ML20203N855
| ML20203N855 | |
| Person / Time | |
|---|---|
| Site: | 07109103 |
| Issue date: | 04/29/1986 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20203N853 | List: |
| References | |
| NUDOCS 8605060133 | |
| Download: ML20203N855 (5) | |
Text
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[O Mac Fone cia U.S. NUCLEA? RE!ULATORY COMMISSl!N
- u CERTIFICATE CF CCMPLlANCE
'o cra n FOR RADIOACTIVE MATERIALS PACKA2ES d
I 1 s CERTIFICATE NUMBER D REvtSaON NUMBER C PACMAGE IDENTIFICATeON NUMBE R d PAGE NUMBER e TOTAL NUMBtX P&caLS g
g 9103 5
USA /9103/B( )F 1
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l 2 PREAMBLE i
a This certif.cate s issued to certify that the packaging and contents described en item $ below, meets the applicable safety standards set forth in Title 10. Code U
l of Federal Regula. ions. Part 71. ~ Packaging and Transportateon of Radioactive Material"
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l b Thes certihcate does not reheve the consignor from compliance with any requirement of the regulationt of the U S Department of Transportation of other h
l applicable regulatory agencies, including the government of any country through or ento wfuch the package will be transported I
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V 3 THl3 CERT 6FICATE IS ISSUED ON THE BASIS OF A SAF ETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATeON a ISSUED TO f%eme amr Ad*essi b TITLE ANO IDENTIFICATION OF Rf PORT OR APPLICATION i
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g Nuclear Assurance Corporation NL Industries, Inc. application dated
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t 5720 Peachtree Parkway September 7,1977, as supplemented.
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i Norcross, GA 30042 I;
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71-9103 c 00Cetti NUMetR
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a CONOtTIONS U
This certificate is conditio ul upon fulfilling the requerements of 10 CF R Part 71. as applicable, and the conditions spocitied be6ow f
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(a)
Packaging I
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(1) Model No.
NLI-6502 4
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(2)
Description I
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i A steel, lead, and depleted uraniun shielded shipping cask.
Its I
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overall dinensions are 33.5 inches in diameter by 130 inches long. The f
g loaded cask weighs about 45,300 pounds.
The wall thickness of the g
cavity and outer shell is 1/2 inch.
The wall thickness of the inner k.
q shell is 1 inch.
The nain body of the cask is divided into two 4
regions.
The inner region, which is a maximun of 5-3/4 inches thick, k
I contains uranium shielding angles at the four corners, the remainder E
f ll of the shielding region is filled with chemical grade lead. The outer (sacrificial) 3-inch thick region is filled with lower melting point p
gl 6% antimonial lead. The cask contains six fusible " weep holes" p
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around the cask at each end.
This sacrificial region also contains 10
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i layers of 0.013-in terne plate. The main body of the cask is equipped E
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with two lids, one on each end.
The two lids are similar in construction l
each being 24.5 inches in diameter and extending 5 inches into the f
I cask recess.
The lids, like the main cask body, contain an outer p
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y sacrifical region (2" thick containing ten 0.018-in terne discs with pi l
l the remaining volume filled with 6% antimonial lead) and an inner h i f>
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regien (4-5/3" thick) containing chemical grade lead.
The sacrificial I
region in each lid is fitted with exterior weep holes, I
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I 8605060133 860429 PDR ADOCK 0710 3
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l CONDITIONS (contonued) 1 i
I Page 2 - Certificate No. 9103 - Revision No. 5 - Docket No. 71-9103 h
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I 5.
(a)
(2) Description (Cont'd) p i
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One lid contains a 1/2-inch drain line and valve.
The other lid 4
I contains two,1/2-inch lines for a pressure relief valve and the other lE l
line is capped.
ll The fuel rods are contained within an approximate ll-1/2-inch square gf H
by 128-1/2-inch long openwork basket constructed of stainless steel j
angle and strap.
The basket has a full-length lid along one side, for h
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horizontal loading, and a lid on one end for vertical unloading.
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vertical, stainless steel-clad Boral poison plate divides the basket f
qi into two, full-length halves, and two partial poison plates are
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incorporated into the sides of the basket.
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Nl A metal screen enclosure surrounds the package in transport to serve i
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as a sun-shade and prevent inadvertent use of structural parts of the I
f package,:other than the tie-down devices for securing the package to q'
the vehicle during transport.
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The cask rests horizontally on its integral supporting structure at each en'd, and the supporting structure is holted to a separate structure i
f attached to the deck of the special trailer provided for its use.
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(3) Drawings v1
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The Model No. NLI-6502 shipping package is constructed in accordance National Lead Company Drawing' Nos.:
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5797-P, Rev.1 Details-Safety Shield i
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5798-), Rev.1 Cask Tie-Down dj 650*-01, Rev. 5 Basket Details l
Ri 650J-03, Rev. 4 Latch and Basket Details f
6502 04, Rev. 3 Basket and Lid Assembly p
g 6502-07, Rev. 5 Cask gj 6502-08, Rev. A Lid Assembly and Details E!
