ML20214U054

From kanterella
Jump to navigation Jump to search
Certificate of Compliance 6003,Rev 7,for Model M-130. Approval Record Encl
ML20214U054
Person / Time
Site: 07106003
Issue date: 06/05/1987
From: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20214U021 List:
References
NUDOCS 8706110029
Download: ML20214U054 (8)
v • d • e


Text

_ __-- ----------------_ --------------=--------- ~="-=4 k u.S. NUCLEAR REGULATORY COMMISSION j I, m ies

.M .3 , CERTIFICATE CF CCMPLIANCE ,

l q' ircen r' FOR RADIOACTIVE MATERIALS PACKAGES g l k ,.eicEnTiricATE NUMBER D REVISION NUMBER c. PACKAGE IDENTIFICATION NUMBER d PAGE NUMBER e. TOTAL NUMBER PAGES l  ;

6003 7 USA /6003/8( IF 1 g

I z PauuetE 5

I a Tnis eertinc ie is inued to certity inat ine packaging and contents desenbed in item s be'ow meets tn* *pphcab'* **tr 't'nd*rd* **t ' 'tn 'n Titie to. code k

g cf Federal Regulations. Part 7i," Packaging and Transportation of Radioactive Material" lI' n Tnes certificate does not reheve the consignor from comphance with any requirement of the regulations of tne u S Department of Transportation or other appbcabie reguistory agencies. inciuding ine govemment of any country enrougn or min =nion tne packag'"d' b* transpo't*d-i I p I s I

l x p gcA y siss yurNE e4 sis or 4 sArErv ANAusis,aEgTgt,Nge,x,4ogsgoga PPL Cg,N,,,9 e i

i l l (LS. Department of Energy Safety Analysis Report for M-130 shipping I

Efvision of Naval Reactors container dated December 30, 1968, as >

I Washington, DC 20585 supplemented.

l l e. oocxet NuweEa 71-6003 l lI Tne to is conditional upon fulfilhng the requirements of to CFR Part 71, as appbcaDie, and the conditions specified below.

'Il S.

p (a) Packaging N I E I (1) Model No.-

il M-130 f

ll (2) Description E

p 1,

I I g The M-130 shipping container is an upright cylinder 84 inches in N l diameter by 158 inches overall height. The container walls consist of 8 I a finned 1-inch thick outer shell (fabricated from either carbon I steel, carbon steel with stainless steel clad, or solid stainless l

y I

steel), 10 inches of lead shielding, and a 1-inch thick inner pressure g vessel (fabricated from carbon steel clad with stainless steel). The B top of the container is covered with a shielded closure head which is >

bolted to the container and seals the pressure vessel. An access E opening with a bolted shield plug is provided in the closure head for l loading and unloading spent fuel, l h The pressure vessel has an inside diameter of 55 inches. The central g region contains a secondary heat exchanger (not used during shipment) k I surrounded t,y a 1/2-inch thick carbon steel backup cylinder 29 inches l' I in diameter. The annulus which remains between the backup cylinder E I and the pressure vessel provides a space 13 inches wide and 130 inches l high for spent fuel. The spent fuel is contained in the annulus by p

l' module holders designed for the particular core to be shipped.

g t.)

I E g The container has external penetrations to the pressure vessel for >

I steam and water relief lines and a fill and drain line (which are i I capped during shipment) and a pressure sensing line which remains open I to a pressure gage during shipment. The container also has penetrations l y

l which do not open to the pressure vessel for secondary heat exchanger y y lines (which are capped during shipment) and a temperature sensing I g line. >

l l I E I N I N n

,l; C I

L___--.r--------------------------------------------- M

^~

i l conomous (continued) " * " !E H

R <

l . Page 2 - Certificate No. 6003 - Revision No. 7 - Docket No. 71-6003 E l

l N I

5. Packaging (cont'd) i (a) y I

(2) Description (cont'd) i I

i For LWBR spent fuel shipments, the heat exchanger and associated structures have been removed, external penetrations plugged and seal l l i y l welded, and an external shield and energy absorber added during y <

l modifications. I l I N  !

