ML20149G375
| ML20149G375 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 10/13/1994 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20149G372 | List: |
| References | |
| NUDOCS 9410200308 | |
| Download: ML20149G375 (18) | |
Text
.
I Table 3.2-9 3D INSTRUMENTATION WHICH INITIATES REClRCULATION PUMP TRIP gp4 =N Oun-Ref.
Instrument Trip Required Trip Setting Remarks o
No.
Condition Operable bJ c (a)
Nomenclature Channels DO Z per Trip OO System O GJ GO.-.
D 1.
Reactor Vessel Water Level Low 2*"*'
at-73 inches H,0 Power must be reduced and the l
mode switch placed in a mode o4 other than the RUN Mode.
ts 3 Os OO 2.
Reactor Pressure High 2mw '
s109S psig Power must be reduced and the e
tow (ATWS RPT) mode switch placed in a enode C W4 other than the RUN Mode.
XM 3.
EOC - RPT*
- 1. Turbine Stop 2""'
- 1. Stop Valve Trips recirculation pumps on Valve Closure 590% Open turbine control valve fast
- 2. Turbine Control
- 2. Control Valve closure or stop valve closure Valve Fast Hydraulic when reactor is > 30%.*
Closure Press Trip Point W
The column entit ed *Ref. No.* is only for convenience so that a one-to-one relationship can be established l
(a)
N between items in Table 3.2-9 and items in Table 4.2-9.
No Ib.1) Whenever the reactor is in the RUN Mode, there shall be two operable trip systems for each parameter for each operating recirculation pump. If the required number of operable channels cannot be met for one of the trip systems, place the inoperable channel in the tripped condition or take the indicated action within 14 days.
If the required number of operable channels cannot be met for both trip systems take the indicated action within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
(b.2) One instrument channel may be inoperable for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to perform required surveillances prior to entering other applicable actions.
c+
(c)
Anticipated Transients Without Scram - Recirculation Pump Trip to@
(d)
End of Cycle - Recirculation Pump Trip un V
(e)
Either of these two EOC - RPT systems can trip both recirculation pumps. Each EOC - RPT system will trip if y
2-out-of-2 fast closure signals or 2-out-of-2 stop valve signals are received.
s to (f.1) The requirement for these channels applies from EOC-2000 MWD /t to EOC. The RPT system may be placed in an inoperable f
status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to provide the required monthly surveillance. If one EOC-RPT system is inoperable for longer then 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or if both EOC-RPT systems are simultaneously inoperable, an orderly power reduction will be o
immediately initiated and reactor power will be <30% within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
cn C
E (f.2) One instrument channel may be inoperable for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to perform required surveillances prior to entering other applicable actions.
t2 2
(g)
Either of these two ATWS-RPT systems can trip both recirculation pumps. Each ATWS-RPT system will trip if 2-out-of-2 reactor low water level signals or 2-out-of-2 reactor high pressure signals are received.
e-a tre u
LIMITING CONDIYIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6.E. Recirculation Pumo SfJLti 4.6.E. Recirculation Pumo Start An idle recirculation pe g shall Prior to starting a recirculation not be started unless the ?tmpera-pump, the reactor coolant temper-ture differential between tha atures in the dome and in the reactor coolant within the dow bottom head drain shall be compared and the bottom head drain is *145'F.
and pennanently recorded.
If the temperature differential cannot be determined, and both recirculation pumps are tripped, the restart of the recirculation pumps is allowed within 30 minutes of the trip of the pumps, provided that drive flow remained above 40%
in either loop prior to the pump trip, no HPCI or RCIC injection occurred after the trip of the pumps, and the feedwater tempera-ture remained above 300*F after the trip of the pumps. With either approach, the requirements of Specification 3.6.D must be con-sidered.
