ML20209D404

Certificate of Compliance 5942,Rev 12,for Model 700. Approval Record Encl

ML20209D404
Person / Time
Site:	07105942
Issue date:	09/04/1986
From:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20209D396	List: ML20209D392 ML20209D404
References
NUDOCS 8609090285
Download: ML20209D404 (6)

Text

'

I mac rones sie u.s. NUCLEAR REGULATORY C MMISSION I.

I *al CERTIFICATE OF COMPLIANCE I I to crR n FOR RADIOACTIVE MATERIALS PACKAGES I 1 a. CERTIFICATE NUMeER D REVISION NUMBER c. PACKAGE IDENTIFICATION NUMSER 6 PAGE NUMBER e. TOTAL NUMaER PAGES g 5942 12 USA /5942/B( )F 1 4 i I .PRErwetE 1 I a. Tnis c.rtificate is inueo to certify tnai tne packagma ano cententi ae.cnneo in item s neiow. meets ine appucani safety stanoaros sei fortn in Titi. io. code I g of Federal Regulations, Part 71," Packaging and Transportation of Radioactive Matenal." l I n. This emficate ooes not reiseve the consignor from compnance with any requirement of the reguistions of the u.s. Department of Transportanon or otner I I appocaele regulatory agencies. including the government of any country through or into which tne package will be transported. I I I I I l 3T g igicAy S;SS gUCN THE BASIS OF A SMETY ANALYSIS RE T THE KAGgS G OR PPL CA ON 1 I g General Electric Company General Electric Application dated May 30, 1985, I I Vallecitos Nuclear Center as supplemented. I I Pleasanton, CA 94566 I l ,.

3 I l . i OOcxET NuM ER - c 71-5942 1 4 CONOiTIONS ~,* -#

This certificate is conditional upon fulfilleng tne requirements of 10 CFR Part 71, as appacable, and the conditions specified below.

5 l (a) Packaging , -] ' +

l l - v '

i g (1) Mode 1~No.: ~

700 _ I g .  ? ,

l g (2) Description. ,

J. i i tf ... - . l l Alsteel encasedElead' shielded shipping cask enclosed'by a double- 1 I walled protective Jacket of;the; same shape with a rectangular baseplate. I I The' cask is a ' double-walled steel circular cylinder,(37-inch-diameter I I

by'65-inch high withia centraLcavity 15-inch-diameteruby 40-inch l l high. Appioximately-10.25 inches'of' lead surround the: central cavity. l g The cask ris equipped withta cavity drain' line, pressure relief valve s i I s'et'at 100 p~sig, and:lf fting l device. -Closure .is accomplished by a I I silicone rubber gasketed and^ bolted' steel lead filled plug. The 1 I maximum gross (weight /of thel package (contents, cask ~ assembly, protective i I l Jacket and base) is135,500 pounds; i  !

3 l 1 The cask may' be modified with a 14-inch high cavit extension with an I I additional silicone rubber gasket. The. modified cask is 79 inches high. The maximum gross weight of the package (contents, modified l l cask assembly, protective jacket and base) is 40,200 pounds, i

g i i I I (3) Drawi ngs -

I c 1 1 l

1 The packaging is constructed in accordance with the following General l Electric Company Drawing Hos.: 129D4768, Rev. 3; 12904769, Rev. 4; l and 129D4770, Rev. 5.

y i l i I !p I Lifting and/or tie-down devices W1ich are a structural part of the l package must be in accordance with the above drawings.

l l l 1 I I N I I I I l l I

(

l l

l l l l l

8609090285 860904 l l

l' PDR ADOCK 07105942 1 C PDR l i

l 1

I

~ ~ ' ~

conolTions (cor,tinued) * "" M "G* M*w l Page 2 - Certificate No. 5942 - Revision No.12 - Docket No. 71-5942 g I I I

I

5. (b) Contents l I

! (1) Type and form of material l

l (i) Byproduct, source, and special nuclear material as solid oxide or  !

