sata onoop. can nicos. yenursses - PaoucAn. nr-xny 3-28-66 rwassev
~~
== vissa 3-26-68 FIRE RESISTAh"f PHENOLIC )QW e...
1 5
SCOPE This specification shall :cver materials and procedures for mixir4 and applying foamed-in-place fire resistant phenolic foam where specified on the drawirgs.
MATERIALS AND PROPORTIONS All materials used in the fire resistant foam shall be as listed below and shall be prepared by blending, screening, etc., as defined. Sub-stitutions of materials may be made only where noted. Total q'antity of materials shall be as required to fill the centainer cavities and provide the finished foam weight as defined on the drawings. Individual weight quantity of each component material shall be such to provide a finished fa material mixture of the proportionate blend specified below.
Cmponent Weight per 100 Lb. of Matl.
Material Vendor - Trade Name (Lb s. )
Liquid Cmponents Phenolic Resin UCC Plastics Division 65.8 + 0.2
~
BRL-2760 (Foam Density 1.8-2.0 Lbs./ft.3)*
Surfactant UCC Plastics Division 2.0 + 0.1 Silicone Surfactant
~
L-530, or equal 6.6,,0.1 Refrigerant 113 DuPont Freon 113, or f
eq'al Powder Cmponents Boric Anhydride Varlaccid Chemical 14.1 + 0.1 (42 2), Powder, Cmpany No.13 36, or
~
0 Reagent Grade, equal
-100 + 200 Mesh
- Resin foam salue as determined by method used at the Marietta Ohio Plant of the UCC Finstica Divisian.
N p
3:
4pe-no av.
45 M Waw
~
1110 045
PU0lFORHR
^ - -
STANDARD HEFERENCE INFORMATION
- =a JS-31536-1 Rev. 1 04TE 3-28-66 3-28-68 FIRE RESISTANT PHENOLIC FQAM e4es 2
5
.e C aponent Weight per 100 Lb. of Matl.
Material Vendor - Trade Name (Lbs.)
Pouder Caponents (Contd)
Boric Anhydride (B23)
V"#l** id Ch'*i**1 k'1 *
- 1 Powder, Reagent Ccagany No. 1137, or Grade, -200 Mesh egaal.
Oxalic Acid, H C 0,
Baker and Adamson 8.2 + 0.1 224 Anhydrous No.1135, or equal Pouder, Reagent Grade Rein *crcing Ccuponent Eiberglass Ravings Owens-Corring Fiberglas 9 2 + 0.1 1 / 16 " Chopped Lengths No. 805 (hsI),or equal MATERIAL SM* AGE RMUIRENT.NTS Phenolic Resin 1.
Store in airtight stors.ge container.
2.
MmHen shelf life is three months frca date of manufacture if stcared at roca temperature.
or MmM-shelf life is six mcsiths fra date of manufacture if stored at a temperature of 400 + 50F.
AIE: Inte of manufacture should be marked cn the etorego ccntainer.
Pre-blended Liquid Cmpenents The three liquid emponents may be pre-blended or stored separately.
If pre-tlendd, the liquid mixture ray be stored in airtight storage ccritainers at a temperature of 40 + 5 F for a period of time not ex-caeding one nonth prior to final blending, provided this additional time does not exceed the maximum stors.ge life for the rhenolic resin.
If the ligaid ec ponents sre stcred separately, the same storage re-gairmants rust be cbserved for the phenolic resin caponent.
Fevder-ccepctee.ta 23U All povaerc she.L1 be stored in airtient storage centainers at rocza 5:
temperature acfc re and after pre-bler.dtri,s. to prevent abscrption of moi r.t ur a.
Approveo er: _
1110 046
A-20 STANDARD REFERENCE INFORMA110N
'a-aa JJ-31536-1 Rev.1 n.v.
3-28-6o
.w.s..,
3-28-68 FIRE REGISTANT 11Lv.NOLIC FCAM
'u.
5 3
All other Materials Store all other con:ponent asterials in airtight storage containers at rocan temperature until ready for blending.
PREPAPATION OF RII'EIVER CONTAINER AND ACCESSORIES Centainer In preparing a ex.tainer for receiving the foamed-in-place filling, all loose inner pieces shall te securely anchored in place to prevent dis-placement by the fomn, and vent holes to prevent voids in the finished foam and to provide gas relief when exposed to high heat shall be drilled as defined m the drswicgs. The necessary blocking, framira, tracing, etc., shall be installed to hold in place the container shell, ends, linir4, etc., as applicable, and prevent distortion to out-of-tolerance condition during the fesair4 operation.
