ML20151H221

Certificate of Compliance 6003,Rev 9,for Model M-130. Approval Record Encl

ML20151H221
Person / Time
Site:	07106003
Issue date:	07/22/1988
From:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20151H211	List: ML20151H209 ML20151H221
References
NUDOCS 8808010190
Download: ML20151H221 (8)

Text

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[ U.S. Department of Energy Safety Analysis Report for M-130 shipping  !

container dated December 30, 1968, as I l Division of Naval Reactors l Washington, DC 20585 supplemented. l l

! - P. k n k O / }1-6003 l

' O **<' .conoi.o,w w iw a na y , b b [ov50 ceR.cor.rt n. spac**d te l

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Y (a) Packaging

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• 2. l l (1) .

Mode u 7M. :O'M-130 C' ,

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5 l f j I (2) Descrfption ', s

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The Model No. M-13 shipping contain'er fI an upright h nder 84 inches i in diameter by 158 inches overalthef ti The container 3 walls consist !i l of a finned 1-inch tht d outer shelb pbricated from Sj)her carbon il g

s sp at et clad,.or sol G stainless ;I l

I steel},

steel carbon;steelwit4stai 10 inches of' lead M fog - l i i vessel (fabricated fron care teekahd a 1-inch clad witto staintest thitfinner steel). pressureThe I j!y '

bolted to the containe Fani{feafs~t Ws prqs'ure vesst C An accesstop ll o l ded in the: closure head for 1 g

g opening'with a bolted shield'pTug is gL.

l o a d i ng a nd ,u n l oa d i n g~ s p eh t , f u e l, . '

, ,, s i ThepressuMresselhasaninsidediameteroC65Unches. The central I region contafnd' a secondary heat exchanger (not' used during shipment) !g l surrounded by a 1/2 W ch thick cathon st(el backup cylinder 29 inches ll I

in diameter. The aninulhrr$ reinsfbetween the backup cyltnder if 1

I g and the pressure vessel provfdes a' space 13 inches wide and 130 irches I high for spent fuel. The spent fuel is contained in the annulus by l 1 module holders designed for the particular core to be shipped. lg The container has external penetrations to the pressure vessel for g steam and water relief lines and a fill and drain line (which are si capped during shipment) and a pressure sensing line which remains open il e

I to a pressure gage during shipment. The container also has penetrations j i which do not open to the pressure vessel for secondary heat exchanger jl l lines (which are capped during shipment) and a temperature sensing l line.

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l mammm m m m mm mm um u m m mm m m m m m m m m m m m m am m mmm = = = = = =M m m M" m u m m m W WW 3 conomoNs (contsnved)

I I I I I -l Page 2 - Certificate No. 6003 - Revision No. 9 - Docket No. 71-6003 l

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l l l l l 5. (a) Packaging (cont'd) l l -1 (2) Description (cont'd) l l

l For LWBR spent fuel shipments, the heat exchanger and associated l l

structures have been removed, external penetrations plugged and seal ,i i welded, and an external shield and energy absorber added during i I modifications. I The container is s bn s vehicle by an "A" frame l i structure. Gr b t of the loaded inAr without its support i i structure i 6ximately 228,000 pounds. $sf i I .I l

(3) Drawings Q j l

The p ging is. constructed in accordance with gen Electric l i, Drawi os. 247E M2 Sheet 1, Rev. R; Sh34 2g Rev. dSheet 3, Rev. i l T; S l

i 4, Revati;Q %\$heet 5 of'JL' 5, Rev. F'M247E228, tG Rev. F. l I

l For R spent fuel?shiprents.-the contatNr: has been r?dified in 1 acco(dance with Westisghouse Electric'. Drawing ll76J48, 3heet 1 Rev. G, l I ,

Sheet 2 Rev. E and an external anergy absorber added in.accordance ,e l with'?estinghouseElectricDrawing1525E32,Rev.A. { ll l il I (b) Contents 11 I ll (1) Type and form of material l

l Irradiated fuel asserrtlies, activated corrosion products and structural  ;

i parts containing up to 40 gallons of residual contaminated water. The I I fuel assemblies and structural parts are of the following types: !I I

l (1) S3W/S4W fuel subassemblies of core type 2. ill l (ii) SSW fuel modules of core types 2 or 3.  !

l Il I (iii) SSW corner fuel modules of core types 2 or 3. lI l .I (iv) DIG fuel modules of core types 1 or 2. l l

I I I (v) DIG removable fuel asserblies of core types I or 2. 'I I fll I (vi) SIC /S2C fuel modules with control rods. I l lI l (vii) SIC /S2C peripheral fuel modules.  !!

