ML20024B527
| ML20024B527 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/04/1979 |
| From: | Labelle D BABCOCK & WILCOX CO. |
| To: | Taylor J BABCOCK & WILCOX CO. |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-07, TASK-2.B.1, TASK-2.B.2, TASK-2.B.3, TASK-2.B.4, TASK-2.B.5, TASK-7, TASK-GB, TASK-TM GPU-0292, GPU-292, NUDOCS 8307090083 | |
| Download: ML20024B527 (49) | |
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The ability of,5&W NSSS to safely shutdown following as accident
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.yy-,4,
..g p 3-;.g.g.m,w g w.x.,m
..,- -.,.:. w..
.c
~
.LT 5mk f_
'l i ;.
l a
r-
=
.v a
~... ~
j ';
e
- t
[Gp
'9l'
}:
I propez actuation of the AW occurs.
f
{
L.
. p
-The objective of the parametric study of delayed AN con-w, Wi'
'ditions is to demonstrate the amount of time existing before
..s (1) PCRV actuation. (2) pressurizer fill time, or (3) onset of two-
.W n
phase conditions. The reactor trip coincEd'ent with loss of main Gues8t' Pf,,
.;, s
. feedvater and/or turbina trip is included to determine the amount
$f"'
of time to actuate auxiliary feedvater prior to challenge of the FOR7 h.
[{$f C -*
or filling the pressurizer obtainable by advancing the reactor trip
.-h
,7
- w...e time.
%I?.;:
~
'~
l 3 2.2 Sumuza'ry and Conclusions P?
g%.r <
g ;.[
The ability of the analytical model and CADDS computer code ' -
N;i :
<ssed in this study to predict the primary systen response for such
'Q;'T n.g;. i N':
o
~.
. actions as loss of main feedvater, turbine trip, steam and two-phase 1
e.7 -
f;h','
.. release out of the PCRV valve and anittag feedvater actuation has
..i S
L:
'"been demonstrated through a benchmark to data measured during the },>,... ' p. ' rh.;,
=.
. '. =
,, ~.
- m.
' ~..
i SMI-2 accident of March 23. 1979. The CADDS code limitation of not-W EGC.'
n saturation properties has limited this analysis to the initizi. s N/s}
4 hm t:*.e -
i
'I
~ phases of the transient (4-10 minutes). Emy parameters of (a) total r.,'.),..
power. (b) systee and pressurizar pressure. (c) core inlet / outlet ft..e.
,'*c we.
and I
'T.P 4;
.tamperature. (d) pressurizer level are gives in section 3.2.3.3 compared..
4
%;L.
3 L
.s
[
-g
'to the 3M1-2 data.
,..,,_f,,__..,
N:C.
Jo reduce the In.gae.n* g ++ ekane.Q the PORY valve.; ;.
g;
?m.,
.a change in high RC pressure trip setpoint from.2335 psig to 2300.741g..
g M a change in P017 open pressure setpolat froe 2250 psig to 2456 (ga
. v.,
M=tf m is
,, y; peig is recommended.. The an=1ysis supporcing this s ;
w.
siven in Section 3.2.4,1.
Ancicipated high pressure transients of h
ly[,,
,.. =.--
ICW and turbine trip a.u44 e6aktm 4 the PCRV with these f-
}g, r
Furthermore, the changes in setpoints for operating 177 FA plants.
g
-:. s.
g;,,
w
'*Q" Pj y a,*
'N.
fY
~, f
- e
,., ' n.<.'. m q,, ;u,.&
. ~,.. ;.;
- T~~,'*.
~,, *,,".
- Y'l y
.. l M Y
f '~
~.s
~~;
4..
T-
?):.
,,. e.:
,e.-
54 n
m_
... s
- \\. _:' ' ' ' '
,,f.'.. ***,'"'",I'
[
- q M.. ; V
~
,,Q e
M h,[
i r
l.
changa in these setpoints does not increase the frequency of shall,enge to lif ting of the safety valves for anticipated tran-T.
A e.
u.3 aiants even under ySAR assumptions.
'gg 2.
na parametric study on Am delay t's initiation indicates M27 that on a LOW event, there us.3 minutes before the.POR7 setpoint
$5. ;
~
of 2450 psig is reached and 10 ninutes before the pressurizer tills, g.r P..
p's.
