ML19309E193
| ML19309E193 | |
| Person / Time | |
|---|---|
| Site: | 07001007, 07109019 |
| Issue date: | 05/24/1974 |
| From: | Tschaeche A GENERAL ELECTRIC CO. |
| To: | US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML19309E183 | List: |
| References | |
| 15758, NUDOCS 8004180525 | |
| Download: ML19309E193 (10) | |
Text
.
G E N E il A l. $ggd" E l.E CT R I C W
ilUCLEAR ENERGY EQ DIVISION 95125 GENERAL. ELECTRIC COMPANY,175 CURTNER AVENUE, SAN JOSE, CALIFCRNIA Em Phone (408) 297-3000, TWX HO. 910 333-0116 May 24,1974 Mr. C. E. MacDonald Chief, Transportation Branch Directorate of Licensing Office of Regulation U. S. Atomic Energy Commission Washington, D. C. 20545
Subject:
Modification 23 to Appendix D License SNM-54, Docket 70-1007
Dear Mr. MacDonald:
General Electric has been granted Amendment 71-21 and Amendment 71-22 (and Revision 1 thereto) to License SNM-54 authorizing delivery
,()
of special nuclear material, UO, to a carrier for transport in the 2
packages designated as Models BU-4 and BU-5, respectively.
Safety' analysis has been completed for a package designated as GE Model BU-6, constructed in a manner similar to BU-4 and 5 with identical contents but smaller in physical size and for Ic.sser amounts per package.
The inner and outer drums of the BU-6 are fabricated according to a military specification (copy enclosed for information) which is equivasnt to DOT Specification 17H.
In addition, tests and safety analysis have been completed for a package designated as GE Model BU-7 which is constructed os materials identical to that of the BU-4 and BU-5, except for the insulating and gasket material.
The contents of the BU-7 consist of " dry" uranium oxide powder and pellets identical to those authorized for the BU-5 except that the enrichment is limited to 4%
Accordingly, General Electric hereby requests amendment of License SNM-54 to authorize delivery of special nuclear material to a carrier r
a
.)
800418ogggg UE SURE TO INCLUDE MAIL CODE ON DETURN CORRESPONDENCE n_
GEilER AL [h ELECTRIC Mr. C. E. MacDonald
-2 May 24,1974 for transport in the GE Model BU-6 and the GE Model BU-7 as shown in the enclosed Modification 23 to Appendix D of the application for that license. Modification 23 consists of new Sections 1.7 and 1. 8 on pages 1-71 through 1-83, dated May 24, 1974, which should be added to pages of Appendix D previously submitted.
We trust that this application is sufficient to permit issuance of the appropriate amendment and will be happy to furnish further information if necessary.
Very truly yours, hYh,.
..... 7.. -
Aw&V A. N. Tschaeche Administrator-Licensing M/C 273, Ext. 2235
%)
hb enc.
O e
e O
.,)
S S'
' e+ N e 9
,M SW (P ge
,- # Se'W
- eg
=9
- gg $ *W4pr g"gf neg* g 3
s p
?
1.8 PAIL (S) IN STANDARD DRUM - GE MODEL BU-7 h
1.8.1 Package Description - Packaging (a)
Gene ral: Inner contaiment is a nominal 16-gallon drum closed by a gasketed-bolted lid, centered and supported within an outer 55-gallon drum by solid insulating media, and containing two or more steel pails which contain UO2 (see Figure 1. 8.1).
(b)
Gross Weight:
347 pounds, maximum (c)
Uranium oxide powder container: One or more closed containers,
- 11. 25" inside diameter fabricated of minimum 24-gauge steel, vertically stacked in each BU-7 unit.
3 (d)
BU-7 inner containment: A nominal 16-gallon, DOT Specification 17H drum constructed of 18-gauge steel, modified by the welded Q
attachment of a closure flange to accept a 3/16" thick steel lid which is gasketed for resistance to high temperature ~ as shown in Figure 1.8.1 and attached by twelve 5/16" minimum steci bolts. The inside dimensions of the inner containment drum are
- 13. 75" diameter by 27" high. The maximum hydrogen to uranium atomic ratio within the inner containment is 0.45.
9 (c)
BU-7 outer container: A nominal 55-gallon, DOT Specification 17H,18-gauge steel drum with nominal outer dimensions 22. 82" diameter by 36. 5" high.
(f)
Insulating material: The inner containment drum is centrally held within the outer container by, and the space between the inner SNM-54 70-1007
- 1. 8.1 Lic3n s No.
Docket No.
3,,,, g,,
- peg, Appeautx v.
"Y Amends Sur.(s) y,77 Am snd. No.
Do 3 I==m
.W--
and the outor containers is completely filled with, solid insulating media composed of fire-retardant phenolic foam as h
specified in Figure 1. 8.1.
Four 1/4" diameter holes near the top of the outer container, covered with waterproof tape, would permit steam to escape in the event free moisture in the insulating material were exposed to the heat from an accidental fire during transport.
