ML20247B738

Certificate of Compliance 5450,Rev 26,for Models RCC,RCC-1, RCC-2,RCC-3 & RCC-4 Packages.Approval Record Encl

ML20247B738
Person / Time
Site:	07105450
Issue date:	03/20/1989
From:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20247B728	List: ML20247B723 ML20247B738
References
NUDOCS 8903300023
Download: ML20247B738 (7)

Text

, d ,,e ron ,et, u.s. NUCLEAR CEGULATORY COMMISSION I il m CERTIFICATE OF COMPLIANCE to crR 7 FOR RADIOACTIVE MATERIALS PACKAYES ION NUMBER c. PACXAGE. lDENTiF sCATION NUMBER d.PAGE t"JMBER 3. tot AL NUMBER PJ.GES h

.  ! 1.a. CERM HUMBER ttRNY USA /5450/AF 1 5 i

! I E 2. PREAM'BLE

a. This certificate is issued to certify that the packaging and contents described in item 5 below. meets the apphcable safety standards set forth in Tit e 10. Code l i l f i of Federal Regulations, Part 71, Packaging and Transportation of Radioactive Material." l 1 b. This certificate does not reheve the cons gnor from comphance with any requirement of the reguistions of the U.S. Department of Transportation or other i apphcabie reguiatory agencie.. inciuding the government of any country through or into which the package wi'l be transported- ,

i  !

i I 7 g t, 3. T7sgi s;ssuEo oH THE aAsrs or A sArETv Analysis reg 9,HQQGgSsGN ON e ,,,

p b

l Westinghouse Electric Corporation Westinghouse Electric Corporation application I dated December 20, 1985, as supplemented. I i P.O. Box 355 i

! Pittsburgh, PA 15230 1  ;

l' -  % SETId (ll-5450 a coNoirious s si <

• U/ l 1 j

I This certificate is conditional upon fulfilhng the requaements of 10 CFR Part 71, as apphcable, and th,e conditions specified below.

! s - 4 e.  ;

'N I

' ~

i (a) Packaging 7*3 l i

g

(1) Model Nos.

s

< W N ./

/ ] @eA o I i

l i Qy MW M}

b7 l

I i, RCC,n RCC-1, RCC22, RCC ,3, and JCC-4. f) p n

% j ,,.,e>

). . ,p; ' a ,

l y

(2) Description g' (p) j i}{7; .

_s = 1

(

/:7m iy q m

i l Steel fuel $lemebtkradle assembly [cohsisting ofra stro'ngback and l l adjustable' fuel element clamping assembly, shock mounted to a 14-gauge a i steel outer ccontainer byJshear mounts." Neutron absorber plates are I i required for'the contents tas specified. Gross weight'for the RCC and l

! and RCC-4 is i l RCC-'2,is 6,300 ;1bs. JCC-1 and 8,400Jbs. 'pfp#f , [RCC-3 CQ , = is 7.200 f lbs. ,,/j i l l

l (3) Drawings'h g,

ki.Ligy k* (y l

I I The packagings are constructed in accordance w 'ith the following  :

l Westinghouse' Electric Corporation Drawing Nos7: i I

l 2

\ Y. i , l \

j For the RCC and RCC4 pickagingskl596E24, Sheets 1 through 3, Sub 1; I l 1596E25, Sheets 1 & 2, Sub li 1553E31, Sub 1; SKD-86008, Sheets 1 I I

I through 3, Rev. 2. I I

For the RCC-1 and RCC-1 and RCC-3 packagings: 1596E24, Sheets 1 through  !

l 3, Sub 1; 1596E25, Sheets 1 & 2, Sub 1; 1553E30, Sub 1; SKD-86008, Sheets i @o@ I i @o@c- 1 through 3, Rev. 2. I I

i o .,

I$S For the RCC-4 packaging: SKE-85002, Sub 3; SKE-85003, Sub 3; SKE-85004, l jcg Sheet 1, Sub 3, and Sheet 2, Sub 2; SKE-86004, Sub 3; SKD-86009, Sub 2. i ,

~o i

!08 (4) Fuel rod container reinforced 13-gauge steel box constructed in i 8< accordance with Westinghouse Electric Corporation Drawing No. C5650D55, I m I Rev. 7. l oct O'o i N (5) Dimensions and placement of neutron absorber plates in accordance with i unnumbered drawing attached to Westinghouse Letter # LA 89-19 dated I 2L1ALB9, i 1, - --- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - .v '

r

~ '""***"W* (

I U CONDITIONS (continu:d) l gi i l ll '

I i

, i P age 2 - Certificate No. 5450 - Revision No. 26 - Docket No. 71-5450 g l

l I I I I 5. (b) Contents I ,

l I

l (1) Type and form of material l l I I (i) Uranium dioxide as Zircaloy or stainless steel clad unirradiated g i fuel elements. Two neutron absorber plates consisting of 0.19" l ,

I thick, full length stainless steel containing 1.3% minimum boron or I l 0.19" thick 0FHC copper are required between fuel elements of the j i following specifications: g I I i 14x14 15x15 14x14 15x15 17x17 16x16 14x14 y I Zr Zr . p SST Zr Zr Zr i I

h Clad .