l The container is supported on its transport vehicle by an "A" frame i structure. Gross weight of the loaded container without its support structure is approximately 228,000. pounds. l  ;

j i g e I s V..'h, d U E- b e / ,

I p  ;

(3) Drawings p

(.v I ,, i l * { Af ,

y l

l The packagin pis constructed in accordance with< General Electric I ,

ll Drawing Nos. 247E209, Sheet 1, Rev. R; Sheet 2L Rev. K; Sheet 3, Rev. I T; Sheet 4,sRev. U; Sheet 5 of 5, Rev. F and.247E228, Rev. F.

l l A.

(

p 1 For LWBR' spent fuelishipments, the contsiner has been modified in l p ,

I accordance with Westinghouse Electric Drawing ll76J48, Sheet 1 Rev. G, N .

I Sheet 2~Rev. E and an external energy-absorber added-in accordance i I withWestinghouseElectricDrawing1525E32,Rev.A.j I I i

') (b) Contents '~

l 1 I g (1) Type and form of material b I E II Irradiated fuel assemblies, activated corrosion products and structural 1

-ll parts containing up to 40 gallons of residual contaminated water. The

.jg fuel assemblies and structural parts are of the following types:

~

l II N je (i) S3W/54W fuel subassemblies of core' type 2.

p IB N I (ii) S5W fuel modules of core' types 2 or 3. I l I

(iii) S5W corner fuel modules of core types 2 or 3.

l R 1 (iv) DIG fuel modules of core types 1 or 2. N k

(v) DIG removable fuel assemblies of core types 1 or 2. B B

,) (vi) SIC /S2C fuel modules with control rods.

l p

(vii) SlC/S2C peripheral fuel modules. p b

(viii) S3G-3/3A fuel module with or without control rods.

(1x) SAD cell.

l N

N N

l I

llN I

,,,,,,,.,,,,,.,,-----____-_______--___.._.__-._-_-.-___-__--.____.___----a

______________________,__________ata -

.< . ' . . ' .' . . ' +

R

.' conomons (continued)

'~ ~"

B

, P'aga 3 - Certificate No. 6003 - Revision No. 7 - Docket No. 71-6003 R R

I

5. (b) Contents (cont'd) l N

(1) Type and form of material (cont'd) I i

(x) S3G-3/3A irradiated thermocouples and thermocouple cases.

l (xi) LWBR blanket fuel modules. l 4

(xii) LWBR reflector fuel modules. 1 (xiii) LWBR seed fuel modules. y s

n r~ , y (xiv) S8G full size fuil cell ~ w,ith or,without control rod. y y - v

.' i

,7 (xv) 58G part-ial size fuel cell with or~ wi.thout control rod. N N

(2) Maximumquaniityofmaterialperpackage (

, l l

(i) 52fuelassembliesasdescribedjin5(b)O)(1).

p

,- l (ii) 12 fuel assemblies as described-in 5(b)(1)('ii) or 9 fuel N assemblies as described in 5(b)(1)(ii) and 4 fuel assemblies i as described in 5(b)(1)(iii). ~.

8 g

i g (iii) 6 fuel assemblies as described in 5(b)(1)('iv) aria' y 4 fuel assemblies as described in 5(b)(1)(v).

