ML19332D468
| ML19332D468 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/21/1989 |
| From: | NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML19332D466 | List: |
| References | |
| NUDOCS 8912040007 | |
| Download: ML19332D468 (6) | |
Text
W nM.fh.aa@SW P i%..m$s % ' y!m% v MWVM, ;S. Mv M%.. _i' c'*
1 -
A c W.
"M*
- L MQ WQymm.. w e; pMp# -,smVVFy
-..W s&.Q:: W- _.
- 8 o
~
,~
jW
'y
. 5 i:g
- f x
. m -
r 3-r.
wu
,w..,_
_ %r
>: A t..:3.. c.o7:
4 h,,m r
.v----
- e..-. c.,
s.
s s
w s
4 f@' M r#.m; ; ges'.'M M.w:e m+, f.c@ (
m.>-
g.-
- p~
a.
&_+
g 4.
m.
m sy ne m t./gyyC-s c'-
~-
3+y-
'~
3 c.
- t.
g mt L WM.
..n e
4 v
g a s
c i._
T
- 3l t
<; g W
+
?'
G,pp or k s, u.,
,a m
q a=.
.q 4, =;f f[.s.
7
~
,a w-p.,.~ 7,, v~e.k j
r.g, x n. +'
A+.
.m n
c. _"._, ' n [; g R,=
'w, w n
+
1 n.
I(( *\\p i[}'
l' h
s*
s-
=
h,.
F i
4 t
S 9%yW' q ca ' >
imp y
7 P
. Dock [et No; ' 50-2451 d..,
n.w m
- e. ewn-a w u,m~n%. m j [= w,. -
w:g 7
m r t
e - s,,.,
- 4
- \\
f.
,o emee N w w m'+d ea m,3 -/W A 4;..
e-r n
+
=
~-, &
3 L., J e
x;1s g
p
- 9 4..,,w: p
..,..[
y
.,M n u m,... o. /
w
- v..r.a y
s w
L w]-
b i*s
/-
k ';[
y e._. w(,q y =
-g fii
-'c r,
e W 3 m m i ' y,+ (' ^ l e,([ 'b[
'?f' 4 i s
(;
k'? g N'
- .3 s
[dw.IM.f$:
Of&- Nj '
gy %
_h a'
g,, y y,.w~ m; ww w,..
.,em
,s o.
~m 1 y win 2-
+
_~, \\ E 7.g, j\\
..c.~
Y
} p m
R N
~:). "
f 2
i g,
, m
-~
w
,um r
w y ~y r w.w:. w gs;.
- i t
s-.. -
v..
m.
- 3; t
-s 1
-~
1 z.s.
a "MM 1;f Q f
%pg$
4 a
+
- _- m m
~
A x-
.~
q h[l 7: :b.
- led e
~, :qw::Q3* 4 w
Pp.
.. 8
.+
i
+
a 1
.@ S r
. v e
s
<y.
"A 5
g..
- M n
cn
-w.
m
^
a s..
bh'
- U: ' -
-n
- y' '
^
^'
i ia a
3 *'^~
fj^-[
s s
J 9;;
i 'T1/
'i 3
u.3,:
.a
_ lq
~.%
s v~
sq :
w.., ; _ ;w w_ m
<\\
welff M, '
- y e,,,
ma
- - y'd 1.
t
-n q.
~ s ax D ' ;'
Q:V.6 s,
+
n.c;%.,sA j
o m
~
g,5 J L;Q sy
[.3 i
y-. a t.-.
- s.
v..,.
3 M f,,:v.
v A
o J.. u, _.
g a,-
up g,
v t yff. ;,
< ww
Attachment:
1 4
e..a J WR,,U>m s'
.o.
.c
~..,
x, ~
-i w
s, g '*'*$;
y g
.l4.gh n'y-w' ' ' < ; 7. -
4..__-
s Millstohe: Nucle'arPower? Station,dnitNo.l' s
m nS. m.
y a}l m
~
r zv..
pa y
=:-
1 SigW
%'J Proposed:Changeskto'TechnicarSpecifications; i
nau a..s. ~-
+y m. ~yggm-9 ;.y
, n' k ' I C ".[ f'D '
s' i
$#I
$N\\,' { y'
)
..; y,
'.(Nl.
i' f,
2 3
,u o,
/
$ k
+
- ' h 27
~
m, I
+
e'tV' : p. g, ;.5.
t g('?," gy.,.,
.J *- Wr uT_.
