ML19324A983
| ML19324A983 | |
| Person / Time | |
|---|---|
| Site: | 07106003 |
| Issue date: | 10/19/1989 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19324A981 | List: |
| References | |
| NUDOCS 8910300105 | |
| Download: ML19324A983 (7) | |
Text
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l U.a. NUCtaAR Re0ULATORY N"**"
1. m.=m m CERTIFICATE CF COMPUANCE I
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a wa ti-Fon RActoAcTtyt asATEntALS PACKAGES
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.pon.te or other l
mory new,ince e.no v.
i e may country virouen or iaio **cn = p.ca.e..m t. tr.a. con.d.
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l U.S. Department of Energy Safety Analysis Report for M-130 shipping l
Division of Naval Reactors container dated December 30, 1968, as l
i l Washington, DC 20585 supplemented.
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(a) Peckaging l
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(1) Mode 1, Joe : ' x130,
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(2) Description Q
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J4~an upright 6 4nder 84 inches I
The Model No. M 130 shippin,g container i
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in" diameter by 13851hchesJveral lhel
- t. 3The containar walls consist l
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ofia finnedlleinch"thiclC) stainless [steE1? clad,'ro' outer sheD.$febficated.from wither carbon I
l steel carbotiistes1?sith r solid' stainless I
steel},103nches of leadishjelding S l
vessel (fab'ricatekfrom carbon'steek 'an'd a :1'-irich thiciDinner pressure i
I clad with stainless steel). The l
top of)the container js2covere' !withia shielded clos 0re head which is l
~d I
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boltddgto the chntainer-end' seals"thelpressure vessel? An access l
l openi with a"b'ol'te shje'1d TugNisproiidedini$efclosureheadfor
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I loadin (a unloadin " spent e
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The pressure' vessel has an inside diameter off65' inches. The central i
I region contafrp' a secondary heat exchanger (not used during shipment) l I
surrounded by a 1/2-inch, thick caraon Jteel backu ) cylirider 29 inches l
I in diameter.
The (nnults +h4&h reiss'instbetween tie backup cylinder I
l and the pressure vessel"p'rovfdes a" space 13 inches wide and 130 inches l
l high for spent fuel. The spent fuel is contained in the annulus by l
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module holders designed for the particular core to be shipped, i
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I The container has external penetrations to the pressure vessel for l
I steam and water relief lines and a fill and drain line (which are I
l capped during shipment) and a pressure sensing line which remains open I
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l to a pressure gage during shipment. The container also has penetrations i
I which do not open to the pressure vessel for secondary heat exchanger i
I lines (which are capped during shipment) and a temperature sensing i
I line.
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8910300105 891019 I
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Page 2 - Certificate No. 6003 - Revision No. 11 - Docket No. 71-6003 I
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I 5.
(a) Packaging (cont'd) l (2) Description (cont'd).
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For LWBR spent fuel shipments, the heat exchanger and associated I
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structures have been removed, external penetrations plugged and seal
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welded, and an external shield and energy absorber added during l
modifications.
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The container is suppo eHnitstransportvehiclebyan"A" frame 1
I structure. Gross wei ttftthe hn! d po(u/cAntainerwithoutitssupport l
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structureisapqx,$g Iy228,000 nds/[
a Drawings &%
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L(3) l The packegihg is constructed in accordance with Ge(ne)r.a1 Electric I
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Drawing.Nos.w247E209, Sheet 1, Rev. R; Sheet 2,.RevfKt Sheet 3. Rev.
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T; Sheet':4, Rev.?tl Sheet 5of5,Rev.Fand-247E228,)tev.F.
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hlsments,-theco
'a s been ified in J
For L R spent u l
accof dance with Weslinglouse'Elett'ric rewing 1176J48,'$heet 1 Rev. G.
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I Sheet 2 Rev. E and an'. externa 1' energy \\ absorber added inaccordance I
I with'WestinghouseIle6tricDrawinL1525E32,;Rev.A.
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l (b) Contents g Type and forstofMteriald g( ; L 5 3 p;..,
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Irradiated fuel as% A 1;.
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Gy semb11es',7 activated: corrosion produ' cts and structural I
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parts containing4 up to.40,ga11ons 'of residual contaminated water.
The l
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l fuelassembliesandstructura}lpartsareofthefollowingtypes:
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(1)
S3W/S4W fuel sube:semblies of core \\ype 2.