I p N

(iv) 9 fuel assemblies as described in 5(b)(1)(vi) and i 8 fuel assemblies as described in 5(b)(1)(vii). .l II (v) 10 fuel assemblies.as de' scribed in 5(b)(1)(viii). l l B L (vi) 9 fuel ~ assemblies as described in~5(b)(1)(viii) and one fuel 3 assembly as described in 5(b)(1)(ix). p Y

'f 4 (vii) 9 fuel assemblies as described in 5(b)(1)(viii) and 8 g one structure as described in 5(b)(1)(x). l

+: p (viii) 3 fuel assemblies as described in 5(b)(1)(xi). g 5

(ix) 4 or less fuel assemblies as described in 5(b)(1)(xii). N l r 0 I l (x) 6 fuel assemblies as described in 5(b)(1)(xiii). ,

i ly (xi) 4 fuel cells as described in 5(b)(1)(xiv); or p 2 fuel cells as described in 5(b)(1)(xiv) and ,

,5 1 2 fuel cells as described in 5(b)(1)(xv). jf l p i 5

.a >

%' s I

.q p lI I

![ > N h W I. I J s  ! l l Id

-m . ......Tr,vrT. ....u . . . . . . . . . r r v rr r r,,,, rr m . vr,- a  !

i -. ........... ... .... . . .. . . . . . . . . . . ' . . .......s .. . .s

- , coNomons (continued) l R I Page - A Certificate No. 6003 - Revision No. 7 - Docket No. 71-6003 i I l l l i

5. (b) Contents (cont'd) l l N I Shipments shall be further limited by shielding and thermal requirements N I as follows: I l (1) Shipment of contents specified in 5(b)(1)(iv) and 5(b)(1)(v) and l l limited in 5(b)(2)(iii) shall have a decay heat load not to exceed y l 33,500 Btu /hr per shipment. I I I I (2) Shiptrent of contents specified in 5(b)(1)(vi) and 5(b)(1)(vii) and i I

I limited in 5(b)(2)(iv) shall be made in a stainless steel M-130 container l g and shall have a decay heat load-not to exceed 18,960 Btu /hr per  ;

shipment.

i I

,; S A Ti C (j (j! n . g l

l (3) Shipment of content [specified in 5(b)(1)(viii.), 5(b)(1)(ix) and I I 5(b)(1)(x) and'11mited in 5(b)(2)(v), 5(b)(2)(vi.) and 5(b)(2)(vii) I I

shall be made'at a time after shutdown as determined from Bettis I I

Atomic Power Laboratory report WAPD-OP(PP)S 440lidated June 29, 1979 g

g and shall have a decay heat load not to exceed 28,620 Btu /hr for the l; i- shipboard core and 30,000 Btu /hr for the. prototype core.

~

p I . .'. C .' I I (4) Shipment of contents specified in 5(b)(1)(i), 5(b)(1)(ii) and 5(b)(1)(iii) i I I and limited in 5(b)(2)(i) and 5(b)(2)(fi) shall be made no earlier l than 72 days after shutdown and shall have a decay heat load not to y exceed 33,500' Btu /hr per shipment. l i

\\ l

'll (5) Shipment of contents specified'in 5(b)(1)(xi) and limited in 5(b)(2)(viii) N I shall have a heat load not to exceed 48,000 Btu /hr and a residual

~

i j water quantity not to exceed 4.6 gallons.

l ll (6) Shipment of contents specified in 5(b)(1)(xii) and limited in 5(b)(2)(ix) l Ig shall have a heat load not to exceed 3,672 BTU /hr. p 1 .

N

( (7) Shipment of contents specified in 5(b)(1)(xiii), and limited in 5(b)(2)(x) i W shall have a heat load not to exceed 27,600 BTU /hr and a residual N water quantity not to exceed 7.5 gallons. I l

(8) 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 heat load not to exceed 15,400 BTV/hr per shipment. fr l '

(c) Fissile Class III )

l Maximum nimber of packages per shipment: one l

6. Fcir shipments bvolving the contents specified in 5(b)(1)(ii) or 5(b)(1)(iii) I the M-130 package sha.ll be inspected to verify that boron poison plates are in I 4

the module holders. N N

I l

q I

+

N I

N l

. . . . . . . . . . uw. . . . . . . ~ .. . . . . . . . . . . . . . . . . . . . . . .Y

ll.. - . . . .. . . . . . -------------_-----------4 l ,I ii

~ '

(

CONOlTIONS (continued)

I it I

it I Dage 5 - Certificate No. 6003 - Revision No. 7 - Docket No. 71-6003 't

\' t i

I' 7.