4 HATCH - UNIT 1 3.6-3 techsp\\h\\94-0601B. pro \\0
l 900 7 NOTE: SCALE IN INCHES ABOVE VESSEL ZERO e
WATER LEVEL NOMEN 0LATURE HEIGHT ABCVE 800 --
VESSEL 7ERO NO HNCHED READING INSTRUMENT (8) 373.5
+56.5 BARTON/ROSEMOUNT 750 - -
171 559
+42 G E /M AC VESSEL _
(4) 549
+32 GE/MAC 722.75 FLANGE (31 517 0.0 BARTON/ROSEMOUNT (2) 40
-47 BARTOWROSEMOW 700 - -
(11 404
- 113 BARTON/ROSEMOUNT (01 315
-202 BARTON/ROSEMOUNT 650 --
-- 640 -
W" 600 - -
577
- 573.5 18)
+60 - -
+60 - -
+60 -
+ 60 - -
N
- 559 17)
(g3-56.5 (7) 42 HI RARM
~"
HPCI 8 idl '32 LO AL ARM BOTTOM OF STE AM RCIC T' RIPS
- ORYER SKIRT 517(3fI U 0 - 0(3) o--
0(3)-- RE ACTOR SCRAM 500 --
RO (b CORE l% -
FEED _ 4g3$
CONTRIBUTE TO AOS LOW (LEVEL 3)
WATER
" 47
-- 47 LOW LOW (LEVEL 2)
SPRA Y g
-73 INITIATE ATWS-RPT
- 404 (1) 400 - -
- 367
- 150 --
INITI ATE RHR, C.S.,
350 -" 358.56 START OIESEL ANO CONTRIBUTE TO A O.S.
2/3 CORE CLOSE MS!V%
- 202 MEIGHT 315 (0)
P E R MISSIVE 300 --
(LEVEL O)
ACTIVE FUEL 250+--
-317 - -
200
- 208.56 RECIRC
-1 56 -DISCH ARG E RECfRC SUCTION - 1615 NOZ2LE NO2ZLE 150 --
100 --
50 --
0.-
e.tso.:
I FIGURE 2.1-1 REACTOR VESSEL WATER LEVEL HATCH - UNIT 1 techsp\\h\\94-06U1. pro \\187
o 900 T-NOTE: SCALE IN INCHES ABOVE VESSEL 2ERO e
WATER LEVEL NOMENCLATURE HEIGHT ABOVE 800 --
VESSEL ZERO
{ ONCHES)
R E ADING INST R UM E NT (8) 573.5
+56.5 BARTON/ROSEMOUNT 750 --
17) 559
+42 GE/MAC (di 549
~ 722.75 F LANGE (3) 517 0.0 BARTON/ROSEMOUNT 700 --
(2) 470
-47 BARTON/ROSEMOUNT (1) 404
- 113 BARTON/ROSEMOUNT (0) 315
-202 BARTON/RUSEMOUNT
\\
650 --
-- 640 -
LINE f
600 --
577
+60 -
+60 - -
- 573.5 18)
+60 - -
+60 -
56.5 9
- 559 871 (81-471 42 HI M ARM 550 -e 549(4)
HPCI 8, 441 '32 LO ALARM BOTTOM OF STE AM RCIC T RIPS
-ORYER SKIRT 517(3l 0- 0(3) 0--
0(3F-RE ACTOR SCRAM FEEO 500 --
CONTRIBUTE TO ADS LOW ILEVEL 3)
~~
WATER'~
~
~ 470 (2)
~'M CORE
. 47 LOW LOW (LEVEL 2) l SPRAY g
450 --
l
~
4 400 --
- 367
- 150 -- INITI ATE RHR, C.S.,
h START DIESEL ANO 350 -L358.56 CONTRIBUTE TO A.O.S.
CLOSE MSIV%
2/3 CORE
- 202 HEICHT 315 (0)
PERMISSIVE 300 --
(LEVEL O)
ACTIVE FUEL 250 --
317 - -
200 -- 208 56 RECIRC RECIRC
~
^ ~ ' "
$UCT ION - 161.5 NOZ2LE NOZZLE 150 --
100 - -
50 - -
1 0.
