ML20005E022
| ML20005E022 | |
| Person / Time | |
|---|---|
| Site: | 07105450 |
| Issue date: | 12/22/1989 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20005E018 | List: |
| References | |
| NUDOCS 9001030136 | |
| Download: ML20005E022 (9) | |
Text
--,
- - - - - - - - - - - - - - - - - 8813N I 7
U.S. NUCLSAR REOULATORY CO98081 l
If tenc Pomes 81g' CERTIFICATE OF COMPLIANCE
!l l
l11 ees in cra'ti FOR RADIOACTIVE RAATERIALS PACKAGES li s,..e
~, i. ic., -a-
...e.......-ete e.
o e -,_e..
Ni, e.,,,S 28 USA /5450/AF 1
6 ki This certificate is issued to certsty that the packsping and contents oeecribed in ttom 5 t=too. meets the applicatHe setoty eten6 ero k
2 PRE.Ahs.J i
O
$t Feoeral Regulations Port 71, 'Pockagin0 ano transportation of Radeoective Meter al
- e l
b This certificate ooes not relieve the consignor from compliance witn any roQuiremoni o' the reguistions os the U $ Department o Trans r
I applicable regolatory agencies. metuning the government of any coontry througn or ento which the package wili be transponed I ;
I '
d
- '"id'R E 'J','"d L "' "* " "'"" ""I',7"'.To'E U E s s'8%i M W Z cato~
f b
I,) Westinghouse Electric Corporation Westinghouse Electric Corporation application 5
I i
P.O. Box 355 dated December 20, 1985, as supplemented.
I y13 Pittsburgh, PA 15230 l
t g!
71-5450 l!
, ooc,,, m ac.
' E cEie is conasisonei upon fu ang ene, cow,roments of so era Pan n es speceo* ene the coaoitions specite be'o-n i
,4 l
I(!,
I (a) Packaging I
h O
l (1) Model No.:
I RCC, RCC-1, RCC-2, RCC-3, and RCC-4 Il g
l Il i
(2) Description i
11 f
Steel fuel element cradle assembly consisting of a strongback and g!
adjustable fuel element clamping assembly, shock mounted to a 14-gauge steel outer container by shear mounts.
Neutron absorber plates are l
required for the contents as specified. Gross weight for the RCC and i(
RCC-2 is 6,300 lbs., RCC-1 and RCC-3 is 7,200 lbs., and RCC-4 is i,
l 8,400 lbs.
i ili Ij h
(3) Drawings M
(l The packagings are constructed in accordance with the following l
r Westinghouse Electric Corporation Drawing Nos.-
{
[f l
For the RCC and RCC-2 packagings:
1596E24, Sheets 1 through 3, Sub 1;
/
1596E25, Sheets 1 & 2, Sub 1; 1553E31, Sub 1; SKD-86008, Sheets 1 l
through 3, Rev. 2.
For the RCC-1 and RCC-3 packagings:
1596E24, Sheets 1 through c,e 3, Sub 1; 1596E25, Sheets 1 & 2, Sub 1; 1553E3C, Sub 1; SKD-86008, Sheets gp 1 through 3, Rev. 2.
i f}j; For the RCC-4 packaging:
SKE-85002, Sub 3; SKD-86009, Sub 3; SKE-85004, l
Sheet 1, Sub 3, and Sheet 2, Sub 2; SKE-86004, Sub 3; SKD-86009, Sub 2.
i 1c l,$$
(4) Fuel rod container reinforced 13-gauge steel box constructed in accordance with Westinghouse Electric Corporation Drawing No. C5650055,
,pc
'i Rev. 7.
i :$$
i e a-(5) Dimensions and placement of neutron absorber plates in accordance with unnumbered drawing attached to Westinghouse Letter # LA 89-19 dated
.i 2/14/89.
w---wwxss.nCiiWirrw--====-
,a r;x x x x s w - - - w - - -,- x - - - - w w w - w - -
- g7 CONDITtONs (contmu:d)
U *
""%'~
~ ' ~ ' " ~
Page'2 - Certificate No. 5450 - Revision No. 28 - Docket No. 71-5450 5.