1.8.2 Package Description - Contents (a)
Type and form of Uranium oxides enriched not more than material:
4% and of bulk density not greater than
- 10. 96 grams per cc.
(b)
Maximum quantity:
89 kilograms per package except that enrichments above 3. 00% shall be limited V
~ to twice the safe batch sizes given in para-graph 7. 3. 3, Appendix A to the application for License SNM-1097, 'Dockct 70-1113.
For mixtures of powder and pellets, the pellet batch size shall be used with such limitation beginn?ng at 2.7% and the maximum quantity shall be 90 kilograms per package.
- 1. 8. 3 Package Evaluation Ti.ere are no components of the packaging or its contents which are subject to chemical or galvanic reaction during normal transportation, SNM-54 Docket No.
70-1007-soci, go,
- 1. 8. 3 pop s
Licon., No.
spendix D _
Amend. No.
- Doe, M y 24, 1974 Amends Sect.(s)
'ew 1-78 h fh f f{ % "ghg f
fq ?,50W**D%Qf}QgQ y*
.QfQep,yypg qg
.g
~
The package cannot be open o inadvertently, uses no coolant and has no lifting or tiedown attachments.
,%/
- 1. 8. 3.1 Single Package - Normal. Transport Conditions (a)
The rmal: Packaging components, i.e., metal drums and pails, phenolic foam and gasket material are unaffecteel by temperature extremes in excess of 130* F as demonstrated by the fire test described later. There are no plastic components, therefore no loss of structural integrity at very low tempe ratures. Since uranium oxide is generated at operating temperatures far in excess of 130*F, there can be no further effect at this temper-ature.
(b)
Pressure: The outer container is pierced by four 1/4" diameter pressure relief holes so that no differential pressure will exist NJ at 0. 5 atmospheres. The inner containment is pressure tested to 7 psi after fabrication including flange installation.
(c)
Vibration: The metal-insulating media construction of the BU-7 precludes damage by vibration, and voids cannot be created in the insulation during normal transport.
(d)
Water spray and free drop: Metal drums are unaffected by water.
A 4-foot free drop produces no damage of consequence to the ship-ment of dry, low-enriched material.
(e)
Penetration: A 13-pound,1-1/4." diameter bar was dropped four l
70-1007 Sect.tio.
- 1. S. 3.1
- pog, SNM-54 Docket No.
l
/
Lic nsetio.
Appendix D Amend. No.
Date _ May 24. 1974 Amends Sect.(s)_ M**
I-79 M d. #23 L-
- Y*
'D
^
feet onto the midpoint of the side wall of the drum. The resulting k.Y.
indentation (about 1/8" deep) is of no effect on containment or overall spacing.
(f)
Compi e s sion:
The loaded container is capable of withstanding five times its weight with no change in spacing.
(g)
Summary and conclusions: The tests or assessments set forth above provide assurance that the powder or pellet contents are contained in the pails during normal transport and there is no reduction in effectiveness of the package system. Since the maximum quantity of fissile material in the paile is controlled to not more than 907 of the minimum critical mass by administrative control of loading, it is concluded that single package would be suberitical assuming water inleakage re-D sulting in optimum moderation of contents with full reflection.
It has been demonstrated, moreover, that there would be no water inleakage to the product during normal transport conditions.
- 1. 8. 3. 2 Single Package - Accident Evaluation (a)
Free drop: One Model BU-7 test unit loaded with two 5-gallon '
pails, each containing 100 pounds of iron chips, was dropped from a height of 30 feet, the top head striking a solid concrete pad at an angle. This is believed to be the most damaging attitude i
from the standpoint of retaining the two pails within the drum.
70-1007 Licon se No.
Docket No.
Sect. No.
- 1. 8. 3. 2 pop Appendix D
- M d. #23 May 24,1974 New 1-80 Amund. No.
Dora Amends Sect.(s) k mesma u_
yv'.L I
1'- -~_-'M
The drum, inner containment and pail lids remained intact and in place, and there was no loss of contents from product pails. Three 2.5-gallon pails occupy essentially the same volume as two 5-gallon pails and, with the maximum uranium oxide loading produce the same test results within the limits of reproducibility.
(b) Puncture: A 40" drop onto a 6" diameter mandrel resulted in no reduction of effective spacing nor was the drum penetrated.
(c) Thermal: Following the free drop and puncture tests, the package was subjected to a thermal test in an electric furnace at 1475'F for 30 minutes. There was no damage to the container of conse-quence to nuclear safety and the gasket of the inner containment remained far below the 400*F service temperature. The temper-U ature measurement method for the test unit is described in paragraph
- 1. 6. 7 on pages 1-54. 0,1-54.1,1-54. 2 and 1-55 of this Appendix D.
The test includes measurements on the outer and inner surfaces of the 3/16" thick lid which demonstrate that the maximum temperature ;
of the gasket in contact with the lid and flange is 200*F.
(d) Water immersion: The package which passed sequentially through the three tests above was immersed under at least three feet of water for not less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. No water leaked into the inner containment.
70-1007 s,c,, gjo,
- 1. 8. 3. 2 Pogs SNM-54 Docket flo.
Licens,tio.
Appendix D
- Amend tio.
M d. /!23 Date May 24, 1974 Amends $3ct.(s)
New-1-81 i
l l
t-
(c)
Summary and conclusions: The accident tests or assessments described above demonstrate that the package is adequate to N
retain the product contents and that it would remain suberitical assuming the contents changed from a cylindrical to a spherical form at the most reactive degree of moderation and closely reflected by water on all sides.
- 1. 8. 3. 3.
Array The criticality safety of the BU-7 package is demonstrated in GE Document No. NEDO-11277, "The General Electric Model BU-7 Uranium Shipping Container - Criticality Safety Analysis," which is attached to this application. The analysis results indicate that the BU-7 may be transported as Fissile Class I, authorization for which is therefore requested.
k;)
~ ~ ~ ~
1.8.4 Procedural Controls Inspections, loading and closure will be as described in paragraph
- 1. 5. 4 of this Appendix D.
l i
SNM-54 Docket No.
70-1007 Soc,, No.
- 1. 8. 4 Pc;.
Licens No.
Agendix D,
~
/
May 24, 1974 Amends Sect.(s)
Amend. No. __
Def:
h=
W'-
' __L
~
5/16" min. C.S. Cad. plated cover. bolts - 12 cach
.o 3/16" steel cover Q
M[ f
/ I Flat 400*F Rogers Corp. #3590 or
\\ ' -l Belmont Packing Co. #6734 fcited blue M
asbestos gasket or Garlock li4121
] ','
"((]
gasket or equivalent.
7
} f* i
. /,
7
.. s
.lgVs.igh t
' l/2"xl-1/2"x DETAIL A
- /16" C. S. Eq.
- F
.ngle flange I
Four 1/4" dia. holes equally spaced around circumference Outer cover lock ring, DOT 17H Drum cover, DOT 17H
.7
-- -. f)..
yl {.,~ N. \\))]N yf n-
,, m.
Top plug solid insulatio material, 3" thick min.g'gushioning
' NC 6.- -- = ---.------
f --
/'-il:- -
.. _ _...k l/.
/ /
I:-
6<r j
/
j
/
55-gallon d rum, 22. 5" ID, min. 18" z
ji:
(
Y j
/*
'p
- 2. 5-or 5-gallon uranium oxide pails 7
,/
/
with covers, 11. 25" ID, min. 24-T
)
gauge body sheet
/
, Solid insulation-cushioning material,
,/
7 ],
3-1/4" thirlj min. except for cover j,
g
/
//
clearance i
/[b A/7 l
,,,. Modified 16-gallon inner containment.
f l
'f
- 13. 75" ID, min.18-gauge, fabricateel
,' j'g
/
in accordance with 49 CFR 178.118-3
/
/
/
/
/./
/ /
- 5, - 6,
-7, -te st at 7 p s a.g for k
water tightness after fabrication Insulation, poured in place consisting of phenolic foam per USAEC Spec. SP-9; minimum density 8 lha/cu. ft. except top plug min. density 20 lbs/cu.ft.
I GE MODEL BU-7 CONTAINER I
Licens, No.
SNM - 54 Docket No.
70-1007 Sect. No.
Fie. 1. 8.1
- Peg, Appendix D
- d. F23 New 1-83 Amand. No.
Date May 24, 1974 Amends Sset.(s) j
.:a
s'
- _;p;..
a "TRAftSPORTATI0ii APPROVALS"
!E Docket I!o. 7/'f#/ f William O. Miller License Fee Management Branch ll..
Office of Administration
- ?.".J g
- :
MATERIALS TRANSPORTATI0tl APPROVAL CLASSIFICATI0tl
}.':..::.;
Applicant:
M t.
6 Fee Category ///3 h.
l Approval No:' 90/9 Application Dated:
3 />'/ /[0 + 3/D//o Received: 7// 9/4 h..
Applicant's Classification:
$..s The above application for amendment has been reviewed by the HMSS Transportation Branch, in accordance with Section 170.31, and is classifted as follows:
- 1. ' Amendments to Acorovals in Fee Cateaories'11A throuch 11E (a}
Major
...q..
(b) / Minor (c)
Administrative ME 2
Justification for reclassification:'
-[
u.=-
- . ~
3.
Theapplicationwasfiled(a) cursuant to written HRC
.:n-request and the amendment is being issued for the convenience of the Commission, or (b)
Other(Statereason):
=
h..
~~
m Signature:
/b[G_
ad-f Transportation Branch,' IMSS l
Date: '3fi'l/FO s
~
'..:].w".0.'d.Y ?;l
. 5
- 4.:
.0..-
^f
_ y._ _ _ _ __
n.~
v
- - -.. _ _