ML17277B660
| ML17277B660 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 03/13/1985 |
| From: | WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | |
| Shared Package | |
| ML17277B659 | List: |
| References | |
| TAC-57260, NUDOCS 8503200386 | |
| Download: ML17277B660 (14) | |
Text
lH TRIP I
fUHCTIOH REACTOR WATER CLEANUP SYSTEN ISOLATION a.
A Flow - Nigh 1, 2, 3
TABLE 3.3.2-1 (Continued)
ISOLATIOH ACTUATIOH IHSTAUNENTATION VALVE GROUPS HIHIHUH APPLICABLE OPERATEO BY OPERABLE CllAHHELS OPERATIONAL ACT10N 22 b.
lleat Exchanger Area Temperature - lligh 7
c.
lleat Exchanger Area Ventilation 6 Temp.-
lligh 7
d.
Pump Area Terrrperature - lligh I)
Pump Room A 2)
Pump Room B
e.
Pump Area Ventilation h Temp. - Nigh 1)
Pump Room A 2)
Pump Room B
1 1, 2, 3
1, 2, 3
1, 2, 3
1, 2, 3
1, 2, 3
22 22 22 22 22 22 0'rr "PJHA wO0 mo OO IAlA mo mo HD OQ
,OC Gl
,m
~ Ofc rA@
m0.0 f.
SLCS Initiation 7(f) g.
Reactor Vessel Mater Level - Low Low, Level 2 7
h.
AMCU/ACIC Line Routing Area Temperature - lligh 7
i.
AMCU Line Routing Area Temperature - lligh j.
Hanual Initiation Veom 50 l goon Kl l i go~ 405 Roo~ 40q H. A.
1/group l
1, 2, 3
1, 2, 3
1, 2, 3
1, 2, 3
>g 2)E 22 22 22 24
'K2.
221 2K 22
I J.
N
TRIP FUNCTION TABLE 3. 3. 2-1 (Continued)
ISOLATION ACTUATIOtl INSTRUHENTATION VALVE GROUPS Hltill'IUH OPERATED BY OPERABLE CHANNELS APPLICABLE OPERATIONAL CONDITION ACTION 4.
REACTOR CORE ISOLATION CODLING SYSTEH ISOLATIOtl ae b.
C.
d.
e.
RCIC Steam Line Flow - High RCIC/RHR Steam Line Flow - High RCIC Steam Supply Pressure
- Low RCIC Turbine Exhaust Diaphragm
.Pressure
- High RCIC Equipment Room Temperature
- High RCIC Equipment Room d Temperature - High RWCU/RCIC Steam Line Routing Area Temperature - High Drywell Pressure - High Hanual Initiation(h) 8, 9
0 +P 1
8 f
1 1, 2, 3
1, 2, 3
1, 2, 3
1, 2, 3
1, 2, 3
1,2,3 1, 2, 3
22 22 22 22 22 22 22 22 24 5.
RIIR SYSTEH SHUTDOMtl COOLING RODE ISOLATIOtl a.
Reactor Vessel Water Level - Low, Level 3 6
b.
Reactor Vessel (RHR Cut-in
. Permissive)
Pressure
- High 6
c.
Equipment brea Temperature - High 6
d.
Equipment brea Ventilation d Temp. - High 6
e.
Shutdown Cooling Suction Flow Rate - tligh 6
f.
RHII I!eat Exchanger brea 6~X Teepere lure - Ill<ye 1, 2, 3
ls 2e 3
1, 2, 3
1, 2, 3
1, 2, 3
26 26 26 26 26 g.,
llanual Initiation Reeeee (o O (a Roe' aq Roem boS Roou SG5 6
Co 1/group I
I le 2, 3
I) 2)$
I) R)5 I)E 3 24 2(o 2'Q
PA ap
TRIP FUNCTION TABLE 3. 3. 2-2 ISOLATION AC1UATIOtl IHSTRUHENTATIOH SETPOIHTS TRIP SETPOINT ALLOMABLE VALUE 1.
PRIHARY COHTAItlMEHT ISOLATION b.
C.
e.