~

For shipments involving the contents specified in 5(b)(1)(viii), 5(b)(1)(ix) or l n g I,

Il 5(b)(1)(x) the thermocouples and thermocouple cases if included or the vacant module holder shall be located in the mid position of either cage and module

)

I holder assembly. 4l1 1 II f 8. Shipments shall be made in the dry condition, except for residual water as f ll Itmited in 5(b)(1), 5(b)(2)(5), and 5(b)(2)(7). y ll t 11 9. Ex,31 ration date: May 31, 1988. 1 II ,. t ll - , li ll . P l / p ) I I ,,

c,. ['; (-} (2 ,f .4

-- I I -- s I ,

< 7 ',

, 4{t 5 , ,; #

, m l$

l - .,' f

')

p ">-ci ' , E 1 . - /~ t g .

1; . . - g g . y _

g I -

.- 4 t, 4 y

n ,- , a - A. t 5 ^

.J K y ': -

.., t 4 ,

I

I ."~ t 5 ,ir- s' g I t
1 i R c,

t

1 .
1 ,> , t 1 L
1 1 1

.j .

g

1 p. pi 11 E
i1 E i

~1 f L U E v1 [

-1

[

1 ,.. . / g "1 h
1 i
1 [

=

I E

1 [

.1 E

1 E il L M E

'l E 1 F

.lJ ii b i J E

1 E il N a i h__- _ _____- _ _ ---___-m m m __--- _-- _ __-_-___l,I

, conomous (continued) l I I l l Page 6 - Certificate No. 6003 - Revision No. 7 - Docket No. 71-6003 l' l I

I l I I I ll l l REFERENCES g I I I Safety analysis report for M-130 shipping container, MAO-E8-703 dated December 30, I ,

I 1968. I I I l Supplements: Naval Reactor letters A#2256 dated February 24, 1969 and G#1931 dated l l March 3, 1969; General Electric Company letter ONP-74520-526 dated April 3, 1972; p I Naval Reactors letter G#3207 dated April 27, 1972; General Electric Company letter I I OMF-74520-528 dated April 28, 1972; Naval Reactors letter G#3250 dated June 6, 1972; I ll General Electric Company letters ONP-74570-635 dated October 25, 1972; ONP-74570-654 I I dat:d December 4, 1972; ONP-74570-666 dated December 12, 1972; ONP-74570-682 dated January 12, 1973; ONP-74570-698 dated'Jin~uarVi 3I,(1973; 0NP-74570-687 dated February 6, l

, ~

, y il T973; ONP-74390-65 dated March p ll 26,11973; DLGN-85570-854 DLGN-85570-901 dated January 10/1974; ettierNaval Reactors G#4061 dated January l(dated September 29, I24, 1 I 1974; General Electric Compa'ni' letters DLGN-85570-924 dated February 15, 1974; DLGN- N

  1. 85570-923 dated March 6, 1974; DLGN-85570-969 dated May 24, 1974; Naval Reactors I letter G#4991 dated Novesb'er 25, 1975; General Electric Company')etters ONP-74340- ,I JTT-73 dated December 17, 1975;'CGN-85570-1145 dated September 9, 1976; CGN-85570- g TI46 dated September 1,021976;5CGN-85570-1148 dated Septemb~r e 14, 1976; Bettis Atomic p Power Laboratory letter-WAPD-R(X)-1378 dated August'30, '1976; WAPD-OP(PP)S-4401 dated i Jena 29, 1979; Naval Reactor letters:G#6197' dated Julyjl3',1979; G#7136 dated i March 17, 1982; and WAPD-LD(CES)SE-181/ dated September; 1.981; WAPD-LP(CES)SE-96 1 dated February,1982, WAPD-LP(CES)SE-170. dated-July ~ 1981; Naval Reactors letter I G#r7160 dated May 18,.1982; and NavaFReactors , letter G#7582. da'ted September 7, l 1983. . g

