ML17285A323
| ML17285A323 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 03/08/1989 |
| From: | WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | |
| Shared Package | |
| ML17285A322 | List: |
| References | |
| TAC-72620, NUDOCS 8903170138 | |
| Download: ML17285A323 (6) | |
Text
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TRIP FUNCTION 1.
PRIMARY CONTAINMENT ISOLATION a.
Reactor Vessel Water Level" 1)
Low, Level 3
2)
Low Low, Level 2
b.
Drywell Pressure - High c.
Radiation - High 2)
Pressure
- Low 3)
Flow High d.
Main Steam Line Tunnel Temperature - High e.
Main Steam Line Tunnel h Temperature
-. High f.
Condenser Vacuum - Low g.
Manual Initiation 2.
SECONDARY CONTAINMENT ISOLATION CHANNEL CHECK S
N.A.
N.A.
S N.A.
S
~ N.A.
e.k.
N.A.
N.A.
CHANNEL FUNCTIONAL TEST CHANNEL CALIBRATION R
R N.A.
a.
b.
C.
d.
Reactor Building Vent Exhaust Plenum Radiation - High Drywell Pressure - High Reactor Vessel Water Level - Low Low; Level 2 Manual Initiation S
N.A.
N.A.
N.A.
M R
R N.A.
TABLE 4.3.2.1-1 ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE RE UIRED 1
2 3
1,2,3 1, 2, 3
.Q 1 j 2 j 3 K
1 1 j 2 j 3 Q
1,2,3 I
1,2,3 ITI 2*
3A',
2, 3
Qg 1, 2, 3, and "" ~
1, 2, 3
1,2,3, and¹ 1, 2, 3, and ""
O
P, yl
~i 1
I
C TABLE 4. 3. 2.1-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREHENTS.
CHANNEL TRIP FUNCTION CHECK 3.
REACTOR WATER CLEANUP SYSTEM ISOLATION CHANNEL FUNCTIONAL TEST CHANNEL CALIBRATION OPERATIONAL CONDITIONS FOR WHICH.
SURVEILLANCE RE UIRED a.
b.
C.
d.
e.
f.
9.
h.
3 ~
h Flow - High Heat Exchanger Area Temperature
- High Heat Exchanger Area Ventilation h Temperature-High Pump Area Temperature - High Pump Room A Pump Room 8 Pump Area Ventilation b, Temp. - High Pump Room A Pump Room B
SLCS Initiation Reactor Vessel Water Level - Low Low, Level 2 RWCU/RCIC Line Routing Area Temperature - High RWCU Line Routing Area Temperature - High Manual Initiation X
N.A.
N.A.
X( g,A.
N.A.
P sA X ~>
g sh R
R R
N.A.
R N.A.
1 2
3 1, 2, 3
1 j 2 j 3
1 2.3 1
2 3
1,-2, 3
1 2
3 1
2 3
1 2>>3 1 2.3
.1. 2.
3 1, 2, 3
A0K Xl0 O0
~O REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION a 0 b.
C.
d.
e.
RCIC Steam Line Flow - High RCIC/RHR Steam Line Flow - High RCIC Steam Supply Pressure-Low RCIC Turbine Exhaust Diaphragm Pressure - High RCIC Equipment Room Temperature - High RCIC Equipment Room h Temperature - High N.A.
N.A.
p).R.
g
]v.g.
M 1
2 3
1, 2, 3 1, 2, 3
1, 2, 3
1 j 2 j 3
S
'0 f
e 4v s
M Cl C
m I
bJ LO I
TABLE 4.3.2.1-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREHENTS CHANNEL FUNCTIONAL TEST OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE RE VIREO CHANNEL CALIBRATION CHANNEL CHECK TRIP FUNCTION 4.
REACTOR CORE ISOLATION COOLING SYSTEH ISOLATION (Continued)
RWCU/RCIC Steam Line 'Routing Area Temperature - High Drywell Pressure - High Manual Initiation 9.
1, 2, 3
1, 2, 3
1, 2, 3
N.A.
h.
N.A.
N.A.
5.
RHR SYSTEH SHUTDOWN COOLING HODE ISOLATION Reactor Vessel Water Level-Low, Level 3 Reactor Vessel (RHR Cut-in Permissive)
Pressure - High a.
1,2,3 1, 2, 3
N.A.
c.
Equipment Area Temperature-High d.
Equipment Area Vent)lation h Temp. - High e.
Shutdown Cooling Return Flow Rate - High f.
RHR Heat Exchanger Area Temperature - High g.
. Manual Initiation 1, 2, 3
1, 2, 3
1, 2, 3 N.A.
I, 2, 3
1 2
3 N.A.
N.A.
TABLE NOTATIONS When reactor.
steam pressure
> 1037 psig and/or any turbine stop valve is open.
When handling irradiated fuel in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
During CORE ALTERATION and operations with a pote.-".<al for draining the reactor vessel.
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