ML20149H265
| ML20149H265 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 02/09/1988 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20149H253 | List: |
| References | |
| TAC-66787, TAC-66788, NUDOCS 8802190194 | |
| Download: ML20149H265 (2) | |
Text
.
~ABLE 3.3.2-3 1
ISCLAT:CN SYSTEu INSTRUVENia'! N ;ES D.55 T!vi TRIP FUNCTION RE5;0NSE I:ME (ie:09dsj' l.
P,RIMARY CCNTAINMENT ISCLATION a.
Low (Level 3) 513*
2.
Low Low (Level 2) 513*
3.
Low Low Low (Level 1), except MSIVs sl3*
b.
Drywell Pressure - High 513*
c.
Radiation - High'**
s1.0**
2.
Pressure - Low s13*
3.
Flow - High s1.0**
4.
Reactor Vessel Water Level - Low Low Low s1.0**
(Level 1) d.
Main Steam Line Tunnel Temperature - High 513*
e.
Condenser Vacuum - Low NA f.
Turbine Building Area Temperature - High NA 2.
SECCNDARY CONTAINMENT ISOLATION a.
Reactor Building Exhaust Radiation - High***
sl3*
b.
Drywell Pressure - High s13*
c.
Reactor Vessel Water Level - Low Low (Level 2) 513'
.d.
Refueling Floor Exhaust Radiation - High'**
sl3*
"The isolation actuation instrumentation response time shall be measured and recorded as a part of the ISOLATION SYSTEM RESPONSE TIME.
Response time specified is diesel generator start delay time assumed in a:cident analysis.
- Isolation actuation instrumentation response time.
- Radiation detectors are exempt from response time testing.
Response
time shall be measured from detector output or the input of the first electronic component in the channel.
- Times to be added to valve movement times shown in Tables 3.6.3-1, 3.6.5.2-1 and 3.9.5.2-1 to obtain ISOLATION SYSTEM RESPONSE TIME for each valve.
I
- With time delay of 45 seconds l
HATCH - UNIT 2 3/4 3-19 Amendment No. 33, 39 8802190194 880209 PDR ADOCK 05000366 P
7AELE 3.3.2-3_(. Continued) 250LATION SYSTEM !NSTRUMENTATION RESPONSE TIME IRIP CUNCTI.";
RESPONSE TIME (Seccnqsj" 3.
REACTOR WATER CLEANUP SYSTEM ISOLATION a.
A Flow nigh sl3*
b.
Area Temperature - High 513" c.
Area Ventilation Tempeciture ai - High
$13*
d.
SLCS Initiation NA e.
Reactor Vessel Water Level-Low Low (Level 2) sl3*
4 HIGH PRESSURE COOLANT INJECTICN SYSTEM ISOLATION a.
HPCI Stean Line Fluw nigh 3 s Isolation Time s 13' b.
HPCI Steam Supply Pressure - Low s13*
HPCI Turbine Exhaust Diaphragm c.
Pressure - High NA d.
HPCI Pipe Penetration Room Temperature - High NA Suppression Pool Area Amoient Temp. - High NA e.
f.
Suppression Pool Area ai - High NA g.
Suppression Pool Area Temp. Timer Relays NA h.
Emergency Area Cooler Temperature - High NA 1.
Drywell Pressure - High 513*
j.
Logic Power Monitor NA 5.
REACTOR CORE ISOLATICN COOLING SYSTEM ISOLATION a.
RCIC Steam Line Flow - High 3 s Isolation Time s 13*
b.
RCIC Steam Supply Pressure - Low NA RCIC Turbine Exhaust Diaphragm c.
Pressure - High NA d.
Emergency Area Cooler Temperature - Hign NA Suppression Pool Area Ambient Temp. - High NA e.
f.
Suppression Pool Area AT - High NA g.
Suppression Pool Area Temperature Timer Relays NA h.
Drywell Pressure - High s13*
1.
Logic Power Monitor NA 6.
SHUTDOWN COOLING SYSTEM ISOLATION Reactor Vessel Water Level - Low (Level 3)
NA a.
b.
Reactor Steam Dome Pressure - High NA HATCH - UNIT 2 3/4 3-20 Amendment No. 33, 39