ML20210S953
| ML20210S953 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 09/26/1986 |
| From: | Capstick R VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | Rooney V Office of Nuclear Reactor Regulation |
| References | |
| FVY-86-88, NUDOCS 8610080269 | |
| Download: ML20210S953 (5) | |
Text
=
VERMONT YANKEE l NUCLEAR POWER CORPORATION RD 5, Box 169, Ferry Road, Brattleboro, VT 05301
,,,Ly 7, ENGINEERING OFFICE p
1671 WORCESTER ROAD FRAMINGHAM, MASSACHUSETTS 01701 TELEPHONE 617-672-6100 September 26, 1986 FVY 86-88 United States Nuclear Regulatory Commission Washington, DC 20555 Attention:
Office of Nuclear Reactor Regulation Mr. Vernon L. Rooney BWR Project Directorate #2 Division of BWR Licensing
References:
(a) License No. DPR-28 (Docket No. 50-271)
(b) Letter, VYNPC to USNRC, FVY 86-34, dated April 25, 1986,
" Proposed Technical Specification Change for Spent and New Fuel Storage" (c) Letter, USNRC to VYNPC, NVY 86-147, dated July 24, 1986 (d) Letter, VYNPC to USNRC, FVY 86-73, dated August 15, 1985
Subject:
Response to Request for Additional Information - Spent Fuel Pool Expansion
Dear Sir:
By letter, dated April 25, 1986 (Reference (b)), Vermont Yankee submitted a proposed Technical Specification change for spent and new fuel storage. In response to staff questions discussed during a telephone call on September 12, 1986, we are herein providing, as enclosures to this letter, several diagrams as additional supporting information.
Specifically, Enclosure 1 is a diagram of a typical spent fuel rack outside boundary region indicating the relevant dimensions of several cells and the locations of neutron poison material (Boral). Enclosure 2 identifies
)
the locations of each cell weldment along the periphery of each spent fuel rack as found in the installed condition. The cell weldment locations illuatrate where the stainless steel can and Boral assemblies (Boral on all four sides) are placed vertically and then welded to the fuel rack base plates. By this " checkerboard" arrangement of the assemblies in every other j
location, resultant fuel storage cells are created. This manufacturing process results in all fuel stored in one fuel rack being adequately poisoned from all other fuel stored in the same rack.
\\
l 0
0 8610080269 860926 PDR ADOCK 05000271 j\\
PDR p
United States Nuclear Regulatory Commission September 26, 1986 Attention:
Mr. Vernon L. Rooney Page 2 Additionally, Enclosure 2 depicts the neutron poison interaction between adjacent racks. As indicated, the alternating scheme of cell weldments is l
continued such that a poisoned cell on the periphery of one rack is opposite a resultant, unpoisoned cell on the periphery of the adjacent rack. The criticality analysis parformed and documented in Section 3.1 of the Vermont Yankee Spent Fuel Rack Replacement Report [ Reference (b)], demonstrated that during a postulated seismic event, the maximum rack sliding displacement will have no effect upon keff. In addition, the criticality analysis considered the accidental placement of fuel adjacent to an unpoisoned location at the fuel rack edge. The results demonstrate that there is no positive impact on the worst case keff reported in Section 3.1.3.2 of the Vermont Yankee Spent Fuel Rack Replacement Report provided two additional Boral sheets are installed at the positions indicated in Enclosure 2.
[Also refer to Nuclear Energy Services Final Design Drawing 83E2245, Revision 1, " Fuel Storage Rack Arrays"; Items Number 24 and 29 are the two poison sheets (see Enclosure 3.)]
The criticality analysis verified the design adequacy of the racks by calculating the keff for an infinite lattice under normal conditions and then adding any positive effects on keff due to abnormal conditions. Where applicable, neutron reflection was considered in calculating effects on keff from abnormal conditions (i.e., fuel handling error). Because an infinite lattice was conservatively assumed in the normal (reference) configuration, leakage of neutrons and subsequent reflection does not occur and was not considered."
Should you have any further questions or require additional information concerning this matter, place contact this office.
Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION I&y R. W. Capstick Licensing Engineer RWC/jle Attachment 4
g 075 acm wem o.s 3 sce_ wem
- s. m seu vom na c.zus" s
N
\\\\
N
\\\\
i r
r
_s cru.
I i
- o eszz, k
I l
E
/.
7 eme 0.045' FtlScN O.091
'~
i mm.
005
~ CF.L D.C92 f,
e j _ _ @_ _ _ ____ _ 7 e
4 f.
I CEu.
l nmt
)
t
)
~
i ENCLO 50F.E 1 FUEL STORAGE RACK ASSEMBLY
"'". 7.2 4 5 c """5"'" 3 " '"""
(P ARTIAL)
$3?
CottNER OF 15 587. RACX of:
a sF-l
__(: Z - _O,p5E
~
44b % 9 u M -s T XAFXfN j._]
- d - -- A-(W X,
l a
...L y _g _
v.*._
g i
v_..
r
.c
- ~ -
k
~N
'_t _ # D
- 2..
'. _ ~.. A..
6, x *
',N.,E.*. y7 N,
~~ - *g
X
.N X
~
-w -
, o -
,k
.s, q
y a N m ~
n
~
[ ~ ~I I
y j.h (2 r
.R d.S.E S E E.3 X.. : ~~
l xy y C< x v d 6
~Z Z._.
