ML17277B636
| ML17277B636 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 02/27/1985 |
| From: | WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | |
| Shared Package | |
| ML17277B635 | List: |
| References | |
| TAC-56945, NUDOCS 8503060432 | |
| Download: ML17277B636 (6) | |
Text
TABLE 3.3.3-1 (Continued)
EHERGENCY CORE COOLING SYSTEH ACTUATIOH INSTRUHEHTATIOH 0QQ UQl
%OM O
>0
- CO OA
,- AGl XIV CIGI QlQl OO Otu
'OlO CIA'mI
'%IXI C:
Im M
TRIP FUHCTION C.
DIVISION 3 TRIP SYSTEH l.
HPCS SYSTEH a 0 b.
C.
d.
e.
Reactor Vessel Mater Level " Low, Low, Level 2
Drywell Pressure " High Reactor Vessel Mater Level-High, Level 8 Condensate Storage Tanks I.evel-Low Suppression Pool Water Level-HINIHUH OPERABLE CHANHELS PER 2(b) 2(b) 2(c) 2(d) 2(d)
APPLICABLE OPERATIONAL CONDITIONS ACTIOii 1, 2, 3, 1a 2p 3
1,'>>
3a 4>>
5>>
30 30 4*
5>>
32 4>>, 5" 36 4>>
5>>
36 D
ETO 11/division NINIHUH LS CIIAHHELS P
OPERABLE Py 2/bus 1/bus bus D.
LOSS OF POWER l.
- 4. 16 kV Emergency Bus Under-voltage (Loss of Voltage) 2.
- 4. 16 kV Emergency Bus Under-voltage (Degraded Voltage) 3/bus 2/bus TABLE NOTATIONS 2/bus g.
IIPCS System Flow Rate-Low (Hinimu h.
IIanual Initiation TOTAL HO.
OF CIIANNELS TO 1, 2, 3, 4", 5" 31 1, 2, 3, 4", 5>>
34 APPLICABLE OPERATIONAL CONDITIONS ACTION 2
3 4**
5*>>
37 1
2 3
4*" 5**
38 (a)
A channel may be placed in an inoperable 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 /> during periods of required surveillance without placing the trip system in the tripped condition provided at least one
- other OPERABLE channel in the same trip system is monitoring that parameters (b)
Also activates the associated division diesel generator.
(c)
Provides signal to close IIPCS pump discharge valve only; on 2-out-of-2 logic.
(d)
Provides signal to IIPCS pump suction valves only.
When the system is required to be OPERABLE per Specification
- 3. 5. 2 or 3. 5. 3.
Required when ESF equipment is required to be OPERABLE.
g iiot 2renuired to be OPERABLE uhen reactor steam dome pressure is less than Br'gua) to 12B psig.
Ci':,,
P
~
v
ms ~ "vm TABLE 3.3.3-2 (Continued)
EMERGENCY COBE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS TRIP FUNCTION C.
DIVISION 3 TRIP SYSTEH 1.
llPCS SYSTEH TRIP SETPOINT ALLOMABLE VALUE Reactor Vessel Mater Level - Low Low, Level 2
> -50 inches" Drywell Pressure
- lligh
< 1.65 psig Reactor Vessel Water Level - lligh, Level 8
< 54.5 inches*
.Condensate Storage Tank Level -
> 448 ft 3 in.
elevation Suppression Pool Mater Level - Nig
+
< 466 ft 8 in.
elevation llPCS System Flow Rate - Low (Hinimum Flow) 50 gpm Hanua 1 Intiati on POWER Py a.
4.16 kv Basis - 26k s 66 volts b.
120 V Basis - 82 t 2.5 volts a.
b.
C.
d.
g.
h.
D.
LOSS OF 1.
- 4. 16 kV Emergency Bus Undervoltage Loss of Voltage M a.
Divisions 1 and 2
b.
Division 3 a.
4.16 kV Basis - 3016 i 90 volts b.
120 V Basis - 87 i 2.5 volts
> -57 inches
< 1.85 psig
< 56.0 inches
> 448 ft 0 in. elevation
< 466 ft 10 in. elevation
> 1200 gpm N.A.
2870 4 172 volts 82 i 5 volts 3016 t 180 volts 87 a 5 volts 2.
- 4. I6 kV Emergency Bus Undervoltage Degraded Voltage (Divisions 1, 2, and 3
a.
- 4. 16 kV Oasis " 3632 t 108 volts b.
120 V Basis - 104.0 t 3.0 volts c.
8 t 0.04 sec time delay 3632 2 216 volts 103.8 k 6.0 volts 8 t 0.8 sec time delay TABLE NOTATIONS "See Bases Figure B 3/4 3-1.
NNThese are inverse time delay voltage relays or instantaneous voltage relays with a time delay.
The voltages shown are the maximu'm that will not result in a trip.
Lower voltage conditions will result in decreased trip times.
I
(.
~
~
.h,
TRIP FUNCTION CHANNEL CtlECK TABLE 4.3.3. 1-1 (Continued)
EHERGENCY CORE COOLING SYSTEH ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREHENTS CllANNEL OPERATIONAL FUNCTIONAL CHANNEL CONDITIONS FOR MNICN TEST CALIBRATION
. SURVEILI.ANCE RE UIREO C.
DIVISION 3 TRIP SYSTEH 1.
ilPCS SYSTEH a.
Reactor Vessel Water Level-Low Low, Level 2 S
H b.
Drywell Pressure-Iiigh N.A.
H c.
Reactor Vessel Mater Level-lligh~
Level 8 H
d.
Condensate Storage Tank Level-Low e.
Suppression Pool Water Level - Nigh H.A.
1A 2A 3A 4*A 5" 1, 2, 3, 4", 5*
1, 2, 3, 4", 5" 3
4KK 5'A g.
IIPCS System Flow Rate-Low (Hinimum Flow) h.
Hanual Initiation D.
LOSS OF POWER
- 4. 16 kV Emergency Dus Undervoltage (Loss of Voltage)
N.A.
N.A.
N.A.
N.A.
R N.A.
1, 2, 3, 4", 5"
]
2 3
4** 5**
2.
- 4. 16 kV Emergency Bus Undervoltage (Degraded Voltage)
N.A H
TABLE NOTATIONS 3
4+KK 5**
PNot required to be OPERABLE when reactor steam dome pressure is less than or equal to 128 psig.
"When the system is required to be OPERABLE per Specification
- 3. 5.2.
""Required when ESF equipment is required to be. OPERABLE.
Ct l
~
V+