9300 2 BASES FIGURE B 3/4 3-1 REACTOR VESSEL WATER LEVEL HATCH - UNIT 2 B 3/4 3-6 techsp\\h\\94-06U2. pro \\126
l R
MUM IN IM N
O ITATN EM U
RTS IN M
E T
1 S
1 YS 9
P 3
I R
3 T
E P
LB M
A U
T P
NO ITA LU C
R IC E
R S
WT A
wo L
h ig H
lev e
e L
ru re s
t s
a e
W P
r le le s
s s
s N
e e
O V
V I
r r
T o
o C
t t
N c
c a
a U
e e
F R
R P
I R
T 1
2
+DO7mO/7/DAIOCCr u1O wwO n o hsnI t EZo wN4 Wt@N r(
4 r
TABLE 3.3.9.1-2 h
-c n
ADVS RECTRCULATION PUMP TRIP SYSTEM INSTRUMENTATION SETPOINTS
- r t
C ALLOWABLE TRIP FUNCTION S POINT N
1.
Reactor Vessef, Water Led. Low 2 -73 inches 2 -73 inches i
2.
Reactor Vessel Pressure - High 51095 psig s 1095 psig w
N A
w e
Gco I
l e>
ton 2
enc
/
7
/
LD b
I l
ocn cru CD l
'O
-s O(
- See Bases Figure B3/4 3-1.
s-.
O
s TABLE 4.3.9.1-1
-4 ATWS RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION z
SURVEILLANCE REQUIREMENTS Cz CHANNEL Q
CHANNEL FUNCTIONAL CHANNEL TRIP FUNCTION CHECK TEST CALIBRATION
- 1. Reactor Vessel Water Level-Low S
O R
I
- 2. Reactor Vessel Pressure - High S
Q R
W N
4 W
I C) e+
(D C2 7
tn V
/
7
/
O 4
1 O
c)
C N
CD M
O
/>a N
U1
REACTOR COOLANT SYSTEM IDLE RECIRCULATION LOOP STARTUP LIMITING CONDITION FOR OPERATION 3.4.1.3 An idle recirculation pump shall not be started unless the temperature differential between the reactor coolant within the dome and the bottom head drain is s 145 F.
If the temperature differential cannot be determined, and both recirculation pumps are tripped, the restart of the recirculation pumps is allowed within 30 minutes of the trip of the pumps, provided that drive flow remained above 40% in either loop prior to the pump trip, no HPCI or RCIC injection occurred after the trip of the pumps, and the feedwater temperature remained above 300 F after the trip of the pumps. With either approach, the requirements of Specifications 3.4.1.3.a and 3.4.1.3.b must be considered.
a.
The temperature differential between the reactor coolant within the idle loop to be started up and the coolant in the reactor pressure vessel is s 50 F when both loops have been idle, or b.
The temperature differential between the reactor coolant within the idle and operating recirculation loops is s 50 F when only one loop has been idle, and the operating loop flow rate is s 50% of rated loop flow.
APPLICABILITY:
CONDITIONS 1, 2, 3 and 4.
ACTION:
With temperature differences and/or flow rate exceeding the z.bove limits, suspend startup of any idle recirculation loop.
SURVEILLANCE REQUIREMENTS 4.4.1.3 The temperature differential and flow rate shall be determined to be within the limit within 30 minutes prior to startup of an idle recirculation loop.
HATCH - UNIT 2 3/4 4-3 techsp\\h\\94-06U2A. pro \\0 f
l
4.
[
Table 3.2-9
-4g INSTRUMENTATION WHICH INITIATES RECIRCULATION PUMP TRIP Ref.
Instrument Trip Required Trip Setting Romerke No.
Condition Operable E
tal Nomencleture Channele ca per Trip
-4 System 4
1.
Reector Vessel Water Level Low (Level 21 2*
-t-4Hnchee HP Power must be reduced and the (ATWS RPTl*'
>.q3 ;'(** q ' e mode switch placed in a mode other then the RUN Mode.
2.
