ML040120517

Technical Specifications Pages 3.3-48, 3.3-56 & 3.3-58, Changes to Primary Containment and Drywell Isolation Instrumentation Requirements

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

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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 1.2.3 I F SR 3.3.6.1.1 s 64 inches Flow-High SR 3.3.6.1.2 water SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.7

b. RCIC Steam Line Flow 1.2.3 I F SR 3.3.6.1.2 2 3 seconds and Time Delay SR 3.3.6.1.4 s 7 seconds SR 3.3.6.1.7

c. RCIC Steam Supply Line 1.2(d),3(d) 1 F SR 3.3.6.1.1 2 53 psig I Pressure - Low 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. RCIC Turbine Exhaust 1.2.3 2 F SR 3.3.6.1.1 s 20 psig Diaphragm SR 3.3.6.1.2 Pressure - High SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.7

e. RCIC Equipment Room 1.2.3 1 F SR 3.3.6.1.1 5 191-F Ambient SR 3.3.6.1.2 Temperature- High SR 3.3.6.1.5 SR 3.3.6.1.7

f. Main Steam Line Tunnel 1.2,3 1 F SR 3.3.6.1.1 s l91-F Ambient SR 3.3.6.1.2 Temperature- High SR 3.3.6.1.5 SR 3.3.6.1.7

g. Main Steam Line Tunnel 1.2.3 1 F SR 3.3.6.1.2 s 30 minutes Temperature Timer SR 3.3.6.1.4 SR 3.3.6.1.7

h. 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

i. RCIC/RHR Steam Line 1.2.3 1 SR 3.3.6.1.1 s 43 inches Flow - High SR 3.3.6.1.2 water SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.7 (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) J SR 3.3.6.1.1 - 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) Only one trip system required in MODES 4 and 5 with RHR Shutdown Cooling System integrity I maintained.

(f) With reactor steam dome pressure greater than or equal to the RHR cut-in permissive pressure. I (g) With reactor steam dome pressure less than the RHR cut-in permissive pressure. I

.GRAND GULF 3.3 -58 Amendment No. 4.0, Th2