(b) Contents (1) Type and form of material (1) Urenium dioxide as Zircaloy or stainless steel clad unirradiated fuel elements. Two neutron absorber plates consisting of 0.19" thick, full length stainless steel containing 1.3% minimum boron or 0.19" thick 0FHC copper are required between fuel elements of the following specifications:
14x14 15x15 14x14 15x15 17x17 16x15 14x14 ST:
SST Zr Ir Zr Zr Zr C1Ed p01edh[jCai l
Clad Clad Clad.
g Clad.
g
-V Q
Pellet diameter 0.344-J
. A 0.308-(nom),in 0.367 0.367 0.384 0.834 0.322 0.322 0.3805 Rod diameter 0.400-0.360-0 0.422 0.422 0.422 i 374 0.374 0.44 (nom),in C.422 6,7 l
Maximum fuel 9
Y fi44 120 120f 168 144 144 length, in (G144 i-A '
gS
-iT (2
Maximum rods /
p,180 R 204 pl80 04 2g 235 176 j
element l
Naxinurr cross Q
9 gg
, p f.
,,q
- section, e, n e
,g;-
(nom), in sq [w. 7.84!a
'8,.4g j l'
7(.8 m N ~B.4/3 4 7
QG 8,*4' 7.8 7.98 Maximum U-235/
Wj-lsh
%j ii Cf element, kg 17.7 W C,18.31
~18.5 i 18.7M 16295 16.6 19.0 L,A Gj;M43[., _ B MpW g(144"L) lg/ 2 t7"
- yh7p 4.19.8 l
gl (168"L) e b w /l p p fjjy l
w s
I 3.657(9 L
Maximum U-235
'4 tf i M 3.65 4.0 3.85 enrichment,w/o 4.07 ',3 3.65
" 4.0 s
(ii) Uranium dioxide"as Zircaloy clad.unirradiated fuel elements contained within the Model No.) RCC-4' packaging.
Two neutron absorber plates consisting of 0.19" thick carbon steel are required between fuel elements of the following specifications:
17x17 g
Zr Clad Pellet diameter, in 0.308 - 0.322 Rod diameter, in 0.360 - 0.374 Maximum fuel length, in 168 Maximum rods / element 264 Maximum cross section (nom)insq 8.4 Maximum U-235/ element, kg 19.3 Maximum U-235 enrichment, w/o 3.55 m xxaz m ---ww-----weme,.,.w.c+,wwwas m sww-wwm
~
~
._=
U.S. NUrLE AR REGULATORY CotNtS$ ton l
{ tooe.*m g
l 1
1 Page 3 - Certificate No. 5450 - Revision,No. 28 - Docket No. 71-5450 l
l l 5.
(b) Contents (continued)
(iii) Uranium dioxide as Zircaloy clad unirradiated fuel elements.
)
Two neutron absorber plates consisting of carbon steel, 0.035 (0.02gm-inchesigthickness,with4milsofGd0.affixedtoeachsideofth$hlatearerequire 1
I Gd 0 /cm )
l be$w$enfuelelementsofthefollowingspecifications:
14x14 15x15 14x14 15x15 17x17 17x17 16x16 16x16 ad C ad C ad I
Jyvge ad C ad C
- f V
l 0.344-Q 7
Pellet diameter 0.367 0.384 0.384 0.322
- 0. h 0.322 0.325 l
l (nom),in I Rod dianeter 0.40lb Q
l (nom),in 0.4fd0.422 0.422 0.422 0.374 0.360' A.374 0.382 l Maximum fuel g734 150 l
1ength, in 1.
Il.. '-
20 120 168 Maximum rods /
4/
i I
element fJ,Q0 204 w.
0
,204 9 64 2@
236 l Maximum cross
~
s
(?
yV i
O I
- section, S
+ ^ ' ). N '8.4 7.
