ML20203N186

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Proposed Tech Spec Changes,Revising Table 3.3.2-2, Isolation Actuation Instrumentation Setpoints, by Changing to Four Setpoints Instead of One
ML20203N186
Person / Time
Site: River Bend Entergy icon.png
Issue date: 09/12/1986
From:
GULF STATES UTILITIES CO.
To:
Shared Package
ML20203N175 List:
References
NUDOCS 8609230189
Download: ML20203N186 (4)
v • d • e


Text

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TABLE 3.3.2-2

= ISOLATION ACTUATION INSTRUMENTATION SETPOINTS E

E ALLOWABLE VALUE g TRIP FUNCTION TRIP SETPOINT E 1. PRIMARY' CONTAINMENT ISOLATION

[ a. Reactor Vessel Water Level -

>-47 inches l 5 Low Low, Level 2 >-43 inches

  • l H b. Drywell Pressure - High 1 1.68 psig 5 1.88 psig l

l

c. Containment Purge Isolation Radiation - High 5 1.3 R/hr 5 1.57 R/hr
2. MAIN STEAM LINE ISOLATION
a. Reactor Vessel Water Level -

Low Low Low, Level 1 >-143 inches *

>-147 inches

b. Main Steam Line Radiation - High -< 3.0 x full power background 5 3.6 x full power w background O
c. Main Steam Line Pressure - Low > 849 psig

> 837 psig

d. Main Steam Line Flow - High  ; 170 " y.;d i 17^** pid
e. Condenser Vacuum - Low > 8.5 inches Hg.

> 7.6 inches Hg.

vacuum vacuum

f. Main Steam Line Tunnel l Temperature - High 5 135*F 'i 142.5*F
g. Main Steam Line Tunnel A Temperature - High 5 51*F $ 55*F
1. l.ine, A 6 l% esid 6 151 esd IN5ERT U B d 156 MJ & I M P 9 d.
3. Line C 6 153 r*5d 6 158 P5id
4. Lin e. D 6 164 est 6 te9 es;d.

8609230189 860912 PDR ADOCK 05000458 P pgR

m -

- . , {

3 TABLE 3.3.2-2 (Continued) h ISOLATION ACTUATION INSTRUMENTATION SETPOINTS '

99 '

ALLOWA8LE a,

TRIP FUNCTION TRIP SETPOINT VALUE ,

52 l c' 4. REACTOR WATER CLEANUP SYSTEM ISOLATION (Cont'd) *

' d. Equipment Area a Temperature - High Si 1. Heat Exchanger Room 1 33*F 5 36.5'F Z 2. Pump Rooms A and B 5 78'F $ 82*F '

g 3. Valve Nest Room 5 46*F 1 49.5'F

4. Demineralizer Rooms 1 and 2 < 46*F < 49.5'F
5. Receiving Tank Roon 546*F 549.5*F f I
e. Reactor Vessel Water Level -

Low Low Level 2 1 - 43 inches

  • 1 - 47 inches
f. Main Steam Line Tunnel Ambient Temperature - High 5 135'F i 142.5'F u, g. Main Steam Line Tunnel

) A Temperature - High 5 51*F $ 55'F SLCS Initiation NA i'

ro

h. NA
5. REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION '
a. RCIC Steam Line Flow - High 5 Eggs' H 2 0M i 90er6" 135.g H0+ l 124
b. RCIC Steam Line Flow - High Timer 1 3 seconds 1 13 seconds
c. RCIC Steam Supply Pressure - Low 1 60 psig 1 55 psig
d. RCIC Turbine Exhaust Diaphragm Pressure - High 1 10 psig 5 20 psig
e. RCIC Equipment Room Ambient Temperature - High 5 182*F 5 186.4*F
f. RCIC Equipment Room A Temperature - 1 96*F i 99'F High

TABLE 3.3.2-2 (C:ntinued)

ISOLATION ACTUATION INSTRUMENTATION SETPOINTS h .

"m' ALLOWABLE TRIP SETPOINT VALUE h

o TRIP FUNCTION

5. REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION

' (Cont'd)

E g. Main Steam Line Tunnel Ambient '

q Temperature - High $ 135*F $ 142.5"F

h. Main Steam Line Tunnel A Temperature - High 5 51*F S 55'F

.l

i. Main Steam Line Tunnel Temperature Timer 0 seconds NA
j. RHR Equipment Room Ambient l Temperature - High $ 117'F $ 121.1*F I R

+ k. RHR Equipment Room l (p A Temperature - High 5 29'F 1 33.6*F 4

1. RHR/RCIC Steam Line Flow - High 5 156" H2 0** $ 164.5" H2 0**

i

m. Drywell Pressure - High 5 1.68 psig 5 1.88 psig
n. Manual Initiation NA NA
6. RHR SYSTEM ISOLATION

) a. RHR Equipment Area Ambient

! Temperature - High 5 117'F $ 121.1*F

b. RHR Equipment Area A Temperature -

High 5 29'F 1 33.6*F

c. Reactor Vessel Water Level -

Low Level 3 1 9.7 inches

  • 1 8.7 inches
d. Reactor Vessel Water Level -

Low Low Low Level 1 1 - 143 inches

  • 1 - 147 inches I

l . . - . .

j

-~, .-

p.

TABLE 3.3.2-2 (Continued) m 2 ISOLATION ACTUATION INSTRUMENTATION SETPOINTS i 9 co ALLOWABLE g TRIP FUNCTION TRIP SETPOINT VALUE -

. 6. RHR SYSTEM ISOLATION c- (Cont'd) 5

e. Reactor Vessel (RHR Cut-in Permissive) Pressure - High 5 135 psig 1 150 psig s
f. Drywell Pressure - High 5 1.68 psig 5 1.88 psig
7. MANUAL INITIATION NA NA
  • See Bases Figure B 3/4 3-1.

I R*

    • Initial setpoint. Tinal ::tp; int t; be detemin d durin; :terte; t::t pr:;r=. Any l required change to his setpoint shall be submitted to the Commission within 90 days V of test completion.

O Final setPoinh }o be dejerms' ned clur'ang -des 4thg prsor- 40 c9ercMen m he steam ccedeas.nq osede folln n9 %s i

Nuclear Regula4ory Conn.,s'an's appraal -la opera 4e. en 4hal mede- (Reference. Laien,e cond,4.6n 5.a. 4a NPF-47).

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