! (viii) 53G-3/3A fuel module with or without control rods,

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I (ix) SAD cell. I i I I II l i l i II i 1 l-_--.-.- _---_- ,.,,,, _ _ g_ _ _ ,g,,,,,,,,,ggggagggggg)4

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I I Page 3 - Certificate No. 6003 - Revision No. 9 - Docket No. 71-6003 I

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! 5. (b) Contents (cont'd) i I (1) Type and form of material (cont'd) l (x) S3G-3/3A irradiated thermocouples and thermocouple cases, j l

! (xi) LWBR blanket fuel modules.

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(xii) LWBR reflect 1 ge l (xiii) LWB hgj el modules. [

! (xiv) f 11 size fuel cell with or wit hontrolrod.

(xv) G partial size fuel cell with or witho ntrol rod.

(xvi) S 4A overable irradiated f kesyd.hcontrol

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• 57G recovt 1e irr;adi+ ed f 0

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(2) Maximum quantity of materia L par packa 7 [ i l s' .... - w f y

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. 52 fuel asserbliassas:descritid in 5(b)(1)(if L g  ; . +i . .-.-

3 12 fuel assemblies!aside;scr,1 bed in 5(b)(1)(tG or 9 fuel 1 (ii) assemblies as dantited pn 5(b)(1)(ii) and .4' fuel assemblies j

I t l asdescribedirr5(b)(17(ift). . .?  !

! (iii) 6fuelassembliesasdescribed;n5(b)(1)(fv)and 1 1 4 fuel assemblier as. described in 5(b)(1)(v). [

I I (iv) 9fuelassembliesasdescribedin5(b)(1)(vi)and l 3 fuel assesblip as. described:.,in 5(b)(1)(vii).

' I g .. s I (v) 10 fuel assemblies as' des ribed in 5(b)(1)(viii). [

I y (vi) 9 fuel assemblies as described in 5(b)(1)(viii) and one futi  !

assembly as described in 5(b)(1)(1x). l l (vii) 9 fuel asserblies as described in 5(b)(1)(viii) and !i jj e one structure as described in 5(b)(1)(x).  ;

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I (viii) 3 fuel assemblies as described in 5(b)(1)(xi). i J

l l (ix) 4 or less fuel assemblies as described in 5(b)(1)(xii). l

! (x) 6 fuel asserblies as described in 5(b)(1)(xiii).

E v i (xi) 4 fuel cells as described in 5 xiv);or L I 2 fuel cells as described in 5 xiv) and I l 2 fuel cells as described in 5 xv). l B L

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I page 4 - Certificate No. 6003 - Revision No. 9 - Docket No. 71-6003 I

I l 5. (b) (2) Contents (cont'd)

I I (xii) 6 fuel assemblies as described in 5(b)(1)(xvi). I I

l (xiii) 8 fuel cells as described in 5(b)(1)(xvii). l l I

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(3) Shipments shall be further limited by thermal requirements as follows: I I

I I (i) Shipment of conte t ecQiG 5 b)(1)(iv) and 5(b)(1)(v) and I I

limited in 5(td2 sM14- Scay heat load not to exceed j

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1 33,500 B g)ershipment. i l l i

(ii) Ship contents s and 5(b)(1)(vii) and I I

I limi n 5(b)(2)(iv)pecified shall be in 5(b)(1) made in a st less steel H-130 I I con er and shall have a decay heat load n exceed 18,960 I B hr Der sh pment. , .-y i (iii) ment oO tits specified in 5 M viii) 5(b)(1)(ix)and 4 5(b)(2)(vii) i i c b (1)(x) an nHted in 3(b)( (v %(b)(2)(vi) l I s all be made' time Etei s l 1s detertii from Bettis 1 I w tomic Power Cabfratory report P(f P)S-4401 d June 29, 1979 I I and shall have rdecay heit.loafr teto~ exceed 28 Btu /hr for the l

,1hipboard core and 34,000 Btu /

gF the prototyp re. i l  %.;nv.

, r. i n (iv) ~ Shipment of contents.spe(if ed.in 5(b)(1)(4, 5(blO)(ii) ,

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1 All be made no earlier 4tf1 472,daysaftershutdewnandshall beve a decay heat 1oad re;tt (3 exceed.33,500 Btu /gper shipment. l i l ,

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(v) Shipment of contents specified in Sdr)(1)(xi) and limited in i l 5(b)(2)(viii) shall have a heat Toad.tiot to exi:eed 48,000 Stu/hr i e

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.I l and a.gsidual water quantity not to exceed 4.6 gallons. I i I l

l' (vi) Shipment of contents specified in 5(b)(1)(xii) and limited in 5(b)(2)(ix) shall haye a heat loaCaot s to exceed 3,672 Btu /hr. i