Reactor Vessel Mater Level 1)
Low, Level 3
2)
Low Low, Level 2
Drywell Pressure
- lligh Main Steam Line 1)
Radiation - lligh 2)
Pressure
- Low 3)
Flow - lllgh Hain Steam Line Tunnel Temperature - lligh Hain Steam Line Tunnel 6 Temperature - lligh Condenser Vacuum - Low g.
Hanual Initiation 2.
SECONDARY CONTAltNENT ISOLATION
> 13.0 inches*
> -50 inches*
< 1.68 psig
< 3.0 x full power background sig sid DELC~
< 150 F
N. A.
> 11.0 inches
> -57 inches
< 1.88 psig
< 3.6 x full power background
> 811 psig
< 108 psid
<+eeoIp 170 F
< ee p
lO'F
> 24.5 inches Ilg absolute pressure N.A.
b.
C.
Reactor Building Vent Exhaust Plenum Radiation lligh Drywell Pressure
- Nigh Reactor Vessel Mater Level - Low Low, Level 2
Manual Initiation 1%.0 w 'R/h
< 1.68 psig
> -50 inches" N.A.
.)Q.O ~RJ+
< 1.88 psig
> -57 inches N.A.
0r gJ
~
Zoo+ ~0'I g0nhn, Sll goo~ 409 Room 40$
0 P
~>toF
< lt O'
~ lI,DF f/'
c lPOoF
~ )QDF w +4g,, ~Q
<illF TRIP FUtlCTIOtI TAOI.E 3.3.2-2 (Contio<ied)
ISOLATION ACTUATION INSTRUMEtITATION SETPOINTS TRIP SETPOINT ALLOWABLE VALUE 3.
REACTOR MATER CLEAtIUP SYSTN ISOLATION
'a ~
C.
d.
h Flow - High lleat Exchanger Area Temperature - High Ileat Exchanger Area Ventilation A Temp. - High Pump Area Temperature
" High Pump Room A Pump Room 0 Puaip Area Ventilation I Temp.-
High Pump Room A Pump Room B
SLCS Initiation g.
Reactor Vessel Mater Level-Low Low, Level 2
h.
RMCU/RCIC Line Routing Area Temperature - tligh i.
AMCU Line Routing Area Temperature - High j.
Hanua Initiation
< 50.5 gpm
< ~~&0 F'(o0
+
< +3fPF M l60 F QO F g< <8<+
'70~ F Q
N.A.
< 65.5 gpm
< +88~ Ito0 F
<~~ao'F
< ~~ISD F
<~a~ ISO'F F
IOO tl.A.
4.
REACTOR CORE ISOLATION COOLING SYSTEH a.
ACIC Steam Line Flow - lllgh b.
AIIR/ACIC Steam Line Flow - High c.
RCIC Steam Supply Pressure
- Low d.
ACIC Turbine Exhaust Oiapt>ragm Pressure
- lligh e.
ACIC Equipment Room
~ ITemperature - High I y i,)
> -50 inches"
~140 I
N.A.
ISOI.ATION
< 290K of rated flow
< 101.5 inches He0
> 62 psig
< 10.0 psig ll o F
> -57 inches
<~ I Qo'F N.A.
< 300X of rated flow
< 107.5 inches Il>0
> 58 psig
< 20.0 psig lSG F I
P 1
/p'I
/~)
lg
'i l a
-I C3 I
C M
4J C
3W CO TABLE 3.3.2-2 (Continued)
.ISOLATIOH ACTUATION INSTRUMENTATION SETPOINTS TRIP FUNCTION TRIP SETPOIHT 4.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION (Continued) f.
RCIC Equipment Room A Temperature-lligh g.
RMCU/RCIC Steam Line Routing Area Temperature - High h.
Drywell Pressure
- High i.
Manual Initiation
< ~petteh ~ F
< 174 inches H 0~~><~'~~< ~
TABLE HOTATIOHS "See Bases Figure 0 3/4 3-1.
< ~~ltoo F
< 1<65 psig N.A.
5.
RHR SYSTEM SIIUTDOMH COOLING MODE ISOLATION a.