Reactor Pressure High 2 *"
51095 poig Power must be reduced and the IATWS RPT) mode switch placed in a mode other then the RUN Mode.
3.
- 1. Turbine Stop 26'"
- 1. Step Velve Tripe recirculeelon pumpe on Velve Closure s90% Open turbine control velve feet
- 2. Turbine Control
- 2. Control Velve closure or stop velve closure Velve Feet Hydraulic when roector le > 30%."'
Closure Prese Trip Point sa le)
The column entitled *Ref. No." is only for convenience so that e one-to-one relationship can be establiehod betwen items in TetA. 3.2-9 and items in Table 4.2-9.
rw e'o fbil. Whenever the reactor is in the RUN Mode, there shall be two operable trip systems for each parameter for o
eech operating recirculation pump. If the required number of operable channele cannot be met for one of the l
trip systems, piece the inoperable channelin the tripped condition or take the indicated action within 14 days.
If the required riumber of operable channels cannot be met for both trip systems, take the indicated action willun 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Ibl2. One instrument channel may be inoperable for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to perform required surveillences prior to entering g
other applicable actione.
(c)
Anticipated Trenaiente Without Screm - Recirculation Pump Trip cLg tal End af Cycle - Recirculation Pump Trip
- s c+
tel Either of these two EOC - RPT systems een trip both recirculation pumps. Each EOC - RPT system will trip if 2
2-out-of-2 feet cleeure signale or 2 out-of-2 stop velve signale are received.
?
(fil. The rCa.; for these channele applies from EOC-2000 MWD /t to EOC. The RPT system may be placed in en inoperable j
status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to provide the required monthly survedience. If one EOC-RPT system ie inoperable for
.M longer then 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or if both EOC-RPT systems are simultaneously inoperable, en orderly power reduction will be immediately initiated and reector power wdl be <30% within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
(fl2. One instrument channel may be inoperable for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to perform required surveillances prior to entering l
w other opphceble actione.
t (g)
Either of these awo ATWS-Af'T systeme een trip both recirculation pumpe. Each ATWS-RPT system will trip if 2-out-of-2 reactor low water level segnale or 2-out-of-2 reactor high pressure signale are receeved.
m
.o M'
tJ1
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6.E.
Recirculation Pumo Start 4.6.E.
Recirculation Pumo Start e reactor recirculatio mps Prior to starting a recirculation sh not be starte ess the pump, the reactor coolant temper-coolan e
es between the atures in the dome and in the dome an head drain bottom head drain shall be com-are in 145'F.
g pared and permanently recorded, n eg/ 4 c<.
Ql egyef*
,4 pay
~
^'1 1,,5n 1
, g ey e;,, '
.= g su n. u n;,.,
s*
2.
-.ay %m,,,M+
n
-, ~.
' p. ' f
'N
.g L
e
..,_.~*t~
g L
,+,
m y+
,t i
[
l 1
HATCH - UNIT 1 l
3.6-3 i
J
i
')
An idle recirculation pump shall not be started unless the temperature differential between the reactor coolant within the dome and the bottom head drain is < 145 F.
If the temperature differential cannot be determined, and both recirculation pmnps are trripped, the restart of the recirculation pumps is allowed within 30 minutes of the trip of the pumps, provided that drive flow remained above 40% in either loop prior to the pump trip, no IIPCI or RCIC injection occurred after the trip of the pumps, and the feedwater temperature remained above 300 F after the trip of the pumps.
With either approach, the requirements of specification 3.6.D must be considered.
