ML20235U478
| ML20235U478 | |
| Person / Time | |
|---|---|
| Site: | 07105450 |
| Issue date: | 02/24/1989 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20235U441 | List: |
| References | |
| NUDOCS 8903090216 | |
| Download: ML20235U478 (7) | |
Text
-_-_
6,.
u.s. HUCLEAR REGULATORY COtansS80N [
Tfm CERTIFICATE CF C3MPLIANCE l
- Cm 7i FOR RADIOACTIVE MATERIALS PACKAGES
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25 USA /5450/AF 1
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.; e e. -euw.on. e e. u.s. o.p.n=-in a v.e or oew
.ppiec.,4. e.gui.tnry.g.nce.s. includsng one gov.rvim.nt o,.ny ovuntry ihrough or sneo whee she pas:1.g. nll is. ^__
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l Westinghouse Electric Corporation Westinghouse Electric Corporation application I
I P.D. Box 355 dated December 20, 1985, as supplemented.
Pittsburgh, PA 15230 l
% L & (11'-5450 l
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J, E.. m e.,,7.. J 4 l
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-(a) Packaging T
A i
./
l (1) Modeldos.:
/,,/ f MQN 4[
l l
RCC,,,RCC-1, RCCg;n -)3, and;RCC-4.
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(~)
l JCC (2) Description t A j % _/cp (r
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r; i
/
Steel fuel element i:radlie assemblyM.i, p,'sisting off.a sttjingback andI y., 1 l
~ ~.
~
adjustable?. fuel element _clampingissembly, shock: mounted to a 14-gauge I
steel outer-container-by1 shear. mounts.' Neutron absorber plates are l
required for'the contents ins ispecified. GrossteighrtertheRCCand i
RCC-EJs6,300-5bs.,,ACCQ;ndRCC-3ys7,E00lbs.,,andRCC-4is i
$ h.! g.' &{ f ;,
~};Q " 4,Q b.?
l V
I 8,400Gbs.
/jy
\\
J (3) Drawingsy g
As
~.
i The packagtegsy re constructed in accordanc the following i
Westinghouse EJectric Corporation Drawing No.:
I
$j M
I 96E24, Sheets 1 through 3. Sub 1; I
For the RCC and RCC-7 p ta1,Fs:
155 31, Sub 1; SKD-86008, Sheets 1 l
1596E25, Sheets 1 & 2, u
through 3, Rev. 2.
i I
For the RCC-1 and RCC-1 and RCC-3 packagings: 1596E24, Sheets I through l
3, Sub 1; 1596E25, Sheets 1 & 2, Sub 1; 1553E30, Sub 1; SKD-86008, Sheets I
1 through 3, Rev. 2.
l 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.
i I
(4) Fuel rod container reinforced 13-gauge steel box constructed in I
I accordance 'with Westinghouse Electric Corporation Drawing No. C5650D55, Revision 7.
l l
l (5) Dimensions and placement of neutron absorber plates in accordance with i
unnumbered drawing attached to Westinghouse Letter # LA 89-19 dated I
nnoR*L FiDR ADOCK.071o*gO
1
'D conomous (continuw)
" " " * ^ " '
I L
Page 2 - Certificate No. 5450 - Revision No. 25 - Docket No. 71-5450 f
i I
(b) Contents t
5.
I I
(1) Type and form of material t
(i) Uranium dioxide as Zircaloy or stainless steel lad unirradiated f
fuel elements. Two neutron absorber plates consisting of 0.19"
[ :
thick, full length stainless steel containing 1.3% minimum boron or f
0.19" thick 0FHC copper are required between fuel elements of the
<l I
following specifications:
p t
14x14 15x15 14x14 15x15 17x17 16x16 14x14 r;
Zr ISST p SST Zr Zr Zr I
Zr tCla'd.pi ' Clad J hlad Clad Clad Clad i
M Clad I
e \\.,
~.. >
1 L
0.834'h 0.308-Pellet diameter 0.344' >
f-g (nom),in 0.367 0.367 0.384 Q0.322 0.322 0.3805 l
Rod diameter 0.400-
.A.360-t-
1 (nom),in 0.422
~
0.422
.0.422 0.422 J 0.374 0.374 0.44
{
(
l Maximum fuel e-144.