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pwammmmmmmmmmmmmmmmmmmmmmmmmmmmmm==mmmmmmmmmmmmmmmmmmmmy l
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CONotilONS (conhnued)
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I Pace 3 - Certificate No. 9103 - Revision No. 5 - Docket No. 71-9103 l
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g 5.
(b) Contents
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I (1) Type and fonn of material l
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Irradiated aluminun-uraniun alloy fuel rods enriched in the U-235 l!
isotope with the following specifications:
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NRU NRX and tiiscellaneous*
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8 fiaximum U-235 content per rod 495 550 D
l prior to irradiation, g (1.8 per cm)
(4.0 per cm) g 4l flininun average turnup,' %
45 45 g
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lj Minimum decay time, days 120 120 nl
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- May be.a mixture of NRX fuel rods, NRX fuel rod element sections 5!
in a can; bundles of SLOUP0KE fuel elements in a can and sections f
of fast' neutron _ fuel tubes and plugs in a can.
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(2) fiaximum' quantity of naterial per packa'ge The maximum decay heat load per package not to exceed 14,000 Btu /hr; I
l and 9.9 kg U-235 in the form of NRU fuel rods or 15.4 kg U-235 in the W
form of NRX fuel rods or miscellaneous SLOUP0KE elements, fast neutron n!
tubes and plugs.
W (c) Fissile Class III dg!'
flaximum number of packages s!
per shipment One(1)
A Hi 6.
Poison inspection and loading of fuel rods must be sub.iect to the following conditions:
h (a)
Poison inspection and loading of fuel rods in accordance with Section VII-g!
B.2.(B.)(3.) (pp. VII-10 thru VII-ll) of the application, and N
4.
(b) The package nust not be loaded with a mass which exceeds 75% of critical, l
detemined by extracolation to zero reciprocal count rate.
l 7.
Dunmy fuel rods consisting of empty aluninun pipes must be installed in every pl q
fuel rod position not occupied with fuel.
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8.
The cask cavity must be dry (no free water) when delivered to a carrier for E'
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t rans oort.
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l CONDITIONS (continued)
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Page 4 - Certificate No. 9103 - Revision No. 5 - Docket No. 71-9103 1
II I
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9.
The cavity pressure relief valve rust be tested at set pressure every twelve 1
(12) months.
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10.
Additional contents in accordance with Nuclear Assurance Corporation application l
dated February 17, 1982.
Fuel rods rust be contained within a fuel basket to nininize damage to the rods during nomal conditions of transport.
4; 11.
Prior to each shipment, the Buna-N rubber lid gasket (s) (if opened) nust be 4;
i nspected.
These gaskets must be replaced if inspection shows any defects or l
replace both gaskets every twelve (12) nonths, whichever occurs first. Cavi ty li j
lines rust be sealed with appropriate sealant applied to threads of pipe caps or g
plugs.
lEl 12.
The cask contents must be so limited under nomal' conditions of transport that h
lHj the dose rate will not ' exceed 10 arem/hr at one meter from the external surface b
of the cask.
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13.
The package authorized by this certificate is hereby approved for use under the hl general license provisions of 10 CFR 671.12.
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i-K 14.
Expiration date: llay 31, 1988.
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' REFERENCES fl d
NL Industries, Inc. applicatio.n dated ' September 7,1977.
f Supplements dated: fiay 1,1978; and December 16, 1935.
f FOR THE U.S. NUCLEAR REGULATORY C0f titISS10N t
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ll MfAw U n
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Charles E. fiacDonald, Chief Transportation Certification Branch
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Division of Fuel Cycle and M
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Material Safety, fitSS hl N:
dl Date:
APR 2 91986 il
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UNITED STATES 8
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e NUCLEAR REGULATORY COMMISSION y
WASHWGTON D. C. 20555
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Transportation Certification Branch Approval Record Model No. NLI-6502 Package Docket No. 71-9103 By application dated July 18, 1985, as supplemented December 16, 1985, Nuclear Assurance Corporation requested additional contents in the Model No. NLI-6502 package.
The applicant requested that the contents of the fiodel No. NLI-6502 package (cask) be revised to pemit shipment of miscellaneous fuel rods totaling no more than 15.4 kg U-235 (the maximun quantity currently pemitted) but can have denser loadings:
4.0 gm U-235/cm versus the current 2.0 gm U-235/cm for the NRX fuel.
The applicant established the subcriticality of the requested shipment by performing KENO-IV, 27 group calculations taking into account the fol lowing:
1.
Included close reflection of the basket by depleted uranium.
2.
Actual boral sheet lengths in cask cavity.
3.
Reduced B-10 number density by 25% to account for possible non-honogenities and clunping.
The maximum calculated k
's we re :
eff Case Q
l.
HRX fuel (normal) 0.895 2.
NRX fuel (75% B-10, nomal) 0.905 3.
NPX fuel (nax. vol.)
0.852 4.
iiisc. fuel (nomal) 0.838 5.
Misc. fuel (max. vol.)
0.782 The staff has reviewed the KENO-IV inputs and outputs and found them to be accurate and to represent the cases intended.
All masses per region have been validated.
Based on our review, the statements and representations contained in the application, we find the revised contents for the Model No. NLI-6502 cask meets the requirements of 10 CFR Part 71.
=
Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS APR 2 91986 Date:
_