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l (ii)
SSW fuel modules of core type.s 2 or '3.
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(iii)
S5W corner fuel ' modules of core types 2 or 3.
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(iv)
DIG fuel modules of core types 1 or 2.
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(v)
DIG removable fuel assemblies of core types 1 or 2.
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(vi)
SIC /S2C fuel modules with control rods.
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I (vii)
SIC /S2C peripheral fuel modules.
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I (viii)
S3G-3/3A fuel module with or without control rods.
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(ix)
SAD cell.
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l' Page 3'- Certificate No. 6003 - Revision No. 11 - Docket No. 71 6003 5.;
(b)' Contents.(cont'd) l
-(1) Type and form of material (cont'd)
-(x) S3G-3/3A irradiated thermocouples and thermocouple cases.
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(xi) S8G full size fuel cell with or without control rod.
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l (xii) 58G partial size fuel cell with or without control rod.
(xiii) SSW-4A recoverabl 61 h di b b h dules with control
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l (xiv) 57G r etable irradiated fuel cells.
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(xv)'D2Wku'elcellswithcontrolrods.
l (xvi) Nd-1fuS1hduleswithorwithoutcontro1r$I[s.
I Maximum) quantity $';pi. :
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(1)q$2.fuelassiblie'sa)sdesTribedinofJeaterial.per.
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I (ii)F12 fuel-assemblies,a's~ dss &i d'in 5 )(1)(11,) or E fuel-L I
assembliesasdescribedin>5()(1)(i and'4 fuel essemblies r
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- es desepibed in 5(b)(1)(iii). g "
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I (iii) 67fuelassembliesas' scribedJin.5 iv) ands.,.
I 4 fuel assemblies as described in;5 v).
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l (iv) 9 fuel. assemblies as(described.'in 6 vi). $ <
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8 fuel.essemblies as described in 5 vii)'-
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I (v) 10 fuel a'ssemblies as described in 5(b)(1)(viii).
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I (vi)9fuelassemblie'sas/ described'in5(b)(1)(viii)andonefuel l
assembly as described iniS(b)(1)(ix) l (vii)9fuelassembliesasdescribedin5
)(viii)and I
one structure as described in 5(b)(
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Page'4-CertificekNo.6003-RevisionNo.11-DocketNo. 71-6003 51 (b)' (2) Contents.(cont'd) 1 (viii) 4 fuel cells as described in 5
- xi);or I
2 fuel cells as described in 5 lxi))and 1
2 fuel cells as described in 5 xii,
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l (ix) 6fuelassembliesasdescribedin5(b)(1)(xiii).
l (x) 8fuelcellsasdescribedin5(b)(1)(xiv).
(
'4fuelcellsasdin.ched nk(T1)(xv f
(xi)'
2 corner fughills'or 1 RFA fue l cell /) plus I
(xii) 4fue(ho esasdescribedin5(b)(1)x )[
l (3) Shipments (Nall be further limited by thermal reqbments as follows:
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I cm (1) Sh'tpmentxof' contents in 5(b)(1)(iv) and 5(b)'(1)('v)han 75 d I
'and I
JimitedinI5(b)(2)(iii)shallbenadeinojarlier"t l
iafter shutdownfandsshall..have a decaf heat load notsto exceed i
f33,500' Btu /hrpershipment'.')
fM rg E ntents s /
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Shipment of co$ l /
(ii)blimited in 5(b)(2)(iv')pecifield i ' 5(b)(1)(vi) and 5(
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shall"br eedelin a stainless steel M-130 I
kcontainer and'shalllhave4 dec '7 heat load'no't to eitteed 18,960 l
Btu /hr jer;shjpment.] i l (f M' ? ? Jr an~m Q
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(iii) Shi ment of ^ con' tent's1 spi,ci in 5(b)(l')Niii) >
2)(v),:5(b)(2)(vl)6(b)(1)(ix)and'and5(b)(2) e h
I 5(b (1)(x) and I Mited in.5 b I
sha 1,be made at a timetafter shutdown as determined from Bettis-t I
Atomic.PowerLaboratoryreportWAPD-0P(PP)S4401'datedJune 29, 1979 l
andshallhaveadecahheatiloadnot"toexceed'28,620 Btu /hrforthe "i
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shipboard,coreand30,000' Btu /hrforthepptotypecore.