(Cla'

. d a ' [SST:g(f Clad / Clad Clad Clad Clad I

, rv s , ,

Pellet diameter 0.344 1 j

w ,/(' 0.322 0.308-0.322 g

! (nom),in 0.367 0.367 0.384 0.834 0.3805 g Rod diameter 0.400- .360- t i

I (nom),in 0.422 x.. 0.422 0.422 0.422 ,7 A)/0,.374 0.374 0.44 I I Maximum fuel M .7. ,AA "" 1 ,

length, in e.,144 I

! s 1144. 120 /y120f 168 4 144 144 l l Maximum rods /

element 180 7 .

- 204 }

C N) [ 'y .

/180 204 V

2641 235 176 ll i 5 g

l Maximum cross section, C.

~

.3, 7y h 4 [v.f'

.

.2

.a

,cf h

f g I

! (nom), in sq . 7.8- 8. 4 ' - Ti ;7. 8 : ' . 18. 4 : " 8.4 7.8 7.98 1 ,

l i

Maximum U-235/

element, kg

.-17.7'

. . ao j 18.5,4 18.3].{yl3: .

t i,t;; m 18.7f 5

16.95 16.6 19.0

[

gl g ,.s.,

((144at) , ,

( , ,J i s .

7 19.8 ll C(-(168"L) 4 "

d; ,

? < ,

^

ll, 4 Maximum U-235 > '

O' enrichment,w/o 4.0' 4.0 4.0 l

d j 3.65 3.65.l' '

3.65 3.85

{0 S i' (ii) Uranium dioxide as Zircaloy clad unirradiated fuel elements contained g g

( within the Model No. RCC24 packaging. Two neutron absorber plates I i consisting of 0.19" thick carbon steel are required between fuel I 5 elements of the following specifications: O N ll i l 17 x 17 h Type Zr Clad g Pellet diameter, in 0.308 - 0.322 I Rod diameter, in 0.360 -0.374 l i I

Maximum fuel length, in Maximum rods / element 168 264

[gl '  ;

( Maxirnum cross section, p 4 (nom), in sq 8.4 E 4 Maximum U-235/ element, kg 19.3 I Maximum U-235 enrichment, w/o 3.55 l

i (o

4 il l l i

I_

- - _ _ _ ,r>x m _ _ --- - l lo I l

______1_____________o

conosinous ccontonued)

I i Page 3 - Certificate No. B450 - Revision No. 26 - Docket No. 71-5450 f I-1 (iii) Uranium dioxide as Zircaloy clad unirradiated fuel elements. I Two neutron absorber plates consisting of carbon steel, 0.035 I:

inchesigthickness,with4milsofGd0 (0.02 gm -

Gd0/cm)affixedtoeachsideofthepla.te 2 are required [:

i bekw$enfuelelementsofthefollowingspecifications: g, l.

14x14 15x15 14x14 15x15 17x17 17x17 16x16 16x16 1:

Zr Zr SST SST Zr Zr Zr Zr i  !

Type Clad Clad Clad Clad Clad Clad Clad l C_l a_d,

(( I L

Pellet diameter 0.344- g I (nom),in 0.367 0.367 0.322 0.325 r I Rod diameter 0.400- d. N

0.384@*.384'{D.322["0.308 V // I (nom),in 0.422 0.422 \ 0!422 0.422 0.374 0.360 0.374 0.382 5 Maximum fuel sV 7h E J

1ength, in Maximum rods /

144 eb

,144 120 120 168 168 ' ,144 150 [

g. j element 180 ~2 04 - 180 204 264 264 4 235 ', 236

, Maximum cross '

x.1 , ,e m - v-section, (nom), in sq 7.8.,

!~

8.4 W. x s7.8, \ 8.4 S 8.4' ( 8.4

/ ,/J ^

7.8(,#7.98 E

E-Maximum U-235/

element, kg 22.1 21.5

/  ?' \ i _.