T_
._7 XA s X A X X ~X A X p' x >q x X ix x x (x. x x /j x x
'x-F.9 l
+X I
X+
~
~. 4X
-gi+
t I
i i
y L__X L _ _ _l X._ _J
. L_% x _ _J x
1_ _ x F-f X,a r-x X _~
Ry-x X-l b
'1x-i
+x x ix j
x x' _;i o p
_x x
l w
x i
x L -- x
. x ' _J q 2
Io
'x Y-j 9
i L _ _X N
X X_
N +L _7 X_
L r-A N
_y. IX_ _ q y _ _,.
7_ __,!
I l
l+
X+
1 d
+[
3
--X L
X+
v-y't( y d y y
' b '>d y X y V [ v v.Y y Y Y v o
Y X X X f-- Q % X F X_.X._74.X.A f _ X: X X PC X.X' _b
,f o
m
+2 :X l
.ii__.. Mn+
l
_ T _3: b--~_)i
'a+
i i
i t
X
__J
. L _J X ~
1.0 x
i X
i M}x z_ _J L_j. X _ _ J.
i g
r-_
X--1 g 4
-X M-7 x - -
rQ r-x i
i
.2 :
1~-
i
.,y X Y X
s
's '
_x i
s,,
i I w <h x _,'_ _I N +
_ i_
N
$x o
1 "x k I
x-i Y__ i N
_X X__J 1_ _ 7 J
X L_ X N
X X
K y,y--i
,- y y-x l
x-,l j.
~
~_.
x i
~- :: X+
l I
2-l X
-O
- yvvvyi v x -Y 7
Xv y! y y x y [ yyyy A A X X >$ A d
~
b g.X: A X X X Ap p x 6 X X $ X X X 1
L_J j
f1
+
!x+
i
_i
+X.~ 2-a:wx r
X i
I i
i i
_X i
%__J
^
L _ _X
)
4 J
,.g
._y ~DC _ _
g m
,X 0
X -
'1 s~W-h l-__X t
I 6
K___
i X
s
./
.X a" N
I X+
ix i
i d
X,-
.g X
t X 9
I X
o i
Xi.X.J - __l S
IX _ _ a %
X l
O 1
N u _ _2
.___X N
c.
i X___i t_ X D(
(n L-,
- --- 2 X-f 8
x---
r-y g
__t I
1 X
i X
3
'1 -
/'
4 XP i+
4
>y+y,v y y V y*
,.x y X y y d v 'X2 fy '2 y y y y 2 c
j i
l
& ?5 5bE?N55[5 Nf3YOEL STOREG5RACKT hn 4
83EZZ454l 2Ox/5 FDEL STORAGE RACK l
'X 3 83E2245-312Ox14 FUEL STORAGE RACK l
IfX 2
83c2245-2 l ZOxl8 FUEL STORAGERACK..
L r...
tn
-- / ><'
/
.83E2245 -
.Y.
TERIAL SOURCE
-3
- 2.
-1 ITEM PART NO OJj bl CONTROLL TOLERANCES UNLESS g
OTHERWISE SPECIFIED DECIMALS
~
U ACE i 2 PLACE 3 PLACE L
f o
it
}1 ECI W S~ TNWS CHAMFERS
'AP THis onAunNG IS THE PROPERTY OF 2
M NtWAR ENEW SEREES,lNC.
DR'AWNP MIL AZZO b 'zWl DANBURY, CONNECTICUT AND CONTAW$ CONitDENTIAL INFORMATION. N ACCEPTN F ACE FlmSH-AA~
7j g_
DRAf,wG, THE USED AGREf$ THAT E IS FOR itiE USER'S SOLE i
m ITER I
PROO USE. AND THAT THE DRAW:NG AND THE INFORMATION CONTAMED LETS- 02 TO 03 RADIUS D g N /M. g g~ I
- /j HEPEW W:LL NOT BE USED M ANY MANa*ER DETRiWEkTAL TD
~
E AK EDGES _02 RADtUS OR g
y hf[jf[A y
"##" E** 3E"8' "
11 b3.
-g 4-
~
~ '
~ '
J
~
10NAL TANDARD TOLERANCES It 4
PLY TO CCMMERCIAL MATLS '
M6El V M -f-
?
E.-
~ ~.
bl.,
A i; p g a g'
- p _ e j..:AM AYS
~S-EET 8
~-
FE ADS-UNIFIED CL 2A.~
R Asm, AENSt0NS ARE tN INCHES -
^
a A/E U M [ p O ~g.... lI
. '4 - '
~
~-
SED ON 55'F (20*C1 -
H6R F
l '# U 4 I
- ' SIZE FSCM NO.
DRAWING NO.-
REV 3
AS 00 h0T INCLUDE ALLOWANCE -
.s 1:
1 83E22L5
~
- rE
.53603
~
r MS AND TOLERANCES ARE TO WElGHT.NO TED ;~--
?-
. INTERPRETED IN ACCORDANCE
~ PROJECTITASK 587GM/20'.. l SCALE. dRTED iTH ANSt Y14 5-1973
.J Al 7
~
u
, l,,.q
. g'**~~j.
. -. ~
0
~.
. ~. *, -
.,.c.';w.
g
_