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(iv) Shipmentofcontentsspecifiedin5(b)(1)'(i),5(b)(1)(ii)
I shall be made no earlier,thanJ2 days after shutdown and shall p
j have a decay heat load not4 to +xceed 33,500 Btu /hr per shipment.
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(v) Shipment of contents specified in 5(b)(1)(xi) or 5(b)(1)(xii)
I as limited by 5(b)(2)(v11) shall have a fully loaded container I
head load not to exceed 15,400 Btu /hr per shipment.
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(vi)Shipmentofcontentsspecifiedin5(b)(1)(xiii)andlimitedin l,
5(b)(2)(ix)shallhaveaheatloadnottoexceed23,800 i
Btu /hr and shall be made no earlier than 92 days after shutdown.
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N ) Page 5 - Certificate No. 6003 - Revision No. 11 - Docket No. 71-6003 i
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. (3) Contents (cont'd)
I.5.i(b) 1 3
(vii)
Shipment of contents specified in 5(b)(1)(xiv) and limited in l
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5(b)(2)(x) shall have a heat load not to exceed 22,400 Rtu/hr I
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and shall be made no earlier than 122 days after shutdown.
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I (viii)
Shipmentofcontentsspecifiedin5(b)(1)(xv)andlimitedin l
l 5(b)(2)(x1) shall'have a heat load not to exceed 19,100 Btu /hr-l l
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and shall be made no earlier than 420 days after shutdown.
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(1x)
Shi ment pf J)nkatsPsdii(agri (b)(1)(xvi)andiimitedin l
l 5(b (2)(xU)'shall-have a heat ad not.to exceed 6,000 Btu /hr I
I and shall' be made no earlier than%Q'klays af ter shutdown.
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.(c) Fissile Class M tp JIJ l
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Maximum number'of; packages per shipment:
-One)
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For-shipments ilivo'lving theMntents specified in 5(I)((1){ii) or 5tb)(1)(iii)'
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the Model No. M-130. package 'shall be inspected to' verify that bogn, poison i
J plates;areinthemoduleholders./
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7..Forship(mentsjnvolving,the1contentsspecifiedin,5(b)(1)(viii),$(b)(1)(1x)or l
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.5(b)(1)x)the<thermocouples;and;theYmocoupleleasesifincludedor;thevacant l
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module. holder shall be locatedlinithe mid-position of either cagevend module l
bolder assembly ?
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i 8.. Shipments shallibe made in'the' dry condition; fexcept for residual. water as l
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l limitedin5(b)(1),5(b)(3)(v.),-and5(b)(3)(vii)..
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9.; Container number thNe (M-130-3)'has;been modifi5h by adding,(two 4-inch thick l
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by 8-inch wide steel' plates welded betweenfins 25 and 50 and'between fins 110 l
l and 135 at approximately,14.75 inches from the bottom ofithe' container. The l
I cooling fins in this localized area are removed to permit' attachment of I
l the plate directly to the outer'shell of the container.
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T % &.A 7-I 10. Container number four (M-130-4) has been modified by adding a 2-inch thick j
l by 4-inch wide steel plate welded between fins 32 and 49 at approximately l
l 18.4 inches from the bottom of the container. The cooling fins in this l
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localized area are removed to permit attachment of the plate directly to the l
l outer shell of the container.
l l 11. Containers M-130-3, M-130-4 and M-130-10 may be used for the contents specified
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in 5(b)(1)(viii) and 5(b)(1)(x) only.
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I 12. Container M-130-11 may be used for NR-1 shipments only.
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i l 13. Expiration date: December 31, 1992, i
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s Page 6 - Certificate No. 6003 - Revision Ne, 11 - Doctet No. 71-6003 s
i REFERENCES Safety analysis report for M-130 shipping container, MAO-E8-703 dated December 30, j
i 1968.