223.1 /s 22!0 121.75 219.9 20.7 1 21.1 O [4 I

, -[744,t)(344,g), g t f.

y n 25.5 23.3. r .7 E- l

.< I ? (168"L)(168"L); E 4

l Maximum U-235 J e j*! [ ? < [: 1 [C lj 1 enrichment, w/o 4.2' 4.3 :4.2.14.35:t!f4.7~ 4.3 4.31 4.2 g ]

. < . r.

(iv) Uranium dioxide as'Zircaloy'or stainless steel clad unirradiated fuel E rods of the following specifications: ( '

E i

~

E Type SST C1ad Zr Clad Zr Clad 3 Zr CNd Zr Clad Zr Clad [

i Pelletdiameter(nom),

in 0.384

^

0.344-

) "

~

Y 0.308- ' 0.322 0.3805 0.325 f3 E l Rod diameter 0.367 0.322 5 in 0.422 0.400- 0.360- 0.374 0.44 0.382 E Fuel length (max), 0.422 0.374 in 120 144 168 144 144 150 l

g U-235 enrichment (max), g w/o l Note (1) 4.0 4.0 3.65 4.0 3.85 --- I Note (2) 4.2 4.2 4.3 4.3 --- 4.2 Nl l

Note (3) --- ---

3.55 --- --- ---

ll t

i E:

E E

~

t R:

5:

l'

.-.-__,,,,.-_w.,.;.,,.._.._...._.,._,,,,,_E lE

i ~ T conoursons tcontmuod)

" ' * * * " " " " " " " l l ll l I!

s l

Page 4 - Certificate No. 5450 - Revision No. 26 - Docket No. 71-5450 fI  !

I I Notes: i l l l (1) Two neutron absorber p(lates consisting of 0.19-inch thick, full length stainlessl 1

steel containing 1.3% minimum) Boron or 0.19-inch thick 0FHC copper are required g i between the rod boxes. I )

i i I

(2) I l Two with 4neutron absorber mils of Gd,0 p(minimum 0.02 gm Gd 0 /cm ) affixed to each side of thelate l l 3 plate are require 8 5etween the rod boxes. 3 p l d

! (3) Two neutron absorber plates consisting of 0.19-inch thick carbon steel are required g l

between the rod boxes.

c gR{gu l l

(. \,V i (2) Maximum quantity bf material per package si i A/

• p(~T ll l i (i) Forthe'contentsdescribedin5(b)(1)(i),5(b)(1)(ii),and i

5(b)(1)(iii)

-) r,*

g

-~

g)l 1

1 ,

Two fuel elements.

.s q ., z i[eg', ' fS se ll ,

O f

~

h (ii)For'thecontentsdes'cribe' din 5'(b)(1)(iv):

a .. .

!: L j ' ' m N d Two-inner LeontainersJcontaining.not more 'that 804ilograms U-235. ll  !

4 -

P gr r ; a . g 3  % 11 1

5. (c) Fissile Class I -

( ;j}(( s

(

g 6. Fuel rods must be blosely packed :indhe fuel ' rod container on-no more than an d equivalent metal-to-metal square lattice. Partially loaded fuel rod containers a must be fitted with a minimum of'three, equally spaced blocks, of which the  !

noncombustible portion of the blocks and the method by which they are secured must

~

4 I assure that the rods are. maintained on no more than anl equivalent metal-to-metal  !

l square lattice within the' fuel. rod container. ,

q .s .. ; _. 1 I A 7. Each fuel assembly must be unsheathed or,must be enclosed in an unsealed, 4 polyethylene sheath which will not extend beyond the ends of the fuel assembly.

The ends of the sheath must not be folded or taped in any manner that would l prevent the flow of liquids into or out of the sheathed fuel assembly. i q

( l l 6 Alternatively, the fuel assembly may be enclosed in an elongated plastic bag or sheath g i along its full length. At the bottom end of the fuel assembly, the bag will be cut offg i or folded back to assure that the entire cross section of the lower end of the assemblyi

! is unobstructed. When folding is used, the portion of the sheath that is folded back I ,

j will be cinched with tape near its end to hold it in place, and the length will be such hl

that when the assembly is loaded in the packaging, the folded sheath will be clamped in I d place in at least two grid locations. The top end of the bag may be gathered together y ,

and taped closed. However, the top end then will be slit on all four sides. The slitsu

~

will run perpendicular to the axis of the assembly and will extend the inner distance li between the top nozzle pads and spring clamps (approximately 60% of the length of each g

a side). The slits will be made in a plane near that formed by the top of the fl g

l pads and clamps. gj I

l l '

5 l 4

- . _ m..... _ ,.... m.~.m ... _..~. ... _

llll: ,

'.'"' conom:ns ccontinaw)