I metal in the form of fuel rods, or plates, fuel assemblies, or g I meeting the requirements of special form radioactive material . I I I l (ii) Co-60 metal contained within sealed liner and sleeve described in I l Neutron Products, Inc. Drawing Nos. 240139, Sheets 1 through 3, l l Revision No. F and 240138, Revision No. . y I I I (2) Maximum quant <ty of material per package i I

Not to exceed + T 700, 2poundk(inc1[dfjgjshoring), VI and y I (i) 740 gm U:235, provided that the ma~xim,,um,U-235 enrichment does not  ;

I exceed'6' weight percent; or / ' g I es O_ i (ii) 1,200 gm U-235, provided that the fuel material is in the form of I l MTR-type' fuel elements with a minimum 1 active fuel length of 23 I i inches;

~

orp. ,

ry j l

• • r; l , 73 , ._m .  ;

I (iii) !220 am fissile materiali'or ( ; g, - i i s ,.

f  ; -

7y %v g l (iv) 1,650 gm U-235,; provided that ,the maximum U-235 enrichment does I l cnot exceed 3;5~ weight percent'andithe fuel material is in the

~

I g r form of_88 rods, loaded: with 0.'376-inch' diameter pellets with a -

l l ' minimum? active fuel length of 37 inches; -

or 04 g

3 ,i I (v) those valuesiresented1fn' Figure 1, U0,, Weight Limits for Model 700 1 I Shipping Container, of Exhibit A-to this application, applicable l l to fuel material in .the form of' rods with a minimum pellet diameter I

of 0.40' inch; or s. ;

l g .. s

~ ,

I (vi) 5,100 gm U-235, provided the fuel is in the form of ETR-type fuel i I elements (GETR Fuel). with each element containing no more than I 510 gm U-235 and inserted in the spaced stainless steel fuel I

{ shipping basket described in GE Drawing No. 10604150, Rev. 0.; or i l l l q (vii) 6,200 gm U-235, provided the fuel is in the form of MURR TRTR i i type elements containing not more than 775 gm U-235 per element; p i loaded and spaced in the stainless steel fuel shipping basket as I I described in MURR Drawing No.1228, Sheets 1 thru 5, Revision 0. I l Fuel elements shall have at least 150 days cooling time since ,1 y last reactor operation; or i l i I (viii) 3,510 gm U-235 provided the fuel is in the fonn of MTR-type fuel g I elements with each element containing no more than 351 gm U-235 I l and inserted in a spaced stainless steel fuel shipping basket I

]

lq described in GE Drawing No.106D4150, Rev.1 for GETR fuel . A shoring device to limit vertical motion of the fuel elements must l q be included, p I I I I I I II ;I l1.

---

r-__ww___________,,,________w, ll

l conomons tcontinvec) ' ' * ** M w " = " "

I r l Page 3 - Certificate No. 5942 - Revision No.12 - Docket No. 71-5942 I

[

I l 5. (b) (2) (continued) l I

I I

(fx) 7,020 gm U-235 provided the fuel is in the form of MTR-type fuel l l elements with each element containing no more than 351 gm U-235 I i inserted in a spaced stainless steel fuel shipping basket described I i in GE Drawing No. 10604150, Rev.1, for 24-inch length fuel, l Each shipment must contain 20 fuel elements in 2 fuel baskets f l

l with the spacer plate shown on GE Drawing No. 21886061, Rev. O, l l located between the baskets. A shipment may contain less than 20 t I

elements provided each absent element is replaced by an aluminum I

or steel spacer in the form of an open-ended pipe with a minimum I-i outer diameter of 2.5 inches and a minimum wall thickness of [

i 0.125 inches. The space must be of sufficient length to replace r I the absent fuel element? ~ es 1 c D,. i C O i,f f l r

f (x) 7,000 gm U435'provided the fuel is in g ,the form of MTR-type fuel I i sections with each section containing 'no more than 175 gm V-235 L inserted into the stainless steel Cask Divider (fuel shipping i

l basket) shown in General Electric Company [ Drawing No.183C8253, (r i Rev. ~1. When a shipment contains less than#the maximum number l l (40) of' fuelnsections, empty fuel section basket spaces must be l I

provided withJan aluminum or stdeltsp'acer in,.the form of an open- I ended pipe with a minimum' outer; diameter of 2.5 inches and a I l ~

q 'Y minimum wall thickness'of 0.125-inches. TheIspacer must be of E g sufficient l_ength' to replace thetabsent fuel ' sections. [

