ML20141K251
| ML20141K251 | |
| Person / Time | |
|---|---|
| Site: | 07105450 |
| Issue date: | 01/16/1986 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20141K247 | List: |
| References | |
| NUDOCS 8601220382 | |
| Download: ML20141K251 (6) | |
Text
'p-----------------------------------------------mmmm_mg I U.S. NUCLEAR REGULATORY CfMMISSl!N I i
- eu Pones sis I . Nac CERTIFICATE OF COMPLIANCE i l l 'o CFR n FOR RADIOACTIVE MATERIALS PACKAGES i-l t aCERTIFICATE NUM8ER D REvaSION NUMBER c PACKAGE iCENTiFICATION NUMSER d PAGE NUMBER e foi AL NUM8ER PAGES g 5450 22 USA /5450/AF 1 5 !r !
I 2 PREAM8LE h l a. This certificate is issued to certify that the packaging and contents desenbod in item 5 below, meets the apphcable safety standards set forth in Title 10. Code i l
g of Federal Aegulations, Part T1," Packaging and Transportation of Radioactive Matenal." I l b. This certificato does not reheve the consegnor from compliance with any requirement of the regulations of the U S. Department of Transportation or other I apphcabie regulatory agencies, includeg the government of any country through or into wnsch the package will be transported. I l l L I I K
l 2 T g , gR,TI,F g y S;SS gu THE SASIS OF A SAFETY ANALYSIS RE T OF TH S O CAT I I I Westinghouse Electric Corporation Westinghouse Electric Corporation application jl l P.O. Box 355 dated December 17, 1980, as supplemented. I Pittsburgh, PA 15230 l f
! e. OOCxET Nuu ER 71-5450 I e CO.oT.ONS I
TP,4 :ertificate es condetsonal upon fulfishng the requirements of to CFR Part 71, as apphcable and the cor dations specified below I s I l (a) Packaging [
I I l (1) Podel Nos.: l I I I RCC, RCC-1, RCC-2, RCC-3, and RCC-4. I I i f (2) Description l
! Steel fuel elenent cradle assembly consisting of a strongback and I adjustable fuel element clanping assembly, shock nounted to a 14-gauge l I steel outer container by shear mounts. Neutron absorber plates are l I recuired for the contents as specified. Gross weight for the RCC and RCC-2 is 6,300 lbs., RCC-1 and RCC-3 is 7,200 lbs., and RCC-4 is 8,400 l l lbs.
g g l l l l (3) Drawings l l t I The packaging is constructed in accordance with Westinghouse Electric i
f Corporation Drawing Nos.: 1596E24,1596E25, and 1553E31 for the RCC i t
l l and RCC-2; 1596E24,1596E25, and 1553E30 for the PCC-1 and RCC-3; and r i 1596E22,1596E23, and 1548E55 for the RCC-4. ,1 I 'l I (4) Fuel rod container reinforced 13-gauge steel box constructed in accordance I with Westinghouse Electric Corporation nrawing No. C5650055, Rev. 7.
[ l 1 I I l l l l l- 1 I I l l I I f 86012203028%d50 ADOCK O '
1 PDR PDR l I c l l I I I l l l
l 8
pummpm anjammma n a mm m m mmmm mmm uunn um mmm _ m mmmm m mm mm mmm4 ll 1 l
\
lf, C:NolTioNS (continu:d) [ j l E l lE Il' I:
Page 2 - Certificate No. 5450 - Revision No. 22 - Docket No. 71-5450 lE ll '
,[
Ii E l
l: 't lll 5. (b) Contents ,r lI, 't (1) Type and form of material j (i) Uranium dioxide as Zircaloy or stairJ 2ss steel clad unirradiated (
fl fuel elements. Two neutron absorber plates consisting of 0.19" t l thick, full length stainless steel containing 1.3% mininun boron 1 or 0.19" thick 0FHC copper are required between fuel elements of E the following specifications: lj I
I t
14x14 Zr 15x15i Zr -
14x14- 15x15 SST ~SST.