Molds Molds to shape exposed surfaces of foes shall be installed and secured in position just after the final foes raw n.aterial is placed so foes can expand into thy mold. Air vent holes not exceeding 1/4" in diameter may be made at intervals in a mold to allos for escaping air and thereby prevent void spaces in the finished surface. Molds shall be made of such strength to prevent distortion to out-of-tolerance condition during the foaming operation. A mold release (e.g. Er.erson and Cuming mold release ecz: pound No.122S cr DuPont Tefloa) shall be applied to mold surfaces which will contact fcam material so that %e mold can be removed without damaging the finished fcan surface.
Cleaning Befere Foaming All sawdust, aits cf wood, metal filings, water droplets, grease, oil, and other fcreign particles shall be removed frczn the molds or container cavities b-fere fcem raw raterial is added.
MIXING PROCEDURES Pre-Blending Liquid Cemperents - Pre-blend liquid components in any order by combinir.g the ingredients r.nd atirring to a uniform consistency. Temperature of the p'lenolic resin stall c e 600 +- $oF vhen it'is added to.the mix. If final blending is to be delayed, reseal the blende<1 cct:ponents so atmospheric exposure is reduced to a minimus.
.,-if E:
prmove a en 9
1110 047
A-21 STANDARD REFERENCE INFORMATION
~~ s a ear.JS-31536-1 Rev. 1 3-28-66 w.o FIII PR4TR"JulT FHENGLIC FQAM k
5 Powder Cmpments Screen all empt:rtents through a sieve (National Bureau cf Standards No. kO) and pre-hlend to a uniform consistency. Reseal blended emponents so atmospheric exposure is reduced to a minimum.
Final Bleniing 1.
Add liquid ccumponents or pre-blended liquid ceponents to mixer tub and stir to a uniform consistency, e. bout 2 minutes for pre-blended c m ponents. Temperature of the phenolic resin or pre-blended liquid ccuponents aball be 600 + 5 F when it is added to the mix.
2.
Add fiberglass and mix to a uniform ecnsistency.
3 Add the pre-blended powder emponents rapidly and mix to a unifozu consistency, 30 to 60 seconds.
4.
Quickly transfer the mixed raw material to the receiver container so that the foaming action takes place within the container.
~
PIACId3 AND CURI!C FCAM FMDIAL The mixed feem raw material shall be spread evenly over the bottom surface of the receiver ccetainer so foas expands in relatively uniform layers.
The first pear of bottcm section snould be tamped immediately after foam-ing begins to minimize size of void spaces. Air cure at roca temperature for at least ene hotr to allow for full expansion of foam.
After foaming action and curing is ccupleted on a pour, the next pour of material car be spread evenly on top of the previous expanded layer. All sequential pours shall proceed with a minir s delay so that atmospheric exposure of the internal fibers is minimized. The rider of pours shall be as specified on the drawings. After the final pou, the foam shall be allowed to cure at least four hours at rocn temperature before bracing, molds, and accessories are removed.
FOTE: Seqantial pcr2rs are self bonding to the previous pour with no apparent voids or cleavage planes.
REMOVAL OT E'40IX3, MCLES. AND ACCESSORIES AND FINISMIN", WORK General All bracing, molds, and any accessories not part of the finished container, as defined on the drawings, shall be removed after foaming and curing opera-ticals are completed. Any extruded foam material (e.g. extrusions thro 2gh I
s:
A PP'toVE D p f -
4 Il10 048
A-22 STANDArtD 9EFEhENCt: INFORMATION
~~aa a JS-31536-1 Rev.1 o v.
3-28-66 3-28-68 FIRE REISTANT P!IEiOLIC FQM4 5
5 air vent holes) #.s.ll be careful 3;/ trimned ar.d removed to provide a smooth surface over the crterict and interior surface of the container. Foam material splashed onto expcsed surfaces of the ccr.tainer shall be removed.
All molci release, grease, dust, etc., which would prevent a coating frm adhering properly shall te removed frco the finished fosa rarfaces, prior tb coating, by wiping with a soft cloth saturated with tri-chloroethylene.
Patebirt.g Voids in FinishM Fcamed Surface Material Void; spaces in the finiched fca.m surface shall be patched by filling with additic m1 foam raw material and alleving the r.aterial to expand and cure.
