ML043630025

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Station,Technical Specification Pages Re Containment Isolation Logic Change for Reactor Vessel Water Level
ML043630025
Person / Time
Site: Cooper 
Issue date: 12/23/2004
From:
Office of Nuclear Reactor Regulation
To:
Honcharik M, NRR/DLPM, 301-415-1774
Shared Package
ML050050329 List:
References
TAC MC3320
Download: ML043630025 (3)


Text

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 2 of 3)

Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE

3.

High Pressure Coolant Injection (HPCI) System Isolation

a.

HPCI Steam Line Flow - High

b.

HPCI Steam Une Flow-Time Delay Relays

c.

HPCI Steam Supply Line Pressure - Low

d.

HPCI Steam Line Space Temperature - High

4.

Reactor Core Isolation Cooling (RCIC) System Isolation

a.

RCIC Steam Line Flow - High

b.

RCIC Steam Une Flow-Time Delay Relays

c.

RCIC Steam Supply Une Pressure - Low

d.

RCIC Steam Line Space Temperature - High

5.

Reactor Water Cleanup (RWCU) System Isolation

a.

RWCU Flow - High

b.

RWCU System Space Temperature - High 1.2,3 1,2,3 1.2,3 1.2,3 I

1 2

2 per location F

F F

F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6

< 250% rated steam now

<6 seconds

> 107 psig

< 195'F 1,2.3 1.2,3 1,2.3 1,2.3 1

1 2

2per location F

F F

F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6

< 288% rated steam flow

< 6 seconds

> 61 psig

< 195-F 1,2,3 1,2,3 1

2 per location F

F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6

<191% of Rated

< 195-F

c.

SLC System Initiation

d.

Reactor Vessel Water Level - Low Low (Level 2) 1,2 1,2,3 1

4 H

F SR 3.3.6.1.6 NA SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6

> - 42 inches Cooper 3.3-52 Amendment No. 178, 209

Secondary Containment Isolation Instrumentation 3.3.6.2 Table 3.3.6.2-1 (page 1 of 1)

Secondary Containment Isolation Instrumentation APPLICABLE MODES OR REQUIRED OTHER CHANNELS SPECIFIED PER SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS TRIP SYSTEM REQUIREMENTS VALUE

1. Reactor Vessel Water 1.2.3.

4 SR 3.3.6.2.1

>-42 inches Level - Low Low (Level 2)

(a)

SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.4

2.

Drywell Pressure - High 1.2.3 4

SR 3.3.6.2.2

< 1.84 psig SR 3.3.6.2.3 SR 3.3.6.2.4

3.

Reactor Building Ventilation 1.2,3, 4

SR 3.3.6.2.1

< 49 mR/hr Exhaust Plenum (a).(b)

SR 3.3.6.2.2 Radiation - High SR 3.3.6.2.3 SR 3.3.6.2.4 I

(a)

During operations with a potential for draining the reactor vessel.

(b)

During CORE ALTERATIONS and during movement of Irradiated fuel assemblies In secondary containment.

Cooper 3.3-57 Amendment No. +6-, 209

CREF System Instrumentation 3.3.7.1 Table 3.3.7.1-1 (page 1 of 1)

Control Room Emergency Filter System Instrumentation APPLICABLE MODES OR REQUIRED OTHER CHANNELS SPECIFIED PER TRIP SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM REQUIREMENTS VALUE

1. Reactor Vessel Water 1.2,3.

4 SR 3.3.7.1.1

> - 42 inches Level - Low Low (Level 2)

(a)

SR 3.3.7.1.2 SR 3.3.7.1.3 SR 3.3.7.1.4

2. Drywell Pressure - High 1,2.3 4

SR 3.3.7.1.2

< 1.84 psig SR 3.3.7.1.3 SR 3.3.7.1.4

3. Reactor Building Ventilation 1.2,3.

4 SR 3.3.7.1.1

< 49 mR/hr Exhaust Plenum (a).(b)

SR 3.3.7.1.2 Radiation - High SR 3.3.7.1.3 SR 3.3.7.1.4 I

(a)

During operations with a potential for draining the reactor vessel.

(b)

During CORE ALTERATIONS and during movement of irradiated fuel assemblies In the secondary containment.

Cooper 3.3-63 Amendment No. 48A, 209