ML17291A756
| ML17291A756 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 04/25/1995 |
| From: | WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | |
| Shared Package | |
| ML17291A754 | List: |
| References | |
| NUDOCS 9505030443 | |
| Download: ML17291A756 (9) | |
Text
Attachment 3 TECHNICALSPECIFICATION PAGES WITH PROPOSED CHANGES INDICATED 9505030443 950425 PDR ADOCK 05000397 j
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TABLE 3. 3. 2-1 (Continued)
ISOLATION ACTUATION INSTRUHENTATION 7
7 7(f)
VALVE GROUPS HINIHUH OPERATED BY OPERABLE CHANNELS TRIP FUNCTION
~PR I II 3.
REACTOR MATER CLEANUP SYSTEH ISOLATION a.
A ow -
g 1
b.
Heat Exchanger Area Temperature - High 7
1 c.
Heat Exchanger Area Ventilation h Temp.-
High 7
1 d.
Pump Area Temperature
- High 1)
Pump Room A 7
1 2)
Pump Room 8 7
1 e.
Pump Area Vent) lation h Temp. - High 1)
Pump Room A
1 2)
Pump Room B
1 f.
SLCS Initiation N.A.
g.
Reactor Vessel Hater Level - Low Low, Level 2
7 2
h.
RMCU/RCIC Line Routing Area Temperature - High 7
1 RWCU Line Routing Area Temperature - High Room 509 7
1 Room 511 7
1 Room 408 7
1 Room
$ 09 7
1 Hanual initiation 7
1/group k.
Blase Joutn Flout " Mich 7
l APPLICABLE OPERATIONAL CONDITION 1, 2, 3
1, 2, 3
1, 2, 3
1, 2, 3
1, 2, 3
1, 2, 3
1, 2, 3
1,2,3 1, 2, 3
1, 2, 3
1, 2, 3
1, 2, 3
1, 2, 3
/) 2i3 ACTION 22 22 22 22 22 22 22 22 22 22 22 22 22 22 24 2'7
ACTION 20 ACTION 21 ACTION 22 ACTION 23 ACTION 24 ACTION 25 ACTION 26 AC71od27-TABLE 3.3.2-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION ACTION STATEMENTS Be in at least HOT SHUTDOWN within,12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Be in at least STARTUP with the associated isolation valves closed within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />'.
Close the affected system isolation valves within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and declare the affected system inoperable.
Be in at least STARTUP within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Restore the manual initiation function to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or close the affected system isolation valves within the next hour and declare the affected system inoperable or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Establish SECONDARY CONTAINMENT INTEGRITY with the standby gas treatment system operating within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Lock close or close, as applicable, the affected system isolation valves within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and declare the affected system inoperable.
Q(osa. Vde PNEUM-V-92 wi6ini4our or ps~Ar~ ACTlNf22.
TABLE NOTATIONS "May be bypassed with reactor steam pressure
< 1037 psig and all turbine stop valves closed.
""When handling irradiated fuel in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
PDuring CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
(a)A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance without placing the trip system in the tripped con" dition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.
(b)Also actuates the standby gas treatment system.
(c)DELETED (d)A channel is OPERABLE if 2 of 4'etectors in that channel are OPERABLE.
(e)Also actuates secondary containment ventilation isolation dampers per Table 3.6.5.2-1.
(f)Closes only RWCU system outboard isolation valve RWCU-V-4.
(g)Only valves RHR-V-123A and RHR"V-123B in Valve Group 5 are required for primary isolation.
(h)Manual initiation isolates RCIC-V-8 only and only with a coincident reactor vessel level-low, level 3.
(i)Not required for RHR-V-8 when control is transferred to the alternate remote shutdown panel during operational conditions 1, 2
8 3 and the isolation interlocks are bypassed.
When RHR-V-8 control is transferred to the remote shutdown panel under operational modes 1, 2, and 3 the associated key lock switch will be locked with the valve in the -closed position.
Except RHR"V-8 can be returned to, and operated from, the control room, with the interlocks and automatic isolation capability reestablished in operational conditions 2
and 3 when reactor pressure is less than 135 psig.