_ i

" FOR TsE U.S. NUCLEAR REGULATORY COMMISSION i

. - v i s , I N

N Charles E. MacDonald, Chief N N' > Transportation Branch I

  1. Division of Safeguards and I Transportation, NMSS l l

. i g Date: M 5 BBT I E

4 i W R H I 3 1 2

i 4 i i N 4 5 4 1 4 I i i i I i

l i i i i i I

I I I

i

_---.....,ti

fn M%g

# q UNITED STATES

[ % g[,i e

NUCLEAR REGULATORY COMMISSION

n,yM I I wasamoToN. o. c. 20sss s gy,/

. i

$ Transportation Branch Approval Record-4 Model No. M-130 Package

Decket No. 71-6003 ,

t 1

i By application dated May 18, 1982 (G#7160), Naval Reactors, U.S. Department of Energy, req'uested an amendment to NRC Certificate of Compliance No. 6003 to.

provide for transporting irradiated S8G fuel cells in the Model M-130 shipping-cask.

The.M-130 container has been previously analyzed and scale-model tested to show compliance to the requirements of 10 CFR Part 71. The weight of the container loaded with the S8G fuel cells is less than the weight authorized in the current Certificate of Compliance No. 71-6003, review of the structural integrity of the M-130 container is deemed unnecessary. Thus, the review is concentrated on the container contents to determine the extent of damage or rearrangement of the fuel-4 cells which may occur during the 30-foot drop impact conditions.

In the top and bottom 30-foot drops,Lthe contents are considered subjec't to i impact on an unyielding surface and to absorb all of their own drop energy.

i In the side drop, the contents are considered subject to impact; force of.213 g which is the maximum impact force as determined by the. analysis of the M-130

container.

Because the internal heat load and pressures are within the bounds for which 4

the M-130 package has previcusly been evaluated, the NRC staff concludes the package is adequate for the thermal conditions in 10 CFR Part 71. The NRC-staff also reviewed t' ! criticality and shielding models and analyses of the

, M-130 package containi.ig irradiated'S8G fuel cells (with or without control rods). The NRC staff concluded that the package meets the requirements of '

4 20 CFR Part 71.

For the top and bottom drops, the contents (i.e., internal structures and fuel cells) are modeled by lumped mass and nonlinear spring' systems. The motions i of the spring-mass model are then solved with respect to time by using the-t MIMIC computer program. The analysis has shown that the drop energy was

' absorbed almost entirely by crushing the soft aluminum bars. As 'a result,

there is negligible deformations of other components. The control rod may also move, however, it is not important since the criticality analyses are made considering the fuel cells are unrodded. In all instances, the stresses in the fuel cell cladding remain below yielding and therefore the fuel cladding will not rupture.

The analysis of the side drop has shown that the wedge assemblies could 1 collapse 0.479 inches,-permitting the fuel cells at the closest to be '

-separated by 22.38 inches center to center. This distance was used in the

criticality analyses. The control rod and the fuel cell cladding will not fail at the 213 g side drop impact load.

. . . - , .~ -, -

2 Also, the application has shown by analyses that corner drop, oblique drop, and the puncture drop all will result in less impact forces than those of the side drop therefore they will not be the controlling loading case.

The NRC staff agrees with the applicants conclusion that the fuel cells will not be damaged in a 30-foot drop impact condition and no radioactive materials will be released.

The above change will not effect the ability of the package to meet the requirements of 10 CFR Part 71.

Mk Charles E. MacDonald, Chief M 5 1987 Transportation Branch Division of Safeguards and Transportation, NMSS I

l 1

I

.

Retrieved from "https://kanterella.com/w/index.php?title=ML20214U054&oldid=3241878"