.9 ne equivalent ATU delay case for an anticipatory trip at tina zero v
E: ~
seconds longer to reach F017 setpoint and 3 minutes p ;. -
indicates. (.o,
L'. Y W
longer before the pressurizer fills than tripping on high RC pressure.
W....
E....f..(
~
[
- y 3.2.3' Analytical Bases ry. -
l Se n t.:
..i 3.2.3.1 CADDS Computer Code Description l7 tv.
The CADDS' digital conputer code (EAW-10098-P) is used g"L:
- W.
to analyze reactor transients in a heterogeneous pressurized p
Edh -
.t It solves the time-dependent neutron kinetics E.._.,
+
wM-water reactor.
,e 1
J.
+
6
~
equations in conjunction virh a t ermat-hydraulic so'lution for h
NAN The simula-sa a.rerage fuel pin during r. yeactivity transient.
Wd-M.;
c.ica includes the major reactivity feedback mechanians as well ip.%
iW' as detailed single-phase nucleate beiling, transition and stable k@x T
film boiling core heat transfer =Ma.
The reactor coolant p'..;. -
,{..
system including the pr 2ssurizer is simulated. The preesurizer.
p
- gg. '.
.is a non-equilibrium model allaving, heat tranaf er to the pressu-TIf.
rizer valls, heat transfer across the steam-liquid intF**ce.
kw
. condensation, and evaporatica.
'.?
1 Yar transient control, the pressurizer model has pro-7 Pr in pasmsble options for relief valves, heaters, and spray operation.
- k...
n.
The code permits the pressurizar to fill completely with liquid, f.r.
with liquid flow through the relief welves.
I.T,.
f*
Tr
- 8'" Me
( p a
8
-e t'
e 4,9
.,:.,.,.~...... -
S. _ti.hiziQ. isQ'
~-
n*
g..
- p(~-
8,.
~
- E... ~~
~
e
2.
~
~~
s.
. w.- : s...u.-c
- ..u....
- L.w _-, e -
s
,t M. !,7 r
i
.n F
s [
'*Ihe code is presently 14=" J to a single loop t
M,.5.
h g
i
?-v- *%y:
. simulation. System effects are valta for subcooled operation I
y.'
only since the code vill not execute beyond two-phase satura-t
...k L.
- t. ion conditions in the coolant loop-The code also does not 8
.gg L. -
l L.
.w
- c. t directly allow for changes in coolant makaup s.4 letdown.
I J.
To
- - +.:
simulatt high pressure injection or normal system makeup, it g.f 3-is necessary to alter the pressuriser spray input to obtain b.,.....
- 9 g
moltane change effects and alter syssam cooling response via L' ~....
r V-the heat transfer of the steam genera. tors.
e
..e:: :N J
.?
"f.'.c.h'.J..
1 3.2.3.2 Initial Conditiona L.
N i. -
The base case for the CADDS analysis is model/ed for.
{;,-
J:- '
j r
{f '
a 2772 Mut.177 yA plant such as 'DG-2.
h reactivity feed-h' back coefficients used are representative of approximately 100 g
g.
, ;?
y(W.1 ErPD operation. A core nuclec (RC system) pressure of.2185..
..,i
~
s?,... -
r, ysig (2200 psia) was assumed, which corresponda to a hot let
,g.
c n:. :.
..I
-tip measured value of 2155 psia. h core inlet temperature is -
Cf.,.g;.
?
~
'. j m,
f.-.
1 357* at 100 power and Taverke t's S E2* F. -
s c.s -
1 c:.
gg.
2a. ~.a 44 3cm.m<-..
cho.a.
. n,.....
w J
s,,Eey input para-N,4..s to mod.el the IMI-2 measured system ansponse
.e V
analysegare provided in Table g..
9t.wst e.
d
. matars applicable i:o tk3 n
v,t.
'W..
a
..3.2,1.
m..
g**
=Y
- 9.. =.
2
- w..
p.
s r,..
~
V.
1
~
c 4
V::..
s-1.e{
f;;
F
. -. =....
s'.,;.',
- m. - c n
t..
W.
n
- g-p,..
p..
L
..,, sy-
~-W
- C', f f.. _.
..,=.,. ~r.:.1se.+c..,
. a.,.
_m s
4 N
f.*
a
\\l
= *
. ;;w s.
s.
t' h " __., w ' k u.u.
a'(
?
