ML20133P304
| ML20133P304 | |
| Person / Time | |
|---|---|
| Site: | 07109262 |
| Issue date: | 01/15/1997 |
| From: | Kay J YANKEE ATOMIC ELECTRIC CO. |
| To: | Chappell C NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| BYR-97-002, BYR-97-2, NUDOCS 9701240168 | |
| Download: ML20133P304 (3) | |
Text
~
YANKEEATOMICELECTRIC COMPANY
"'l$"*,T.g1lT,*l" g
580 Main Street, Bolton, Massachusetts 01740-1398 v.
January 15,1997 BYR 97-002 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Attention:
Mr. Cass R. Chappell, Section Chief Package Certification Section Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards
References:
(a) Docket No. 71-9262 (b) USNRC Letter to YAEC, dated February 6,1996 (c) YAEC Letter to USNRC, dated March 23,1995 (d) YAEC Letter to USNRC, dated November 14,1996
Subject:
YNPS Reactor Pressure Vessel (RPV) Package Safety Analysis Report (SAR) -
Updated Drawing (Figure 1.2-1)
Dear Mr. Chappell,
In Reference (d), Yankee submitted a revision of our SAR for the YNPS RPV Package. The purpose of this revision was to present a reduction in density of the non-structural concrete fill.
The reduction was necessary to reduce the overall package weight for rail shipment. On November 20,1996, the reactor vessel was successfully removed from containment and placed into its shipping container. Subsequently, the vessel interior and annulus between vessel and cask were filled with concrete and the top cover welded in place in accordance with the SAR and NRC Certificate of Compliance (Reference (b)). This letter provides an updated drawing, Figure 1.2-1, reflecting the actual concrete density values within the package.
Based on the actual concrete densities, the resulting package weight is approximately 7 tons less than the projected 328 tons stated in the revised SAR (Reference (d)). Furthermore, based on a
'/
survey conducted on January 10,1997, the package dose rates, both on contact and at 2 meters, meet the limits in 10CFR71.47(a), (c). These limits are 200mr/hr on contact and 10 mr/hr at 2
[{Ti 'I meters.
The actual concrete densities have been compared to those used in the revised SAR. Their impact on the thermal and structural analyses is determined to be negligible. The re-analysis presented in Reference (d), both thermal and structural, shows little impact resulting from the reduced concrete densities, primarily due to the small heat source of the package and overall strength of the package. The thermal performance of the package continues to meet the requirements of 9701240168 970115 PDR ADOCK 07109262
, h, C
PDR G dt[L : ( 3if f
>{
i 0
l i
U. S. Nuclear Regulatory Commission Page 2 4
10CFR71. Since the structural analysis incorporates the weight of concrete, but takes no credit i
l for its strength, the reduction in weight further increases the overall strength-to-weight ratio of l
the package.
r Status / Schedule On December 18,1996, the cask was placed in the horizontal position under the containment for temporary storage during the winter. Shipment of the cask to Barnwell, S.C. is expected in the Spring of1997.
Summarv l
This letter simply updates a drawing previously provided in Reference (d) based on the actual concrete densities. Overall package weight reductions have been successfully achieved. Actual j
dose rates for the package (surveyed January 10,1997) demonstrate that the package meets the 1
dose limits of 10CFR71.47. Conclusions of the thermal and stnictural analyses described in the 1
SAR are unaffected by the reduction in concrete densities.
i Ifyou have any questions or desire additional information, please contact us.
l Very truly yours, I
YANKEE ATOMIC ELECTRIC COMPANY i
f J. A. Kay Principal Licensing Engineer i
I l
cc:
Document Control Desk (1 original + 10 copies)
M. Fairtile, NRR J. White, NRC - Region I 1
l i
l 4
2
{
a
' S j j".1 c\\dgn\\yrdecomb.t.^iiO5.dpi
.V
. n
. G.
A==h * -
.P E5g esy z
35 S
it'-8
- FLANGE 0.D.