" ' ' ' "' " M*

Page 5 - Certificate No. 5450 - Revision No. 26 - Docket No. 71-5450  ;

I I

! 8. The package authorized by this certificate is hereby approved for use under the 1 l general license provisions of 10 CFR 571.12. l l l l 9. Expiration date: July 31, 1991. g i I i REFERENCES I I i l Westinghouse Electric Corporation application dated December 20, 1985. l l t i Supplements dated: April 28, July 1, July 21, 1986, and January 4, 1989. g i i i I i Department of Energy supplement pp>< dated:, MarchT1,019_84,j*~u( p l r+ bV FOR THE U.S. NUCLEAR REGULATORY COMMISSION l

l yy,

• y. y s

- < O g

-n.

y +

h Charles E.;MacDonald,"Chie

& l 1

Transportation Branche- ll

' ; Division;of Safeguard's / l l

f .  ; f and Transportation, LNMSS g N it f'f.

l i

N VAR 2 0198a .

ra l l

N

(

Date: -

J my o

,f, -

h I

I 1, -

( ,

4 s ,-

,7 g l , * .L; .

e d,3' g ]

g- s. <

e

'2 c

, y y y J j '

t ' ;; 1 :* , g l h ,

4 -

(.[ p j

( u - -

.s  ; .

g .1 1

+

n, -

p l

l ,

cj[*

lf a @

g  ; . ,-  ; ^

y p n- . g 4 a N i W p, 4 a N l 4 N A B 5 i i y N i

( si H l '

l l

1. 1

$ n I

l II l t l l l N B 1

R I Hj i a; p

===ws--===vy ----vy-mmmmyyss,-mmyymmyymmm.myymyyym . ,,m; l

im_________ . _

m

1. % UNITED STATES

-[ k NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 rn  : [-

'+, . , . . . /

Transportation Branch Ap3roval Record Model ios. RCC, RCC-1, RCC-2, RCC-3, and RCC-4 Docket No.-71-5450 Revision No. 26 Certificate of Compliance No. 5450, Revision No. 26 is being issued to correct several typographical errors in Revision No. 25.

Charles E. MacDonal , xD,l/

hi Transportation Branch Division of Safeguards

and Transportation, NMSS 1

i l  !

)

,,y -- - '

- * '

• ADVANCED NUCLEAR FUELS CORP.

ATTN: MR. L. D. GERRALD P. 0. BOX 130

.. RICHL,*.ND WA 90352 ALABAMA PDWER CO.

ATTN: PLANT MANAGER DRAWER 470.

ASHF0,RD - AL 30312 ,__,

BABC0CK & WILCOX CO.

ATTN: MR. A.F. OLSEN P.O.80X 11165 LYNCHBURG VA 24506 BATTELLE COLUMBUS LABORATORY ATTN: MR. HARLEY L. TOY 505 KING AVENUE COLUMBUS OH 43201 DEPARTMENT OF ENERGY ~

ATTN: MR. E. McCALLUM DP-4 WASHINGTON DC 20545 DUQUESNE LIGHT CD.

ATTN: MR. J. D. SIEBER P. O. BOX 4 SHIPPINGPORT(BEAVER VALLEY)PA 1507T IRT CORPORATION ATTN: MR. PAUL R. MASCHKA. RSO P.O.80X 85317 SAN DIEGO CA 02138 NATIONAL NUCLEAR CORP.

ATTN: MR. RICHARD N. OLSEN 1904 COLONY ST.

MOUNTAIN VIEW CA 94043 NEW YORK POWER AUTHORITY ATTN: MR. WILLIAM G. GREENMAN P.O. BOX 215 BUCHANAN

• NY 10511 -

NORTHEAST NUCLEAR ENERGY CO.

ATTN: MR. JOHN P. KANGLEY P.O. BOX 128

• WATERFORD CT 06385 TENNESSEE VALLEY AUTHORITY ATTN: MR. R. L. GRIDLEY 02/02/1989 09:01:08 ,

LIST OF USERS FOR CERTIFICATE - 5450

. FOR MODEL - RCC SN 157B LOOKOUT PLACE CHATTANOOGA TN ST401 VIRGINIA ELEC. & PWR. CD.

ATTN: V.P. NUCLEAR OPS P.O. BOX 26666 RICHMOND VA 23261 WESTINGHOUSE ELECTRIC CORP.

ATTN: MR. A.J. NARDI P.O. BOX 355 PITTS8URGH PA 15230 WOLF CRFEK NUCLEAR OPERATING C -

ATTN: mR. JOHN A. BAILEY P. O. B0X 411 BURLINGTON KS 86839

__mc ,-=-m . _ . - -