?-
p.4 SCQ(
I s.
Zahls 3.2 1 Y,.dl 1
1 3
EZY INFITI PARAMEIIRS FOR L
.W
.TA nt ANALYSIS,
..h v
.I
.g*
YAIRE 1
yARAMETER
,o.
-Ggarauc.STwo f "T"MT.-7.
y-4
'l Resetor Coolant Systemt
-,gy 2772 (100% TP)
GB8 (.*l*7N N1 f
Reactor power' MWe 2185 (core outlet) 7@
Systaa Pressure, psia RCS Coolant Flov I design TInw
.104.0 j
f'I q
teactor Temperature, y g:
. 357 Inlet f.;
'.- 542 607 W.
Aversse
^
..I,owered Imop U. *
[h.),'.
Outlet I
Coafiguration
? s.
j f
M-N j
C. -
Pressurizert
- -a.
220 g,.
Operating p el, in.
a lg-Yolume, it
- ;... - gff l
1 108 3
sesam w%
800
- e 12155 Water
.l
'j.
Operating Pressure, pois f!f Code Safsty valves
. e., ff _.y....,*,
,,g..,,.
E_
-.j f
2 - r..
. j ~ 4 e.1,' p Maeber 2
- 3,34
' 3~
, ;,.,s.
pp ylow Area in 2
Yalve Capacity. Ib/a-fL qv i
74T'y
.. u.,
. a
~. -
41
. rj y
e.<.
p%
. + ~.
i.
~.,
Stes's
}.
^ -Setpoints, psig m
,2300 Q,<
.j opea
-2460
- close e
ih y
.;rory
- .*1
- 1
.gamber c1.05 -
Flow Area, in2 c
,t J
2 g.
s Yalve Capacity. Ib/s-f t
....,j.: '
4:
.4.,' sy.
Ltquit
~
steam k,
36 Set ts, paig
,,.2,T's
- i W29 13
. zvoo f.J 1
3
.c1.
l A
r teactivity Feedbackt t
1 4
-s
-L 36x10
., 4 g-
' Doppler coefficient. Ak/k/r
. -l.05x10-4
-o.LS m 1
3soderator coefficient. Ak/k/r k.
j
~
f
.temeter Protections r.
l UN
[
-2300 seRigt RC Pressure Trip Setpeint, pais 1
0.4 g
Righ RC Fressure Trip Delay, sac e
[;
5 eAs mesoured at hot les tap k
j
{
n m m. g w.. z.
1
,,.w_ m. m
- w. _m. _y r r
--..- - =,.; ;<.,.;..._;.m,. r.gn.* am.._;.r,rr,,f. g.,,yn,~y,., ~.%; h w.'.y 7 ;
~
.,3..-
~.
y=
. ~;
.y*
..=.
,h-
- ^
s',
M Y
.D L
=..
- - - ~. -
- ~. -
- m.,
=-
...s.
.. 4:
.:. 4.%
.. :.:$~ y ;:_.g. g.;.x.c, w(
s-
~
- - '. t g,_~
^
[{51 h ilrdt $
~
TMI-2 Benchnark
-%.3,- h.
"V 3.2.3.3 The CADDS computer code was used to model the ini-
' ',=3 h Y.
?.T-u.t Since CADSS cannot
. g.
/
c tial phases of the TMI-2 LOIV accident.
r coolant 3
compute beyond two-phase conditionsfin the reacto ient is bench-system only the first six minuter of the trans g[.y*f..~.'i.-
Initial conditions for this study were as shown in N."...5.
marked.
d d to its gf. - --
Section 3.2.3.2 except that reactor power vsa re uce f4$jf.-
Reactivity level at the time of the I:iI-2 accidenc of 97% FP.
pwq.. r
,7' y{
the burnup.'
~.ft.
- feedback coefficients have been used which approximate d[:"L 2
'T f
A reactor trip setpoint for high RC pressure oc.w["
$'[.
.ef the THI-2 core.
i e....
ef 2.194 psig, and P017 setp61nt of 2355 ps g m..
b.2 9 -
...~c
~ ~ ~ ~ '
a r..
were assumed.-
s
.S:
s
?,n=. s..1...
for The comparison of CADDS to IMI-2 systca response s...
r h.gl S
- ~ ~.-~ _
ture is
." IC system pressure., pressuriser level, and hot leg tempera p.&.