7.98 I
(nom),insq h.8
- M,4 $ 7)1
/ 6 '9.9'/f l Maximum U-235/
M i
element, kg (Jf.1 41'.5 13 gmyrvel 76'
.1 2Q7 21.1 A 1'44"L)/(144"L)
M(5.5
-o i
i 4
l D
f h
9-99 l323.3 I
y'f.:(Qyp68)[Lt)f(168"L)h I
I Maximum U-235
\\N MTR t9
[Q,] U u.,3, Q 4,.7 h ' 4.3 Q5.0 5.0 l
enrichment,w/o 5.0 4.
d I
/
I (iv) Uranium,' dioxide as Zircaloy. clad unirradiatEd fuel elements I
contairiing' a mininun of 48 IFM rods and 25 Instrument / Guide I
tubes per _specif,ication and louding pattern described in i
l Westinghouse drawinpSKA-89044,, Sheet 1, Rev. 2.
Two neutron F
absorber plates' consisting oficarbon ~ steel, 0.035 inches in
=
2 toeachsideoftheplatear$feq(0.02gm-Gd0/cm)affixeduiredbetw$e thickness, with 4 mil' of Gd 0 s
l I
I the following specifications:
I I
17 x 17 l
Tm Zr Clad l
I Pellet diameter I
(nom),in 0.308 I
Rod diameter l
(nom),in 0.360 l
l l
l l
l l
l l
w,---..----------- ------------- --------- ------
?
V l
u.s nuctun ntcutuony covvission
" "?
cowomows teontinew, l
I r
f Page 4 - Certificate No. 5450 - Revision No. 28 - Docket No. 71-5450 1
1 I
l l
5.
(b), Continued I
Maximum fuel I
length, in -
168 i
lr Maximum rods /-
element 264 Il g
Maximum cross
- section, l
(nom), in sq-8.4 i
8 Maximum U-235/
l element, kg 22.5 l
"N E G gj(,8g l
R rods /assenb1h[h.
Minimum ZrB 4
I I
i Minimum ZrB/ IFBA 1081A 1
l 1engthdih I
Maximu,abu-235 4.85 h
l enrichme w/o N
A)9 b
I (v) Uranium diox'1 e,as Zircaloy clad unirradiated fuel elements.- Two I
neutron absorbes plates / consisting' offcarbon ste'el 0.035 inches in I
I thickness, with 4,-mils of Gd 03(0.02gm-Gd0/pm',)affixedtoeach l
sideoftheplate:a'rerequir$dbetweenfue$$1ementsofthefollowing specificati,on:g 6 :j~"~~"tfsl s j,
g g
~1 IIl. _..
. Av si y
h
[t't[ k dkg['
(.O
$$ m.
,x.,
$2 17 x 17 I
M
?3
.Y/
I (N Zr Clad l
b".gC$dQSA MIlh"D >di L
?iR ! '/'
l Pellet' diameter ph JP p0 0.308 g
g l
(./ li" 0 @' "r (nom)', in '
s Maximumfuellength,in{J)&
. %(~p 0.360 i
Rod diameter (nom), ini.
168 i
8 Mayirr.um rods / element
?
204 b'
Maximum cross section-MaximumU-235/ element,k(g T! P 8.4 l
3 R~
(nom) in sq l
22.5 g
(144"L)
Maximum U-235/ enrichment, w/o 4.85 I
I (vi) Uranium dioxide as Zircaloy or stainless steel clad unirradiated fuel l
rods of the following specifications:
I g
SST Clad Zr Clad Zr-Clad Zr. Clad Zr Clad Zr Clad I
I E
Pellet diameter (nom),in 0.384 0.344-0.308-0.322 0.3805 0.325
(
0.367 0.322 y
Rod diameter 0.422 0.400-0.360-0.374 0.44 0.382 g
in 0.422 0.374 I
II I
I l'
lIl
m----------m---_.---_..........,
w I
i n.ve "
us, weeton nrcuteacnv covvenu y
~
g i
p I
l l Pag) 5 - Certificate No. 5450 - Revision No. 28 - Docket No. 71-5450 1
I I
I l
I Fue1~ length (max),
l
'in 120 144
-168 144 144 150 g
I U-235 enrichment
-l I
l
-(max),w/o I
(!
i
. Note I I) 4.0 4.0 3.65 4.0 3.85 4.2 i
-Koted2) 4.2 4.2 4.3 4.3 l
3.55 g
l Note (3) 11 I
I I Notes:
i l
l (1) Two neutron absorber plates consisting of 0.19-inch thick, full length stainless l
15-inch thick 0FHC copper are required g
steelcontaining1.3%(minimum)Boronop6Cu[]
l between the rod boxes.