1 m. , .; w 4 c' n , f, < r I (3) Maximum quantity ofqradioactive- decay-h~ eat pe,r pack (age t I '

c,. :q;i;,} l1 ; ' -

q l l

i (i) 6,500 wattss fo'r dry shipments, or

~'1 _ ..c-l' 4

Q [

y (ii) 1,500 watts ' forTwst' shipments ~,'provided that-the cavity shall [

i t contain at least; atl,000 cu in air void (at' standard temperature r I and pressure) at the time of delivery teia carrier for transport. t I -

W t l (c) Fissile Class ', . III

[

l Maximum number of packages per shipment 2 [

'n The liner required for Co-60 metal which does not meet the requirement for i

j4 6. t lI special form radioactive material, must be dried, leak tested, and back-filled j with an inert gas in accordance with Enclosure 2, Rev. 2 to Neutron Products, Inc. letter dated February 28, 1986.

L

[

y f

l t q 7. Shoring must be provided to minimize movement of contents during accident conditions t I of transport, t I [

U

8. Prior to each shipment (except for contents meeting the requirements of special I l be leak tested by a method capable f g form of radioactive determining thatmaterial),

a leakagethe pachge of 10 mus}/s at standard temperature and atm an g q pressure is not exceeded. t 14 I d 9. Prior to each shipnent the silicone rubber lid gasket (s) must be inspected. E l This gasket (s) must be replaced if inspection shows any defects or every twelve (12) months, whichever occurs first. Cavity drain line must be sealed with [

g appropriate sealant applied to threads of pipe plug. t g

I I .L I --------------,.ir-ww--r--------________----__,I I

conomous tcontinued)

' " " " < m u' " M ' m

! Page 4 - Drtificate No. 5942 - Revision No.12 - Docket No. 71-5942 l I I I

I I

I l 10. The applicant must confirm annually that the pressure relief valve is operable I i at 100 psig. ,1 l

I I 11. Een needed, sufficient antifreeze in the cask must be used to prevent damage of g I any component of the package due to freezing. I I

I l 12. Fabrication of additional packagings is not authorized.

l I I l 13. The package authorized by this certificate is hereby approved for use under the g I general license provisions of 10 CFR $71.12. g I

I I 14. Expiration date: July 31,1990. 1 l ,,

,x O ,M !~ iQ > I I

i . Y REFERENCES " U/

i ( * ,b ' Ms*^ l l General Electric application' dated May 30, 1985. / g I

I a

Supplements dated: June'.5 and 7, August 7, and September 1.6,4985; and February 28, O i I

l May 8, July 11, and August 15~,s1986. ,

'r '/ ~ l I

, gf x ,3 .fwf u University of Missouris letter ' dated' March _.20,,1980. '-U (-) i l H-  ? , t:,? . (f A i 1 Appendix 6-A regarding University'of Missouri!,s quality; assurance. program is not I I Lo ;; I I considered part of th}s a'pplication. '

.%.. s ;c ,,'

7 l

~

1 l Neutron Products, Inc; supplements datedfDNov'e'mbee>11 1985; andfebruary 28, March 11 l l and 31, and April 1 and 10s;1986.., D<1 ,

.! - 4 i l .

