ML20125B552
| ML20125B552 | |
| Person / Time | |
|---|---|
| Site: | 07106003 |
| Issue date: | 12/04/1992 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20125B550 | List: |
| References | |
| NUDOCS 9212100053 | |
| Download: ML20125B552 (7) | |
Text
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li une roam sis U.S. NUCLEAR REGULATOQY COMMISSION I; so CERTIFICATE OF COMPLIANCE I.
ll lo cFR n FOR RADIOACTIVE MATERIALS PACKAGES I
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D REvtslON NUMBER
- c. PACKAGE IDENTIFICATION NUMBER d P.GE NUMBER e TOTAL NUMBER PAGES 1 a CEF TIFICATE NUMBER 6003 14 USA /6003/B( )F 1
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.. Tni e.na.c t.. issu.a io c rtity tnet in. p.cs.ama no coni.nt o cno.o in item s o.io.. m..t. tne.ppac.oi. rety st.no.ros t torin in Titie io. coo.
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of F.deral Regul.tions, P.n 71," Pack.ging nd Tr.nsport. tion of Radto.ctive M.teri.l."
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o Tnis c.,ta.c.i. oo.. not r.n... in. consignor from eomon.nc..iin any reau. rem.nt of ine regui tions of in. v.s oep.nment of Transport.i on or ott er Ii Rj
.ppac oi. r gui tory.g.nc.
. incivoing in. govemm.ni et any country inroven or intu, nicn in. poca.g..ai o. ir.nspon.o I!
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li U.S. Department of Energy Safety Analysis Report for M-130 shipping
[i h Division of Naval Reactors container dated December 30, 1968, as f
g Washington, DC 20585 supplemented.
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. ~71-6003 L:
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Tn. cena cat... cono, tion.i upon tuivanng in. r.quir m.nts et to cr A e.rt ri....opnc.or...no tn. cono<tions so.cir..a o.io.
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Ej (a)
Packaging Q
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(1) Model No.: M-130 F
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(2) Description d
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The Model No. M-130 shipping container is an upright cylinder 84 inches in H
I, diameter by 158 inches overall height.
The container walls consist of a y
5 finned 1-inch thick outer shell fabricated from either carbon steel, carbon h
[i steel with stainless steel clad, or solid stainless steel,10 inches of lead n
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shielding, and a 1-inch thick inner pressure vessel fabricated from carbon R
gl steel clad with stainless steel. The top of the container is covered with a H
shielded closure head which is bolted to the container and seals the pressure E;
vessel.
An access opening with a bolted shield plug is provided in the
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f; closure head for loading and unloading spejt fel.
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The pressure vessel has an inside diameter of 55 inches. The central region I;
contains a secondary heat exchanger (not used durir.g shipment) surrounded by Hi 1/2 inch thick carbon steel backup cylinder 29 inches in diameter. The l
annulus which remains between the backup cylinder and the pressure vessel
[i provides a space 13 inches wide and 130 inches high for spent fuel. The spent g
fuel is contained in the annulus by module holders designed for the particular g!
core to be shipped.
I' The container has external penetrations to the pressure vessel for steam and water relief lines and a fill and drain line (which are capped during 4
i shipment) and a pressure sensing line which remains open to a pressure gage during shipment. The container also has penetrations which do not open to the l
pressure vessel for secondary heat exchanger lines (which are capped during shipment) and a temperature sensing line.
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CONO(TIONs (continued) l i
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Page 2 - Certificate No. 6003 - Revision No.14 - Docket No. 71-6003 p
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- l. 5.(a) Packaging (cont'd)
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i (2) Description (cont'd) l f
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For LWBR spent fuel shipments, the heat exchanger and associated structures n
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i have been removed, external penetrations plugged and seal welded, and an I
i external shield and energy absorber added during. modifications.
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The container is supported on its transport vehicle by an "A" frame structure.
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Gross weight of the loaded container without its support structure is y
i approximately 228,000 pounds.
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ll (3) Drawings lj ry h itu e r,f' li The packaging is constructed in accordance with. General Electric g
i Drawing Nos. 247E209,* Sheet 1, Rev. R; Sheet 2, Rev. K; Sheet 3, Rev.
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For LWBR spent: fuel shipments, the container has been' modified in accordance i
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with Westinghouse. Electric Drawing 1176J48, Sheet 1 Rev.LG, Sheet 2 Rev. E and I
an external energy absorber added in accordance:with Westinghouse Electric l
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Drawing 152SE32, Revs A'.
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(b) Contents
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4, (1) Type and form of mate-talf "
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y ll, Irradiated fuel assemblies, activated" corrosion products and structural parts g!
containing up to 40 gallons of residual contaminated water. The fuel 1
gj assemblies and structural-parts are of the following types:
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(i)
S3W/S4W fuel subassemblies of core type 2. '
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ll (ii)
S5W fuel modules of core types 2 or 3..
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S5W corner fuel, modules of core types 2 or 3.
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(iv)
DIG fuel modules of core" types 1 er 2.
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DIG removable fuel assemblies of core types 1 or 2.
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SIC /S2C fuel modules with control rods.
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(vii)
SIC /S2C peripheral fuel modules.
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(viii)
S3G-3/3A fuel module with or~ without controi rods.
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(ix)
SAD cell.
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- 5. (b) Contents (cont'd)
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(1) Type ano form of material (cont'd) l E
g gj (x) S3G-3/3A irradiated thermocouples and thermocouple cases.
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llI (xi) S8G full size fuel cell with or without control roi i
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(xii) S8G partial size fuel cell with or without control rod.
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(xiii) S5W-4A recoverable irradiated fuel modules with control p
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rod.
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,m i-(xiv) S7G recoverable irradiated fuellcells'.j i
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(xv) 02W fuel cells $it$ control rods.
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l (xvi) NR-1 fuel. modules with or without control rods./
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s (xvii) ATC fuel mo'dules with or without control rods.'
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u A1W-3recoverableirradiatedfuelmodules.- Fuel mcdules that use f
h (xviii) gj control rods shall have, control rods inserted.
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gj t-I; (2) Maximum quantity of material per. package.
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1j (i) 52 fuel assemblies ~as described in 5'(b)(1)(i).
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(ii) 12 fuel a.csemblies-as described in~5(b)(1){ii) or 91 fuel e
i assemblies as~-described in 5(b)(1)(ii). ar.d 4 fuel assemblies r
I; as described in 5(b)(1)(iii).l
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(iii) 6 fuel as'semblies as described in 5(b)(l')(iv) and
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4 fuel assemblies as described in 5(b)(1)(v)J t
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(iv) 9 fuel assemblies as described in 5(b)(1)(vi) and
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l 8 fuel assemblies as described in15(b)(1)(vii).
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(v) 10 fuel assemblies as described in 5(b)(1)(viii).
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q (vi) 9 fuel assemblies as described in 5(b)(1)(viii) and E
d one fuel assembly as described in 5(b)(1)(ix).
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l (vii) 9 fuel assemblies as describad in 5(b)(1)(viii) and
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[j cne structure as described in 5(b)(1)(x).
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CONotTIONs (continued)
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'! Page 4 - Certificate No. 6003 - Revision No.14 - Docket No. 71-6003 g
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l IL 5. (b) (2) Contents (cont'd)
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(viii) 4 fuel cells as described in 5(b)(1)(xi); or
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2 fuel cells as described in 5(b)(1)(xi) and
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pl 2 fuel cells as described in 5(b)(1)(xii).
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(ix) 6 fuel assemblies as described in 5(b)(1)(xiii).
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f (x) 8 fuel cells as described in 5(b)(1)(xiv).
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(xi) 4 fuel cells as described in 5(b)(1)(xv) plus tl 2 corner fuel cells or 1 RFA fuel cell.
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il (xii) 4 fuel modules as.describ'ed dn !5(bl(1)(xvi).
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(xiii) 10 fuel modulesfas described in 5(b)(1)(xvii).,
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ij (xiv)
For contents' described in 5(b)(1)(xviii), 6 fuel' modules, or I
t lj 8 fuel modules, as described in supplement dated March 30, 1992, i
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l (3) Shipments sbll bbfurther limited by thermal requirements as follows:
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gi (i) Shipment of contants specified in 5(b)(1)(iv) and 5(b)(1)(v) and limited 0
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in 5(b)(2)(iii) shall be made~ no earlier than 75 devs I.
after shutdown and shall haven l decay heat load rnt to exceed I
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i 33,500. Btu /hr per ghipment.
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7 ll (ii) Shipme'n't of contents specified in 5(b)(1)(vi) and 5(b)(1)(vii) and
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limited in S(b)'(2)(iv).shallybeaade in a -stainless steel M-130 t,
g container and shall have 'a.decayiheat load not to exceed 18,960 Btu /hr L
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per shipment.
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f (iii) Shipmentif'contentsspecified1F5(b)(1)(viii)/5(b)(1)(ix)and I
5(b)(1)(x) and limited in 5(b)(2)(v), 5(b)(2)(vi) and 5(b)(2)(vii) shall r
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be made at a time after shutdown as determined from Bettis Atomic Power I:
l Laboratory repcrt WAPD-0F(PP)S-4401 dated June 29, 1979 and shall have a 1
Nli decay heat load not'to exceed ~ 28,620 Btu /hr for the shipboard core and I
30,000 Btu /hr for the prototype core.
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(iv)
Shipment of contents specif ed in 5(b)(1)(!), 5(b)(1)(ii)
L: l shall be made no earlier than 72 days after shutdown and shall t.
i have a decay heat load not to exceed 33,500 Btu /hr per shipment.
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(v)
Shipment of contents specifie>l in 5(b)(1)(xi) or 5(b)(1)(xii)
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l as limited by 5(b)(2)(vii) s'sall have a fully loaded container y
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heat load not to exceed 15.400 Btu /hr per shipment, r ;
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(vi)
Shipment of contents specified in 5(b)(1)(xiii) and limited in I
N 5(b)(2)(ix) shall have a heat load not to exceed 23,800 ll
[i Btu /hr and shall be made no earlier than 92 days after shutdown.
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p 1l CONolTlONs (continued) tk 4p Page 5 - Certificate No. 6003 - Revision No. 14 - Docket No. 71-6003 Qj q j
- 5. (b) (3) Contents (cont'd)
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l (vii)
Shipment of contents specified in 5(b)(1)(xiv) and limited in 5(b)(2)(x) shall have a heat load not to exceed 22,400 Btu /hr a
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and shall be made no earlier than 122 days after shutdown.
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(viii) Shipment of contents specified in 5(b)(1)(xv) and limited in I
q 5(b)(2)(xi) shall have a heat load not to exceed 19,100 Btu /hr p'l 1
and shall be made no ear'..er than 420 days after shutdown.
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(ix) Shipment of contents specified in 5(b)(1)(xvi) and limited in I
5(b)(2)(xii) shall have a heat load not to exceed 6,000 Btu /hr I
lj and shall be made no earlier, than 50 days after shutdown.
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d (x)
Shipment of contcats specified in 5(b)(1)(xvii) and limited in g
1 5(b)(2)(xiii)lshall have a heat load not to exceed 27,400 Btu /hr H
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and shall be made no earlier tien 195 days after shutdown.
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j (xi) Shipment'of contents specified <
5(b)(1)(xviii) and limited in il 5(b)(2)(xiv) shall have a heat load not to exceed 43,800 BTU /hr and
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shall be made no earlier than 400 days after shutdown.
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1 (c) Fissile Class
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Maximum number of packages per shipment: u One
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For shipments involving the contents specified in 5(b)(1)(ii) or 5(b)(1)(iii) h the Model No. M-130 package shall be inspected to verify that boron poison r;
plates are in the module holders.
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7.
For shipments involving the contents specified in 5(b)(1)(viii), 5(b)(1)(ix) or li 5(b)(1)(x) the thermocouples and thermocouple cases if included er the vacart
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module holder shall be. located in the mid-position of either cage and module g
holder assembly.
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Shipments shall be made i the dry condition, except for residual water as l'
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limited in 5(b)(1), 5(b)(3)(v), and'5(b)(3)(vii).
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9.
Container number three (M-130-3) has been modified by adding two 4-inch thick I
by 8-inch wide steel plates welded between fins 25 and 50 and between fins 110 1;
i and 135 at approximately 14.75 inches from the bottom of the container.
The C
1 cooling fins in this localized area are removed to permit attachment of i:
j the plate directly to the outer shell of the container.
l i 10.
Container number four (M-130-4) has been modified by adding a 2-inch thick l,
9 by 4-inch wide sisel plate welded between fins 32 and 49 at approximately R.
0 18.4 inches from the bottom of the container.
The cooling fins in this E
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loceltzed area removed to permit attachment of the plate directly to the l
q outer shell of the container.
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4 11. Containers M-130-3, M-130-4, M-130-6, and M-130-7 may be used for the contents t
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specified in 5(b)(1)(viii) and 5(b)(1)(x) only.
Containers M-130-10 and M-130-15 4l
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may be used for the contents specified in 5(b)(1)(viii), 5(b)(1)(x) and l
5(b)(1)(xviii) only.
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CONDmONS (continued)
I lPage6-CertificateNo.6003-RevisionNo.14-DocketNo. 71-6003 g
I l 12. Container M-130-11 may be used for NP-1 shipments only.
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! 13.
For shipments involving the contents specified in 5(b)(1)(xvii) which do not E
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contain a full com;,lement of fuel modules (i.e. one position is occupied by r
l either two flux thimbles or a vacant fuel module holder with pocket shield l
l plug), that position shall be located in the middle 'odule holder of either
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j half of the cage assembly.
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14.
Expiration date: December 31, 1997.
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REFERENCES I
i Safety analysis report for M-130 shipping container,, MAO-E8-703 dated Decembt.r 30, r
! '968.
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l s v l Supplements: Naval Reactors $ letters A#2256 dated Februa'Ey 24, 1969 and G#1931 dated I
j March 3, 1969; General Electric Company letter 0NP-74520-526 dated April 3, 1972;
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i Naval Reactors letter G#3207 dated April 27, 1972; General Electric Company letter y
ONP-74520-528 dated April-28, 1972; Naval Reactors letter G#3250 dated June 6,1972; ly General Electric Company letters _0NP-74570-635 dated October 25,-1972; ONP-74570-654 T
. dated December 6, 1972;: 0NP-14570-666 dated December 12, 1972; ONP-74570-682 dated i
l January 12,19H;ONP-74570-698~datedJanuary 31, 1973: 0NP-74570-687 dated February 6, I
j 1973; ONP-74390-65 dated March 26,-:1973; DLGN-85570-854 dated September 24, 1973;
(
j DLGN-85570-901 dated January 10, 1974; Naval Reactors letter G#4061 dated Janaury 29, g
- l 1974; General Electric Company letters DLGN-85570-924Jdated February 15, 1974; DLGN-g
! 85570-923 ated March-6, 1974; DLGN-85570-969 dated May 24,1G; Naval Reactors i
i letter G#4991 dated November:25,1975;' General Electric Company letters ONP-74340-JTT-73 I
l dated December 17,1975; CGN-8557C~1145 dated-September 9,1576; CGN-85570-1146 dated E
l September 10, 1976; CGN-85570-1148 dated September;14,.1976; Bettis Atomic Power f
l j
- Laboratory letter WAPD-R(K)-1378 dated August ~30, 1976;:Wi$PD-0P(PP)S-4401 dated June 29, g
4 l
! 1979; Naval Reactors letters G#6197 dated July 13, ID); G#7136 dated March 17, 1982; I
l
! Naval Reactors letter G#7022 dated July 14, 1981. and WAPD-LD-(CES)SE-181 dated L
4 j
l September, 1981; WAPD-LP(CES)SE-96 dated Februarn 1982, WAPD-LP-(CES)SE-170 dated July
[
' 1981; Naval Reactors letter Gd7160 dated May lo UB2; Naval Reactors letter G#7582
[
- dated September 7,1983; Naval Reactors letter GdC87-5692 cated September 2,1987; Naval p
i Reactors letter G#C87-5689 dated September 23,,1987; ~ and Naval Reactors letters G#C87-t-
! 8008 dated January 19, G#C88-5931 dated May 12, and G#C88-5961 dated July 25, 1988, t
l Haval Reactors letter G#C89-2863 dated August 11, 1989; Naval Reactor letter G#C89-2825 t
-dated March 29, 1989; Naval Reactors letter G#C92-03392 dated March 30, 1992; and Naval E
Reactors letter G#92-03729 dated October 20, 1992.
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q FOR THE U.S. NUCLEAR REGULATORY COMMISSION 1
i
[
J Charles E. MacDonald, Chief
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q Transportation Branch g
Division of Safeguards and t
i Transportation, NMSS I
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DEC 4 1992
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Date:
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D. C. 20555 g
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APPROVAL RECORD i
.Model No. M-130 i
Certificate of Compliance No. 6003 Revision No. 14 By application dated October 20, 1992, the Department of Energy, requested I
renewal of Certificate of Compliance No. 6003.
Naval Reactors stated that there had been no operational experience or container modification which would preclude continued use of the package.
The application also included changes to the certificate.
The Certificate of Compliance has been renewed for a five-year terr, which expires on December 31, 1997. No changes have been made to the certificate.
l The changes to the certificate will be considered as a separate amendment.
i 1-Charles E. MacDonald, Chief Transportation Branch Division of Safeguards and Transportation, NMSS l
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Date:
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