.. ?
,=,,,pv a ' ~ n.q gjy,
y
-g g
o.x s
w-,
s s
6 y,
d Ek1 ~ %q ' >
4'
- g 4 Ut yh x+
x, c y -4, c
'c i-m y, q, ::
.i*
- Yq' y
+%-
t I
I.-
I,'..);,.l'4 5.
^
j~, '
l.*
?
z Sm w, <%.
ij r
u ~
~
m w
m v u w.
,..xr r.
s.
.c &
r
+m ~ ~1
- g p# *F's p
n
)
3'
. u..
!g
,n%,>,h-_,'
4 W
I i
ol g '
.,.g
' -d 1' 'Y,
,n v;
t h. '.:Q'h' 4 ' h' -.
M',..
'c?,
's
,- y > E t 1 -X., *
- d, i' '
'M i
b;
.6
(
m
)f $
1 I
y.
t j.
y
'T mt..
m_g s,,
4
.&~
jg\\ i ' <
+
N W-
..,s,]
C h'.
n
., e x
m' l.
.Y l
' h'? g 3
y
. _ ' _ ~ %
.n'm y,,%,
s/
a y',
. }
s q
\\ g ] :j. ;-. 3 W
.-j-.
d_.
I
.,'I l ; y' c'y'M
',,f, w
..j
-,.l.Nb 1
-h_ ;
t 6
-- [%
,.}[ Fj H O
l n.e<
ky(n x
p g
- 6
'q em.-.
3 l
November 1989 L)S O
3912040007 891121 l
PDR ADOCK 0500024g, 1
2 s,
p PDC.
s y a4 i;
- 2. 2 ?> !
v:; 'oc 4 :n.
. ]'
\\ %,,-[s.y.glg:.k.$'.l-i.. -' fl.! 4
- - W g
a.3
y.,.
Qi
- X a
.g' t
5.0 DESIGN FEATURES
[
5.1 Sita
-The Unit 1. reactor building is located on the site at Millstone Point in P
Waterford, Connecticut. The nearest site boundary on land is 2063 feet northeast of the reactor building (1620 feet northeast of the elevated stack), which is the minimum distance to the boundary of the exclusion area as described in 10 CFR 100.3(a). No.part of the site that is closer to the reactor building-than 2063 feet shall be sold or leased except to The Connecticut Light and Power Company, Western Massachusetts Electric-Company or the Northeast Nuclear Energy Company or their corporate affiliates for use in conjunction with normal utility operations.
5.2 Reactor A.
The core shall consist of 580 fuel assemblies.
B.
The reactcr core shall contain 145 cruciform-shaped control rods.
The control material shall be hafnium and/or boron carbide powder (B C) compacted to approximately 70% of theoretical density.
4 5.3 Reactor Vessel The-reactor vessel shall be as described in Table IV 1 of the FSAR.
The applicable design codes shall be as described in Table IV-1 of the FSAR.
5.4 -Containment.
A.
' The principal design parameters and applicable design codes for the primary containment shall be as given in Table V-1 of the FSAR.
B.
The secondary containment shall be as described in Section V-3 of the FSAR and the applicable codes shall be as described in Section XII of l
the FSAR.
C.
Penetrations to the primary containment and piping passing through such penetrations shall be designed in accordance with standards set forth in Section V-2 of the FSAR.
5.5 Fuel Stgrace l
A.
The new fuel storage facility shall be such that the Keff dry is less than 0.90 and flooded is less than 0.95.
B.
The K of the spent fuel storage pool shall be less than or equal to0.6b7 This K value is satisfied if the minimum gadolinium loading in a minNbm of three fuel rods per fuel assembly lattice-type versus the initial U-235 enrichment is within the acceptable region of Figure 5-1.
