ML060170623

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Tech Spec Pages for Amendment 212 Revision of the Required Channels Per Trip System for Primary and Secondary Containment Isolation and Control Room Emergency Filter System Instrumentation
ML060170623
Person / Time
Site: Cooper Entergy icon.png
Issue date: 10/27/2005
From:
NRC/NRR/DLPM/LPD4
To:
Honcharik M, NRR/DLPM, 301-415-1774
Shared Package
ML053050418 List:
References
TAC MC5031
Download: ML060170623 (5)


Text

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

Primary Containment Isolaton Instrumentation APPLCABLE REQUIRED CONDITIONS MODES OR CiHiANELS REFERENCED SURVEILLANCE ALLOWABLE FUNCTION OTHER PERTRIP FROM REQUIREMENTS VALUE SPECIFIED SYTM REQUIRED CONDITIONS S

ACTION C.1

1.

Main Steam Urne IsolaUon

a.

Reactor Vessel Water Level -Low Low Low (Level 1)

b.

Main Steam Une Pressure - Low c

Main SteamLlne Fkw -

HIgh

d.

Condenser Vacuum-Low

e.

Main lSteam Tunnel Temperature - High

2.

Prlmary Containment Iso aton

a.

ReactorVesselWaler Level. Low (Level 3)

b.

Drywall Pressure - FUgh

c.

Reactor Building Ventilation Exhaust Plenum Radlation-High

d.

Main Steam Line Radiaton

-High

8.

Reactor Vassal Water Level

-Lew Low Low (Level 1) 1.2.3 t

123 1,

2(a). 3(a) 1.23 2

2 2 per MSL 2

2 per location 0

E D

0 D

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3..6.1.4 SR 3.3.6.1.6 SR 3.3.6.12 SR 3.3.6.1.3 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 3.3.6.12 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6

.113 Inches e835 psig 1 1445% rated steamflow

' 8 Inches Hg vacuum

< 195F 1.2.3 12.3 1,2,3 1,2,3 1,2,3 2

2 2

2 2

G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 G

SR 3.3.6.-.2 SR 3.3.6.1A SR 3.3.6.1.6 F

SR 3.3.6.1.1 SR 3.3.61.2 SR 3.3.6.1.4 SR 3.3.6.1.6 F

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.6 a 3Inches

! 1.84 pslg 5 49 rnRAhr Il 1 3 tImes hun power background

> -113 Inches F

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 (continued)

(a) WIth any turbIne stop valve not dosed.

Cooper 3.3-51 Amendment No. 212

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 SURVEILLANCE SPECIFIED PER TRIP REQUIRED REQUIREMENT ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 S

VALUE

3.

High Pressure Coolant Injection (HPCI) System Isolation

a.

HPCI Steam Line Flow - High

b.

HPCI Steam Line 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 Line 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 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 flow

<6 seconds

> 107 psig

< 195'F 1,2,3 1,2,3 1,2,3 1,2,3 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

< 288% rated steam flow

< 6 seconds 2 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 c 195'F

c.

SLC System Initiation

d.

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

2 H

SR 3.3.6.1.6 NA SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.4 151` 3.3.0.1.0

> - 42 inches I

Cooper 3.3-52 212 Amendment No.

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1.1 (page 3 of 3)

Primary Containment Isolation Instrumentallon APPLICABLE REQUIRED CONDITIONS MODES OR RNNELS REFERENCED RVElLANCE ALLOWAE FUNCTION OTHER PHNER S FQJROM SRELANE ALDL SPECIFIED PER TRIP REI FRED REQUIREMENTS VALUE CONDITIONS SYSTEM AC71ON C.1

6.

RHR Shutdlown Cooling System IsolaUon

a.

Reactor 1,2,3 1

F SR 3.3.6.1.2 72 psig Pressure-It1h SR 3.3.6.1.A SR 3.3.6.1.5

b.

ReactorVesselWater 3,4.5 2 1b)

I SR 3.3.6.1.1 3 Inches Levsl - Low (Level 3)

SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 I

(b)

Only one ip system Is requIred in MODES 4 and S when RHR Shutdown Cooling System Integrty maintained.

Cooper 3.3-53 Amendment No.

212

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.

Drywall 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 (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. 212

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. ReactorVessel 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. Drywall 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. 212