120
, r120'
- 168, 144 144 f
l length, in 144
[
g element
. 180
- 204
/180,.
/ (~
t
- Maximum rods /
(i:204 264l 235 176 L
q Maximum cross 7
L.
,R t.
I
- section, Maximum U-235/
8.4 c 7.8 '
8.4 8.41 7.8 7.98 f
(nom), in sq 7.8 I
l element, kg 17.7
.18.3 / r : 18.5 18.7 16.95 16.6 19.0
[.
(144"L)
[
i
.. ~
sy O(9.8168"L)
(
1 L
i l
/
(
I Maximum U-235 J
I L
I enrichment,w/o 4.0 3.65
'4.0 3.65 ~ '
3.65 4.0 3.85 I
I C
f (ii) Uranium dioxide as Zircaloy clad unirradiated fuel elements contained h
i within the Model No. RCC-4 packaging. Two neutron absorber plates L-i consisting of 0.19" thick carbon steel are required between fuel i
elements of the following specifications:
I C
E i
17 x 17 I
N Type Zr Clad l
C i
Pellet diameter, in 0.308 - 0.322 i
i Rod diameter, in 0.360 -0.374 f
I Maximum fuel length, in 168 I
l Maximum rods / element 264 g
Maximum cross section, g
g (nom), in sq 8.4 t
i Maximum U-235/ element, kg 19.3 I
N Maximum'U-235 enrichment, w/o 3.55 i
g i
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N n
l i
l I
L i
I.
w-------w-----r----.c--.------w.----ww------.-
x
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conomous (continued, n wcw ucumcwr w:a s:. cu i
L Pa 71-5450 L'
l ge 3 - Certificate No. 5450 - Revision No. 25 - Docket No.
b (iii)
Uranium dioxide as Zircaloy clad unirradiated fuel elements.
{! !
i Two neutron absorber plates consisting of carbon steel, 0.035
[)!
(
inchesig) thickness,with4milsofGd0.
(0.02 gm -
Gd,30 /cm affixedtoeachsideoftheplatearerequired h;l 2
3 between fuel elements of the following specifications:
g! )
[
14x14 15x15 14x14 15x15 17x17 16x16 16x16 E
Zr Zr SST SST Zr Zr Zr li '
I Type Clad Clad Clad Clad Clad Clad Clad i;
f
- Pellet diameter 0.344-0.308-(nom),in 0.357 C P,g p2384 g'(,f,e 0.367 0,.384 0.322 0.322 0.325 t'
1
. Rod diameter 0.400-0.360-I (nom),in 0.422
\\A422 0.422 0d22 0.374 0.374 0.382 8
Maximum fuel s C/
1 h I
i[
'; 1ength, in 144s?
144 120 120 Q168 144 150 Maximum rods /
e-element
,180 204 180 204. 7,264 235 236 gl'
. Maximum cross t
e-t
- section, Il
,/
Ej V
7 f,.
iMaximum U-235/
- 8.4 j Q.8
/ r B.4 8.'4 '
7.8 7.98 Ej (nom), in sq 7.8 h
s ',
N23.1
)
20.7 21.1 g!
element, kg s 22.1
-21.5.~. u - y)' 22.'O 21D5g)
(344 g;
g5,5 gy
.,p.,... y (168"L)
- 1 (1
Maximum U-235 enrichment,w/o
- 4.2 4.3 i.
' 4.2
. ; 4.3 4.7 4.3 4.2 x
(iv) Uranium dioxide'as Zircaloy or stainless. steel clad unirradiated fuel rods of the following specifications:
[
Type SST Clad Zr Clad Zr Clad.Zrblad Zr Clad Zr Clad m
7 3
Palletdiameter(nom),
e-in 0.384 0.344-0.308-0.322 0.3805 0.325
. Rod diameter 0.367 0.322 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 g
l U-235 enrichment (max),
Il w/o I!
ll Note 4.0 4.0 3.65 4.0 3.85 I
4.2 Note 4.2 4.2 4.3 4.3
[l 3.55 Note l
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N,l ll I r I;
B lI l
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- ---xxx.xxxwmxxxxxxxv mwwwxx----.vv.
