ML20129F540

Informs That Westinghouse Does Not Intend to Request Renewal of Existing NRC Coc USA/5450/AF That Expires 960930

ML20129F540
Person / Time
Site:	07105450
Issue date:	09/30/1996
From:	Sanders C WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:	Travers W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
CON-NRC-96-049, CON-NRC-96-49 NUDOCS 9610040173
Download: ML20129F540 (1)

Text

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Westinghouse Commercial Nuclear Drawer n Electric Corporation Fuel Division fgggaYeg2so e

NRC-96-049 September 30,1996 U.S. Nuclear Regulatory Commission ATTN:

William D. Travers, Director Spent Fuel Project. Office Office of Nuclear Material Safety & Safeguards Washington, DC 20555-0001

SUBJECT:

RC_C SHIPPING CONTAINER COC (USA /5450/AF)

The Westinghouse Electric Corporation does not intend to request renewal of the existing USNkC Certificate of Compliance USA /5450/AF that expires September 30,1996. Enclosed fer reference is a copy of the current certificate.

If you have any questions or require additional information, please write to me at the above address or telephone me at (803) 776-2610, Extension 3426.

Sincerely, WESTINGHOUSE ELECTRIC CORPORATION xAn C. F. Sanders, Manager Nuclear Materials Safety and Safeguards Enclosure

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9610040173 960930 PDR ADOCK 07105450 C

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tM 00rio The I$tshhghouse Commerch/NuclearFue/Dhhion - Winnerofthe 1988MalcolmBaldnpeNanonalOualii)' Award

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I 6au u.s. NUCl. EAR REGUI.ATORY COldedlSS pone eis I

CERTIFICATE OF COMPLIANCE il I

'0 C'" 7 FOR RADIOACTIVE MATERIALS PACKAGES Il 1 s.CERflFICATE NUMSER Il REVISION NUMBE.R

c. PACKAGE IDENTIFICATION NUMBER a PAGE NUMBER e foTAL NUMBER PAGES i

5450 33 USA /5450/AF 1

7

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.PaE4 stE

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a. Tnis c rtificat. is issu.d to certifgtnat tn. packaging and cont.nts d. scribed in item S b. low, meets tn. apphcabi. safety standards s t forth in Tati.10. Cod.

p g

of Federal Reguistions. Part 71,"PaCaaging and Transportation of Radioactiv. Matenal."

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l

b. rnis c.nivicat. do.. noi r.i..

in. consignor trom compnanc. w.in any reauer.m.nt av in. r.guistion. or tn. u.s o.panm.nt or Transponai,on or ein.r ll l

appncabi. reguistory agenci.e. inciuding in. government of any country inrouan or into wnicn tne pecuage wiii be transported.

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Westinghouse Electric Corporation Westinghouse Electric Corporation lI I

P.O. Box 355 application dated December 20, 1985, il l

Pittsburgh, PA 15230 as supplemented.

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71-5450

,.. oocar NUM.ER I

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a coNoirioNs l

rni conificat. i condmonai upon tummnagt.abirements or to cFA Pan 71, as.ppheabl., and tn.condstsons sp.ctfs.d below.

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N I

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I (a)

Packaging

s. j,

g i

y

<7, i

RCC, Rh RCC-3., and RCC-4 c'

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(1)

Model N n.:

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/

l

,s g

I (2)

Descriptfon

- 9 I

l

?. (4 W, -

l Steel fud eleme t cradk%spembl adjustahls fueF;g'a}emenDclany 1*] y consisting of a str'osgback andHsembly, s I

l i

I I

steel outer co r'by sheP9s4dts'. Neutron absorbi'r plates are 1

I required'for the.

Tis hdcyteds Gross weight.Jor the RCC is 6,300 I

I lbs.,RCC-Fand

, -T,2uir 7tgr. ', and-RCC-4 i s 8,400 l bs.

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,. w s

.g/

9, /. N g[y l

l (3)

J/ %*

Drawings Thepackaging$

w.

i y

sthconstructedinaccordanceNththefollowing l

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Westinghouse Electri orporation Drawi Nof.:

l l

For the RCC packaging:

CCLOO2, Sheets 1 through 3, Rev. 2.

I For the RCC-1 packaging:

RCCL102, Sheets 1 through 3, Rev. 2.

I I

For the RCC-3 packaging:

RCCL302, Sheets 1 through 3, Rev. 2.

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For the RCC-4 packaging:

RCCL402, Sheet 1, Rev. 3; Sheets 2 I

l through 3, Rev. 2.

l l

(4)

Fuel rod container reinforced 13-gauge steel box constructed in accordance l

I with Westinghouse Electric Corporation Drawing No. C5650D55, Rev. 7.

I I

I I

(5)

Dimensions and placement of neutron absorber plates in accordance with l

l unnumbered drawing attached to Westinghouse Letter # LA 89-19 dated y

i 2/14/89.

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1

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coNOITCNS (continued)

U.S. NUCLEAR NEOULATORY COtetelSSION j:

I I

i l Page 2 - Certificate No. 5450 - Revision No. 33 - Docket No. 71-5450 i

l 5.(b) Contents E

I l

(1)

Type and form of material l

I I

(1)

Uranium dioxide as Zircaloy or stainless steel clad unirradiated fuel I

elements. Two neutron absorber plates consisting of 0.19" thick, l

full length stainless steel containing 1.3% minimum boron or 0.19" i

1

]

g thick 0FHC copper are required between fuel elements of the following i

g specifications:

I i l 1

14x14 15x15 14x14 15x15 17x17 16x16 14x14 i

I Zr Zr SST SST Zr Zr Zr I i l

Iyag Clad Jladm rfW C1ad C1ad C1ad I

i Pellet diameter

$._$44'-AD ncug[Cld_

ig q

0.308-i I

(nom),in QV.367 0.367 0.384 0.

4 I

Rod diameter y

0.400-p 0.322 0.322 0.3805 il

.360-ll l

(nom), in 0.422' O.422 0.422 0.422 74 0.374 0.44 il i

I Maximum fuel I !

j length, in N 44 144 120 144 144 j

i i

Maximum rods /

i i

element D

lg 20 80 26 O 235 176 l !

1 Maximum cross b h

it !

t 4

O in l

I

section, 1

l (nom), in sq i

Maximum U-235/ p--

7,;-

E.

~4 4

8.4 7.8 7.98 ji i

/

n i

element, kg g Q

17.T c

i t

g 1

' 16 5 16.6 19.0 lg I

e 9 '.6 (1(EL)

l i

h k [

(

"L) l Maximum U-235 M

,/

l 6

M.65 l

enrichment, w/o f/g

.0 5

4.0 3.85 ip

-J O

n I

(ii) Uranium dioxh as Zircaloy clad uni rrad ed fuel elements contained I

nd(larerequiredbetweenfuel within the Model & RC -4 nack Two neutron absorber plates j

l consisting of 0.1 P th elements of the following $

tea j

spec ications.

i g

I JlE i

17x17 l

IXE1 Zr Cla_d j

l Pellet diameter, in 0.308 - 0.322 i

Rod diameter, in 0.360 - 0.374 l

Maximum fuel length, in 168 l

l Maximum rods / element 264 I

Maximum cross section (nom) in sq 8.4 i

l Maximum U-235/ element, kg 19.3 e

i Maximum U-235 enrichment, w/o 3.55 l

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i l

I l

i i

l i

I 1

CONDmONS (continu d)

U.S. NUCLEAR REQULATORY COMMISSION l Page 3 - Certificate No. 5450 - Revision No. 33 - Docket No. 71-5450 l

=

1 g 5.(b) (1)

Type and[orm of material (cont 1nued)

~~

I I

(iii)UraTiumdioxideasZircaloycladunirradiatedfuelelements.

Two

l I

neutron absorber plates consisting of carbon steel, 0.035 inches in l

l thickness,withacermetGg03 coating affixed to each side providing l

g a total of 0.054 g-Gd 0 /cm for both sides of the plate, are j

required between fuel ebements of the following specifications:

2 q

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14x14 15x15 14x14 15x15 17x17 17x17 16x16 16x16 l

1 Zr Zr SST SST Zr Zr Zr Zr l

Iygg

[.]3L

[lai

[.litd_

C,liuL.

[. lad _

C1ad

[ lad _

[. lad _

i Pellet diameter 0.344-39 }

. hhp.322 l

(nom), in 0.367

\\,45 0

6 0.308 0.322 0.325 i

Rod diameter 0.40 Q

v l

(nom),in 0.4 U.422 0.422 0.422 0.Np 0.360 0.374 0.382 I

Maximum fuel l

1ength, in 144 120 120 168 8

144 150 g

Maximum rods /

o I

element GAf0 D 4

180 204 4'

254 235 236 i

Maximum cross g

(.

I

section, C

x a

l (nom), in sq b 7.8 R.

7., 2m4.

y

8. g 7.8 7.98 E

MaximumU-235/q b

i t?.N"(?

f g

q element, kg 22.1 2ti 1.75 19.

20.7 21.1 L

I h

0 144L)(1

)

J g

f l

' )

L)

+

I

%74 W,4,g f.q q) y{

Maximum U-235 N

i l

enrichment, w/o 0

x.

7 4C8 5.0 5.0 q

i Y

H a

N f

/

O Iyng (8 a 4

j Pellet diameter l

(nom),in k 40167 M

j!

1 Rod diameter M M

't l

(nom),in 0.422 l

1 Maximum fuel l

f:

I length, in 141.8 l

Rods / element 208 g

Maximum cross i

't I

section,(nom),

I-1 in sq 8.5 I-I Maximum U-235/

['

l element, kg 17.8 t

Maximum U-235 i

l enrichment, w/o 3.95

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l lil i

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f.

I % " '*

CCNOm!NS (contmurd)

U.S. NUCUEAR REOut.ATORY COMGMSSHM I

I Page 4 - Certificate No. 5450 - Revision No. 33 - Docket No. 71-5450 i

I I

I

{

g 5.(b) (1)

Continued [

l (iv) Ura'nium diox,ide as Zircaloy clad unirradiated fuel elements I

containing a minimum of 48 IFBA rods and 25 Instrument / Guide tubes I

i per specification and loading pattern described in Westinghouse i

l drawing SKA-89044, Sheet 1, Rev. 2.

Two neutron absorber plates il i

consisting of carbon steel, 0.035 inches in thickness, with 4 mils of

],

i Gd 0 (0.02 gm-Gd 0 /cm ) affixed to each side of the plate are 23 23 I

required between fuel elements of the following specifications:

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4 I

ja REGg[

lj 17 x 17 j

l Iyg Zr Clad f

Pellet di l

i (n

0.308

g i

I Rod er p

l i I

in n

0.360

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um fuel V

'l

(

ength, in 168 j

gx ds/

/

f i

t l

l ele 264 i

I aximum s ect

()

l[

i I

b (nom),I 4

1 O

i' -

l' 84 I

Maximum 2

L 4(

f l '

l l

el nf(2 i

1{

22.5 (144"L) i H Min Z

, f,'

b I

(f) Mini 178A l.

r ss 48

t w.

I l

108

.t l

1 le n

l Il xim

(/

J' g)

I nric M % w/o 4.85 e

l (v)

Uranium ide as Zirca d unirradi uei elements.

Two t

4 i

i neutron a Ar plates consisting of ca steel 0.035 inches in i

I 2

thickness,

@4 ils of Gd o (0.0

-G

/cm ) affixed to each

{[.

l side of the plate rquie2 fu elements of the following z

3 l

y specification:

t

g t

j i

17 x 17 1.

Iyg Zr Clad j

l Pellet diameter

(

i (nom),in 0.308 g

i Rod diameter (nom), in 0.360 1

I Maximum fuel length, in 168 I

1 I

Maximum rods / element 264 j

i I

Maximum crt:s section (nom), in sq 8.4 Maximum U-235/ element, kg 22.5 (144"L) 1 g

i Maximum U-235 enrichment, w/o 4.85

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l l

r i

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I iI l

.i l

lI i

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[ 7***

l CONOmONS (contsnued)

U.S. NUCLEAR REGULATORY COMMISSION I Page 5 - Certificate No. 5450 - Revision No. 33 - Docket No. 71-5450 I

_1 1

1 q

l 5.(b) (1)

Continued-

)l g

c I

(vi) Uranium dioxide as Zircaloy or stainless steel clad unirradiated fuel rods i i I

of the following specifications:

li l

1

)

l SST Zr Zr Zr Zr Zr I

i xm u

u u

u u

u

)j I

ii i

l Pellet diameter 0.344- 0.308-

'i I

(nom),in 0.384 0.367 0.322 0.322 0.3805 0.325 lt I

Rod diameter, 0.400- 0.360-

I l

in 0.422 0.422 0.374 0.374 0.44 0.382 i

4 4;l '

Fuel length (max),

h(J68 j

g in 4

O 144 144 150 1

U-235 enrichment Qy.-

p I

(max), w/o 3.65p

't I

Note (1) y 4.0 4.0 lI

.0 3.85 I

l Note (2) 4.2 4.2 4.3 4.2 l

(9

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3 p' 2.

l Note (3) g Notes:

n l

(

i I

(1) Twbutron abiIo lakbs 0.19-inAthick, full k

4 I

leqstti stainlefs contaigin inimum) Defon or 0.19-inch 4

l f

thiM OFHC pie adM h he od bo j

l W

i t

pf/,ifbon el,p.035inchin ir I

(2) Twar19utr sortfe a t t

r thiU(ness, 4,mbe I

c f 9

nimum' gm 0 /cm ) affixed to

)

t i j b

the boxes.

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l each de la (3)Twondonab$

s f 0.1 ch thick carbon f

I steel a equired we,e d

s.

(vii) Unirradiated, ura di fu elements, with annular l

pelletsatthetopandhoide,zircaloyel omends ofD tive fuel length. Two neutron j

i absorber plates consistirfg oWcalRin Del, 0.035 inches in thickness, with y

I a cermeg Gd 023 coating affixed to each side providing a total of 0.054 g-l ll i

I Gd 0 /cm for both sides of the plate, are required between fuel elements.

I 23 I

The fuel assemblies shall be held in place by at least 7 clamping frame 1

1 l

l arms. Specifications for the fuel elements are as follows:

j l

Iyag 14x14 1 s14 CE-1 I

I I

Pellet diameter (nom), in 0.3444 0.3765 lI I

Annular pellet inner diameter (nom), in 0.172 0.183 j;I I

g Rod diameter (nom), in

a. 000 0.4400 i

g Maximum active fuel length (nom), in 144 136.25 lg i

l Solid pellet stack length, in 132 122.65 ll I

Annular pellet stack length at the top and il I

bottom ends of the active fuel length, in 6

6.8 j,1 I

Rods / element 179 176 l

Maximum cross section, (nom), in sq 7.8 8.110 l

Maximum U-235/ element, kg 18.1 18.6 l,

lll 1

l Maximus U-235 enrichment, w/o 5.0 4.8 l

q I

Ig""

CowomONS (continued)

U.S. NUCt. EAR REQUuTORY CoastNe800 I

l Page~6 - Certificate No. 5450 - Revision No. 33 - Docket No. 71-5450 1

I l

l 5.

(b)

(2)

Ma imum quantity of material per package I

i (1)

For the contents described in 5(b)(1)(i), 5(b)(1)(ii),

i 1

5(b)(1)(iii), 5(b)(1)(iv), and 5(b)(1)(vii):

I

?

l Two fuel elements i

p (ii)

For the contents described in 5(b)(1)(v):

1 3

i One fuel element l

l l

(iii) For the contents described in 5(b)(1)(vi):

Two inner so rs b g ot more than 80 kilograms I

U-235 Q l

(c)

Transport Inde Criticality Control l

l Minimumtrankrtindextobeshownon label for gleiiQM icality control:

j

/

g I 6.

Fuel rods must losely in tihs fuel c

ainer o more than an ll l I

equivalent met o-metal lat

/P l

loaded rod containers il

{

l must be fitted 4h a mini

hr al

, ego ed blocks f which the j

noncombustible artion f e

by hich y are secured j

i i

i must assure th he a

ained on thjyane valent metal-to-in I

metal square 1 ce %

n i

' r 4

)1 I

^h

• ~

p,he l7 Each fuel assemb us sheer ed in w unsealed,

,l e i o

l polyethylene she hic 1

il g

The ends of the s h must sbe

'F ends o(/yhe fuel assembly.

i 4

t n any ner that would j

j prevent the flow of quids int a of e

thed assembly.

1 Alternatively, the fu embly may be enclosed in ongated plastic bag or l

I sheath along its full 1 h.

At the bottom en f

fuel assembly, the bag

)t i

I will be cut off or folded bac sur th t

ntire cross section of the

)

l lower end of the assembly is u c

r.

ien folding is used, the portion of i

the sheath that is folded back will be c nched with tape near its end to hold it j'n 1

in place, and the length will be such that when the assembly is loaded in the lE I

packaging, the folded sheath will be clamped in place in at least two grid J

a I

locations. The top end of the bag may be gathered together and taped closed.

f;#

l However, the top end then will be slit on all four sides.

The slits will run i

perpendicular to the axis of the assembly and will extend the inner distance I

between the top nozzle pads and spring clamps (approximately 60% of the length of ljl I

each side).

The slits will be made in a plane near that formed by the top of the

{;t.

j pads and clamps.

l 8.

Use of packaging fabricated after February 28, 1986, is not authorized.

f i

'l -

l l 9.

The gros.s weight must not exceed 6,300 pounds for the RCC packaging, 7,200 pounds

't j

for the RCC-1 and RCC-3 packagings, and 8,400 pounds for the RCC-4 packaging.

I I

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• _, * * *

• conom:ns tcontinueo) u s.

mum comssen I Page Certificate No. 5450 - Revision No. 33 - Docket No. 71-5450 I

,I 10.

In addition to,the requirements of Subpart G of 10 CFR Part 71:

I g

(a)

ThepackIgemustbemaintainedinaccordancewiththemaintenance I

procedures submitted with Westinghouse supplements dated June 20, September l

1 16, and September 19, 1991.

4 I

5 l

l (b)

The package must be prepared for shipment and operated in accordance with y

the operating procedures submitted with Westinghouse supplements dated June g

20, September 16, and September 19, 1991.

I I

1 11.

The package authorized by this certificate is hereby approved for use under the j

general license provisions of 10 CFR 971.12.

Oph. R E Gg f 12.

Expiration date: September

)

ip REFERENCES Westinghouse Electric Cor tion application dated December 985.

l Supplements dated: Ap 28x 1, 21, 1986; January M rua d 14, April 18, i October 5, and Novemb 1.

ch 5, April 17,

, September 16, September t {

19, and September 24, 1; Feb _

, Mg(l, 27,199f) l 3

O I DepartmentofEnergygplement E Mar 1

jl l l

H dn k OR THE U ll EARpsGULA Y COMMISSION 1

x l

,[%

4 a

s l

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l 1 I

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Y /L.-&-<.$

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a t

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.__. _. ~ _ _. _. _ _. _. _.. _.. _

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UNITS: sua, ka CORIAINER TYPE t

ITEM RCC RCC-1 RCC-3 RCC-4 i

l l

l Lenath 4267 4852 4941 551L

. Maximum Cross Wt.

2858 3267 3267 4003 Stacking Bra ket Sh 11 Ol I.-

\\

NOTE: RCC-2 type containers are no O

I longer in service.

,1 1

Fuel t

RAP l

Grid ad ji l

\\

Clamp Frame Top

\\

Nozzle i

l Pad L

Top

?

I Nozzl b

, 3' 'f-I p

Clam i

f3[-

l Bottom f

l y

Shell

(

s Crid l

g:l s

Clamp Pad Bolt Rubber Casketed Sealing Flange l

Container Control No zie Stacking Support Cluster Clamp l

i Control Cluster Pad

[

WESTINGHOUSE RCC MODEL SilIPPING CONTAINERS FOR 14x14, 15x15, 16x16,,17x17 FUEL ASSEMBLIES i

.