WASHINGTON NUCLEAR - UNIT 2 3/4 3-15 Amendment No.
SH, N, ii2
o) 4
't
TRIP FUNCTION TABLE 3.3.2-2 (Continued)
ISOLATIOtt ACTUATION IHSTRUHENTATION SETPOINTS TRIP SETPOINT ALLOWABLE VALUE 3.
REACTOR WATER CLEANUP SYSTEH ISOLATIOtl a.
b.
A Flow - lligh lleat Exchanger Area Temperature - Iligh Heat Exchanger Area Ventilation h Temp. - Iligh Pump Area Temperature
- Iligh Pump Room A Pump Room B
Pump Area Ventilation A Temp.
lligh Pump Room A Pump Room 8 SLCS Initiation
< 58.5 gpm
< 150'F
< 60'F
<160F 160oF
<70F
<70F tl.A.
< 65.5 gpm
< 160 F
<70F
<180F
< 180 F
< 100F
< 100 F
tl.A.
h.
Reactor Vessel Mater Level-Low Low, Level 2
RWCU/RCIC Line Routing Area Temperature - lligh RWCU Line Rout.ing Area Temperature
- lligh Room 409 Room 511 Room 408 Room 409 j.
Hanual Initiation K.
Bfou)doe)u Clot@-Aiph 4.
REACTOR CORE ISOLATION COOLING SYSTEH
> -50 inches*
< 160 F
< 160F
< 160oF
< 160 F
160oF H.A.
4 264.5gp~
ISOLATIOH
> -57 inches
< 180'F
< 175'F
< 180 F
< 180 F
< 175'F N. A.
4 2'. 7 gp~
a.
b.
C.
d.
RCIC Steam Line Flow - High RIIR/RCIC Steam Line Flow - Iligh RCIC Steam Supply Pressure Low RCIC Turbine Exhaust Diaphragm Pressure
- Iligh RCIC Equipment Room Temperature - Iligh
< 290K of rated flow
< 101.5 inches ll20
> 62 psig
< 10.0 psig 60oF
< 300K of rated flow
< 107.5 inches II20
> 58 psig
< 20.0 psig
< 180 F
TABLE 4.3.2.1-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS CHANNEL TRIP FUNCTION CHECK 3.
REACTOR MATER CLEANUP SYSTEN ISOLATION a.
4 Flow'- High S
b.
Heat Exchanger Area Temperature - High N.A.
c.
Heat Exchanger Area Ventilation h Temperature-High N.A d.
Pump Area Temperature - High Pump Room A N.A Pump Room 8 N.A.
e.
Pump Area Ventilation h Temp. " High Pump Room A N.A.
Pump Room 8 N.A.
f.
SLCS Initiation N.A.
g.
Reactor Vessel Water Level-- Low Low, Level 2 N.A.
h.
fNCU/RCIC Line Routing Area Temperature - High N.A.
.i INCU Line Routing Area Temperature - High N.A.
j..
Manual Initiation N.A.
K..
'H[C ~doWRL HO~ High 4.
REACTOR CORE ISOLATIOA COOLING SYSTEM ISOLATION CHANNEL FUNCTIONAL TEST Q
SA SA R
1, 2, 3
20 2
3 1 ~ 2 j 1, 2, R
R N.A.
R R
N.A.
1,2,3 2
3 1, 2, 3 1, 2, 3
13ZT 3 OPERATIONAL CHANNEL CONDITIONS FOR NICH CALIBRATION SURVEILLANCE RE UIRED aO b.
Co d.
e.
RCIC'Steam Line Flow - High S
RCIC/RHR Steam Line Flow - High S
RCIC Steam Supply Pressure-Low-N.A.
RCIC Turbine Exhaust Diaphragm Pressule - High N.A.
=-
RCIC Equipment Room Temperature - High N.A.
RCIC Equipment Room h Temperature - High N.A.
SA 1, 2, 3
1, 2, 3
1, 2, 1, 2, 3
4
~ -4