.e.
~.
@* :r 7; t
ctively. A cor-
.e A
- ~~
3.2-3. 3.2-4. and 3.2-3. respe Mc c:.
N.$ m.
ebowa in Figures in Table 3.2-2.
The D'..-
-responding sequence of major,eventsis showaboth m
h,. ?
-enalysis shows good agreement, ll as predicting the magnitude *.. p,i
~j-g :
ted tre.nds in the variables, as we
.-M the changes.
This carve-was derived through
{h..
h Tha OTSC heat demand curve used for th
' % k is shown in Figure 3.2-6.
his a h p in system response
~
. ;.K'-
g;f.'
x isa iterative process until a r==,== tin e ramp dovu as the inve ep g%'; '
It is a nearly ft.-
vsa obtained.
d ta-couaistent with the w..
boils off in the steam generatnes an The haat demand was add
'p:k-f K:-
expected CTSG dry out time of 4 ufm.:
lats the BFI 7 programmed frca 2-3 minutus et 3% to s mu
. (m.
i J
low.
e + r= =1 1 EFI actuation was ensumed at 2 minutes on
~
c~-
i*"""~ * ~ m oling effect.
HFI voltsse addh to the RCS was a e/c
(( -
6'..
h the pressurizer spray optio'a-g-
'... Ice RC pressure.
W.
h
directly to the pressurizer t roug
,'f";
4
... ~
- v.
r U~
. ~- > Qr.!. -
p p, gg.
. w. ;-; asa..+..=:.
).
,7,7 m ~ m
... a'.
~
s
~
gr.
f.
MA..-~
'%m,__
- _...-.~.,.
-..-....~,-.a w.-...
?
'n
~;.; L.
- J
...a a-
.. '2C" s
_'.,' a. '
- Q. J.* '.r. J _; b., n~;.-~.:. ;;.-
.: _.. c l
I.\\
n..
'rC.l I : M
}
I.
.e M f (Ihis model had zero beat renoval progranned
$ :...- i of the code.
M.>c.* t for ths stama volume, so that no quenching took place.)
f..e*
= = '.
===:- --
As e
EFI, flow was based on TSAI head capacity curve.
\\
k
.sbovn in figure 3.2-3, RC system pressure from CADDS pea s
, Bovever, this gy
~~
~
slightly higher.
p As ressonable agreement considering potential analytical uncer-g
~...
u7.-
- ffect, tainties in assumption of reactor trip pressure POR7 etAcos t.a a peJ14fasa mahLm ATw.t J.h W,,
75:
ris With and the exact delay until control rod trip notion begins.4 M.
par'-J ~
i the g
~
a stu,ck open relief valve and systen pressure decreas ngs
[d4
-~r.
u.
l 7
the aane turn-around pressurizer level, rigure 3.2-4, exhibits
~
',.L...
[Jy/- 1
, ~.
The EPI was actuated at 2 minutes, e.E.
.1 at 50 secs as did 2(I-2.
M The CADDS allowed to run until 5 minutes, and then terrinated.
p: ~.,.
~..
I2 p'.
elaulation eahibited the same slaving of fill ' rate as dfA 21 -
a:.
)
F."$ '
The hot les tienperature, Figure 3.2-5,
$y..
v
^
wyon termination of HPI.
G..,' '
.\\
It exhtntt's, firsc tha".r...".'
j
).s p..
. Im within 5-107 of the rfI-2 data.
ql '.
m t 5 minutes, that is. '.
r p..
. leveling off at 1 minutes and then speurn a
~
a:..
f the EPI '
it '.
shown in the M-2 data, showing the cooling effects o
- s!
1 y..
. T*r :'
The CADDS analysis vent into saturation shortly after- *
- S, action.
a
-+*t an RC system pressure G-
.EFI termination since 15 was
'=h" g,.
i 9.,'
2ower than 2:1-2. (Pressures predM J by CADDS during the HP l
b[;i,,
- ?
l flow period could justifiably have been increased by 30-50 pa drop of the added EPI vster,
(~.
. to account for the surge line pressura,
- e into the g
since-tha CADDS spray option injects the water directly c
It is estimated thatT!I-2 reached asturation
{
M er.)
I;
. condition at about 6 minutes into the transient.
k.
3 l
?
fr W.