Millstone Unit 1 5-1 Amendment No. #
~
^
MILLSTONE UNIT.1 3.0c
,,,r 2.75 [
l 2.50 ;
[
/
$ 12s,:
f o
E
/
u s.co EPTA BLE 00 MAlh o
ACCI 1.75
_ _0F Gd103-LOADING r
f i
L
.1.50
/
I f
1.25 L
1.00 ',
i 0.75
/ Ub ACC EPTAELE DON AIN :
/_
C'F Gd20' LOADING l
0.50 j
l 5
/
b 0.25 7
0 o%.6 '/ "'i:i 'i.i "i.i 'i.i "i.i "i.i "i.i 'i.e
- 2.,
INITIAL ENRICHMENT, WTs U-235 FIGURE 5-1 MINIMUN GAD 0LINIUM LOADING, AS Gd203, IN MINIhUM 0F THREE FUEL RODS PER ASSEMBLY LATTICE-TYPE Millstone Unit 1 5-3 w.
4
+ -*- -
m 2
m.
m m
-.m--
- ' b[
- i-
- Y
- yn, O pr
- 3. u'.r%
%. -r-). r,,t
, c -
4' 4d s (,
I '% - i -
.f.
- hh_,
~-
_m
~N'il
'h F
/
j.'
ry i
h.
(.g,..,
pp
% b N' r..
5-
%a
+
%a'.mw m fr' I*
M
^
4gW m%' i.f.g, '. 3t w*s,u, ~www -. +
w' k \\m.Qh [ z. s. p. $ '..e'w rvg\\
5
,.y y gg
,j m-
++
J Q
+
s :n 3
4:i e A
- v. s tr e: sm m
b.
e e
r-esVy r a v.m.*-4
~ -
%.k.,.y 9.,M./.ML M. y[.}5p.gi M 7,p MLUW WQj r, >mu m e& xl. ;.w.w jW,s.
~'L,-
" [~ M *
- s. l - r -c ' O a g (A.
g 1._
M.c xf
'.e, p#
M
^M, o-e$.t S
i i
x
~.
m-m%
n
%mlm;
- gw c_-~w#m
~
e
, w; n-
.w gnw w
gv a e
- + e as as
- m4 s
wm hQ,;df a,:am&;:
i WNfem.v&m h 'ih d;Wf 4
'J iG
- . Ng R
- ,.. 4 w.
Mr "
m, s
~..
sa w.
bs
- v-
?
- r : w, n
n ay; 1. a > < <# 4 -
a n
- .y
,y...-
+ > a,
- Q w un@4.wmy;~mww. ~ ~
-s, =;. w" A
n w
e w~ <
4-.
v'w.
x 2
. A
- .:r
,- M* mn.% e
, Q r U..p~M: w',, m:n w W :;imA v~
c:
V, :.
w-
".'s-'
f cs ~
,w s.,, p.
Q'-~i s :-
r e' n 2$'
1V.'
e-
=li N.pu s^ ;t m..3._@t h"
- ~ ** * ~
,5
+ s r. D
, +
e l 4;'f@-
i-G Vlw w
-W T, =
ng.
y
- .1 u.
.~
cn 4 --
i
?
_~
eer Dockst No,_f.i.Yo 50-245(
@Qg%w
~g
)
2m; &':i% M "%,',l:n,:lV,% i
- Z M
^
+-,-
o ;,*'
~
^
E
.. >. 4 7
a w
~ _ ;a..
b;ils " 4 4 CR 1~g
- sB13400 "4
e R
%w @w, n s '
m.,
1 9
4 i
- u_
g s
a+ _ #,3,
y ymy
-a v r pP' 4 i tc.gq :m y../.71Ffe
.]
s
~'m
' y-g 3._ _
Q p%,.I; t.D.A u _m aw;
- p w4 p
N_ _4 r
mW v '
i e-r n't. ~,.
M n i 4
+Y e
f
.s
+
++
4 y
+t
- q g
L n*
n gry t
~ <
s iw i+4s.
4d.
+, m ;
$p '-}p{6
~
-n 4
.n.
Y
':i
. 4 e,
s e
- 0.. -y' nn. %,.w uycm : ywy 4 - _ y:s s
' y' u
+
1 c
r ih m,p+
.n.
ac
.: w
,3 i r yJc',e w. w"d M.D ?:
n
.g ;;'
nA
+ -
p j[;
Ae g
N'Q: y=r>
4<
a ~
t
+
op
- f,
s p
t
- t
- ',
.~
r y-gt e m.g t,h~
< +
-, w 3
t n
m!
6 i.
(<a,
%;,. w,e,mh u.' k x
ax R
^
y Acy' A t hmp g'g _..'yg:,l $.-.f?'q;y
~-',.%.6 a
<e
.'.'l%l
&% ',r
,?,$f f.'g '
j 2
_a 4
i 3 (..