- 5.. - j m
=
- g*PMEMEm
=
~
e-3 RG")n M00!FIED EXISTING h. l.k"U' k
.I N dl E
REACTOR HEAD STUD i
(CAP NOT SHOWN) 25*
i
[ RPV CASK COVER g{-g{jg"Rg 4
l g
(A516. GR.70) n mssssssssssssswssw, qc g,
a a
u s
fHt
=R i@,h...
a g
!1 F C T.]
k' 3'-
UPPER INTERIOR T
st l
442l CONCRETE
, r*.
< CONCRETE
..g (25.7. pcf) i j
g9
. g,, 3
.l PLACEMENT
..C 4-i gA C
4*{:/h;h 8 N07ZLE
.s.
5g dl.,
ti:
12 '-4 W * ( MA X. )
! Tii~,ll_,
g COVER (TYP) o
. murs"n r4ct or wante coven etartsp j,..
. :. ' }g (A36) 1
,1 t
- h. b.
12'-4h* SUPPORT LUGS
. M..l 5 r2-h ' ' '.
?
n
& I n
u M
n FMIPPI G CASK.
'h'
- ~ {-. ~- ~~
[,o@ @
..D.'
A-RPv.
'.c.x.; J k'.
a g D g
+i WASTE PKG.
- h eE * *."*
g o
3"S
q.....
8
.' *./ O ONCRETE l
R N
.. "N,' >
1 l 4,
". -w (41 3 PCf) m h j I
.N I l O 6 j4-l M p
x o
l Q l &
+-
p a
e i m i
L ' - ' t-
"E{
i r
3
/.;
I g
5 3j m
4 ri i c-PACKAGE l
i j
INTERNAL 2
D. r y p
l v +--CASK CYL INDER l
a
.n...
M s
(A516. GR.70) l
..........4.......
~
t+
R
/
,[
10 '-5 "
M.v P) gm y
i 1
%,E[h A
[,[. j I.-
i
. t
.11d C,
P n
ER _y g._
> u, 3
' e o(f, ap 4,. m m
w
.r........-
"e n
y
< *. ' ' em *.
- e
' LOWER INTERIOR
- 'w
=.
gg !A N
n
. '. f.j,'*.,..
N CONCRETE N ft ?
,.. ' o M
' ff.RT E '
p i
j Ek ru,. *..
(74.2 pcf)
D
...IF.
n y..
e.
....,. ;.,,s
.e
}
g
...*?
[
- m,
.. O.. -
i
. ' * - 3 n
q _;;:
.... -l.
m p
.. ~.. -
- : I I E' p
i p gA
%"R.(A516, GR.70) s y
Z a
c g3
....V
..~...,......
g-4 z
g v
v
~ ~.
to m,o d,
,, +,
a
~
~.
_L U' E __E.
4 e
BOTTOM COVER e.
e mo
( A516. GR. 70)
? O>
O. <. n 13'-2 0.0.
- n
=
O o2>
U1 o
m I
.*WP-g.lb.W.P J d. 4#. -..
~._x.
j ( c:\\dgn\\yrdecom\\yrb90005.dgn 1
i s
~
\\
~..
!s;E ME? e G
Z O
s'a ;;
11 '-8V2" FL ANGE 0. D.
-,m m-zo
=
mz-m
=
g v)
,- y' o 8 a g. -
~pgn MODIFIED EXISTING RRg80*a REACTOR HEAD STUD
@*pgG^*
(CAP NOT SHOWN) ga,ga' h i
dyy RPV CASK COVER dyh 1
gS*og a, I
/
(A516.
G, R. 7 0 )
Y g.. o-in g g 5; A
,,M EsNN % % NN NN A \\\\ % % % A NN A NN % % \\vxx se% \\\\3t %
- w g
g 9z.y-E ga gng o, p
3._.
........ _.. s ?s 2a.p. :s se r
, :..z s
m w
. +-.
O 3'-#Mjh;g$.'."
g.j paar E~'
MENf 12'-9" TO v7dygd..-
UPPER IINTERIOR aa Vg"g /
TOP OF 1 st
- s85 M
i 7
CONC f'.6g i
(25.1 RETE E
5' CONCRETE I
+t*
pcf)
, -- c-f PLACEMENT j - n,. : w3>,..
o g
m o
u o
o z m
n h
s' 7
l
.;.g
?
y
=
, w f:3 ;e g
g;g
.~
1 :.
wq q
's 8" N0ZZLE 3
- . b ;'j...