,=w--w
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coNomons (continued)
U 5 M ' * *
- C h"W G
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i l Page 4 - Certificate No. 5450 - Revision No. 25 - Docket No. 71-5450 l
I I
i I Notes:
l I
I l (1)
I Two neutron absorber p(lates consisting of 0.19-inch thick, full length stainless steel containing 1.3% minimum) Boron or 0.19-inch thick 0FHC copper are required j
i i
between the rod boxes.
i I
I I (2)
Two neutron absorber p(minimum 0.02 gm Gd 0 /cm ) affixed to each side of thelate I
I with 4 mils of Gd 0 I
I platearerequire$$etweentherodboxes.3 l
2 i
! (3) Two neutron absorber plates consisting of 0.19-inch thick carbon steel are required I
between the rod boxes.
[.] { g l
,,\\.y I
l (2) Maximum quantity 4f material per package
)
[
R e 1 d
(1) Forthecontentsdescribedin5(b)(1)(i),5(b)(1)(11),and lil 4
5(b)(1)(iii) 0 f
g :
i Y
I!
f, f
.~
g i Two' fuel elements.
c.
i<
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(ii) For the contents described in 5(b)(1)(iv):
[.
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Twosinner containers'containing not more 'that 80. kilograms U-235.
I :
I g i 5.
(c) Fissile Clas's 1
'i Y
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w g
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i u
g g 6.
Fuel rods must be closely. packed.in-the fuel-rod container on-no more than an g
i equivalent metal-to-metel square lattice. Partially loaded fuel rod containers g
4 must be fitted with a minimum of three, equally spaced blocks, of which the
-ll 1
noncombustible portion of the blocks and the method by which they are secured must ll 1
assure that the rods are maintained on no more than an equivalent metal-to-metal ll l
square lattice within the' fuel rod container.
l l 7
, 1 7.
Each fuel assembly must be unsheathed or mus~t be enclosed in an unsealed, s
polyethylene sheath which will not extend beyond the ends of the fuel assembly.
ll The ends of the sheath must not be folded or taped in any manner that would ll prevent the flow of liquids into or out of the sheathed fuel assembly.
ll g
Alternatively, the fuel assembly may be enclosed in an elongated plastic bag or sheath f l
along its full length. At the bottom end of the fuel assembly, the bag will be cut off g
i or folded back to assure that the entire cross section of the lower end of the assembly ll 1
is unobstructed. When folding is used, the portion of the sheath that is folded back I!
I lI will be cinched with tape near its end to hold it in place, and the length will be such I
l g
that when the assembly is loaded in the packaging, the folded sheath will be clamped in g
place in at least two grid locations. The top end of the bag may be gathered together y
e and taped closed. However, the top end then will be slit on all four sides. The slits i
ll I
will run perpendicular to the axis of the assembly and will extend the inner distance l
1 between the top nozzle pads and spring clamps (approximately 60% of the length of each lll l
side). The slits will be made in a plane near that formed by the top of the g
pads and clamps.
gl l
I I
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- 1 I!
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,.o.,..,.-.-a'
i t
l e ucm v" consmous ccontinued)
U* "*C"* *(*V " ' " * *'v**
- V I
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! Page 5 - Certificate No. 5450 - Revision No. 25 - Docket No. 71-5450 l
l l
l 1
1 1
1 8.
The package authorized by this certificate is hereby approved for use under the l
l general license provisions of 10 CFR 571.12.
I l 9.
Expiration date: July 31, 1991.
l l
l l
REFERENCES l
1 l
l Westinghouse Electric Corporation application dated December 20, 1985.
I l Supplements dated: April 28, July 1, July 21,1986, and January 4,1989.
ll I
I I Department of Energy supplement dated
. arc y 984 l
l c \\-
FORTHElf.S.JUCLEARREGULATORYCOMMISSION I ;
s'J
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s.
N 4ed
- s n
I (I
Charles E.:MacDonald,-Chief 1
Transportation Branch.
1;,
l
~
Givision,of Safeguards '
ll g
/ and Transportation,(NMSS 1
FEB 2 41989, _
x,' 6_aj< -
a 1 Date:
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y1 UNITED STATES y
g NUCLEAR REGULATORY COMMISSION O
fj WASHINGTON, D. C. 20555
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FEB 2 4 $89 Transportation Branch A nroval Record Models Nos. RCC, EC-1, RCC-2, RCC-3 and RCC-4 Docket No. 71-5450 Revision 25 By application dated January 4, 1989, Westinghouse Electric Corporation requested an amendment to Certificate of Compliance No. 5450, Revision 24. The amendment would authorize an increase in U-235 enrichment from 4.3 to 4.7 weight percent for Westinghouse 17x17 STD fuel assemblies shipped in a RCC shipping container.
Because of the increased enrichment, the RCC shipping container would be equipped with two gadolinium oxide neutron absorber plates between the 17x17 STD fuel assemblies.
The applicant's criticality analysis considered an infinite number of damaged RCC containers. The RCC containers were assumed to be crushed together such that the 17x17 STD fuel assemblies are separated by four inches of moderator on one side, sixteen inches on two sides, and 30 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 to be adequate. The K-eff predicted for these conditions was 0.95479 with a sigma of 0.00309. Staff using a similar model for an infinite array of damaged RCC packages calculated a K-eff of 0.9588 with a sigma of 0.0045.
Staff also assumed a minimum four-inch spacing, optimum moderation, and 75% credit for gadolinium oxide.
The applicant did not analyze a single package in accordance with 10 CFR 71.55 (b).
Staff's calculations for a single package (per 10 CFR 71.55 (b)) predicted a K-eff of 0.901 with a sigma of 0.005.
Based on the applicant's analysis and staff's independent 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. The proposed ship-ment of two Westinghouse 17x17 STD fuel assemblies (with gadolinium oxide neutron absorber plates) in a RCC container satisfies the conditions for a Fissile Class I package.
N:b Charles E. MacDonald, Chief Transportation Branch Division of Safeguards and Transportation, HMSS
ADVANCED NUCLEAR FUELS CORP.
ATTN: MR. L. D. GERRALD I
P..O.
BOX 130 l]Q$$419$$
RICHLAND WA 99352 L
ALABAMA PDWER C0.
L
. ATTN:
PLANT MANAGER DRAWER 470 ASHFORD AL 36312 l
BABC0CK & WILCOX CD.
ATTN: MR. A.F. OLSEN P.O.80X 11165 LYNCHBURG VA 24506 BATTELLE COLUMBUS LABORATORY ATTN: MR HARLEY L. TOY 505 KIhG AVENUE COLUMBUS OH 43201 D"PARTMENT OF ENERGY ATTN: MR, E. McCALLUM DF-4 WASHINGTON DC 20545 l
DUQUESNE LIGHT CO.
I ATTN: MR. J. D. SIEBER P. O. BOX 4 SHIPPINGPORT(BEAVER VALLEY)PA 15077 IRT CORPORATION ATTN: MR. PAUL R. MASCHKA, RSO P.O 80X 85317 SAN DIEGO CA 92138 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 1578 LOOKOUT PLACE CHATTANOOGA TN 37401 VIRGINIA ELEC. & PWR. CD.
ATTN:
V.P. NUCLEAR OPS P.O. BOX 26666 RICHMOND VA 23261 WESTINGHOUSE ELECTRIC CCRP.
ATTN: MR. A.J. NARDI P.O. BOX 355 PITTSBURGH PA 15230 WOLF CREEK NUCLEAR OPERATING C ATTN: MR. JOHN A. BAILEY 8
O. BOX 411 BURLINGTON KS 66839
. _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _. - _ _ _ _ _ _ - - _ _ _.