D g
lates (onsisting of carb n sten, LO35 inch in thickness, I
I (2) Two neutron absorber I
minimum 0.02 gm Gd 0 /cm ) affixed g each side of the l
A l
with 4 mils of Gd 0 p
C platearerequire$$atweentherodboxes.3 j
(3) Two neutron absorbe'r 1EteY consisting of 0.19-inchtthYck r80n steel are required I
betweentherodboxjs.
<fN
'/K.(
I O
I e[
O c;
g.
t i,
(2) Maximumjuantity d'f3alte' rial'per packagi[
j.,
{
l
\\v
& #4)nr
, w, g
ForJthe contents" describe [ g a w l
'in>5b)'(1)(1),5(b)(1)(11),
I 5(b)(1)(iii)pand 5(b)(1)(iv)k($Lr#'
I (i)
I NP I,
l
()
M %%SQ
[.
Two fu'el elements P S) Q ll (; N d y J
l j
1 g;N'N h
l i
V B [L For the contents describedJn\\ (.6()i)(vM):
t-A i
5b) y l
(ii) nr y
i l.
One fuel 'elkinent Y
hj I
[h
.it 5
(iii) For the contents tiesc(ibgd;iniS(b)(1)(vi):
i l
l Two inner containers containing not more than 80 kilograms U-235.
g I
I I
I I
5.
(c) Fissile Class I I
I 6.
Fuel rods must be closely packed in the fuel rod container on no more than an l
equivalent metal-to-metal square lattice.
Partially loaded fuel rod containers y
l I
must be fitted with a minimum of three, equally spaced blocks, of which the a
noncombustible portion of the blocks and the method by which they are secured must I
I ll assure that the rods are maintained on no more than an equivalent metal-to-metal I
l square lattice within the fuel rod container.
li i
i l
I I
I I
'l I
l l
I l
I I
I I
I I-----___----__--,.....,,,w,rv..,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,_;
r---____________________________________________,,_
_ y I
U=
- T ' " "U J M G " " "'
l cinomtNs tcontinuw)
I I
I Page 6 - Certificate No. 5450 - Revision No. 28 - Docket No. 71-5450 1
I I
- 7.
Each fuel assembly must be unsheathed or must be enclosed in an unsealed.
l polyethylene sheath which will not extend beyond the ends of the fuel assembly.
g The ends of the sheath must not be folded or taped in any manner that would I ;
prevent the flow of liquids into or out of the sheathed fuel assembly.
I t
I 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 g
will be cut off or folded back to assure that the entire cross section of the a
lower end of the assembly is unobstructed. When folding is used, the portion of I
the sheath that is folded back will be cinched with tape near its end to hold it I
I in piace, and the length will be such that when the assembly is loaded in the packaging, the folded sheath will be. clamped.in place in at least two grid l
locations. The top end of the bag may be gathered together and taped closed.
g However, the top end then.will be slit on all fourlsides. The slits will run a
perpendicular to the axisi of'the assembly and will extend the inner distance I
I between the top nozzle peds and spring clamps (approximately 60% of the length of each side). The slits will be made in a plane near the ormed by the top l
of the pads and clamps. h
/
l The package authorized by this~ certificate is herib7. j j
(n approvedj)or use under the 2
ll l 8.
general license provisions of 10 CFR 671.12. ( <3 f;;t L
Il
/
i
'r7 (f
.s3) e
~
l
\\'T
' 9.
Expiration date:' duly 31, 1991 4
yijb,[
y >y REFERENCES Westinghouse Electric Corporat' ion application' dated December'20, 1985.
Hj r,
.~
Supplements dcted: April 28, July 1, July 21, 1986',2 Jin'uary 4. February 14, April 18, October 5. and November 30,11989.
J
, Department of Energy supplement dated: March 1, 1984.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION t E'.A $ts Charles E. MacDonald, Chief Transportation Branch Division of Safeguards and Transportation, NMSS Date: W2
.c
/
1'g UNITED STATES
[
NUCLE AR REGULATORY COMMISSION n
g..... )!
