ML20203N186
| ML20203N186 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 09/12/1986 |
| From: | GULF STATES UTILITIES CO. |
| To: | |
| Shared Package | |
| ML20203N175 | List: |
| References | |
| NUDOCS 8609230189 | |
| Download: ML20203N186 (4) | |
Text
- - _ _ _ _ _
TABLE 3.3.2-2 ISOLATION ACTUATION INSTRUMENTATION SETPOINTS
=
E E
ALLOWABLE g
TRIP FUNCTION TRIP SETPOINT VALUE E
1.
PRIMARY' CONTAINMENT ISOLATION
[
a.
l 5
Low Low, Level 2
>-43 inches *
>-47 inches l
H b.
Drywell Pressure - High 1 1.68 psig 5 1.88 psig l
l c.
Containment Purge Isolation Radiation - High 5 1.3 R/hr 5 1.57 R/hr 2.
MAIN STEAM LINE ISOLATION a.
Low Low Low, Level 1
>-143 inches *
>-147 inches b.
Main Steam Line Radiation - High
-< 3.0 x full power background 5 3.6 x full power background w
O c.
Main Steam Line Pressure - Low
> 849 psig
> 837 psig d.
Main Steam Line Flow - High
- 170 " y.;d i 17^** pid e.
Condenser Vacuum - Low
> 8.5 inches Hg.
> 7.6 inches Hg.
vacuum vacuum f.
Main Steam Line Tunnel Temperature - High 5 135*F
'i 142.5*F l
g.
Main Steam Line Tunnel A Temperature - High 5 51*F
$ 55*F
- 1. l.ine, A 6 l% esid 6 151 esd IN5ERT U
B d 156 MJ
& I M P 9 d.
- 3. Line C 6 153 r*5d 6 158 P5id
- 4. Lin e. D 6 164 est 6 te9 es;d.
8609230189 860912 PDR ADOCK 05000458 P
pgR
{
m 3
TABLE 3.3.2-2 (Continued) h ISOLATION ACTUATION INSTRUMENTATION SETPOINTS 99 ALLOWA8LE a,
52 TRIP FUNCTION TRIP SETPOINT VALUE c'
4.
REACTOR WATER CLEANUP SYSTEM ISOLATION (Cont'd) l d.
Equipment Area a Temperature - High Si 1.
Heat Exchanger Room 1 33*F 5 36.5'F Z
2.
Pump Rooms A and B 5 78'F
$ 82*F 3.
Valve Nest Room 5 46*F 1 49.5'F g
4.
Demineralizer Rooms 1 and 2
< 46*F
< 49.5'F 5.
Receiving Tank Roon 546*F 549.5*F f
I.
e.
Low Low Level 2 1 - 43 inches
- 1 - 47 inches f.
Main Steam Line Tunnel Ambient Temperature - High 5 135'F i 142.5'F g.
Main Steam Line Tunnel u,)
A Temperature - High 5 51*F
$ 55'F i'
h.
SLCS Initiation NA NA ro 5.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION '
a.
RCIC Steam Line Flow - High 5 Eggs' H 0M i 90er6" H 0 +
l 2
124 135.g b.
RCIC Steam Line Flow - High Timer 1 3 seconds 1 13 seconds c.
RCIC Steam Supply Pressure - Low 1 60 psig 1 55 psig d.
RCIC Turbine Exhaust Diaphragm Pressure - High 1 10 psig 5 20 psig e.
RCIC Equipment Room Ambient Temperature - High 5 182*F 5 186.4*F f.
RCIC Equipment Room A Temperature -
1 96*F i 99'F High
TABLE 3.3.2-2 (C:ntinued) h ISOLATION ACTUATION INSTRUMENTATION SETPOINTS "m'
ALLOWABLE h
TRIP FUNCTION TRIP SETPOINT VALUE o
5.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION (Cont'd)
E g.
Main Steam Line Tunnel Ambient q
Temperature - High
$ 135*F
$ 142.5"F h.
Main Steam Line Tunnel A Temperature - High 5 51*F S 55'F
.l i.
Main Steam Line Tunnel Temperature Timer 0 seconds NA j.
RHR Equipment Room Ambient l
Temperature - High
$ 117'F
$ 121.1*F I
R
+
k.
RHR Equipment Room l
(p A Temperature - High 5 29'F 1 33.6*F 4
1.
RHR/RCIC Steam Line Flow - High 5 156" H 0**
$ 164.5" H 0**
2 2
i m.
Drywell Pressure - High 5 1.68 psig 5 1.88 psig n.
Manual Initiation NA NA 6.
RHR SYSTEM ISOLATION
)
a.
RHR Equipment Area Ambient Temperature - High 5 117'F
$ 121.1*F b.
RHR Equipment Area A Temperature -
High 5 29'F 1 33.6*F c.
Low Level 3 1 9.7 inches
- 1 8.7 inches d.
Low Low Low Level 1 1 - 143 inches
- 1 - 147 inches I
l j
-~,
p.
TABLE 3.3.2-2 (Continued) m2 ISOLATION ACTUATION INSTRUMENTATION SETPOINTS i
9 ALLOWABLE co g
TRIP FUNCTION TRIP SETPOINT VALUE 6.
RHR SYSTEM ISOLATION (Cont'd) c-5 e.
Reactor Vessel (RHR Cut-in Permissive) Pressure - High 5 135 psig 1 150 psig s
f.
Drywell Pressure - High 5 1.68 psig 5 1.88 psig 7.
MANUAL INITIATION NA NA
- See Bases Figure B 3/4 3-1.
I R
- Initial setpoint.
Tinal ::tp; int t; be detemin d durin; :terte; t::t pr:;r=. Any l
required change to his setpoint shall be submitted to the Commission within 90 days V
of test completion.
O Final setPoinh }o be dejerms' ed clur'ang -des 4thg prsor-40 n
c9ercMen m he steam ccedeas.nq osede folln n9 %s Nuclear Regula4ory Conn.,s'an's appraal -la opera 4e. en i
4hal mede- (Reference. Laien,e cond,4.6n 5.a. 4a NPF-47).
i l
e