L'
~
ET.:
K,..
y 5"* ;
F' 1
L'.
gW E
O M his F. *- W ~ '
N. N. W,8"'*"$ [. @l'~~ W ' 7.h*I gy;f4Q%q 7.,."
q' ',
I.y..EdM'"pMw#
-=.rc.w-.y rc r.F. -'*y. ?. s &. % P 9.f.@
.., y g.g.
' ~-,
g.
.g n
^ ^ '
8
[
I..-{..
..g, 3
a e..
~
y.
- - ;.,.~ y.
s...
. g, -.,,..,..,,......-n. ::. ~ r....?~ a. %..
7:
=
i1. 5 6 1-2
' s
\\1 P p?
&. i
.gg.m
~-
Table 3.2-2 g 2 SEQUCICY. OF E7DrIS PREhkTTW #~
s
..-~.,
ce 4
- - gi, ;
EVDIT 5.
~
_La *-
TIME. SEC.
- m.. _. >
.s
~, c
.. =H, n..
a pi..
l N
W 0
' e.s...
3 FCET Opens (2255 Psig Psigf E,
7
~
?
Righ RC Pressure reactor trip (
10.2 p
'yealr. RCS pressure D':.
3 pogy closure satPoint reacheJ (Port remains fully CPS 2) ,
12 E,. *
- q E 25 p-Minimum Pressurizer level 50' s
9-c3 pressure (1640 pois)
~-
5 M I *eguaged; 105 1000 gpm/90.F E l at full f W e 120 Yw,..
~
n.
".... -.... ~
P.
gz..j-l.
f
,.,. l: ;,..j -
.-(.;[,g;..
.I'28 F300 m a e d.,,,;,,,;1*,'h.,.?{;...**.,.*-',',*.,.*'..**..;..'.....,'
3..,.
~
w;-
s.
.n
- !.ca * **
- ~
.,,, f.,.*;.. '... -
c.
C
. 6. y c.,
,; _. g...,
y.-..-
', j.
.:.,./
at.
g-.-a,
s.
a e..
gr;..
/.
"h RCS reaches saruration
, ;c - -.
~
p 4 -
~
J.;; -
4 Pgo,.
W AT Wst" t M
.e '
5.s..
r 6r
~.
- +y.
.v...
~
~.
y;..
.s s..
s....
av..
(-
p.
..c.;..
- e..
u ! i, -
.;m e.
- ,: 2 a-
.y
..,.f. -:
L.);
y
.n ra r
p -.
p,
....cs.
ri -
9e1.
lP4
'v, O m
.g g*:e-s P
l g.
w 3c
}
W-i t
.k pg b
% ~ ;. ; I e-'
M.JL n. a.*J.f. th.!*.W"M I
- - wx..p WW.1 :h p'*#g ej%X.
- = =
w.
r
--y
,--.-..-< v - y W pT.".W/.yj,. -C$3.'f'h
~
4' s: %r.1 qw::..- -
4_.
,sg
.> is-t, @,.
s.
p..-
-m j
r
,p
- 3. w..
t
.L i:
..;.s-m ;
.w
. i.,
m:.+.w.:
s
_.... =.
... w.
g.,
m.
N-n
..r.
t t
s we n i
.. s
- y
..2
'. d.z
. k..
.s*
'**-l.'" L----
h,..i Y
- ..g Y;tt -
- n. k\\.1 S
l.e"y i
.: 2
. \\.
>e,
<y w.
. \\.
.. m.
~:..
- .. s ~ -- v.
.s..
\\.
.g a!
E-
.a
..n
- ~..
e s
.s c ::..
- ^
~.
.ne-
+
- r. ~.
s
.~
g q...
.n....
u.
s.
.c
\\...
. a.
.\\.
n m
_1 E..
t ~..
. r t...,n...
'7' -
e.
l
. p g..
e.4.....
...s.
.z...,
.....g.
f.:s...
F
- rs 8_......
y f
.R-
- e...
.1 a
~w--
... e. i.
r
. m.
- e. - ;,*.
s x.
. n,.,.
. M.,..
...,.....~..
w...
.... c - m.
~.
....t.
_1=
- u....
..... +. ~.
....-T.,,,....
w m
.. e.
r.
...: ?..
. i..:..........
n
. a+
w
- .v........
..l..
... :.a..