4
,3
~
N.
r g e.-.
.cg 3._ +
'f g.=
y
__,4' s
wh Y')N&Q W&.1 y ' 7
-Tv
...u.r 4 e, 3 %' 'w[ j..-
pg e.
9
-4 i
r h Mt.
' ~q x g, -t i C
' G, p
W
/"/m
- ^ -
i n
r "t
=,
.vyW, w_
9' u "w*'
- :u e
w;%:M Q %dn 4 -
a t
a
- \\
e.,,
W s
Yh;.a. -
-M i N.
n ~.5
.)
I
/, 6
, t_ --lQ f
- y
]M b N^h_-M
- z;:
- p..i',
m
< m, ;- a,
' ij' L 3
n:
v,:,.
s x
- ~
1
%p 1 ' s'4,EQ '
.q i. -(
ats t "t.g s, t
.m o -
- f., ;,-
y
-.4; g;=^
- -. s s-
~;;
si 2 o h.
u
- n.t v->M5 0<
- i 6, -
4 r
RO' gw J A:
- A. <
<4
=.. ? < -s m e-
- 4
= ;
jr m
o'.WW-G,.
yam /
- 4 r
ia t
<w:
ymm2 A
_v.
4 4
'.~ f
-:4 w
j.
y;,-s -. e M x g
c.ygn,mt-.
a
+
t
.3. ; +
Y j
q,
^
y p% 'd,-?v,4y', Q' 4 P
+
^
?
nn < '
'-n', a:c
,..4 5
..,g L s.
.e n.
- f,;_
W ll
'h
^.
T.
7 gQ11 3
4,.'" O '
- S i
' g-
.b b.4, m
.s
?% P~X.p% &n. y'
.w,%
.._sn i
~t t
i a
i
.J m t
- _ d (
^ ^h--
k_[ ",
-11 Y.I'2 I f,([h.,,.h,. -: 'O; f 3,.
% x,,;.
. %n$ ~sw
- 1. u d' i
_y s, -
u.,
~-
.x,,i4 W.. c,.,,
w.:-
-. +
- = --
E DAttachment t o
.m,wl f t.:=t ; -
.qd r,
nA,,..
W]. - f,.-o.v.wM 4W ' S...J.
h.:^ y
?'
..-.s wx - MM
's s'*
\\
t sU aW, '
z q
.<.s%.
'4 i
m L.r.(r
^.
- 9:
k 4
p-4 Mp';y;,..E.sI M,
3
- T Mill stine L Nuclear / Power /SiatNn? Unit-No, I l N
r f4 1
t t
7 if m
l Wg
~ if a
nc-
' ~
.c L;-
..L.
W ;f QQ,.
Wi,sE * ?_. @
EDescriptionsofr Proposed C.hanges.ito Technical-Specification' '
s
.x.n w
. c
-v c
p u p. p@q j
W.:1 g
{
a-q m
r l m
-y,..-
g y
,, ; \\N s n, TW.-
w w,_ w"(4ww
. +
m g
4 o
w @ [-
Y',
0.9
[u1 m._
1
-s y<
m;.p-w--
1 m
mz
)
h,. A',
N 4
=s
$,..C f v,y *,-4 -4if',Qs 1
i.
a s-L t-1 G.'.. '; ( ' Iji 1
s.
3'
-5 ;
.+e 5 -
-3
. g _,y m
s,
3 s --
y.,1
,~
a.. 9y 3,.
3 g ;g
%..s.y g
uqqs
.~ 3 s > bh:..,
"
p, a$o~
t c
-x, m
a o m, n
a,,v%g.-~:
.-- j n.:
,,=
ii
.p:, a c
1
\\
3
%p:u m~~. 4 ow.,n
?
-f m
=
g.1 "
tl 6 y-g.v u
pf>
f c,.
U
- ? ?