Supplements: llavel Reactors letters A#2256 dated February 24, 1969 and G#1931 dated March 3,1969; General Electric Company letter ONP-74520-526 dated April 3, 1972; Naval Reactors letter GJ3207 dated April 27, 1972; General Electric Company letter DNP-74520-528 dated April 28, 1972; Naval Reactors letter Gi3250 dated June 6, 1972; General Electric Company letters ONP-
-6
' ted. ctober 25, 1972; ONP-74570-654 dated December 4,1972; ONP-74570 t;
72; ONP-74570-682 dated panuary 12, 1973; ONP-74570-618 a ar.uary 31,197
-74570-687 dated February 6, i
1973; ONP-74390 65 dated Mar $ E ',' 1973; DLGN-85570-854 d tod'Aestember 24 1973 DLGN 85670-901 dated Januar',10 1974;NavalReactorsletter8#4d61 dated 3anuary;29; 1974; General Electric nyIettersDLGN85570924 dated Feb*rvery 15, 1974; DLGN-85570 923 dated March 6 C1 74; DLGN-85570-969 datui Hay 24, 1974;M aval Reactors letter Gi4991 dated November 25, 1975; General Electric Company : letters ONP-74340-JTT-73 dated Decembertt,7.1975; CGN-85570-1145 dated September 9, 1976 CGN-85570-1146datedSeptember4)0, letter APO.R(K)-1378-datedAugust 30, 1976; WAPD-OP(P
?
1976b 85570-1148 dated Septembe (14, 1976 ' bettis Atomic Power I.aborap1979; Naval Reactors letters ᠵ' dated July 13 or 4401 dated June 29, 1979; Gi7136 1
' dated March 17,1964f Naval Reactorsaletter Gi?022 datsd? July 14, 1981 and WAPD-LD-I l
CES SE-181 deted September,1981;.WAPD-LP(CES)SE-96 fdsted February,182, WAPD-LP-CES SE-170 dated July 1981; Naval Reactors letterLGi7160 dated May 18 -1982; Naval Peactors letter Gd7482 dated September 7,4983.rWayal Reactors letter 6fC87 5692 dated I
September 7,1987; Wayal Reactors. letter GiC47 5689 dated Sep+ ember 2371967; and I
7 Naval Reactors letters G#C87-8008 ' dated January 096GiC88-5931 dated May 12, and 1
J G#C88-5961 dated July 26,1988d Navaly Reactors iletter GiC89-2863 dated August 11, 1969.
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'i FOR'THE U.S. NUCLEAR REGULATOP,Y COMMISSION n
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f CiarN E. MacDond d Chief I
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Transportation Branen l
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' Division ef> Safeguards and i
" ' Transportation, NMSS l
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UNITED STATES NUCLEAR REGULATORY COMMISSION
- i, W ASHINGT ON, D. C. 20bbb l
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L Ap3roval Record M-130 511pping container i
Certificate of compliance No7 6003 Revision NO. Il By application dated August 11, 1989, Naval Reactors (MR), U.S. Department of i
Energy, requested an amendment to Certificate of Compliance No. 6003 to modify container no. 3 (M-130-3) to add ad:litional shielding. The additional shielding t
would consist of two 8-inch high, 39 inch wide, 4-inch tleick steel plates welded I
to the outside shell of the M-130-3 container. The application also requested i
that the contents of the M 130 3 container be limited to $3G spent fuel.
l W
The additional shielding is being added because of two defects discovered during t
x-ray examination. The defects consist of either void spaces or regions of l
foreign material. Both defects are approximately 0.12 inch thick, located and have a maximum depth of 9 inches.
The defects in the lead shielding are l
approximately 14-3/4 inches above the bottom of the container in an area which would correspond to the surface formed between lead pours.
The applicant calculated dose rates for the modified M-130-3 container for i
normal and accident contlitions for $3G spent fuel. The applicant's calculations for dose rates in the area of the worse defect are summarized in the following table:
i Dose Rates for Shipment of $3G Spant fuel l
in Modified M-130 3 Container (Mrem /hr)
Applicant Regulatory Limit f
Normal condition surface 126 200 two reters 9.1 10 i
Accident condition f
I one meter 18 1000 l
Staff agrees with the applicant that the modified M-130-3 container meets the i
shielding requirements of 10 CFR Part 71 for shipment of S3G fuel.
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Cooling fins in the areas where the plates are attached will be removed so i
that the plates can be welded directly to the container outer shell. Removal l
of these cooling fins will not have a significant impact on the container's thermal behavior during normal or accident conditions, since the number of fins removed is a small fraction of the total.
l The NRC staff agrees that the amendment meets the requirements of 10 CFR Part 71.
t k<hd 4
CharlesE.MacDonald, Chiel l
Transportation Branch Division of Safeguards L
and Transportation, NMSS OCT 19 W Date:
_ _ _ _ _ _ _ _ _ _ _ _.