.. c.. ~........
s.
~
.g s.
. o.
../
R.
+ '.
\\
i
.o
?,,.
o
- a..
L.
n,e
=
m.
..a
,a.
1.
m
- m..
.. s.,.
n..
2-u.
/
g g;)
k.
ct:.
8
.. se
'm
. -- =,.
a..
- 5..z
- n..
4 8
!.a 8
8 y.,.
2.
w g
g g
=
q r
~
4 V.:
g n
g*J3d f.
.. m.t.sas Z(e p
j 1 3.0tX3 r
K' i
r.
]
_.. Figure 3 2-3 i.
. c.
.;-y " Y
-.c.
- '*:'s.*
= - - -
.... ' D.: < a.y'
-#kT.44:NI8 #T
.. -- n v'*"C'."M,W ". * *.9. f'.,. w r
,n-
._.w
.d
- .,.-.T..;.w* ';.r'
- ,'V;. d. =%.'"?
t*,
? ;.. W..
E*-.
%..*--*,,e ) w.a,a
.2.h... e'
..,-s.
\\
4*
- t g.,.:.f.,....,.
.. ?=.".. a 2.&..c,.:n..<.g. r. -
s,
_. as6 h.s... p..
s.
g.:..
t, n
h dI
& a.
,,..f,..,,
.1 ;...
- N..... ce:.
.J:,
p' f
o.
_m W
. J,, *
- ,.gg '
s
,y,.
?.. -
- s T
- 4,,
- h.,.
h.t. '. *.
.r,...
.e
)
e m I.
. t' m*
y...
Y
.== s
. 8.o..
a.
s.. sea.... m *=s
~.
,.."E P
,e
~-.,,..
e.
e
- s.
'e
.,s.
B
.t
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3.2.3.4 coacInsions The ability the CADDS cela to predict operating W }I
.. i.
.]
plant system response within the limitations of its prograssed w.
'N capabilities is demonstrated by the successful benchmark of the 'DG-2 ac,cident in section 3.2.3.3 using the OTSC heat demand F.
.I p'
A i i model of figure 3.2-4.
khis heat demand is used in the subsequent 5,...
suadies of the PORY and reactor high pressure trip setpoints and
- o-
,l
- g. r.
y Unless specified, all Minput parameters for sub-r ATU delay.
sr.4 sovemc.sn.W p.
, sequent sections of analysis will s.-ain as listed,in Table 3.2-1.
Q.;.
-)
94:.:
p%p. *
'5 3.2.4 Accident Analysis 3.2.4.1 PORT and High Fr. assure Tr$p Satpoint Study p;.l %
ks1"_
s A sensitivity study was pasformed to identify combina-tions of initial RCs operating presumre, high pressure trip set.
f.
~
.. UI
.Y point and 70EF setpoint which v1112msalt in reduced probability k m.:,.
kr?[~
Q9 of PORY scruation following anticiW ' transients which have k.,...
IUif
.,J
<m: curred or have a significant probaktlity.of occurring in B&V.
M.. a~-
~
v: -
The anticipated transies.esas concern ares g,
ytants.
p.2 1
I Q) loss of aternal elecesical load g;
re;p
. C) turbine trip
. r -
.j
, t.A Q) loer; of main feedwater y(y~
.-l.
(4) 3mes of condenser vacums.
f m
~
g$$$'
inadvertent closure e[= min steam isolation p.g.
-.0) o 1'
Salves otsiv).
w.-
g-7
.,Zhs loss of external electricallam4. loss of condenaar vacuan, j&
,j y>, '
.ersi inadvertent closure of the 2tSIT'5sall give secondary pressure c.
j
[.'
increases' equivalent to, or less asure than, a turbine trip.
~-
?'.
Therefora, turbine trip and lose of main feedvater bound these f.
o
[
e4,4p.t. 1 tr.asients.
- r..
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c
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.R }g y
e pat Anticipated transients which have not occurred at 3&W plants (low probability events) are:
I 4 /f
~
Q) low worth rod group withdrawals
'...--.3
,3 (2) moderator dilution accident.
i E3.
'Zhe moderator dilution accide.nt ca[ result in a high pressure trip.
l j
M" but ySAR analyses show that peak pressures are well bounded by C:..