12 '-4 V2 " (MAX.)
.f ' ; b COVER (TYP) e, g
- f. ].i.j.~g"..t0UTSIDEFACEOFN0ZZLECOVERPLATES)E j, ; -
/
(A36) h
=
r..
/:
. k,;
f,
- j fh 12'-4V2" SUPPORT LUGS 9
r
.m.
g
-v
- g Ay u
(
Ny;y c.
Vg tyf f
ih m
Q2*
SHIPPI G CASK,
,L_,_7;4;"
I' 58A U'
- RPV,
@i
' J ; d l.
Y
" 4-63 s
- ;. ~;
3 WASTE PKG.
ggIj O#
A o
R ZG G
f ".',i -
i I
CONCRETE
$.$oo
/k7 ' bg l
25 -
l Ne.I..
a f (41.3 pcf) 5 N
a.4 g4 1
rn2 cn nz o
$g E
Q I,",
ay w!; l c >
1 i
qa E 5*
6 hi
~.1 "
j H
6'4" l
a$d}'o f o
9
,7 i
i <
r-a..-
i 2>
=
e
, m
%p ln lt @
r.
nj i
.,u r
s
- sT r
O. ~ i -
G INTERNAL
^
s.e.M 7,
o s
EA PACKAGE
=
s
, c s
SHIELD- - - - - - - -
2 u
s
- %m h
o - A --
"a A~s A m
L------------ -
f-- P -- E E m '
I y?
(
M r-5Y
[
INTERNAL Y
f I
3 s iz j\\?/ gg%
SOLIDIFIED
%j i"
3 BLOCK g i o
WASTE PACKAGE I t-u m
o
$. *. e.
F n +
- f. ~
INSULATION a
y
'c '. -
M o
(CNSI 14-195 LINER
';~"j P
- c. g "4 r
i
s 9 li
' z W/100 PCF (MIN) ml m
f
.,, O,
,f' Sg CONCRETE)
'i M ". - f s
z i
o mi 8~ i
}
g i
i
= ' &
f,' # <
CASK CYLINDER
- ~-
g t ?, g
' Y _ - _ _ _ _ _ _ _ _ _ _ _j _ _ _ _ _ _ _ _ _ _ _
_ _ _: g.p.,f.
1 *
( A516, GR.70) f
%+
e Pt
-t
.n
'.e.
. #p,
?..
4 Mb m
s s
4 z
9,-l 1 0 '-5 "
f.:t*.ss m
f
- n
/
W.~.. -
~
a-om o
n.
no m OE >
h>
4IV
.h4 f l.,,f j$ &
Q 9.?l ((!;
[. *...'. :.
Y y,
p I
g l p,M a
m (K 4
$.m m
g.-
6 1
a s
m
- p
.y gn :.
i I co El kg..
n
'. NLOWER INTERI0Fi
. Oyf
':. 7. [
Es %
P*f o
CONCRETE o E go M-
- R. {M... -
( 74.2 pcf) lP r.
a 9
G o
' ' +
..' : '.,h '. 5 1 ?
N k
9 ?l; _ Y( 5. ' ',: ',.
~
1
, *...1 z
t' 1
m, 7,
I
.-t i
S.
r~'j
~(_.
I
,.f; n3 v. :;S : T,. ~,.
j V;EC N e.--
m e
Y:. :i..
.;.. i i :s
-'J l
5
\\
. ::.:: ~
.a-
+
w
>N
?
.'..'.: 'f :.
- s 4
g o, 1
s.,....
I s.
.g
,/2 "E( A516, GR.70)
-f..,
- g z -<
\\
v
=
<- (.wdf.O, h e '
j 7
p ~D 1
Y r-A Yg g
/
7 @x w 9
w
<sssssssssg.gngggg]gg gg g
V V
m g,
y A
BOTTOM COVER k
h$ h$$
o mo
( A516, GR.70)
- 8F
.T --i --J l
o' ON 13 '-2 " 0. D.
95 OCm x
hl-O od
~
a mo oa m
U1 ZO m
sy a
J e
i=
....