'

,  %. i I ' ~ ._.FOR1THE U.SENUCLEAR REGULATORY COMMISSION I q .m . =

i 1 s'. p l

1 n W l I

I k Charles E. MacDonald, Chief g 1 U ~ Transportation -Certification Branch I 8

Division of Fuel Cycle and I h Material Safety, FNSS I II I ll Date: SEP 0 4 SE l i i i I I I I I I I

, 1 1 I i l

I i I I I I I I lI i

, I I I I I N I Il I I

,. li 4

, )

1. p%g o,, UNITED STATES E" .g NUCLEAR REGULATORY COMMISSION 5 ^j WASHINGTON, D. C. 20055

/

Transportation Certification Branch Approval Record Model No. 700 Package Docket No. 71-5942 i

By application dated February 28, 1986, as supplemented May 8, July 1 and 11, and August 15, 1986, General Electric Company (GE) requested an amendment to the Model No. 700 package to permit the transportation of up to 7,000 gm U-235 in MTR-type fuel sections. Each fuel section contains no more than 175 gm U-235 and is inserted in a stainless steel cask divider shown in GE Drawing i No. 183C8253, Rev. 1. When a shipment contains less than the maximum number.of

. sections allowed, empty divider spaces will be provided with an appropriate aluminum or steel pipe spacer. The use of spacers is also requested for a.

previously authorized fuel loading (Item 5(b)(2)(ix)).

STRUCTURAL The applicant has performed finite element computer analysis as well as hand calculations to show that the cask divider welds will not fail due to 30-foot free drop of the package. The use of spacers minimizes the shifting of fuel material components during shipment. The maximum weight of the fully lo'aded basket and fuel material is approximately 400 pounds which is well below the previously authorized 700-pound limit. We agree with the applicant's conclu-sion that the cask divider will be able to maintain its loaded configuration under the hypothetical accident conditions of transport.

CRITICALITY GE has established the subcriticality of the Model No. 700 package when loaded with fuel in the form of MTR-type fuel sections, with each section containing no more than 175 gms U-235 inserted in a spaced stainless steel fuel divider (0.1875-inch vs actual 0.25-inch (less reactive) thick walls) with the total i

fissionable loading not to exceed 7,000 gms U-235.

i The KENO IV code with the 27-group neutron cross-section set was used with generalized geometry to describe the flooded loaded package in the ten (four sections each) fuel divider locations. The lead reflector followed by a water all-around reflector was modeled in the criticality calculation.

Two flooded packages in contact and surrounded by water reflector were

+

calculated:

(a) Fuel / water in each divider pushed as close to one another towards center;

Max keff = 0.928 (av. keff = 0.892).

l (b) Fuel / water in each divider pushed out towards lead reflector; max keff =

0.869 (av. Keff = 0.834).

4 i

i

. - , . --.,--.----,-----.-,,..,n _ - - . . , - _ - - - - . - . . . . , . , , ~ ,

2 Also calculated to estimate homogeneous vs heterogeneous modeling of fuel; 2 cases of 4 fuel dividers as a 2x2 array:

(a) Discrete fuel plate-water modeling - keff = 0.726 (b) Homogeneous fuel plates-water modeling - keff = 0.724.

The NRC staff has analyzed 9 fuel locations (3x3 array) homogenized U-235/H O 2

regions with cask divider with a' total of 8,540 gms U-235 vs 10 fuel locations with a total of 7,500 gms U-235 actually in the divider. The staff KEN 0 IV (123-group) (NUREG/CR-0200) analysis gave a keff of 0.97610.007, which when nomalized to 7,500 gms U-235 would reduce to a keff of 0.976-0.077 = 0.910 versus 0.892 which is in good agreement with the GE calculations.

OPERATING AND WELDING PROCEDURES GE has provided detailed loading / unloading procedures for the Model No. 700 package with the shielded extension (August 15,1986). In addition, a Structural Weld Inspection procedure has been provided (July 11,1986).

The applicant and the NRC staff have concluded that the revised packaging and contents meet the requirements of 10 CFR Part 71.

FCharles E. MacDonald, Chief U Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS SEP 0 41986 Date:_

l s

l

_ _ _ _ _ _ _ . - _ _ _ _ _ _ _ _ _ _ _ . . - _ - _ - . ,