Excesaive foam or rough spots left by this pro:ess anall be dressed smooth with the surrcrandf 5 surface to give em overall uniform surface.
Waterproofing Seal wa.tcrtight all holes in oater shell and inner liner when applicable, (e.g. vent holes, gaps arcer.d caps fer fill holes, nail and screw holes, etc., a.s applicable) with two coats of epoxy ** prior to finish coat of paint. Seal wr.tertight all exposed surfaces of foam with two coats of
~
epoxy.
CIIAY. IN", AT;"'S Cellossiv, acetone, or other cleaning agen*,s may be used for cleaning utensil.a or resuving particles of splattered foam fr<xa metal parts only of conta.'rer surfaces.
OTHL"4 Ihe fol.1: wing typical chemical ar.alysis of cured foam may be used as reference data for nuclear calculaticns.
Vt. (
Ca.rbon 41.0 Hy:irogen 45 Boren 32 SLlicon 2.2 Ch.lcrir.e 05 Ni regen nil F h crine nil Oxygen 1.3.6 (by diff erence) b Epoxy shQ be Art.ld1* e #502 epoxy with he er #951 as manufactured by s.l Ciba Products C(v.pany. Fairlawn, New Jerse:,
.e eq A1.
-3 55s:
Ap#RC. F o SY.
lil0 049
APPENDIX B Fuel Element Drawings 1i10 050 e
4
P00ROR321.
is'Y
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= Y.
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1110 054 4
APPENDIX C Routine Packaging and Inspection Procedures 1i10 055 G
C-3 PRE-USE INSPECTION CHECKLIST UNIRRADIATED FUEL ELEMENT SHIPPING CASK Oak Ridge National Laboratory Oak Ridge, Tennessee Container Serial No.
Reference Drawings:
X3E-10191-002 X3E-10191-003 BY DATE A
Visually inspect container exterior for shipping damage, rust and general state of repair.
B Visually inspect container interior for rust, condition of foam, moisture and general state of repair.
C Visually inspect neoprene spacers and gasket.
D Visually inspect basket closure Mits, nuts and lock washers for condition and conformance to D-1 through 0-5.
1 Number required - 8 each 2
Bolts - Hex Hd. 3/8"-16 UNC-2 1-1/4" long alloy steel ASTM A-449, SAE 5, 105,000 psi min tensile.
3 Nuts - SST 3/8"-16 UNC (welded to basket) 4 Lock washer - 3/8" carbon steel 5
Nuts and bolts engage freely by hand E
Visually inspect closure bolts, nuts and lock washers for condition and conformance to E-1 through E-5.
1 Number required - 6 ea.
2 Bol ts - Hex Hd. 5/8"-11 UNC-2 1-1/4" stainless steel Type 304 ASTM A-193 Grade B3.
Ii10 056
C-4 3
Nuts - SST 3/8"-16 UNC (welded to container flange) 4 Lock washer - 3/8 carbon steel 5
Nuts and bolt engage freely by hand.
List deficiencies found and corrective action taken below.
Approved by:
W 1110 057
C-5 PROCEDURE FOR LOADING ORR UNIRRADIATED FUEL ELEMENT SHIPPING CONTAINER DATE NAME 1.
Record element numbers 1
2 3
4 5
6 7
2.
Clean inside of shipping container 3.
Inspect container.
No loose or foreign material to be present inside shipping container.
Record container number 4.
Visually inspect cask exterior for shipping damage, rust and general state of repair.
5.
Visually inspect basket spacer and gasket.
6.
Visually inspect basket closure, bolts, nuts and lock washers for condition and conformance to 6-a through 6-c.
a.
Number Required b.
Bolts - Hex Hd.
c.
Nuts d.
Lock washers carbon steel 3/8" nominal size e.
Nuts and bolts engage freely by hand.
7.
Visually inspect lid closure, bolts, nuts and lock washers for condition and con-formance to 7-a through 7-e.
a.
Number Required b.
Bolts - Hex Hd.
c.
Nuts d.
Lock washers carbon steel 5/8" nominal size e.
Nuts and bolts engage freely by hand.
8.
Load elements. This operation to be witnessed by ORNL representative.
Heat seal one end of polyethylene tube.
Slide element into tube.
Heat seal top end of polyethylene bag.
Use vacuum cleaner to pull air out of bag.
}l}() Qjg Place element (s) in container (maximum 7 elements).
Replace cover on container.
Be certain the element is below the flat of the cover and that the polyethylene bag is tucked in properly.
Bolt basket lid in place.
