ML20135G142

Certificate of Compliance 9010,Rev 15,for Model NLI-1/2. Approval Record Encl

ML20135G142
Person / Time
Site:	07109010
Issue date:	09/09/1985
From:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20135G137	List: ML20135G136 ML20135G142
References
NUDOCS 8509180197
Download: ML20135G142 (8)

Text

p--- M-v---mm-------mm--mmmmm--mmmm----------m====m--==9

! NItC F0ftM Sie U.S. NUCLEAL [ EEULATORY CcMMISSl!N I I *au CERTIFICATE CF COMPLIANCE I l to cFR n FOR RADl! ACTIVE MATERIALS PACKAGES I 1 esRTiFicATs NUMeER o REVISION NUMBER c. PACKAGE lOENT6FICAisON NUMBER d PAGE NUMBER e TOTAL NUMaER PAGEs l 9010 15 USA /9010/B( )F 1 5 p-I! : PREAMetE F l' e. Tnis c.rtificat is issued to certify tnat in. packaging and contents d. scribed en item 5 b. low, m ts tn.apphcabl. safety standards set forth in Titi.10. Cod. l l of F.deral Regulations. Part 71,

• Packaging and Transportation of Radioactiv. Mat. rial? l ,

I b Tnts c.riificat. do.s not r.ii. in. consigno, from compi anc. . in any r.quir.m.nt of tne reguiations of in. u s. o.oartm.ni of Transportation or other i ll I appiscaba. r.guistory ag.nc,.s. .nciuding in. go.nm.ni of any country inrougn or into -nica in. packag. -in be iransport.d 0 i R I E 3 THIS TIFICA l$ BSSU THE BASIS OF A SAFETY ANALYSIS RE T OF THE P E $ GN OR A ION I Nuclear Assurance Corporation NL Industries, Inc. application dated I I 5720 Peachtree Parkway March 7,1980, as supplemented. I I Norcross, GA 30092 I I I

~

c. DOCKET NUMBER I

ll a cONOir ONS s . - /

Tnes captificat. is conditional upon fulfschng tne requirements of 10 CFR Part 71, as apphcable, and tn. Conditions specifi.d below.

I ll l 5 (a) Packaging .

4

, I

( ~

u )

I' (1) ModglNo.: NLI-l/2 e I

q ., .

l (2) Description '

lI f[Y-.

l p

I ~

i i g! A depleted uranium, w'ater, and' lead, shielded shipping cask, encased in i I stainless steel, and equipped with7 balsa impact limiters. The cylindrical N I cask body is 195-1/4. inches. lon~g by)47-1/8 inches 00.? The principal I I shielding consists of'2-3/4 inchesiof. depleted uranium,'2-1/8 inches I of lead,;and 5 inches of (borated): water-ethylene glycol mixture.

ll l

') y, l (g

f .: . . ,

'b i

') , g .

A 7/8-inch thick stainless steel outer shellLis welded to a solid l l stain 1ess steel forging' ati each 'e'n d of the' cask. The. outer shel1 of b 1,l the c'ask is -surrounded by 'a 1/4-inch thick ~ steel water jacket that is

~

I li also attached .to-the end forgings. A water expansion tank is welded l

[p to the water jacket shell.r The inner cask cavity'is formed by a 1/2- p inch thick, stainless steel . cylindrical 'shell; welded at its top end '

l to the upper cask forging and "at its botton end to a circular plate. llI '

Il . $ h ,

I There are two separate configurations;of the~ cask. I I , . s

~

< 1 lp Configuration (A): ' The containment ve'ssel is a right circular stainless f steel shell,12-5/8 inches ID by 178 inches inside length by 1/4-inch h l l thick, located within the inner cask cavity. The containment vessel O I is closed and sealed by a 5-inch thick, composite steel and uranium i ,

I closure head, twelve,1-inch diameter bolts, and a silver plated, I '

I metallic 0-ring. Eight of the twelve clcsure bolts l l l l t i I I I I -

1 l Q9180197850909 N I C ADOCK 07109010 l l PDR >

l l .

I  :

( _________.-----------__________------- ----------- --

m----------------------------------------------AAA----

CONomONS (contmuod)

Pagt 2 - Certificate No. 9010 - Revision No.15 - Docket No. 71-9010 f f 5. (a) Packaging (continued) h I f:

I (2) Description (continued) 1 Il 5

[,: are used to secure the containment vessel to the upper cask forging. Rl g Closure of the cask cavity is by a 1-1/2-inch thick steel closure i gl head, eight,1-inch diameter bolts, and elastomer 0-ring. The radioacti Rj contents are positioned and supported within the containnent vessel lggl G: (inner container) by an aluminun basket and internal support structure. 'ti Ri

['g Configuration (B): The containment vessel is the 1/2-inch thick inner cavity shell. The 1/4-inch thick inner container is not used. The

(!B p

g cask cavity is closed by two closure heads. The inner head is a 6- gg N,; inch thick, composite steel:and-uraniun plate secured to the upper L El cask forging by twelve,11.-inchidiameter bolts and sealed with a silver Ej 3

plated, metallic 0-ring. The outer head is 1-1/2-inch thick steel J1 l: plate secured"to' the top of the upper cask forging by eight,1-inch h

( diameter bolts and sealed with an elastomer 0-ring. The radioactive ts s' contents are positioned and supported within the containment vessel Rl (inner c'ask cavity) by a modified aluminum basket and internal support s tructure. s '

.  ;]l i ,- . ,

,1 - j, lj The package, including impact limiters, has an overall length of 237 inches-and an outside diameter of 75; inches. The maximum weight of lj the contents is 3,000 pounds'. ,Theiweight of the package is approxi- jgj mately 49,250 pounds'. fi 4j - -

r1

' ~

i (3) Dradings '

< 'i gm, .

.E H

~

5t((! -

j The Model No..NLI-1/2 shippingicask,is constructed in accordance with b the following Nationalilead Company Drawing Nos.: -

g s s , . y i

j General O ( .. ,

il i '-),@ .

g ;p; 70514F, Sheet 1, Rev. 7, Cask and Trailer General Arrangenent j%

70514F, Sheet 2, Rev. 8, Cask and Trailer General Arrangement j 70885F, Sheet 1, Rev._3,. Spent Fuel Cask Details !g 70885F, Sheet 2, Rev. 2,LSpent Fuel Cask Details 'I 70885F, Sheet 3, Rev. 2,'Spe'nt Fue.1 Cask Details I 70885F, Sheet 4, Rev.1, Spent Fuel Cask Details E 70887F, Sheet 1, Rev.1, Ou.ter Closure Head l l

Configuration (A) y i

I j 70516F, Sheet 1, Rev. 8, Spent Fuel Cask General Assembly I l 70562F, Sheet 1, Rev. 9. Inner Container I ,

t 70562F, Sheet 2. Rev. 5, Inner Container (,

i Configuration (B) y l I Lj 70888F, Sheet 1, Rev. 3, Spent Fuel Cask General Assembly I l 70886F, Sheet 1, Rev. 2, Baskek Concept I lil 70884F, Sheet 1, Rev. 2, Inner Closure Head .

[I N!

1 Hl p i I I i I 1 -

l ... v . . .. . . . . ... . . . . ,. ,, ..

m----------------------------------A-------------------

li U' " ' '

" ~ ' ' " '

I! , conosis:Ns tcontinu:d>

Il Rage 3 - C:rtificate No. 9010 - Revision No.15 - Docket No. 71-9010 H.

[ (b) Contents i f (1) ~ Type and form of material I'

I (1) Irradiated PWR or BWR uranium oxide fuel assemblies of the following I I specifications:

• li l

[

g PWR BWR Consolidated Fuel Rods 1

Il Fuel form Clad UO2 pellets Clad U02 pellets Clad UO2 pellets Cladding material Zr or SS Zr or SS Zr or SS f

Maximum initial fuel il 5 II(.)'t r fl l

I pin pressure at 100 F, psig 550

' - - '~

200

/

'u. 550 E. L? i I Maximum initial U ..

^

<l l ,

f, content / assembly, kg q 475 197 950

! Maximum average initial. ,

U-235 inrichment, w/o 2.65 ,, ,

3.70 s 3.70 c

l -

Maximum bundle cross '

• t , i section, inches 8.75 .5.75 ' , )< - '

8.'75  !

q-  ;

Fuel pin array size 14x14/15x151 ~ 7x7 ~ , Pins from 7x7, 8x8, '

16x16/17x17 >

l8x8, -

14x14, 15x15, 16x16,

, g.L 3 .J U.

,17x17 in triangular j

_ -?, . r -*

, . pitch i z,

• ~

Maximum active fuel * '

i l length, inches _144 ,.144. . ~144 l ,

s  ;

i

, Maximun specific power, ,

kw/kgU 40 e 27 40 i l

! Maximun average burnup, ' s I

MWD /HTU 40,000** 34,000 40,000 j l l

Maximum decay heat, kw 10.6 10.6 0.6 j j

i Minimum cooling time, ';

days 150* 120 4,380  !

N I

l The PWR type assembly may be shipped either with or without burnable poison rods or R control rods. ll

• Four (4) fuel rods may have minimum cooling time of 120 days.  !

i N l l **PWR fuel assembly may have a maximum average burnup of 56,000 MUD /HTU I; Il provided the minimum cooling time prior to shipment is 450 days and E the neutron shield fluid contains 1.0 weight percent boron. (The l li borated fluid may be lef t in the shielding tanks during the shipment gi g gj ofothercontents.) y I- E I!______________________________________________.-r.

E

c------------------------------------------------h----,

U " U " ' # '

. CONDITlONS (continued) l Page 4 - Certificate No. 9010 - Revision No.15 - Docket No. 71-9010

] 5. (b) Contents (continued)

(1) Type and form of material (continued) f(

W

.l h F

(ii) Solid, non-fissile, irradiated hardware and neutron source components.

[

(iii) Byproduct and special nuclear material in the fonn of irradiated uranium and plutonium oxide fuel rods. Prior to irradiation, the

[

g; i] maximum average enrichnent in U-235 plus plutonium not to exceed y 3.70 w/o and the maximum enrichment not to exceed 4.0 w/o. jE)

K:

F (iv) Irradiated PWR uranium oxide fuel assemblies including additional irradiated fuel rods inserted and secured in the guide thimbles. (g)

The fuel asisemblies shall confonn to the maximum active dimensions g, y as described in Item 5(b)(1)(1), except that naximum initial U lt; h content shall be2495 kg and the' maximum average initial U-235 A n enrichment ,

.v

.shall be 3.35 w/o. -

<n

, P e s . ~ , ,

y (2) Maximum Quantity of material per package ,'

a & O,3, ll

{ (i) Items 5(b)(1)(1) or 5(b)(1)(iv) above: ~one (1) PWR fuel assembly;  !

i two (2) BWR fuel assemblies; or one (1) consolidated fuel canister.

~

l[)

s

\ .

/ e g]

2 Above assemblies to be contained in their respective fuel baskets g' j

i as shown on National Lead Company Drawing No. 70562F, Sheet 1, g y Rev. 8 or 70886F, Sheet 1, . Rev." 2. The consolidated fuel canister jt!

j to be contained.-in Configuration (A) fuel basket as shown on ij i

~

National Lead Company. Drawing No. 70562F;; Sheet .1, Rev. 8. ll Il

~

i.

' e d .

, . o.; l ,7:

(ii) Item 5(b)(1)(ii)apove,weightnottoexceedl',600 pounds.

~

{ . . h y .

cfwe ...,ms. e. ' ]

d (iii) Item 5(b)(1)(iii)'ebove, the ma'ximum mass of U-235 plus plutonium lg}

q shall not exceed 4.0'kg. Fuel rods shall be' contained in fuel j l l baskets as shown on National Lead Company Drawing No. 70562F, l1 j Sheet 1, R,ey. 8 or 70886F, Sheet 1, Rev. 2. I j ,

1 i 3 (c) Fissile Class ' , , ,

III g a , q

- e g

T Maxinum number of packages I '

A per shipment One (1) E 1

.1 Ej -

6. The cask cavity and containment vessel (inner container) must be dry (no free h

]l) water) when delivered to a carrier for transport. Residual moisture must be promptly removed from the cask cavity and containment vessel by the methods

[]

I 4

'1; described in Section XV of the Application. Renoval of residual moisture from 1 -

1 j cask cavity when package is used in Configuration (B) is not required providing I f

ll the decay heat load does not exceed 2.0 kw.

[I '

f 1

7. For the shipment of irradiated fuel assemblies or a canister of consolidated irradiated fuel, the cask cavity canister of consolidated irradiated fuel (if u

i 1! _ present), and containment vessel must be promptly inerted following removal of I li the water from the cavity. For contents not vacuum dryed, the cask cavity and I ff containment vessel must be purged at least three (3) times with argon, nitrogen, or helium. Each purge volume must be equivalent to or greater than the cask l p

j! cavity and containment vessel volume. After the final purge, or following g

i vacuuu drying, the cavity and containment vessel cust be promptly filled with I argon, nitrogen, or helium at 1.0 atm pressure.

1 I t

I

...,,,1 . , , , . . . , . . , , , ,

p. -- - - - -- ----- - - -- - - - - - - - -- - - - -- - - - - - e = = = - - - - -munenm! :

' ' ' ~ ' '

. C:NDITl:NS (contonuedI f Page 5 - Certificate No. 9010 - Revision No.15 - Docket No. 71-9010 1

[

g g 8. Known or suspected failed fuel assemblies (rods) and fuel with cladding defects i g.

1 greater than pin holes and hairline cracks must be chipped in Configuration (A). ;p i ip 1

9. The consolidated fuel canister must be provided with vent and drain lines (openings) )

l q

to permit free draining of the canister.

and drain lines.

No valves can be installed on the vent j lh 3 !F 1 10. Prior to each shipment, the package must meet the tests and criteria specified ;p 1;, in Section XVI of the Application. p ik j

H l 11. The neutron shielding tank must be filled with a mixture of water and ethylene gylcol (52% by volume). This mixture nust not freeze or precipitate in a !g i

j temperature range from -40 F to 330 F. lg.

J. ,

r ,

i 12. The structures used to support the package 'on the transport vehicle must be as s

4;

h j described in the Application.' '

t

, [

l13.

a Any system used for cooling down the package must be drovided with a pressure relief device set so that during the cool-down process, the' maximum pressure in

(

!g:

2, the containnent vessel cannot exceed 310 psig when the package is used in 'E:

[ Configuration (A) or 365_ psig when the package is used in Configuration (B).

{

l14. The systems and components of. each packaging mst meet the periodic tests and

-j criteria specified in Section XVI of the Application. ,

lg-1 . , ,, i is:

1 15. Repair and maintenance must be as described in'Section XVI of the Application. [:

jF:

2 (g 16. As needed, appropriate component spacers mst be used 'in the cask cavity to limit movement of contents durinil shipnent.

(

Ig 1 ,

i .

'g-1 17. Prior to first use, each packaging mst meet.the acceptance tests and criteria rl 3

4; specified in Sections XIII and XIV of the Application when used in Configuration E (A) and in Appendix A to Sections XIII and XIV when used in Configuration (B).

R >< -

l 18. The package authorized by this certificat is hereby approved for use under the general license provisions of 10 CFR 971.12.

i jg 1 t' E

3 19. Expiration date: March 31, 1990. ; -

E 4, t.

REFERENCES l l 3

j NL Industries, Inc. application dated March 7,1980. lEp jSupplementdated: July 11, 1980.

8 Nuclear Assurance Corporation supplements dated: September 9,1982; March 14 and 23, @

f,May24,andJune 29, 1983; and January 28 and August 9 and 30,1985.

1 f E i FOR THE U.S. NUCLEAR REGULATORY C0ft!!ISSION b K

J-1 E t Charles . fiacD nald, C ief Ig y

g i Transportation Certification Branch g f Division of Fuel Cycle and B

] Material Safety, NMSS I .

!,Date: SEP 0 91985 r! IlI

4.# ,

'g UNITED STATES 3 o NUCLEAR REGULATORY COMMISSION 3 rj WASHINGTON, D. C. 20555

%, p Transportation Certification Branch Approval Record Model No. NLI-1/2 Package Docket No. 71-9010 By applications dated August 9 and 30,1985, Nuclear Assurance Corporation requested an amendment to Certificate of Compliance No. 9010 to pemit the shipment of consolidated fuel and revise the inner container lid for Configuration (A).

CONSOLIDATED FUEL Structural By the application dated August 9,1985, Nuclear Assurance Corporation requested an amendment to Certificate of Compliance No. 9010 to permit transport of consolidated light water reactor fuel rods contained in a canister in Configuration (A) of the NLI-1/2 cask. The canister is fitted inside the aluminum fuel basket and appropriate spacer is used to limit axial covements of the canister inside the inner container.

The weight of the package loaded with a consolidated fuel canister is calculated to be 49,250 lbs which is about 2.6% above the design weight (48,000 lbs) of the flodel No. NLI-1/2 cask. However, analysis has shown that this small weight increase has negligible effects on the cask overall perfomance. The inner container (i.e., the containment vessel) is analyzed to show that the increased weight will not have adverse effects on the closure bolts, closure plate, and the inner closure head seal.

Thermal The application requests approval of consolidated spent fuel cooled for at least 4,380 days (12 years) to be shipped in the Model No. NLI-1/2 cask. The consolidated pins do not exceed 600 watts internal decay heat, resulting in estimated maximum fuel temperatures of 426*F and 556*F for nomal and accident conditions. This is significantly less than the maximum fuel pin temperatures of 1013 F and 1102'F reported for 10.6 Kw (150 day cooled) fuel for nomal and accident conditions.

The consolidation of the requested 12-year cooled fuel results in acceptably low maximum fuel pin temperatures. Because the temperatures predicted are well below those for presently approved 150 day cooled PUR fuel, approval of the request is acceptable based on thermal considerations.

I

Criticality Since light water reactor assemblies are designed as undermoderated U02 fuel rods in water, consolidating (i.e., packing more rods) the fuel rods within the same as-built envelope can only decrease reactivity.

The applicant has calculated k p's and kspacing withinXSDRNPfi using NITAWL, a 8.75" and x 8.75" square reg $

KENO-IV computer programs. The application does not state what neutron cross-sections were used. The koo's and k 's however, are obviously correct physically. That the steel contaiN ma,intains its geometry during the accident scenarios.

Shielding The adequacy of the shielding for the proposed 2 to 1 consolidation is based on source strengths of fuel assemblies cooled to 730 days, then multiplying by 2 and comparing (both gammas and neutrons) this new source with the source for 1 PWR assembly cooled for 150 days. This procedure resulted in decreasing the 150 day cooled gamma source strength by 0.69 and increasing the 150 day cooled neutron source strength by 1.40. Thus, under normal conditions at midplane 6 feet from cask, the total gamma dose rate decreased from 3.58 to 2.47 mrem /hr whereas the neutron dose rate increased from 5.01 to 7.01 mrem /hr. Under accident conditions at 3 feet from cask surface, gamma dose rate decreased from a 400 to 276 mrem /hr; neutron dose rate increased from 387 to 542 mrem /hr or a total of 818 mrem /hr compared to the acceptable accident value of 1,000 mrem /hr.

Operating Procedures The actual loading and unloading operation pertaining to the consolidated fuel operations were not submitted as part of this application. Discussions with Nuclear Reactor Regulation (NRR), ORB-5 (between Odegaarden and Miller), indicated the unload operations would be considered by NRR.

The loading operations will be at a Department of Energy operated facility.

REVISED DRAWINGS By application dated August 30, 1985,- Nuclear Assurance Corporation requested an amendment to pemit revisions to the Inner Container Lid of Configuration (A) to the Model No. NLI-1/2 cask.

i i

i t , ,

These changes include the addition of lifting lugs and slots for the alignment pins to make it essentially identical to. Configuration (B) lid. Also, the Inner Container Fill Line and Drain Line Pipes are slightly reoriented to be parallel with the top surface of the lid.

The 1/2-inch Snap-Tite Nipple has been changed to a 3/4-inch Snap-Tite Nipple witbout revising the catalogue number on the drawing. It is assumed the correct catalogue number is " SPEN-12-12F(316)."

The requirements of 10 CFR Part 71 are met for the revised contents.

C ar es . MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS Date: EOIE J

f s

I

, _ -