WASHINGTON D, C, Mm66 5
i S
APPROVAL RECORD 1
Model RCC Package Certificate of Compliance No. 5450 Revision No. 28 l
By application dated October 5,1989, as supplemented November 30, 1989, the applicant requested an amendment to the Certificate of Compliance to allow j
shipment of either one 17 x 17 0FA fuel assembly enriched to 4.85% or two 17 x 17 0FA assemblies enriched to 4.85% if each assembly contains a minimum of 48 Integrated Fuel Burnable Absorber (IFBA) rods as specified in Westinghouse i
drawing SKA-89044.
The reduction in reactivity of the fuel assembly caused by the IFBA rods is important in maintaining the suberiticality of the package. Therefore, it is l
important that the Zirconium diboride coating on the fuel pellets in these IFBA rods remain in place during both normal and hypothetical accident conditions of transport. The applicant performed tests on sections of these fuel rods which have shown that the coating is not significantly affected by these conditions.
The applicant performed a criticality analysis on the proposed loadings for an infinite array of damaged packages using the model defined in previous amendments. This analysis is sufficient to satisfy the requirements for l
shipment as Fissile Class I.
The boron coating on the IFBA pellets was modeled in the cladding instead of an explicit coating on the pellet due to modeling constraints. Studies were performed by the applicant to quantify the effect of this modeling approach, and Also, a 5%
biases were applied to correct for the differences in reactivity.
reduction in boron content in the IFBA rods was taken to account for variabilities in the coating process.
Both of the proposed loadings were modeled using the KENO Va code. The results are values including biasis and maximum 95%
presented below, with the reported keff confidence level uncertainties.
Applicant's Analysis KEN 0 Va Results Infinite Array of Damaged Packages Loading K,ff w/ uncertainty applied One 17 x 17 0FA 0.9457 Two 17 x 17 0FA w/
0.9368 48 IFBA rods
o 2
Calculations were performed by NRC staff to verify the results obtained by the applicant. These calculations were performed using the CSAS4 sequence in the SCALE library (NUREG/CR-200). This sequence was used to create input for the KENO Va code.
To determine a conservative value for boron loading to be used in the analysis, staff performed calculations based on the boron loading measurements from representative IFBA pellets presented in Table 2 of the November 30, 1989 applica*:on. These numbers were averaged, then reduced to determine the nominal loading at a 95% confidence level. This nominal boron loading was used to calculate the nominal B-10 loading, which was then reduced by 25% to encompass any uncertainties resulting from the coating and pellet loading processes.
These assumptions are deemed to be conservative in this analysis.
A comparison study was then performed using XSDRN-PM to perform infinite lattice cell calculations, including the B-10 alternatively in the fuel, gap and clad regions. From this study, it was determined that modeling the B-10 in the fuel produced only slightly higher values of k with the increased reactivity resultingfrommodelinginthefuelbeing$b,y1.9%higherthanthereactivity 8l when modeling the poison in the cladding. Staff concluded that modeling the B-10 in the fuel region would provide conservative results while producing only slightly higher values of k,7f than would result from modeling the boron coating explicitly.
The confirmatory calculations were then performed with KENO Va using these assumptions. The results of this analysis are presented below.
Confirmatory Analysis KEN 0 Va Results Infinite Array of Damaged Packages Loading K,ff,w/ uncertainty One 17 x 17 0FA 0.931
.004 "l
Two 17 x 17 0FA w/
48 IFBA rods 0.941 2.004 The results of the analysis for one assembly were similar to that achieved by the applicant and found to be satisfactory.
The analysis for two assemblies yielded a k value of 0.941 i.004.
Although this number is higher than that predictea b)fkhe applicant, the maximum value at a 951 confidence level if 0.949, which is below 0.95.
_,... ~...... ~ - -....
4
.1 F
, o.
Based on the applicant's analyses and staff evaluation, the staff has determined that the proposed amendment would not affect the ability of the Model No. RCC package to meet the suberiticality requirements of 10 CFR Part 71.
Charles E. MacDonald, Chief Transportation Branch Division of Safeguards and Transportation, NMSS DEC 2 21989 Date: