ML20211G181
ML20211G181 | |
Person / Time | |
---|---|
Site: | 07109852 |
Issue date: | 10/28/1986 |
From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
To: | |
Shared Package | |
ML20211G159 | List: |
References | |
NUDOCS 8611030235 | |
Download: ML20211G181 (4) | |
Text
..-----------..............-......--.....a- .._...... f I U.S. NUCLEAR REGULATORY COMMISSION I nec roam sie I is=> CERTIFICATE CF C8MPLIANCE l -io csa Fi FOR RADIOACTIVE MATERIALS PACKA'iES l I te REvistoN NUMSER C PACKAGE iOENYifICATION NUMBER d PAGE NUMBER e TOTAt NUMBER PAGES iecEnts'EU' UMBER 3 USA /9852/B(.)F 1 3 l
l l Pat 4 Mets f I a. Tnes certificate es sesued to certif y tnat tne packaging and contents described in item 5 below, meets tne applicable safety standards set forta in Title 10 Code l l of Federai Regulat.ons. Part 11. " Packaging and Transportation of Radioactive Materiai." l l 3. in,s cenivicate does noi r.i.e.e in. cons.gnor erom compnance ..in any reau.remeni or ine reguiations or in. u s. oopanment os Transponai.on or otner l appi.cabie reguistory agencies. inciuding ine governmeni os any country enrouan or enia wnica ine package wiii be transported. l I 5 I N I I
, a 17.sgarigrysgoN rm eAs s o,4 sArcrv ANAtysis,afgt,o,, , v,gt Pgegi,cgogae,S' " h I b l U.S. Department of Energy Oak Ridge Y-12 Plant Reports No. Y/DD-244, !
i Washington, DC 20545 January 1978; and No. Y/LA-810, Rev.1, p I June 1981, as supplemented. lu l
i e oocxtTNuusta 71-9852 I I a coNoivioNs I in,s cen,v.cate is cond.i.onai upon vun.u.ng ine requirernents of 10 CFR Part 71, as apphcable, and the conditions specified below.
I I 5 l
l (a) Packaging l s W (1) Model No. DT-14 i i
(2) Description l 8
Packaging for uranium enriched in the U-235 isotope. The steel y containment vessel has a 6-1/2-inch ID and 15-1/2-inch deep cavity. ll Positive closure is provided by a breech lock closure or a flanged and il bolted arrangement. The closures are sealed by Neoprene 0-rings. The E!
} containment vessel is centered and supported by cane fiberboard within an 18-gauge 00T Specification 17H3 30-gallon drum. The cane fiberboard lg insulation has a minimum 14 lb/ft density. Plywood discs, 1/4-inch p thick are located at the ends of the container. The overall container pi size is 18-inches diameter by 30-inches high. The package gross weight R is 210 pounds. g'l (3) Drawings l 5:
The packaging is constructed in accordance with the drawings shown in >
Figures 1, 2, and 3 of Oak Ridge Y-12 Plant Report No. Y/DD-244, h!
January 1978. h E.
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k 5:
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k e
R es1102o2ss esm2e ADOCK 0710 2 l
PDR C
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I y ' ' ' ".' "E CONOmONS (continued)
U; NUG.ru rdGUL ATcaY COMwssicN g I . -
p i
~
I
! Page 2 - Certificate No. 9852 - Revision No. 3 - Docket No. 71-9852 l l
l l
l l
l l 5.- (b) Contents l l (1) Type and form of material !
I I
I Uranium as metals, alloys, compounds, mixtures, or solutions enriched to l l any degree in the U-235 isotope. The U-233 isotope not to exceed 1.0 I i w/o of the U-235. l l I i (2) Maximum quantity of material per package g I I I Not to exceed 10 watts i Maximum content weight I l within the containmegt;g -vessel'notnternal to' exceed ,'d30payfeat.
kg, the U-235 density not I i
to exceed 18.76-<f/cm , and contents are further restricted as follows: I
! % Maximum U-235 Mass (k l Sol [d:MetalsorAlloys g OtheNr U-235 Bearing i V/S*& 0.17-inch V/S*40.08-inch V/S*>30.02-inch /J Material l l ys v .s .-; y y -
I i (i 10.0 ) 10.0 M ' 5.0 / (v ' ,- 0.30 I i (11 14.5 -
11.4 s X /<--- / 5? '- 0.45
" -f \ Y ~'
^
i (iii 18.0 ---
'/ (0.58 l l (iv) --- ---
e --- -._ ,
'/~ ~0.70 g I (v) --- - ---
,.< 1,0.75 i I --- - ---
ruf---
- s, ' . ~0.85 E l (v(vi) ii) ---
i t---:
.51.00 l l <
E i *V/S is the volume to surface area ratio.- -
t a i N I
i (c) Fissile Class II'and III N h
l For contents described Minimum Transport Index- Maximum No. of in 5(b)(1) and limited to be shown on label.for packages per shipment l l s i in: Fissile Class II: for Fissile Class III i i N 4 5(b)(2)(i) 0.1 150 i i
1 5(b)(2)(ii) 0.3 150 i l 5(b)(2)(iii) 0.6 150 l
l 5(b)(2)(iv) 1.0 100 g q 5(b)(2)(v) 1.4 70 g
( 5(b)(2)(vi) 2.3 40 W i 5(b)(2)(vii) 5.0 20 h I H l 6. Up to 120 grams of packaging material may be interstitially used for metal pieces; l l however, when greater packaging material masses are used, the restrictions in g g 5(b)(2) for other U-235 bearing material shall be used. g i F I 7. Uranium hydrides with densities greater than 4.55 g/cm3 are not pennitted. W l i I >\
i H i
i I
4 v-v - - - -w - - -w---w- ----- -- --- -- ----- - - -
m------------------------_---- -----___ -________-,___
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-conolisons tcontinued) Mmm ll l .
p I g
! Page 3 - Certificate No. 9852 - Revision No. 3 - Docket No. 71-9852 '
i l
l l l 8. Metals or alloys in solid form must be held within the containment cavity in metal I i cans with nominal wall thickness of 0.254-mm (10 mils). l l u I 9. Powders must be packaged in a water-tight polyethylene bottle with a 1-ns: minimum i I wall thickness. Before loading, the lid on the polyethylene bottle must be i I
visibly inspected to ensure the gasket is present and functional. Each loaded I polyethylene bottle must be inverted and hand shaken; a smear must be taken and l
i checked with an alpha detector to ensure non-leakage of the powder. If all of l n
I these conditions are satisfied, the lid must be sealed and closed using pressure y I sensitive tape. E Solutions must be packaged.in n Q R Foi. m minimun: wall thickness. gBefo{a , Water-tight' polyethylene bottle with a 1-mmril load 10.
l i
l be visibly inspected to. endure the gasket is present endsfunctional. Each filled l g
I polyethylene bottle must'be inverted and observed for 5 ininutes. If no leakage is g i visible, a smear mustube taken and checked with an alpha' detector to ensure t I non-leakage of the. solution. If all of these conditions"ari', satisfied, the lid N
^
I must be sealed usincf pre'ssure-sensitive tape. AQ N l
'%\.
- 11. Containment vessels must beleak testedito)1x107r;atm-cm
.. / kf 3 /sec'at ""'
standard test h i g q conditions of ANSI.N14.5 after/the' third ~ usage,'iand within 1 year from the last g f inspection date thereafter, priortto use.:e._. ' E
. .- E-l 12. The package authorized by this ec'rtificate.is hereby-approvedsfor use under the N q
I general license provisions of 10 CFR,571212'; .
f E
i 13. Expiration date: October 31,~1991.. g i E 4 ' REFERENCES E 4
l Oak Ridge Y-12 Plant Reports No. Y/DD-244, January 1978, and No. Y/LA-810, Rev. 1, lg g June 1981; and D0E, Oak Ridge Operations Office letter dated August 26, 1982.
i R 4 FOR THE U.S. NUCLEAR REGULATORY COMMISSION E l
4 q
JNX 611 Charles E. MacDonald, Chief E
g l
) Transportation Certification Branch 4 Division of Fuel Cycle and (R Material Safety, NMSS E Date: OCT 28 M l
4 N
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-' [#f "N4, UNITED STATES
- 4 _~ NUCLEAR REGULATORY COMMISSION j
. WASHINGTON, D. C. 20555 e
Transportation Certification Branch Aaproval Record Model No. lT-14 Shipping Package Docket No. 71-9852 By application dated October 16, 1986, the Department of Energy requested renewal of Certificate of Compliance No. 9852. No changes have been requested or made to the package since approval of the original application dated August 2, 1978, as supplemented.
The staff concludes that the statements of the original application, as supplemented, satisfy the requirement for renewal of the certificate of compliance.
Due to the limitations on the fabrication of additional packagings, as stated in 10 CFR 971.13 Condition 11 regarding leak test requirements for new packages has been deleted and the balance of the original conditions renumbered accordingly.
Charles E. NacDonald, Chief
) Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS Date: MT28E