(Torque bolts to 25 ft-lbs.)
C-6 9.
Place container lid in place and bolt to
~
container.
(Torque bolts to 25 ft-lbs.)
10.
Radioactivity inspect (10 CFR Part 71)
Write and apply radioactive Class I label.
Accept Reject 11.
Place - tamper - safe seal U.S. Treasury Type "E" (cup type) on shipping contair.er.
Record Seal #
Witnessed by inspection or QA Representative Time Date I have witnessed sequence 11 and accept delivery of the fuel elements.
I certify that fuel element numbers listed in seq.1 and loaded in seq. 8 is tamper-safe sealed in the shipping container with the above numbered tamper-safe seal.
ORNL Representative Enter seal number in daily inspection log.
12.
Check shipping container for: this operation to be witnessed by ORNL Representative.
l.
All bolts in lid and tight.
2.
Tamper-safe seal in place on lid.
3.
Radioactive label.
4.
Shipping label and shipping papers securely attached.
Witnessed oper.12 ORNL Representative 6
1110 059
APPENDIX D Penetration Tests A
1110 060 a
P00R~0RBEl INTERN AL CORRESPONDENCE
=
NUCLEAR DIVISION w ' o ' ' o: rm. es. mo.r M W HEt 3'80
- v. ~.-. File
- o. -
Jaauary 29, 1976 D.....
t u...,
o,
, o...
Development Engineering 4,..
..,s...
c..
K. K. Chipley wk.
E. M. King J. M. Robinson L. B. Shappert On December 22, 1975, I performed the " Penetration" Test described in Annex 1 of AEC MC-0529 on the existing packages and models listed on the attached data sheet.
In all cases the resulting damage was a small dent.
It is now obvious that this test will not reduce the effectiveness of steel or stainless steel jacketed packages and that the resulting damage is insignificant.
{\\g-i [~Edw
,$ohnEvans
/
</
JE:gl s
Attachment e
1110 061
D-4 Page 2 - Certificate No. 9833 - Revision 0 contained in fuel plates as reactor fuel elements.
(2) Fissile Class:
I 1110 062
o DATA SHEET PENETRATION TEST - AEC M 0529 CONTAINER LOCATION INDENTATION DIA.
DEPTH B. of E.
648 Side 3/8
.006 ORNL 8L12-115 Top Body 5/16
.007 ORNL 8 L12-115 Plug 1/2
.065 Y
LLL Test Container Side 3/8
.005 Tube Shield Side 3/8
.003 55 Gal. Drum Side
- 3
.137 55 Gal. Drum Top
- 2 1/4
.147 ORNL 456 200 Side 7/16
.005 Side (g 1/2
.036 A
inum B. of E.
2022 I '*
O
- 3. of E.
2022 S ide 3/8
.020 p
O Ch LN
APPENDIX E Approval Documents 1110 064 O
e
E-3 TC 79-1 INTRA-LABORATORY CORRESPONDENCE OAK RIDGE NATIONAL LABORATORY February 28, 1979 To:
R. W. Mouring Subj ect: Approval of Safety Analysis Report for Packaging:
Unirradiated Fuel Element Shipping Container The draft (received February 2,1979) of the subject SARP has been reviewed by the Transportation Committee. The SARP is approved for technical content and approach -- for submission to DOE.
Comments from individual members of the Committee have been forwarded for consideration.
E.rn.//;?
~~
E. M. King Transportation Committee BfK:j r cc: Committee Members G. H. Burger J. A. Cox J. H. Evans R. V. McCord lil0 065
E-4 June 7, 1979 Union Carbide Corporation Nuclear Division ATTN:
Dr. Herman Postma Director Oak Ridge National Laboratory Post Office Box X Oak Ridge, Tennessee 37830 Gentlemen:
SAFETY ANALYSIS REPORT FOR PACKAGING THE UNIRRADIATED FUEL SHIPPING CONTAINER Reference is given to the letter dated April 26, 1979, from M. E. Ramsey in regard to the above subject.
The draft Safety Analysis Report for Packaging (SARP) has been reviewed by the staff of the ORO Safety and Environmental Control Division.
The SARP is approved for publication.
Enclosed is a copy of the ORO Certificate of Compliance. The original Certificate of Compliance has been sent directly to the authors so that it may be reproduced for inclusion as an Appendix to the SARP. The orig-inal should be returned to ORO after publication.
The closure arrangement for these containers is considered to be an im-provement over the standard drum closure ring used on the 12" diameter UFr, overpack which was successfully tested to Type B package requirements.