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ll g (vii) Shipment of contents specified in 5(b)(1)(xiii), and limited in i I 5(b)(2)(x) shall have a heat load not to exceed 27,600 Btu /hr and I a residual water quantity not to exceed 7.5 gallons, j I (viii) Shipment of contents specified in 5(b)(1)(xiv) or 5(b)(1)(xv)  !

l as limited by 5(b)(2)(xi) shall have a fully loaded container .I g heat load not to exceed 15,400 Btu /hr per shipment. I j I ,

i I I (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 23,800 l ,

Btu /hr and shall be made no earlier than 92 days after shutdown, i l l l l

i, (x) Shipments of contents specified in 5(b)(1)(xvii) shall have a ll l l heat load not to exceed 22,400 Btu /hr and shall be made no il I earlier than 122 days after shutdown. i l

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I Pace 5 - Certificate No. 6003 - Revision No. 9 - Docket No. 71-6003 I

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l5. (cont'd) l l

l l (c) Fissile Class Ill I I

I Haximum number of packages per shipment: one l l l6. For shipments involvirg the contents specified in 5(b)(1)(ii) or 5(b)(1)(iii) l l

the Model No. M-130 package shall be inspected to verify that boron poison I l- plates are in the module holders l I

l For shipments involving GA c W ents specified Tn b ( (viii),5(b)(1)(ix)or l

l and thermocouple cases i ded or the vacant l7.

5(b)(1)(x) the thermoco module holder shall ated in the mid-position of et cage and module i

i holder assembly.

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8. Shipments shall limited in 5(b) . madg)4 the dry condition, except 4for resih water asl l

,and5(b)(3)(vii). -'

l 5(b Q l9. Container nur r four (M- 3 \sbesepodifi ing a 2- h thick  !

I by 4-inch wid s eel plate ) )etW6tqYtts 9 at appr ately I I the bottom o - if container. ofingfins his I I 18.4inchesf("emoved, localized area top'er(i att ., late directl the I l outer shell oP-tte contatner ,g%agl'm9taf,f -

l l e f% .a  % Fr ~n ContainersM-Md-4andA-13G-10%gWaset!or.thiconte.nisspeNiedin

> , .- I i 10. , I i 5(b)(1)(viii)a 5(b)(1)W only.g 4 5 , u, . 4 I i 11. Expiration date:y becembe ,1 P,W 'b;[Y l

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71-6003 lPage6-CertificateNo.6003-RevisionNo.9-DocketNo. l l

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I REFERENCES I l I

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l Safety analysis report for M-130 shipping container, MAO-E8-703 dated December 30, j 1968. j

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l I Supplements: Naval Reactor letters Af2256 dated February 24, 1969 and G#1931 dated I J l March 3,1969; General Electric Company letter ONP-74520-526 dated April 3, 1972; I I Naval Reactors letter Gf3207 dated A lt17, D7c ral Electric Company letter I ,

1 dated April 28, 197 D eaHoFe 3250 dated June 6, 1972; l i l General Electric Company let 4570-635 dated 0 , 1972; ONP-74570-654 lONP-74520-528 i

dated December 4, 1972; ON 666 dated December 12, ' ObP-74570-682 dated j

l I January 12, 1973; ONP-745 dated January 31, 1973; ONP-7 ciO 687 dated Februarv (, .

I 1973; ONP-74390-65 date h 26, 1973; DLGN-85570-854 datedSerT1pber24,1973; I DLGN-85570-901 dated Ja y 10, 1974; Naval Reactors letter Gf4 N ted January i l 1974; General Electr letters DLGN-85570-924 dated a' , 1974; OLGN-omp(74 19 -85570-969 dated May ;N Revetors l85570-923 dated Marc ember l

i letter Gi4991 dated General Electrix letters ONP-74340-l JTT-73 dated Decem 17, 1975;' 70-H4t$ted/$ r9,197ACGN-85570-l 1146 dated Septemb 0, 1976; CG 7 -lll N aved r 14, 1974 ettis Atomic I Power Laboratory 1 erWAPD-R(K)M[8datedAugust ) 7,6; WAPD-OP S 4401 dated June 29, 1979; Navpl Reactors lette' . 1979; Gt71 ated i

l March 17,1982; anR"IlAPD-LD(CES)S(- Nuted Septe Qf(}Q7'v4mt*A 981; WAED-LP( @ )SE-96 i i

i dated February,19@ WAPD;Q4CES)3C- WWra Naval React letter I Gt7160 dated May lir,1982; Nduri Rtact$rd 1: ti t w 3f3562 dated Septe 7 l l 1983; Naval Reactors A tter'G/ -5692,491 e s S epi erb r 2, 198?x and 1 Reactors I

letter G4C87-5689 davd Septe. ' ggf3,d]M  ;, M1d P Q4gReacmors letteN#C88-5931 l ldatedMay 12, 1988. j. .