'E g r'3[
t
.3
[
'6' Q,_. MA,,,4M g ' $ ((g
. F
'_i ~ M..l h
2
s t
=
,fW W.
s.n a h
Op%'
.{
- _ N _, p r
l
, a:.. M v
,o ya., s -. ax-
-yn e
u
- 1
.M j
3
--H I
Q.n' w h:
w,n f.( 1_v 44_
i 9
, J w
i
- he g. %~
~
s 7.~-
y n
1 g
November 1989 A
w f.
p'8. !sv:#-4 p. -, ___
j 4 ' '(_A y. t
..a.
s-7 '
g mR 1
i n#
M.y:."y' _4[ = e-l w&iL; ' c 4
,.,(
i '.'\\I
- '{_
s,_
- 3 op;
~1 ik i -.
s5 ;
u,,j g
.]..
P!M kpW -
." fu.
yf,
~~
%q y
.q;
+g-9y p.
L
- g hW,
.U;S. Nuclear Regulatory Commission--
(B13400/ Attachment-2/Page 1 November 21,: 1989.-
e_
m k
Millstone Nuclear. Power Station, Unit No. 1 Description of Proposed Chanaes to Technical Specifications f
i A'.
' Description'of Chanae--
[h
~
1.
-Section 5.5 B. Fuel Storaae p
[
This section has been revised to~ state that the K of the spent F
fuel storage pool shall be less than or equal to 0.fdfif the minimum
. gadolinium loading in a minimum of three fuel rods per fuel assembly e
lattice-type versus the initial U-235 -enrichment is within the 4
4 acceptable 1 region of. Figure 5-1.
i 2.-
Fiaure 5-1. Minimum Gadolinium Loadina.
Thi.s new figure has been: added to Section 5.0 to designate the acceptable gadolinium loadings per fuel type as referenced by' revised Section-5.5.B.
[>
.B.
Evaluation of Chance lThe : proposed change described above provides an additional control.in-determining the acceptability.of fuel-storage based on gadolinium loading and fuel enrichmeat.
~All of the bundles t.urrently stored in the Millstone Unit ~ No'.1 - spent fuel pool and in the reactor vessel meet. the proposed new Technical Specification figure by a substantial _ margin. All other aspects of fuel storage (e.g., rack design, seismic considerations,
. heavy loads, thermal loading, etc.) have been previously addressed ~ in our i
~ June'24,.1988 (Reference 1), submittal' and the subsequent additional j
information submittals.
This proposed change.is fully consistent with those previously submitted.
Criticality in the spent fuel pool will be precluded as long as. enrich-g'
' ment and gadolinium loadings meet the requirements of the new proposed figure.
Thus, no negative impact can be expected on the consequences of any postulated accident.
This change will not affect any safety systems j
and no increase in the probability of a criticality event can be postu-lated.
-In addition, this change will not modify plant response for any i
event to the point where it could be considered a new accident, no new failure modes are associated with this change, and no increase in the i
probability of any accident exists.
i NNECO has reviewed the proposed change in accordance with 10CFR50.92 and has determined that this change does not involve a significant hazards consideration in that the change would not:
i 1.
Involve a significant increase in the probability or consequences of an accident previously analyzed.
J
N4
- f.,
(
U.S. Nuclear Regulatory Commission
~B13400/ Attachment 2/Page 2 November 21, 1989 There are no design basis accidents - adversely affected due to this proposed change.
The new proposed figure is fully consistent with the-analyses previously provided.to the NRC Staff supporting _the Millstone Unit No. I spent fuel pool reracking submitted June 24, 1988 (Refer-ence 1).
Criticality in the fuel pool will be precluded as long as enrichment and gadolinium loadings meet the requirements of the proposed figure.
Thus, there is no increase in-the probability of a criticality event.
In addition, since criticality is precluded, consequences are also not adversely affected.
2.
Create the possibility of a new or different kind of accident from any previously analyzed.
Since there are no changes in the way the plant is operated, the poten-tial for an unanalyzed accident is not created.
No new failure modes are introduced.
Bundle and storage rack design is such that there is no chance for a criticality event in the Millstone Unit No. I spent fuel pool.- This change also ensures that all future bundles meet the crite-rion that precludes criticality.
Thus, there is no increase in the probability of a new or different kind of. accident.
3.
Involve a significant reduction in a margin of safety.
Since the proposed change does not affect the consequences of any acci-dent previously analyzed, there is no reduction in a margin of safety.
The proposed change is fully consistent with the analyses previously provided to the NRC _ Staff in Reference 1 regarding fuel bundle reactiv-
-i ty. Thus, preventing criticality in the Millstone Unit No. I spent fuel pool is maintained with no loss of margin.
1