17x17 Zr 16x16 Zr 14x14 Zr
}
Type Clad Clad Clad Clad Clad Clad Clad lrI f
- Pellet dianeter . 0.344-
, 0.308- E l
(non),in Rod diameter 0.367 0.400-0.367 0.384 0.384 0.322 ~
0.360-0.322 0.3805 }
l 1
(nom),in 0.422 0.422 0.422 0.422' O.374 0.374 0.44 l l Maximum fuel .I length, in 144 144 120 120 168 144 144 I ticximum rods / 1[
l element 180 204 180 204 264 235 176 !t tiaximum cross lr section, it (non), in sq 7.8 8.4 7.8' 8.4 8.4 7.8 7.98 'I Maximun U-235/ ;I element, kg 17.7 18.3 18.5- 18.7 16.95 16.6 19.0 (144"L)
{
' t 19.8 tr (168"L) !r ftaximum U-235 't enrichnent, w/o 4.0 3.65 4.0 3.65 3.65 4.0 3.85 j (ii) Uraniun dioxide as Zircaloy clad unirradiated fuel elements contained within the Model No. RCC-4 packaging. Two neutron f'i absorber plates consisting of 0.19" thick carbon steel are required I between fuel elements of the following specifications: 'I
.I l
! Type 17 x 17 ZR Clad j
b l il Pellet diameter, in 0.308 - 0.322 It
! Rod diameter, in 0.360 - 0.374 lI flaximun fuel length, in 168 Maximum rods / element 264 g{
, fiaximum cross section, g l (nom), in sq 8.4 f t i j Maxinun U-235/ element, kg 19.3 lI ;
Maximum U-235 enrichment, w/o 3.55 is
, <l i i I <
I g
I _____________________________________________________,i
m--==4 5
! CoNolTl:NS (continu1d) g
- g Page 3 - Certificate No. 5450 - Revision No. 22 - Docket No. 71-5450 l9
.E
'El E
E (iii) Uranium dioxide as 7.ircaloy clad unirradiated fuel elements. Two g neutron absorber plates consisting of carbon steel, 0.g35 inches I.
in thickness, with 4 mils of Gd,03(0.02 gm - Gd,03 /cm ) affixed It
! to each side of the plate are required between faer elements of #
the following specifications:
[
14x14 15x15 14x14 15x15 17x17 16x16 h Zr 7r SST SST Zr Zr I:
Type Clad Clad Clad Clad Clad Clad I{;
t Pellet diameter 0.344- 0.308- k l1 (non),in 0.367 0.367- 0.384- 0.384 0.322 0.322 i
- g! Rod diameter 0.400- 0.360- (
jg: (nom),in 0.422 0.422 0.422 0.422 0.374 0.374 N:
IN. Maxinum fuel E LEI length, in Maxinum rods /
144 144 120 120 168 144
[
element 180 204 180 204 264 235 'g;l g
Maximum Cross lJ section, H)
(nom), in sq 7.8 8.4 7.8 8.4 8.4 7.8 I Maximum U-235/
element, kg 22.1 21.5 23.1 22.0 19.9 20.7
{!
lg (144"L) 5 23.3 p (168"L) jI Maximum U-235 enrichment, w/o 5.0 4.3 5.0 4.3 4.3 5.0 f
'I (iv) Uranium dioxide as Zircaloy or stainless steel clad unirradiated 3 fuel rods of the following specifications: H
't Tvoe SST Clad Zr Clad Zr Clad Zr Clad 7r Clad I Pellet dianeter (non), i'h g
in 0.384 0.344- 0.308- 0.322 0.3805 't 0.367 0.322 lN Rod diameter (nom), H
'n 0.422 0.400- 0.360- 0.374 0.44 I Fuei length (max),
0.422 0.374 j i
g
! in 120 144 168 144 144 ll
'I
, U-235 enrichment (max), lI l ! w/o I l Note (1) 4.0 4.0 3.65 4.0 3.85 Note (2) 5.0 5.0 4.3 f'
5.0 ---
'r l i Note (3) --- ---
3.55 --- ---
lt j 'l i
't lE'
, i l I l
!l
!I.
t
m----T l .5 l
, CONDITl:NS (contonvid) _g l I j l Page 4 - Certificate No. 5450 - Revision No. 22 - Docket No. 71-5450 t '
)>
- 8 Notes: ,p i
(1) Two neutron absorber plates consisting of 0.19-inch thick, full length stainless B steel containing 1.3% (ninimum) Roron or 0.19-inch thick 0FHC copper are required ,j between the rod boxes. g (2) Two neutron absorber plates consisting of carbon steel, 0.035 inch in thickness, g with 4 nils of Gd-203 (minimun 0.02 gm Gd-203/sq. cm) affixed to each side of g the plate are required between the rod boxes. R (3) Two neutron absorber plates consisting of 0.19-inch thick carbon steel are E .
