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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1 TABLE 3.3.2-2 (Continued)

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3 o383 m:oe=J ' ISOLATION ACTUATION INSTRUMENTATION SETPOINTS'

>S i c= . ALLOWABLE RSij~ TRIP FUNCTION .

TRIP SETPOINT~ VAWE M4 5. REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION

" ;~* (Cont'C 04 E g. Main Steam Line Tunnel Ambient l8 ? % Temperature - High i 141*F 1 148.5'F mBE ' W .

{ *"3 h. Main-Steam Line Tunnel A Temperature - High i 61'F 1 5 57'F

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

j. RNR Equipment Room Ambient JUN O81988 Temperature - High. -< 117'F -< 121.1*F u SDC

j. k. RNR Equipment Room 4 a Temperature - High 1 2**F i 33.6*F

1. RHR/RCIC Steam Line Flow - High i 60.7" H2 - Delete 164.2" Hah

• 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

$ c. Reactor Vessel Water Level -..

. >,8.7 inches

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w P Low Level.3 > 9.7-inches

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- d. Reactor Vessel Water Level - . .

Low Low Low Level 1 g-147: inches -o g 1 - 143 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 -

c (Cont'd) z - e. - Reactor Vesseli(RHR Cut-.in .

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a Permissive) Pressure - High 5 135 psig g.150 psig~ ~ ~ ~ ~ =

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f. Drywell' Pressure - High 5 1.68 prig _.-$ 1.88 psig.

7. MANUAL INITIATION NA NA

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• Initial setpo nt. nal setpoint to be determined'during testing prior to operation- --

in the steam condensing mode following the Nuclear Regu?atory Commission's approval ~!

4 to operate in that: mode (Reference-license. Condition S.a to NPF-47).- Any required ' Delete- 1-w change to this setpoint shall be: submitted to the Commission within 90 days of test '

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) I

25. RHR Hx Flow to Suppression Pool MOV 1 1 (1E12*MOVF011A,8) *

-26. RHR' Reactor Head Spray MOV 1 NA i"

'(1E12*MOVF023) 1

27. RHR Test Line MOV 1- 1  !

E12*MOVF 4A, B '

iDelete - 28. HR x w to IC V 1 NA l

29. R o 1 .

(IE12*M0VF027A, 8)

30. RHR Upper Pool Cooling Shutoff MOV 1 1 4 (1E12*MOVF037A. 8)

, 31. RHR Injection MOV , 'l 2I *)

s (1E12*MOVF042A,-8, C)

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• 32.~ -RHR Hx Shell Side' Inlet MOV

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. (1E12*MOVF047A, 8). *

,.. 33. RHR Hx:Shell Side Bypass MOV 1 -

1 L (1E12*MOVF048A, 8)

34. .RHR Discharge to Radweste MOV 1 . NA

. Delete

35. R e 1 tion

• 1 *NOVF0_52A, 8) ,-

%A -- C RHR Injection MOV,

36. 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(,) 3g ,)

(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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