~
gr loss of main feedvater transients. Some rod group withdrawals Wr-ej
{' -f.,
'1 can be shown to conservatively result in peak pressures exceeding
.,]
p.
th,e pressurizar safety valve setpoisk of 2500 psig. However, g.
J. -".
e%
these* events have a very low probability of occurrence which.
- e. w.i
- e...
- J ansvres that the recozzsended setpoint changes are effective for -:
g.a;.
\\
t MW 8
truly anticipated transients and these events can be excluded M.'.e q.
..e : -
The objective of reducing the fre
?v?".
fe,e further consideration.
1
'.guancy of PORV actuation can be reached by raising the PORY h/..,
V..
.i,j
'j.,
the RCS nominal eyerating pressure, lowering-
'L..
p -c.
~3 ',
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. m!s]
hp y
- setpoint,
- :i..
M l
.,1, ;
the high pressure trip setpoint, or through a combination of w:,.
i Y*=
Since these three adjustments ars' not all. 0 p(.,'r 9
these three adjustments.
).
~
~
b egually desirable, an extensive paramarric study was performed '.
2 blL to allow for a setpoint selectima utdah voeld be the most desirable.
6.:/
t:,.
c f/c s
- ~"
. fras every standpoint.
N y
Tor each of the two events' analyzed (turbine trip amt R.
U,....
1
- pi..
floss of feedwater) peak ECS pressmen following the event was
{Jn l
N ebtained as a function of high premmers trip setpoint for-three y&
{.e, l
l;
- 2his setpoints, namely 2255 psig 2305 psig, and 2355 psig.
h wetric study was performed far three different initial opera-.
J
/
u.?
-ting pressure values. 2155 pais. 22n5 pais and 205.i psig.
yar g'
Q(b each initial pressure assumed, a carree-Aiai average tempeza - -
1 1
Xer 1
gure was selected which would - '-+ *- the initial -
o
[.
f.
c.
P.
i
- ~
s
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d
. mm margin at the value for which the plant was. license.
All analyses were performed assuming no PORY actuation.
-g
-.1
..M 3ha parametric study described above was performed twice.
.. U E-
<sce utilizing a realistic model, than utilizing the FSAE
', h1
- model. The differences between the two models utilized are listed in
' Table 3.*1-3.
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mm. =rW.pc4 3O,., * -;** F.;,-m :r r..w 7.k.. y%.. ;~;tdTLC. x7.p.j v T@*..,, c.
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E.7
,3 g
DITTERENCES LETWEEN REALISTIC MODE,L '
l u.
AND CONSERVATIVE MODEL '
W*
~
p.n... ;
s.
c.r r:....
es.p.,,
CONSERVATTVE MODEL REALISTIC MODEL 5:..
?ARAMETER-s
- r...
p%';::
s g ~.
r y..
f 4
g *~ w s
4
-1.0$x10
+0.9x10 Moderator Temperature.
M. m.
Coefficient. Ak/k/F
-3 "4 ".
~5
-1.56x10 y
-1.22x10 Doppler Coefficient.
E.;r.
c.
Ak/k/F.
N
- h..r:c.
Pressurizer Sprays Off Off
- CPM 3 k
M,
. ~
'JFressurizer Heaters
- - 0.*4s
[-
g fff"f,.
.s-Eigh RC Pres'sure Reactor ' Trip O.65a '.,q
~
.~
g!.',
(?..J
~~*;' *.
Instrumentation Dela7 Time, a g.-
g,;
0.0 30.0 Eigh RC Pressure Reactor Trip
- M,i se.tpoint Instrumentation Error, psi W
=
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-g-1 4
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,j through 3.2-10.