Reactor Vessel Mater Level-Low, Level 3
> l~tgches" b.
Reactor Vessel (RIIR Cut-in Permissive)
Pressure - High
< 125 psig~
c.
Equipment Area Temperature - High Pump Room A
< +38'9 Pump Room 0
< 33gstp l40'l=
p d.
Equipment Area Ventilat.ion h Temp. - Iligh
~~6 p Pump Room A Pump Room B
<~~~
I=
e.
Shutdown Cool ing Return Flow Rate-High f.
RHR Heat Exchanger Area
~ at'emperature
- Iligh g.
Manual Initiation H.A.
7 t
ALLOMABLE VALUE
< ~"40 ~
< ~~l~oF
< 1.85 psig N.A.
> 11.0 inches
< 135 psig
<+e~lSo F
< ~~ ISOF gtgl6 4k
< 183 inches lingu N.A.
ROOM 60(c3 QOOMt So'7 ROO bh ho~
Roose SOB 4%0 F
~ 15o'F m l40oF 30op
V t
J 1N
TRIP FUNCTION TABLE 3.3.2-3 (Continued)
ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME
RESPONSE
TIME Seconds 8
4.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION a.
b.
C.
d.
e.f.
g.
h.
1 ~
RCIC Steam Line Flow - High RHR/RCIC Steam Line Flow - High RCIC Steam Supply Pressure Low RCIC Turbine Exhaust Diaphragm Pressure - High RCIC Equipment Room Temperature - High RCIC Equipment Room h Temperature - High RHCU/RCIC Steam Line Routing Area Temperature - High Drywell Pressure
" High Manual Initiation
< 13(a)
< 13(a)
< 13(a)
N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
5.
ae b.
C.
d.
e.f.
g.
RHR SYSTEM SHUTDOlrlN COOLING MODE ISOLATION Reactor Vessel Hater Level - Low, 3
Reactor Vessel (RHR Cut-in Permissi Pressure
- High Equipment Area Temperature-Equipment Area Ventilation I
. " High Shutdown Coolin'g Return Fl te - High RHR Heat Exchanger Area erature - High Manual Initiation zeu*T~ > q%'
13(a)
N.A.
N.A.
N. A.
N.A.
N.A N.A.
'WASHINGTON NUCLEAR - UNIT 2 3/4 3-20
~
4 S
)
f
.V>
~,g I
TABLE 4. 3. 2. 1-1 (Continued)
ISOLATION 'ACTUATIOtl INSTRUMENTATIOtl SURVEILLANCE RE UIREHEtlTS TRIP FUNCTION OIANHEL CIIECK CHAIINEL F UNCTIOtlAL TEST CIIANHEL CALIBRATION OPERATIONAL CONDITIONS FOR MIIICH SURVEILLANCE RE UIRED n
Im 4.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION (Continued) g h.
RMCU/RCIC Steam Line Routing Area Temperature - High Drywell Pressure - High Manual Initiation N.A.
H.A.
H.A.
1,2,3 1,2,3 1, 2, 3
5.
RIIR SYSTEH SHUTOOMH COOLING MODE ISOLATI a.
Reactor Vessel Mater Level-Low Level 3
b.
Reactor Vessel (RHR Cut-in Permissive)
Pressure
- High N.A.
1 2.3 1, 2, 3
c.
Equipment Area Temperature-High d.
Equipment Area Ventilation h Temp. - High e.
Shutdown Cooling Return Flow Rate - High f.
RIIR Heat Exchanger Area
+~XTemperature - iiihh g.
Hanua I Initiat ion tl.A.
N.A.
TABLE NOTATIONS g
R N.A.
le2p 3
1, 2, 3
1, 2, 3 1,2,3 1, 2, 3
Mhen reactor steam pressure
> 1037 psig and/or any. turbine stop valve is open.
When handling irradiated fuel in the secondary containment and during CORE ALTERATIOHS and operations with a potential for draining the reactor vessel.
N During CORE ALTERATIOH and operations with a potential for draining the reactor vessel.
C
~
~
t4 J,
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