reouired between the rod boxes, j$
'E (v) Uranium dioxide as a Zircaloy clad unirradiated fuel element. 5:
Two neutron absorber plates consisting of 0.19" thick, full E!
length stainless steel containing 1.3% minimum boron or 0.19" Il thick 0FHC copper are required in the shipping container. The fuel assembly must have the following specifications: f g
i
! 17 x 17 Zr Clad Element I I:
Pellet diameter (non), in 0.322 I Rod diameter (nom), in Maximun fuel length, in 0.374 144 j
'g
!!aximum rods / element 264 t Maximum cross section, 8.4 i (non), in sq K:
flaximun U-235/ element, kas 17.6 I Maximun U-235 enrichment", w/o 3.80 f:
'I (2) ffaximun quantity of material per package u I
(i) For the contents described in 5(b)(1)(1), 5(b)(1)(ii), and 'E 5(b)(1)(iii): l h Two fuel elenents.
(ii) For the contents described in 5(b)(1)(iv): ;R p
Two inner containers containing not more than 80 kilograms U-235. j (iii) For the contents described in 5(b)(1)(v): f N i
One fuel element plus one dunny fuel assembly. N
- I
- 5. (c) Fissile Class II and III j (1) Minimum transport index to be shown on label for Class II 1.2 g (2) ffaximum number of packages per ,1 shipment for Class III 60 l
.I L' =
s p
. .. _ . . .... . . .. . . . . . .. m ======----__ 2
l h mmmum a maMm mm um a m mm m mm ammmm mum sumum m uumA 'mm mmm mmum a mm mamm mm'M; l k
, . CoNDITl8NS (continuo @ g R l Page 5 - Certificate No. 5450 - Revision No. 22 - Docket No. 71-5450 E :
E i E i R
- 6. Fuel rods must be closely packed in the fuel rod container on no more than an equivalent metal-to-metal square lattice. Partially loaded fuel rod containers f
.Il must be fitted with a mininun of three, equally spaced blocks, of which the :E nonconbustible portion of the blocks and the method by which they are secured Y nust assure that the rods are maintained on no more than an eouivalent metal-to-metal square lattice within the fuel rod container, fg b
7.
~
ach fuel assembly nust be unsheathed or must be enclosed in an unsealed, E 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 nanner that would E prevent the flow of liquids into or out of the sheathed fuel assembly. {
t Alternatively, the fuel assembly may be enclosed in an elongated plastic bag or E sheath along its full length. At the botton end of the fuel assembly, the bag .E will be cut off or folded back to assure that the entire cross section of the M 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 f g in place, and the length will be such that when the assembly is loaded in the g packaging, the folded sheath will be clamped in place in at least two grid g loca tions . The top end of the bag may be gathered together and taped closed. N However, the top end then will be slit on all four sides. The slits will run R perpendicular to the axis of the assembly and will extend the inner distance M between the too nozzle pads and spring clamps (approximately 60% of the length of each side). The slits will be made in a plane near that fomed by the top of
{ g the pads and clamos.
- 8. The package authorized by this certificate is hereby approved for use under the I general license provisions of 10 CFR 571.12.
l Expiration date: April 30,1986. f H
REFERENCES E l9. Westinghouse Electric Corporation application dated December 17, 1980.
Supplements dated: January 21 and September 4,1981; March 8,1982; June 14 and October 4,1983; and April 8,1985. )g R
l E
Department of Energy supplement dated: Parch 1,1984.
[
,R FOR THE U.S. NUCLEAR REGtlLATORY COMMISSION I
aMASay Charles E. MacDonald, Chief
\\
Transportation Certification Branch Division of Fuel Cycle and f[
Paterial Safety, NMSS E Date: JAN I 6126 lR*
5 3
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(og UNITED STATES 8 o NUCLEAR REGULATORY COMMISSION 3 WASHINGTON, D. C. 20555
\..**}E Transoortation Certification Branch Approval Record Model No. RCC-Series Packaaes Docket No. 71-5450 By application dated January 10, 1986, Westinghouse Electric Corporation requested an amendment to Certificate of Compliance No. 5450 to extend the expiration date from January 31, 1986, to April 30, 1986.
The certificate has been amended as requested to pemit continued use of the package for international shipments during the period while the renewal application is being reviewed. Review of the renewal application must be expanded to detennine if the changes proposed by the applicant are acceptable.
(h/ r Charles E. fiacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and fiaterial Safety, NMSS Date:
I I