ML20247F063
| ML20247F063 | |
| Person / Time | |
|---|---|
| Site: | 07105450 |
| Issue date: | 07/18/1989 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20247F037 | List: |
| References | |
| USA-5450-AF, NUDOCS 8907270076 | |
| Download: ML20247F063 (8) | |
Text
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'I I UA 38UCt2AR HEGULATORY reasesarm i "J""
isonn CERTIFICATE CF CSMPLIANCE l
l FOR RADIOACTWE MATERIALS PACKAGES i
l m amg g samam $$ifa ='m "gjg{AF "k' '5 l !
l j FYm i,,,,,,a n,o ,wy in , a goa.g.no .no cons.nts o cnb.o in non s emio mems e= appe.cabie s.ty nere =t sorm inTm a cae I i of Fodend ; C . Part 7i.
- Packaging ams Tarsimp, main of Rad.oectne Masenal."
l A Ttus cartf caso does not n,leve ihe consagnor frorn compleance with any r--- ' - . of ihe reguistens g g. n put W T6 w W i
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I Westinghouse Electric Corporation Westinghouse Electric Corporation application I i l .P.O. Box 355 dated December 20, 1985, as supplemented. I i
Pittsburgh, PA 15230 i l
.. sS (/j-5450 I i
- 7,,,,,c cona,,,on ,,iumr., n. or to crn Part 71. = pphcate arIe== eaadmons as=c*ed t*=- !
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S-s 4
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l (a) Packaging eg o l
i i
(1) Model'Hos.: b /, !
l RCC,Q 7 Nb M I i RCC-1,RCC(2,1CC-3,and;RCC-4. f/ Q j
! (2) Desc 1ption y/ O l I
I LDL 6.o .Q i gg SteelfuelelementicradleassembliIcon)sistingof,astrongbackand
, i I
l adjustable fuel element.clampi,ng,assemblj, shock, mounted to a 14-gauge I i I i requiredforithecontents!a;stspedified. steel Gross outeruconta,inersbyj weight-for the RCC and shear i l 8,400';Jbs.RCC-2 is 6,30091bs) ndRCCf3 tis h, RCC-1~ And RCC-4 is i I
i \y W> / ~a.y q {N" J<200 Mb~ ' lbs. ,(/) i l -(3) Drawingsh U .
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+4 - d O+
The packag'ing.ssare constructed in accordance J1th the following O i 1
i 1 WestinghouserElectric '
Corporation Drawing No C i
I g Js i i
For the RCC and RCC22~ packagSgs:d1596E24, Sheets 1 through 3, Sub 1; I l 1596E25, Sheets 1 & 2, Sub 1 F1553E31, Sub 1; SKD-86008, Sheets 1 I i through 3, Rev. 2.
l l i i l
For the RCC-1 and RCC-1 and RCC-3 packagings: 1596E24, Sheets 1 through i !
I 3, Sub 1; 1596E25, Sheets 1 & 2, Sub 1; 1553E30, Sub 1; SKD-86008, Sheets i l
I 1 through 3, Rev. 2. I I i
! For the RCC-4 packaging: SKE-85002, Sub 3; SKE-85003, Sub 3; SKE-85004, l Sheet 1, Sub 3, and Sheet 2, Sub 2; SKE-86004, Sub 3; SKD-86009, Sub 2. l I i I
I I
(4) Fuel rod container reinforced 13-gauge steel box constructed in i accordance with Westinghouse Electric Corporation Drawing No. C5650055, I l Rev. 7. I
! (5) Dimensions and placement of neutron absorber plates in accordance with !
I unnumbered drawing attached to Westinghouse Letter # LA 89-19 dated i l
' 2/14/89. !