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I Transportation Branch j l Division of Safeguards and i j j Transportation, NMSS I

!Date: M 2 2 S68 I l l

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,1 NUCLEAR REGULATORY COMMISSION WASHING TON, D. C. 20555

%.....J Transportation Branch  !

Approval Record Model No. M-130 / S7G '

Docket No. 71-6003 .

Revision No. O By application dated May 12, 1988, Naval Reactors, U.S. Department of Energy, requested an amendment to Certificate of Compliance No.

6003 to permit shipment of S7G recoverable irradiated fuel (RIF) j modules in the M-130 shipping container. The proposed contents would consist of eight S7G RIF fuel modules per M-130 container, with shipments restricted to one M-130 contair.er per transport vehicle.

i The decay heat for the eight S7G fuel modules is limited to 22,400 BTU /hr, and shipments of S7G fuel would be made no 1 earlier than 122 days after shutdown.

1 Since the weight of the S7G fuel modules is less than the weight

! of other currently authorized conter.ts, the previous structural analyses applicable.of the M-130 shipping container are still valid and i The contents were analyzed by computer code for the thirty foot drop conditions. In the analysis, the applicant neglected the

! M-130 casksurface.

unyielding and impacted the S7G contents directly onto an

• Results of the analysis have shown small I

deformations of the fuel cladding. of the fuel modular holder but no yielding or rupture '

i The applicant also evaluated the possible rearrangement of the contents under the accident conditions specified in 10 CFR 71.

! The criticality analysis was conservatively based upon an assumed i rearrangement of the contents which was greater than that indicated by the structural analysis. Furthermore, the central heat exchanger region was replaced with steam giving raximum i reactivity coupling among the fuel cells. i l l l

i The applicant has established the subcriticality of the proposed l l contents for normal and accident condicions by using Monte-Carlo i 1 calculations based on a Fissile Class III shipment. '

i 3

The SPAN-4 computer code was used to model the M-130 shielding for the proposed S7G contents using gamma and neutron sources f indicative of the actual core power history. '

I modeled normal conditions and the controlling accident conditionThe SPAN-4 program ,

of side and bottom drop with puncture damage. Dose rates predicted for normal conditions were 0.8 arem/hr. for gamma and  !

5.7 mram/hr. for neutron radiation.

1 conditions for neutronatradiation. one meter were 362 mram/hr.The for gamma dose andrates 2 mrem for/hraccident l requirements of 10 CFR 71.The applicant has satified the shielding

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The decay heat load of the contents has been limited to 22,400 Btu /hr. This limitation assures that too maximum M-130 surfcco temperature does not exceed 180 degrees F (the limit for exclusive

use shipment) for normal conditions. The applicant used a finite element computer model, REFLEX, to predict the M-130/S7G's thermal behavior under accident conditions. There was minimal lead melt and no damage to the S7G fuel. The pressure calculated under accident conditions was approximately 400 psia. This assumed that 40 gallons of residual water was left in the cask after loading.

The cask is designed to withstand 450 psig.

Containment for the M-130/S7G is provided by the M-130 container i

and the encapsulation provided by the cladding and weldmen*;s of the S7G fuel. There are no penetrations in either the S7G fuel cladding or veldments. The applicant assumed that the M-130 container vent line could be sheared off during a one foot side i drop or during a thirty foot side drop. The vent line would not be sheared off under a one foot drop onto the bottom and of the cask, the case for which the package was evaluated for normal conditions of transport. The staff agrees with the applicant's conclusion that a one foot side drop would not be a "normal" condition for a cask as large as the Model M-130. Even if the j vent line vore to be sheared off , the applicant has concluded i that the release rate under normal conditions would be less than .

At x 10"'/hr based on experimental venting measurements on three loaded M-130 shipping containers. In those tests, the material released van limited to crud and corrosion products edhering to fuel plates. No fission products were detected in the material ,

released through the vent.

j Previous tests by the applicant (on S5W fuel) indicate that only ,

j 0.10 percent of the crud or corrosion adhering to the plates would  ;

, be loosened under accident conditions, i.e., by a force of 280 ,

4 g's. The applicant has demonstrated that fuel plate cladding I

intregrity is maintained under accident conditions. Therefore, any release of material under accident conditions would be less than an Aa quantity.

Condition No. 8 has been revised to correct a previous i typographical error by changing reference from 5(b) (2) (5) and '

1 5 (b) (2) (7) to 5(b)(3)(v) and 5(b) (3) (vii) .

The staff concludes that the amendment meets the requirements of l 10 CFR 71. ]

Ctb w *Y Charles E. MacDonald, Chief Transportation Branch Division of Safeguards and

Transportation, NMSS l

l Date: JUL i2 VW I i l

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