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~.aw - L*- u., lp{f o }Mt h l-: F '6i 3.2.4.2 Parametric study for AN Delay - ~ l U br - 'e One important factor in the TNI-2 incident was the
- t 8 minute dalay la initiation of a=11tary feedvater flow to
---I the steam generators. Using the assumptions given in Section a 3.2.3.2, an analysis for LON transient' was performed with the 3y.: - if[ realistic model, assuming proper operation of the FORY and re-r f.e n ..a vised setpoints for high RC pressure trip (2300 psig) and T..', ' y.. 70ET setpoint (2450 psis). The resmits for a normal initiation g time of 45 sec as wek.1 as delayed fattiation times of 120 see h vi;.- [T, (2 min.) and no initiation are gives in Figures 3.2-11 through [. ? 3.2-16 Table 3.2-3 shows the sequence of key events for the M -1 r ,c: ;C Fi different A W initiation times. h.6 l The pressurizer level. Figure 3.2-14. shows'that for N.. ..a C..f;; - no auxiliary feedvater, the pressurizer fill (define fill as (N,.),, g J .v. ..J maximum instrument range of 400 inches) eine is 10 minutes.' ' WWi- .p (j., This analysis assumes the PORV operates normally. In the Lf 1 . eta p:. c.. 'ntI-2 incident, with a stuck opeu POEY and HP1 flow for 3 minutes, v r. >:F the fill time was 6 minutes; therefore, the margin gained is Fr., G about 4 minutes. tip,. - .} Q *. W,.' h heat demand curves used to simulate the 147W L. Y,.. I l -j .ssith different AW initiation times is shown in Figure 3.2-16. " h,.. l
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-k Event Time. Sec ~ g $5.^'.^ 40 Sec 120 Sec Delay I .No AM Event. AF-J &..#...,y.
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L:s of an anticipatory trip versus the high RC pressure trip that El ?. I normally occurs on a I.OW transient.- An anticipatory trip j 'l L is defined as a trip on a secondary system parameter that would W t cr sense a loss of feedvater or lov inventory in the steam genera- "y [... tar before the primary side variables sensed the change. For J N.r r j the anticipatory ' trip studies, the LON and reactor trip were 2-. V. *7-both initiated at time zero. (A 0.4 see RPS delay, plus a C.5 - fa:_ second CRDM motion delay are used, which are the same delays h 6'i ' associated with the high pressure trip.) A turbine trip on , 44 $~ lose of feedvater is also assumed. Y. _D'- The heat demand used in this study models the effect [g. -~ 1
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s'~" of a ' secondary system pressure setpoint of 1025 psig following 3 >.". %x.- turbine trip. Because of the inmediata reduction in core power ~ p...h; - a*. with the reactor trip at time zero, the steam generator inventory. F.' q is reduced at a slower rate than would be found for a delayed $) f.b - . reactor trip (i.e., trip on high pressure. 3.2.4.2). The heat g-j .-kg demand profile shown on Figure 3.2-17 was derived from a CADDS $d stesa generator model calculation usig, the same secondary pres-Ij,i; y eures and feedvater flows that were used in modeling the 'DiI-2 {y@ i s - LOFW event, and a reactor trip at time sero. g'. I! C P'-*. m cases were evaluated - cae assumin's proper Auxiliary ,+ e' h:,. The Feedvater (AW) initiation, a second, assuming no AW. W. n~.. eystem response is as shown in Figures 3.2-17 to 3.2-22.. g {l
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q; s ha,C.1 i.M i.'t i into the event. A W level control, with secondary pressures Mh 1 : M.pg set at 1025 psig, maintains this condition. Pressurizer level (.n, - -m - id, is shown to drop to about 10 feet in two minutes, then gradually reduce to about 8.5 feet in 10 minutes. However, the effect of .I gg normal makeup has not been modeled; realistically, pressucizer qW-W P'h level vould increase throughout the event, at about 10 inches M '.t.. 4...- per minute (one makeup punp). 2'L.;.',. h f4 4 RCS pressure drops initially to 1950 psia, then rises , :~ <iue to the effect of the pressurizer heaters. Under the condi.. z, Lt.:.*,',. '. tion modeled, the PORV vi.ll not open, nor vill the pressurizer b'.% MM. D,.'E: fill or empty. D* A similar case, but with no Am, was also evaluated. 4a,. p~.. A' Under these circunstances, the stem generator is shown to .?.!.. f.f ~. ',.-f ..,,., boil dry at about.100 sec., RCS temperatures level out by 50 ~ 9 y,*3;; ~ seconds, then begin to increase at 100 seconds. RCS pressure f:M w;. g,.. E'-C "... 4rops to 1900 psia at 50 seconds, then increases to the FORY vr. 1* [.- setpoint (2450 psis) at about 4 minutes; the PORV then cycles v.x; until the pressurizer fills. Pressurizer level reaches a MJ w:. .r. ' =4nt=um at 50 seconds, then begins a linerr increase until the R.}_.,. (Q..;... Table 3.2-4 conpares the l pressurizer is full at 780 seconds. I
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