However, since the closures are dif ferent and an engineering evaluation does not appear feasible, we request that a drop test be made on a proto-type.
NRC has raised questions on the closure of the ORNL gas cylinder fire impact shield.
Since licensees will be using both the unirradiated fuel shipping container and the gas cylinder fire and impact, NRC ques-tions should be resolved.
Sincerely, oseph A. Lenhard
^
Assistant Manager r Energy MS-334:WAP Research and Dev lopment 1i10 066
P00R OR M U S. C s - %RTMENT OF ENTRGY doe Forra E v4 8 8
=
an an CERTIFICATE OF COMPLIANCE
C#"'I For Red.oactive Matenais Packa3ps la Certif.cate Number Ib. Revis.on No.
Ic. Pacmage Identification No.
Id Page No.
le Iotal No Pages ml 0
USA /1813]BF_
1 3
2 PREAMBLE 2a Th.s certificate is issued to satisfy Sections 173 3934. I 73 394.173 395. and 173 396 of the Department of Transportation Hamdous Materia 6s Regulat.ons (49 CFR 170-189) 2b.
The packag.nu and contents descrebed in. tem 5 betoa. meeis the safety standards set forth in Subpart C of Titie 10. Code of Federal Regulations. Par t 71, "Packag.ng of Rad.oactive Maler.ai for T ransport and Transportation of Radioactive Mater.at Under Certa.n Cond-tions "
2c.
Th<s cer tif.cate does not rei. eve the cons.gnor from comphance w.th any reuw.remoni of the regutations of the US Departnv at of Transportaton or other appucatve regu atory agencies. men d.ng the government of any country through or ento which ths :4ck age u
n.it be t<ansporved.
3 This ertit.cate is.ssued on the bas,s of a safety anaiys.s report of package design or apphcation-(1) Prepared by (%ame and address)
( 21 7 it.e and toentif > cat.on of report or appacat on
- 13) Date Oak Ridge National Laboratory Safety Analysis Report for Pack-Post Office Box X aging: The Unitradiated Fuel Shipping Oak Ridge, Tennessee 37830 Container Report: ORNL/ENG/TM-15 4 CONDITIONS Th.s certif,cate is cond.t.onal upon the fuit,il.ng of the requerernents of Subvert D of to CF R 71,as appbcapie, and the cond tsons specif.ed in item 5 beson 5 Deser tuon of Packag ag and Author ed Contents. Modes Number, Fissile Class. Other Condit.ons, and Ref erences a.
Packaging:
(1) Model: ORNL Unirradiated Fuel Shipping Container (2)
Description:
s Packaging for unirradiated fissile material as fuel elements. The fe l cle-ments are positioned in a basket consisting of seven square cavities fabri-cated from 16 gauge plate and a base fabricated from eleven gauge plate.
The plate is Type 300 stainless steel. Eight 3/8" nuts and bolts retain the basket lid, which is made from 0.125" thick aluminum, in place. The basket is positioned inside a cylindrical outer shell. The outer shell and lid are fabt teated f rom eleven gauge plate and the base is 1/4" t'iick plate.
The plati for the shell is Type. 300 stainless steel. The ouu
.id is held in place by six 5/8" nuts and bolts. The basket is supported on 2" x 6" timbers 1. side the outer shell. The remaining space around the basket is filled wi.h phenolic foam insulation.
Th2re are different types of packages. Table 1 descCbes the detairs of each design, b.
Contents:
(1) Type and form of material 2 nU and is in the oxide form.
It is db%paniumhtenriwed to 193%
The 4 lhd 6b E mpiration Date 6e Date of issuance FOR THE U S DEPARTMENT'OF ENERGY 1a Address lof DOE isswng Omcel 7b S,gnature. Name, and T.ne (of DOE Acorowng Off oad 11a _.Ik _Aci.s U. S. Department of Energy William H. Travis, Director Post Office Box E Safety and Environmental Control Oak Ridge, Tennessee 37830 Division lllo 067
E-6 Union Carbide Corporation 2
June 7, 1979 Nuclear Division
Enclosure:
As stated cc:
C. A. Keller, MS-30, w/ encl.
T. H. Hardin, AD-46, w/ encl.
J. E. Rounsaville, ER-lll, w/ encl.
W. H. Travis, MS-33, w/ encl.
R. F. Hibbs, UCC-NO, w/ encl.
J 1110 068
e i
e Page 3 TABLE I
SUMMARY
DESIGN DATA CONTAINERS AND FUEL ELEMENTS Container Fuel Elements Gross outside Inner Basket Nominal Maximum Weight Length Diameter Base Length Cavities
- Dimensions 235U Per Type (Ib.)