s9o7270076 890718 o --------------- ---===--------="-----'
PDR ADOCK 07105450
_C_______ _ _ _ _ ___
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i y F en .:n. U * """ " * " " ^
- conom:ns (continued)
Page 2 - Certificate No. 5450 - Revision No. 27 - Docket No. 71-5450 I
5.' (b) Contents j (1)Typeandformofmaterial j (1) Uranium dioxide as Zircaloy or stainless steel clad unirradiated i fuel elements. Two neutron absorber plates consisting of 0.19" i thick, full length stainless steel containing 1.3% minimum boron or 1 0.19" thick 0FHC copper are required between fuel elements of.the l following specifications:
m t~
14x14 15x15 i 17x17 16x16 14x14 14x1.4h45x15 Zr s hf *h7 Clao Clad **y Clad SST GST" Zr Clad Zr Clad Zr Clad l
T12e Clad..Q I j\
y-Pellet diameter .0.344- 0.308-(nom),in (0.367. 0.367 0.384 0.834 (Os322 0.322 0.3805 Rod diameter 0.400- .m 0;360-(nom),in ( 0.422 0 422 ' / 0.*374 "'
0.374 0.44 Maximum fuel / g"Q 0.422r Nfhg 0.422 fMv,9 length, in 144 T,%J144 .120 / 120 f^ 168r*;g 144 144 Maximum rods / r;.* RQ \
N204) s.~8 1 d 80f
- p. %
264 V/S jq j [)1204j element rt 180 235 176 Maximum cross N section, ;~ f4 M)4('T Ss -~~~M '{r..j ,
l" L
[
(nom), in sq. 7:. 8 4 L8;4, N 1.8 D 48.4 'u l8.45- 7.8 7.98 (
Maximum U-235 p - N. g , W/fi ; 7y p , ;iU > - -
(
element, kg 17.7a 18.7: .. 16.95~. 16.6 19.0 Q 'f r&r18.'3E g gt.#
51815 m r [': 0/M !; k j [J :b19.8, (144"l)
\<i" ip u p,t ,9.s'S ?"-
?y (168"L)
Maximum U-235 enrichment,w/o Y' a q /,
3.65 "? -c-19 ] .3.65 ' 'c n 3.65 4.0 3.85
<4,.0 ,
44.0l~ (
, ,f,,, s s (ii) Uranium dioxide as Zircaloy clad unirradiated fuel elements contained within ths Model No. RCC-4 pac.kaging. Two neutron absorber plates I consisting of 0.19"sthick carbon steel are required between fuel I elements of the following specifications: [l
[
17 x 17 [
Tm Zr Clad L L '
Pellet diameter, in 0.308 - 0.322 f, Rod diameter, in 0.360 -0.374 (-
Maximum fuel length, in 168 t Maximum rods / element 264 L l Maximum cross section, L (nom), in sq 8.4 Maximum U-235/ element, kg 19.3 [i Maximum U-235 enrichment, w/o 3.55 ,
4
(
L I
L L
__________________----------.n-,_---'-'-
Nna 6l conomous(continued)
U^ "O'" " "" " **'** * " "
Page 3 Certificate No. 5450 - Revision No. 27 - Docket No. 71-5450 (iii)' Uranium dioxide as Zircaloy clad unirradiated fuel elements.
- Two neutron absorber plates consisting of carbon steel, 0.035 (0.02gm-inches Gd,30 2 /cm ig) thickness, with 4 mils of Gd2 0 .
affixedtoeachsideoftheplatearerequired between fuel elements of-the'following specifications:
14x14 15x15 14x14 15x15 17x17 17x17 16x16 16x16 Zr Zr SST SST Zr Zr Zr Zr Type _C lad Clad Clad Clad Clad Clad Clad Clad Pellet diameter 0.344- 60 o g0.384R E0.322 e f ,308 .
(nom),in 0.367. 0.367 0. 0 0.325 Rod diameter 0.400- ( .: V .384
.(nom),in Maximum fuel 0.422(#s 0.422 0.422 0.422 0.374 0.360 0 374 0.382 NQ:.322 s
'(
' length, in Maximum rods /
144T[144 120 120 168 168 144*}gM.50 p
1 1
element 1807 204 O 180 204 264 264[235 ,236 Maximum cross Q '//!M section, (nom),insq f18'j \Qd.N'\
- 1. M . m ;. a 8.4 b 7.8 i' 8.4B '8.4 J8s4 2 7.8
$.' r*)
7.98 Maximum U-235/
element, kg CT $6] / / l .V1 21.5 T23:1%. 22.'On 21,75 /19.9 20.7
. L) 21.1
}~22.1 V PV <
m, t (144"L)(144"L)/ < "
, 25.5' '23.3.?, m t !
@f" % , "$ % h n pl %168"L)(168"L) '
Maximum U-235 enrichment,w/o m, @^ M l4.'3[ ;}i / +J 5.0
,y 4!3m45.04,A:IgjctN}b.3:
y g y-a w p g!I4.7
-Q 4
5.0 , 5.0 99 (iv) Uraniuin7 dioxide 'as Zircaloy?br stainlessisteel clad'un' irradiated fuel rods of'the following' specifications: N gf y s- -
G' w 7 g Type SST Clad Zr Clad Zr Clad Zr Clad v 2r Clad Zr Clad i s Pelletdiameter(nom), Y f' in 0.384 ' 0.344b wD.308- 0;322 0.3805 0.325 Rod diameter 0.367' 'O.322 in 0.422 0.400- 0.360- 0.374 0.44 0.382 Fuellength(max), 0.422 0.374 in 120 144 168 144 144 150 U-235 enrichment (max), ,
i w/o Note 1) 4.0 4.0 3.65 4.0 3.85 ---
Note 2) 4.2 4.2 4.3 4.3 --- 4.2 i Note 3) --- ---
3.55 --- --- ---
l 1
l l'
l
________________________-----r------------_---____-_-_--
D .
- ymm? conomous (continvea)
Page 4L- Certificate No. 5450 - Revision No. 27 - Docket No. 71-5450
. Notes:
. (1)' Two steel neutron containingabsorber p(latesBoron 1.3% minimum) consisting of 0.19-inch or 0.19-inch thick 0FHC thick, full length
~ copper stainless are required between the' rod boxes.
(2)
. Two with 4neutron mils of absorber Gd 0 p(minimum 0.02 gm Gd 0 /cm ) affixed to each side of thelatesco platearerequire$fletweentherodboxes.3 2 (3) Two neutron absorber plates cons $sti g o 0 9'-7'nch thick carbon steel are required between the rod boxes.
G9 4 jr (2) MaximumquIntityofmaterialperpackage ^\
W
.(i) Forthercontentsdescribedin5(b)(1)(i),..5(b)(1)(ii),and
- (%
5 ^/'/
LO(b)(1)(iji N . Y gwofueleleme:nts)
DR %q / /JM.f e
7 (g
3d (ii)f"orthecontent's\escribedin5(b)(1)(iv):
% Q._&& } lQ C~~
, Two inner P ti i tii t more ,that 80 kilograms. U-235.
tn q .y i (c) FissileClassI(w@p;conanersconanng,no%q
'5. e, W%h[rg yp1; , ,
m h'l > p y t. 6 4. -
4@
6 Fuel rods must be' closely'packedMnTtheifue1~ rod' container on no more than an u equivalent metal-to-metar. square 11attice.S PartlallyL loaded fuel; rod containers must be fitted with,a minimum of, three,iequally spaced blocks,. of which the noncombustible portion of the block's'and the* method by which they are-secured must assure that the rods are maintained bn(noimore than"an equivalent metal-to-metal square' lattice withihfthe3fuel rod container. p
>, ga 7 Each fuel assembly must be unsh'eathed or. must be enclosed in an unsealed, 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 ,
prevent the flow of liquids into or out of the sheathed fuel assembly. !
Alternatively, the fuel assembly may be enclosed in an elongated plastic bag or sheath along its full length. At the bottom end of the fuel assembly, the bag will be cut off or folded back to assure that the entire cross section of the lower end of the assembly is unobstructed. When folding is used, the portion of the sheath that is folded back will be cinched with tape near its end to hold it in place, and the length will be suct that when the assembly is loaded in the packaging, the folded sheath will be clamped 1r place in at least two grid locations. The top end of the bag may be gathered together and taped closed. However, the top end then will be slit on all four sides. The slits will run 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 each side). The slits will be made in a plane near that formed by the top of the pads and clamps.
I
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m_ _ _ _ _ _ _ _ _ _ _ . _ _ . . _ _ _ . . _ _ _ _
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l Uvm-n' C:NDITl:NS (continued)
I I I L
l Page 5 - Certificate No. 5450 - Revision No. 27 - Docket No. 71-5450 l j i i 1 I I i
- 8. The package authorized by this certificate is hereby approved for use under the I
I general license provisions of 10 CFR 671.12. l l ; l 3
i l i 9. Expiration date: July 31, 1991. t i I l REFERENCES I I I I
Westinghouse Electric Corporation application dated December 20, 1985. l
, t 4 i Supplements dated: t April 18, 1989. April 28, July 1, jrp July iT21n1986,)
C ( _
January 4, February 14, and I i
l Department of Energy suppleme'nt' dated: March 1, 1984.
