ML040120517
| ML040120517 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 01/08/2003 |
| From: | Bhalchandra Vaidya NRC/NRR/DLPM/LPD4 |
| To: | Gerald Williams Entergy Operations |
| References | |
| TAC MB8958 | |
| Download: ML040120517 (3) | |
Text
Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 3.3 INSTRUMENTATION 3.3.6.1 Primary Containment and Drywell Isolation Instrumentation LCO 3.3.6.1 The primary containment and drywell isolation instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE.
APPLICABILITY:
According to Table 3.3.6.1-1.
ACTIONS
NOTES------------------------------------
- 1.
Penetration flow paths may be unisolated intermittently under administrative control.
- 2. Separate Condition entry is allowed for each channel.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Place channel in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for channels inoperable.
trip.
Functions 2.b, 5.b, 5.c, and 5.d 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Functions other than Functions 2.b, 5.b, 5.c, and 5.d B. One or more automatic B.1 Restore isolation 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Functions with capability.
isolation capability not maintained.
(continued)
GRAND GULF 3.3 -48 Amendment No. 4-2-0, iL2
Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 3 of 5)
Primary Containment and Drywell Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS TRIP SYSTEM ACTION C.1 REQUIREMENTS VALUE
- 3. Reactor Core Isolation Cooling (RCIC) System Isolation
- a. RCIC Steam Line Flow-High 1.2.3 I
F SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.6 3.3.6.1.7 s 64 inches water
- b. RCIC Steam Line Flow Time Delay 1.2.3 I
F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.7 2 3 seconds and s 7 seconds
- c. RCIC Steam Supply Line Pressure - Low
- e.
RCIC Equipment Room Ambient Temperature-High
- f. Main Steam Line Tunnel Ambient Temperature-High
- g. Main Steam Line Tunnel Temperature Timer 1.2(d),3(d) 1.2.3 1.2.3 1.2,3 1.2.3 1
2 1
1 1
F SR SR SR SR SR F
SR SR SR SR SR F
SR SR SR SR F
SR SR SR SR F
SR SR SR F
SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.6 3.3.6.1.7 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.6 3.3.6.1.7 3.3.6.1.1 3.3.6.1.2 3.3.6.1.5 3.3.6.1.7 3.3.6.1.1 3.3.6.1.2 3.3.6.1.5 3.3.6.1.7 3.3.6.1.2 3.3.6.1.4 3.3.6.1.7 3.3.6.1.1 3.3.6.1.2 3.3.6.1.5 3.3.6.1.7 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.6 3.3.6.1.7 2 53 psig I
s 20 psig 5 191-F s l91-F s 30 minutes
- h. RHR Equipment Room Ambient Temperature-High
- i. RCIC/RHR Steam Line Flow - High 1.2.3 1 per room 1.2.3 1
s 171-F s 43 inches water SR SR SR SR SR (continued)
(d)Not required to be OPERABLE in MODE 2 or 3 with reactor steam dome pressure less than 150 psig during reactor startup.
GRAND GULF 3.3-56 Amendment No. 42, 162
Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 5 of 5)
Primary Containment and Drywell Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS TRIP SYSTEM ACTION C.1 REQUIREMENTS VALUE
- 5. RHR System Isolation
- a. RHR Equipment Room 1,2,3 1 per room F
SR 3.3.6.1.1 s 171-F Ambient SR 3.3.6.1.2 Temperature-High SR 3.3.6.1.5 SR 3.3.6.1.7
- b. Reactor Vessel Water 1,2,3(")
2 F
SR 3.3.6.1.1 a 10.8 inchesi Level -Low, Level 3 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.7 3(9),4,5.
2(e)
- 10.8 inchesl SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.7
- c.
Reactor Steam Dome 1,2,3 2
F SR 3.3.6.1.1 s 150 psig Pressure-High SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.7
- d. Drywell Pressure-High 1,2,3 2
F SR 3.3.6.1.1 s 1.43 psig SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.7
- e. Manual Initiation 1,2,3 2
G SR 3.3.6.1.7 NA (e)
(f)
(g)
Only one trip system required in MODES 4 and 5 with RHR Shutdown Cooling System integrity I
maintained.
With reactor steam dome pressure greater than or equal to the RHR cut-in permissive pressure. I With reactor steam dome pressure less than the RHR cut-in permissive pressure.
I
.GRAND GULF 3.3 -58 Amendment No. 4.0, Th2