ML20149H265

Proposed Tech Specs,Revising Tech Spec Table 3.3.2-3, Isolation Sys Instrumentation Response Time, to Indicate That Instrumentation Providing RWCU Sys Isolation on High Sys Differential Flow Contains 45 Time Delay

ML20149H265
Person / Time
Site:	Hatch
Issue date:	02/09/1988
From:	GEORGIA POWER CO.
To:
Shared Package
ML20149H253	List: ML20149H249 ML20149H265
References
TAC-66787, TAC-66788, NUDOCS 8802190194
Download: ML20149H265 (2)

Text

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~ABLE 1 3.3.2-3 ISCLAT:CN SYSTEu INSTRUVENia'! N ;ES D.55 T!vi TRIP FUNCTION RE5;0NSE I:ME (ie:09dsj'

l. P,RIMARY CCNTAINMENT ISCLATION

a. Reactor Vessel Water Level

1. 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. Main Steam Line

1. 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.

1. 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.

1. 1. With time delay of 45 seconds I

l HATCH - UNIT 2 3/4 3-19 Amendment No. 33, 39 8802190194 880209 PDR ADOCK 05000366

, P DCD

. 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*

c. HPCI Turbine Exhaust Diaphragm Pressure - High NA

d. HPCI Pipe Penetration Room Temperature - High NA

e. Suppression Pool Area Amoient Temp. - High NA

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 b.

3 s Isolation Time s 13*

RCIC Steam Supply Pressure - Low NA

c. RCIC Turbine Exhaust Diaphragm Pressure - High NA

d. Emergency Area Cooler Temperature - Hign NA

e. Suppression Pool Area Ambient Temp. - High NA

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

a. Reactor Vessel Water Level - Low (Level 3) NA

b. Reactor Steam Dome Pressure - High NA HATCH - UNIT 2 3/4 3-20 Amendment No. 33, 39

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