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I N FOR THE U.S. NUCLEAR REGULATORY COMMISSION L I
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l *l;(1 N ~ Charles. . Nacona , Chief l P< '
7 Transportation Branch i ' ;' . .i -J r i
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j ~ Division of Safeguards
.and Transportation, NMS.S f~ L L
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I 1 Date:
JUL 18 % " c
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. [p F *%[o UNITED STATES
- g g '.< g g NUCLEAR REGULATORY COMMISSION E* . E WASHINGTON, D, C 20555
%, . . .J Transportation Branch
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Ap)roval Record Model Nos. RCC, RCC-1, RCC-2, RCC-3, RCC-4 Docket No. 71-5450 Revision 27 __
By application dated April 18, 1989, Westinghouse Electric Corporation requested an amendment to Certificate of Compliance No. 5450, Revision 26. The amendment would authorize an increase in U-235 enrichment for Westinghouse 14 x 14 and 16 x 16 fuel designs from 4.2 wt% and 4.3 wt% to 5.0 wt% when shipped in the RCC shipping container with Gadolinium 0xide neutron poison plates.
The applicant's criticality analysis considered an infinite number of damaged RCC containers. The RCC conteiners were assumed to be crushed together such that the 14 x 14 and 16 x 16 fuel assemblies were separated by four inches of moderation on one side, sixteen inches on two sides, and thirty inches on the fourth side. The applicant also assumed that only seventy-five percent of the gadolinium oxide poison was present on the neutron absorber plates. The same model was used on past criticality assessments of the RCC series of containers and found adequate.
The results of the applicants analyses are as follows:
Fuel Design K-eff with error 14 x 14 0FA 0.9239.1 0.003 16 x 16 0.9294 1 0.003 These two fuel designs represent the most reactive for each type considered and provide the highest k-eff values in the analyses.
Staff, using a similar model for an infinite array of damaged RCC packages, performed a confirmatory analysis with the CSAS 4 sequence of the SCALE library.
Two of the 14 x 14 designs and two of the 16 x 16 designs contain zircalloy clad fuel rods while one 14 x 14 design contains stainless steel clad rods. The results of the staff's analyses of the most reactive designs are as follows.
Fuel Design K-eff with error 14 x 14 Zr Clad 0.939 i 004 14 x 14 SS Clad 0.889 1 0.004 16 x 16 Zr Clad 0.9158 1 0.004
L,
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l Based on the applicant's analysis and the staff's independent confirmatory calculations, the staff has determined that the proposed amendment would not affect the ability of the RCC shipping container to meet the requirements of 10 CFR Part 71.
l Charles E. MacDonald, Chief ~l Transportation Branch Division of Safeguards- ,
and Transportation, NMSS i
I
b LIST OF USERS FOR CERTIFICATE - 5450
.' e j POR MODEL - RCC i
I I
. . ADVANCED NUCLEAR FUELS CORP. '
j
. ATTN: MR. L. D. GERRALD P. D. BOX 130 t RICHLAND . WA 98352 AlagAMA 70WER c0. .
ATTh: PLANT MANAGER .
DR*kTR 474
- ASHFDRD .-
. AL '38312 BABCDCK & WILCOX CO. .
ATTN: MR. A.F. CLSEN ,
P.O.80X 11185 '
LYNCMBURG VA, 24508 BATTELLE COLUMEUS LABORATORY ATTN: MR. HARLEY L. TOY -
505 KING AVINUE COLUMBUS ,
. DH 43201 ,
~
DEPARTMENT OF ENERGY * *
- ATTN: MR. E. M0CALLUM .
DP-4 '
- WASHINGTON DC 20545 DUQUESNE LIGHT CD.
ATTN: MR. J. D. SIEBER P. D. BOX 4 SHIPPINGPDRT(BEAVER VALLEY)PA 15077 IRT CORPORATION
ATTN: MR. RICHARD N. CLSEN 2004 COLONY ST.
NOUNTAIN VIEW CA 94043 NEW YORK POWER AUTHORITY ATTN: MR. WILLIAM G. GREENMAN 5 $ N NY 10511, NORTHEAST WUCLEAR ENERGY CO.
ATTN: MR. JOHN P. KANGLEY -*
P.D. BOX 123 WATERFORD CT 08385 TENNESSEE VALLEY AUTHORITY ~
ATTN: MR. R. L. GRIDLEY EN 1578 LOOKDUT PLACE -
CHATTAN00GA TN ST401 .
ATTN: V.P. NUCLEAR OPS P.O. BOX 25888 .
RICHMOND VA 23281 i WESTINGHOUSE ELECTRIC CORP. .
ATTN: MR. A..T. MARDI P.O. BOX 355 PITTSBURGH . PA .15230 WOLF CREEK WUCLEAR OPERATING C ATTN: MR. JOHN A. SAILEY' P. D. BOX 411 SUR LINGTON KS 88838 i
- * "'" es a em. , e e en e e.e, eg g
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