9 i
a 4
I 900 7
NOT E: SCALE IN INCHES j
ASOVE VESSEL ZERO e
WATER LEVEL NOMENCLATURE j
HEIGHT A80VE
=
000 -
VESSEL ZERO
$ flNCHEst R E ADING - INSTRUMENT ISI 573.5
+95.5 SARTON/ROSEMOUNT
)
750 -
171 569
+42 GE/MAC
/
VESSEL _
. tel 549
+32 GE/MAC -
7 g _ FLANGE (3) 517 0.0 BARTON/ROSEMOUNT i
(2)
,470
- 47 BARTON/ROSEMOUNT 700 - -
(Il 404
- 113 BARTON/ROSEMOUNT 103 315
-202 BARTON/ROSEMOUNT 4
650 -
-- 640 -
LINE
/
s00 - -
. 577
- 573.5 (8) 40--
+s0 --
+so - -
+e0 -
54.5 8
- 559 17)
(3)-
(7) 42 HI ALARM
~'
HPCI& (4) '32 LO ALARM SOTTOM OF STE AM RCIC TRIPS
- ORYER SMIRT 51713l 0- 0(3) 0--
0(3F-REACTOR SCRAM ZERO CONTRIBUTE TO ADS LOW (LEVEL 3) -
FEED 500
- 4815 WATER
" 470 (2)
- 47 LOW LOW (LEVEL 2M CORE
~
~
~ SPRAY r
-73, %, T s a k ATd EUI
- )
- 404 (1)
' " ~~
- 367
- 150 -- INITIATE RHR, C.S.,
350 - -358.M START DIESEL AND l
CONTRIBUTE TO A.D.S.
I 2/3 CORE CLOSE MSIVis
- 202 HEIGHT 315 (0) l P E RMISSIV E 300 -
(LEVELO)
ACTIVE l
FUEL 250 - -
-3i7--
200 -= 20us
,,c,,c
. /,,c,,c
-nus-OiSCH4RGE )
SUCTION - 161.5 NOZZL E NOZZLE 150 - -
e y
iOO -
6 i) 50 -
_0 93402 1
FIGURE 2.1-1 REACTOR VESSEL WATER LEVEL HATCH - UNIT.1 Amendment No. 4M, 4M, M4. MB.
187
"" T SCALE IN INCHES feOTE:
ABOVE VESSEL ZERO e
WATER LEVEL NOMENCLATURE HEIGHT ABOVE VESSEL ZERO 300 - -
$ itNCHESI R E ADING INSTRUMENT (8) 573.5
+96.5 BARTON/ROSEMOUNT
)
750 -
(7) 559
+42 GE/MAC VESSEL (4) 549
+32 CE/MAC
'/
722.75-FLANGE
~
I?,
517 0.0 BARTON/ROSEMOUNT
.21 470
- 47 BARTON/ROSEMOUNT
~~
^404
- 113 BARTON/ROSEMOUNT (1)
(0) 318
-202 BARTON/ROSEMOUNT 650 --
)
<- 640 -
LINE
/
600 - -
,. 577
+60 -
+40 - -
- 573.5 (Si
'40 - -
+40 -
54.5 8
-55917)
(8)-
17) 42 Hi ALARM i
550 -r 549(4)
HPCIa, tal 32 LO ALARM 80TTOM OF STE AM RCIC TRIPS g
-ORYER SKIRT 517(3lNS RUMENT 0 - 0(3) 0--
0(3F - RE ACTOR SCRAM CONTR100TE TO ADS LOW (LEVEL 31 FEED 500 - -
~ ~
~
=470(2)
WATER CORE
- 486 SPRAY g
450 --
_ g g,,, % k A7 4 - 4 U III l
~
400-
-367
- 150. - INITIATE RHR.C.S.,
h START DIESEL ANO 350 L358.56 l
CONTRIBUTE TO A.D.S.
2/3 COR E CLOSE N,V%
- 202 MEIGHT 315 (0)
P E RMIS$1VE 300 --
(LEVEL 0)
ACTIVE FUEL 250 --
-317 - -
200 -= 208 %
ECIRC j
- 178.56 -DISCH ARG E
-- ' ""* IM -
NOZZLE
' W " L M *88 h
)
$UCTION - 161.5 NO2ZLE 150 --
-f 100 - -
(
-s
.)
