ML20059B961

Proposed Tech Specs Re Isolation Actuation Instrumentation Setpoints & Remote Shutdown Sys Controls

ML20059B961
Person / Time
Site:	River Bend
Issue date:	08/22/1990
From:	GULF STATES UTILITIES CO.
To:
Shared Package
ML20059B951	List: ML20059B961 RBG-33430, Application to Amend to License NPF-47,revising Tech Spec Tables 3.3.7.4-2,Items 28 & 35 & 3.3.2-2,Item 5.1 Re Loading on Suppression Pool Wall from Possible Operation of Steam Condensing Mode of RHR Sys
References
NUDOCS 9008300191
Download: ML20059B961 (3)

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TABLE 3.3.2-2 (Continued)

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383

' ISOLATION ACTUATION INSTRUMENTATION SETPOINTS' m: =

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ALLOWABLE RSij~ TRIP FUNCTION TRIP SETPOINT~

VAWE M4 5.

REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION

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(Cont'C 04 E g.

Main Steam Line Tunnel Ambient l8 ? %

Temperature - High i 141*F 1 148.5'F mBE ' W

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Main-Steam Line Tunnel A Temperature - High 5 57'F i 61'F 1

1.

Main. Steam Line Tunnel Temperature Timer 0 seconds RECEIVEB NA j.

RNR Equipment Room Ambient JUN O81988 j.

SDC

-< 121.1*F Temperature - High.

-< 117'F u

k.

RNR Equipment Room 4

a Temperature - High 1 2**F i 33.6*F 164.2" Hah

• Delete 1.

RHR/RCIC Steam Line Flow - High i 60.7" H2

- Delete m.

Drywell Pressure - High 1 1.68 psig i 1.88 psig n.

Manual Initiation MA

'NA 6.

RHR SYSTEM ISOLATIO_N a.

RHR Equipmens Area Ambient Temperature - High i 117 F i 121.1*F' g

E b.

RHR Equipment Area a Temperature -

2 High

$ 29'F 1 33.6*F Reactor Vessel Water Level -..

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.,8.7 inches P

Low Level.3

> 9.7-inches

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Reactor Vessel Water Level -

Low Low Low Level 1 1 - 143 inches * ~

g-147: inches

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,w TABLE 3.3.2-2 (Continued)

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5

' ISOLATION' ACTUATION INSTRtMENTATION SETPOINTS

-ALLOWABLE h

TRIP' FUNCTION TRIP'SETPOINT

-VALUE 7

6.

RHR SYSTEM ISOLATION (Cont'd) c

- e.

- Reactor Vesseli(RHR Cut-.in 5 135 psig g.150 psig~ ~

z Permissive) Pressure - High

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Drywell' Pressure - High 5 1.68 prig

_.-$ 1.88 psig.

7.

MANUAL INITIATION NA NA

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F~ ure B 3/4 3-1

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• Initial setpo nt.

nal setpoint to be determined'during testing prior to operation-H in the steam condensing mode following the Nuclear Regu?atory Commission's approval

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4 to operate in that: mode (Reference-license. Condition S.a to NPF-47).- Any required

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change to this setpoint shall be: submitted to the Commission within 90 days of test w

completion.

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TA8LE 3.3.7.4-2 (Continued)

REMOTE SHUTOOWN SYSTEM CONTROLS MINIMUM CHANNELS OPERA 8LE E

RSP2 22.

RHR Shutdown Cooling MOV 2(*)

NA (1E12*MOVF006A, 68) 23.

RHR Outboard Shutdown Isolation MOV 1

NA (1E12*MOVF008) 24.

RHR Inboard Shutdown Isolation MOV 1

NA 1

(1E12*MOVF009) 25.

RHR Hx Flow to Suppression Pool MOV 1

1 (1E12*MOVF011A,8)

-26.

RHR' Reactor Head Spray MOV 1

NA i

'(1E12*MOVF023) 27.

RHR Test Line MOV 1-1 1

E12*MOVF 4A, B iDelete - 28.

HR x w to IC V

1 NA 29.

R o

1 (IE12*M0VF027A, 8) 30.

RHR Upper Pool Cooling Shutoff MOV 1

1 4

(1E12*MOVF037A. 8)

I2 *)

31.

RHR Injection MOV

'l s

(1E12*MOVF042A,-8, C)

I 32.~ -RHR Hx Shell Side' Inlet MOV 1

1 (1E12*MOVF047A, 8).

33.

RHR Hx:Shell Side Bypass MOV 1

1 L

(1E12*MOVF048A, 8)

34..RHR Discharge to Radweste MOV 1

. NA 35.

R e

1 tion

. Delete 1

• NOVF0_52A, 8)

%A -- C 36.

RHR Injection MOV, 1

1 p

(1E12*MOVF053A, 8) i l-37.

RHR Pump Minimum Flow MOV 1

2(,)

L (1E12*MOVF064A, S, C)

L 38.

RHR Hx Water Discharge MOV 1

1 p

(1E12*MOVF058A, 8) 39.. Safety Relief Valves 3(,)

3,)

g (1821*RVF051C, G, D) 40.

SSW Pump 1

.2(,)

(1SWP*P2A,.2C,g) 28, 20)'

l

- 41.

Normal Service Water Isolation MOV 1

l' (ISWP*MOV96A, 8) 42.

SSW Cooling Tower Inlet MOV 1

1 (1SWP*MOV55A, 8) 43.

SSW Component Cooling Water Inlet MOV 1

1 (ISWP*MOV510A, 8) g 44.

SSW Component Cooling Water Outlet MOV 1

1 b

(ISWP*MOV504A, 8) l (a) One per control equipment.

(b) SSW pump ISWP*P2C is provided on panel 1EGS*PNL4C.

, RIVER BEND - UNIT 1 3/4 3-79

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