(In.)
(In.)
(In.)
(In.)
(In.)
(In.)
Fuel L'lement (R)
I.
A. ORR" 580 56 5/8 24 1/2 29 x 29 38 3/4 4x4 A. 38 3/8 x 3.032 x 3.397 370 b
B. BSR B. 34 3/8 x 2.996 x 3.397 370 c
PCA II.
HFBR 700 75 1/2 24 1/2 29 x 29 57 1/2 4x4 57 1/4 x 2.878 x 3.218 370 en III.
NBSRR*
850 87 1/8 26 30 1/2
- 3/16 4 1/2 68 51/64 x 3.125 x 3.8125 370 b
x x
30 1/2 4 1/2 a.
Oak Ridge Research Reactor b.
Bulk Shielding Reactor c.
Pool Critical Assembly d.
High-Flux Beam Reactor
((
e.
National Bureau of Standards Research Reactor CZ)
- 7 Cavities per basket; 1 fuel element per cavity C7s T
ORNL/ENG/TM-15 Dist. Category UC-71 INTERNAL DISTRIBUTION 1.
G. A. Aramayo 28.
E. M. King 2.
M. Bender 29.
R. W. Knight 3.
D. Box 30-34.
R. V. McCord 4.
G. Bowden 35.
J. R. McGuffey 5.
H. G. Burger 36.
J. D. McLendon 6.
C. D. Cagle 37.
R. N. Mouring 7.
D. D. Cannon 38.
F. H. Neill 8.
K. K. Chipley 39.
T. W. Pickel, Jr.
9.
H. C. Claiborne 40.
M. E. Ramsey 10.
R. L. Clark 41.
J. E. Ratledge 11.
J. A. Cox 42.
J. N. Robinson 12.
W. K. Crowley 43-47.
R. W. Schalch 13.
F. C. Davis 48.
R. A. Schmidt 14.
H. R. Dyer 49.
R. D. Seagren 15-19.
J. H. Evans 50.
L. B. Shappert 20.
R. E. Eversole 51.
W. E. Terry 21.
F. C. Fitzpatrick 52.
J. T. Thomas 22.
C. S. Force 53.
J. W. Wacher 23.
J. H. Gillette 48-49.
Central Research Library 24.
K. W. Haff 50-52.
Document Reference Section 25.
S. S. Hurt 53.
Laboratory Records Department 26.
G. R. Jasny 54-68.
Laboratory Records, ORNL R.C.
27.
R. A. Just 69.
ORNL Patent Office EXTERNAL DISTRIBUTION 70.
E. L. Barraclough, DOE, Albuquerque Operations Of fice, Post Office Box 5400, Albuquerque, NM 87115 72.
L. G. Blacok, DOE, Supply Div., ORO 73.
R. B. Chitwood, DOE, Div. of Transportation and Fuel Storage, DOE Headquarters 74.
R.
I. Elder, Chicago Operations Office, 9800 South Cass Avenue, Argonne, IL 60439 76.
J. M. Freedman, Sandia Laboratories, P.O. Box 5800, Albuquerque, NM 87115 77.
Assistant Manager, Energy Research and Development, DOE-ORO
~
79.
W. G. O'Quinn, DOE, Savannah River Operations Office, Post Office Box A, Aiken, SC 29801 80.
R.11. Odegaarden, NRC, Of fice of Regulation, Washington, DC 20545 l110 070
81.
R. W. Peterson, Battelle Memorial Institute, 505 King Avenue, Columbus, OH 43201 82-86.
R. W. Powel, Brookhaven National Laboratory, Upton, NY 11973 87.
Tawfic Raby, Chief of Reactor Operations, National Bureau of Stcadards, Washington, DC 20234 93.
R. Rawl, U.S. Department of Transportation, 6th and D Street, SW, Washington, DC 20590 94.
J. A. Sissler, DOE, Div. of Transportation and Fuel Storage, DOE Headquarters 95.
D. W. Templeton, DOE, Ricilland Operations Of fice, Post Of fice Box 550, Richland, WA 99352 96.
Safety and Health Protection Branch, DOE, ORO 100-270.
Transportation of Property and Nuclear Materials (25 copies - NTIS) e e
9 9
1110 071