50 - -
'l 0--
BASES FIGURE B 3/4 3-1 i
REACTOR VESSEL WATER LEVEL HATCH - UNIT 2 B 3/4 3-6 Amendment No. 48, 67, 443, 126
.~-
TABLE 3.3.9.1-1 I
81W5 RECIRCULATION PtiMP TRIP SYSTEM INS [ GUM WIA[108
--4 m=
NINIMUM OPERABLE CHANNELS PER Jgip_[ygg11QN TRIP SYSTEM Cz 1.
Reactor Vessel Water Level - Low 46, Le.ci 2 q
to 2.
Reactor Vessel Pressure - High 2
N a
<n N
k k
n y
g i ne JD y
] l l~jf
s h
ig e
E c
s t
n p
bE i
5 AU 5
a, -
WL f
9 7
OA 4-1 0
tV t
A 1 i d
S I
N I
O P
I E
S N
O I
T A
I N
EM U
R T
s S
I e
g 2
N H
h i
I Pl c
s ID n
p 1
M N l>
i 5
3 E
1i T
k f5 9 L.
7 4-S S
0 Y
1 3
S 1
i E
P L
I B
R A
I J
P MU P
NO 2
I T
l A
e t
v U
e C
L R
U w
E o
R L
S w
W o
I L
l l
lw A
h
- ii y
ev e
l e
1 r
r u
3 e
s t
s 4
a e
/
W i
3 P
B l
l e
e e
r s
s u
s s
h V V
ig e
e f
01 r
r s
1 o
o e
C t
t s
N c
c a
U a
a B
F e
e R
R e
P e
I R
S I
1 2
>b a CM s t x0. mWe NWo x> c> x, E O 4 o Nb ta np L
- r ecc e
Dr D,
(D
(.
i TABLE 4.3.9.1-1
-4Q ATWS REC 1RCULATf0N PUMP TRtP ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS c$
CHANNEL
--4 CHANNEL FUNCTIONAL CHANNEL TRfP FUNCTION CHECK TEST CAU9 RATION m
- 1. Tleector Voesel Water level - Low S
Q R
l
-L, a.J P
- 2. Rosetot Vessel Pressure - High S
Q R
l l
l l
N b
M l
i On W
E
.O 3
CL B
(D 3c+
2 O
bd 64
.I )
OmmS N
LFt I
=
r
'T" REACTOR COOLANT SYSTEM IDLE RECIRCULATION LOOP STARTUP w.
LIMITING CONDITION FOR OPERATION g up.fa wd r ~y ~s 2-(m _, n +- mn 3.4.1.3 4n-idle i et irculatten-loop-shall-not-be-startedmnless-the-
-tempe r a t u re-d i f f e ve n ti al-be twee n-these a cto r-rool a n t-w i t h i n-t he-dome-a nd
-the-bottom head drain Js:1-1450 F;-and a.
The temperature differential between the reactor coolant within the idle loop to be started up and the coolant in the reactor pressure vessel is s 50 F when both loops have been idle, or b.
The temperature differential between the reactor coolant-within the idle and operating recirculation loops is s 50 F when only one loop has been idle, and the operating loop flow rate is s 50% of rated loop flow.
APPLICABILITY:
CONDITIONS 1, 2, 3 and 4.
ACTION:
With temperature differences and/or flow rate exceeding the above limits, suspend startup of any idle recirculation loop, j
SURVEILLANCE REQUIREMENTS 4.4.1.3 _The temperature differential and flow rate shall be determined to be within the limit within 30 minutes prior to startup of an idle recirculation loop.
i' s
h 1
HATCH - UNIT 2 3/4 4-3 e
u t
An idle recirculation pump shall not be started unless the temperature differential between the reactor coolant within the dome and the bottom head drain is $ 145 F.
If the temperature differential cannot be determined, and both recirculation pumps are tripped, the restart of the recirculation pumps is allowed within 30 minutes of the trip of the pumps, provided that drive flow remained above 40% in either loop prior to the pump trip, no IIPCI or RCIC injection occurred afler the trip of the pumps, and the feedwater temperature remained above 300 F after the trip of the pumps.
With either approach, the requirements of specifications 3.4.1.3a and 3.4.1.3b must be considered.
t 0
I I