ML17290A899
| ML17290A899 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 01/06/1994 |
| From: | WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | |
| Shared Package | |
| ML17290A898 | List: |
| References | |
| NUDOCS 9401240275 | |
| Download: ML17290A899 (16) | |
Text
LIST OF AFFECTED PAGES
~Pa e Section cri ti n of Chan e
3/4 3-5 3/4 3-7 RPS Instrumentation RPS Instrumentation 3/4 3-1S Isolation Actuation Instrumentation Revised Notation (a)
Deleted channel check requirement Revised Notation (a) 3/4 3-28 ECCS Instrumentation 3/4 3-38 ATWS/RPT Instr.
3/4 3-43 EOC-RPT Instr.
3/4 3-48 RCIC Instrumentation Revised Notation (a)
Revised Notation (a)
Revised Notation (a)
Revised Notation (a) 9401240275 940i06 PDR ADOCK 05000397 P
PDR'
EkA E>
't
~ comRottFD cope 0 TABLE 3. 3.1-1 {Continued)
REACTOR PROTECTION SYSTEM INSTRUMENTATION TABLE NOTATIONS be laced in an inoperable status for s
or required surveil ance s stem in the tripped condition prov one OPERABLE channel 1n e
orang that parameter.
(b)
The "shorting links" shall be removed from the RPS circuitry prior to and during the time any control rod is withdrawn" and shutdown margin demonstrations are being performed per Specification 3.10.3.
(c)
An APRH channel is inoperable if there are less than 2 LPRM inputs per level or less than 14 LPRH inputs to an APRH channel.
(d)
This function shall be automatically bypassed when reactor mode switch is not in the Run position and reactor pressure
< 1037 psig.
(e)
This function is not required to be OPERABLE when the reactor pressure vessel head is removed per Specification 3.10.1.
)g,glS<
(f)
This function is not required to be OPERABLE when PRIHARY CONTAINMENT 6>~
INTEGRITY is not required.
gyak ~f fs (g)
Also actuates the standby gas treatment system.
(h)
With any control rod withdrawn.
Not applicable to control rods removed per Specification 3.9.10.1 or 3.9. 10.2.
(i)
This function shall be automatically bypassed when turbine first stage pressure is
< 165 psig, equivalent to THERMAL POWER less than 30K of RA ED THERMAL POWER.
(j)
Also actuates the EOC-RPT system.
"Not required for control rods removed per Specification 3.9.10.1 or 3.9. 10.2.
When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into the associated Limiting Conditions For Operation/Action Statement may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated function maintains RPS trip capability.
WASHINGTON NUCLEAR - UNIT 2 3/4 3-5 AMENDMENT NO. 90
TABLE 4.3.1.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREHENTS C) n m
Average Power Range Monitor a.
Neutron Flux
- Upscale, Setdown FUNCTIONAL UNIT l.
a.
Neutron Flux - High b.
Inoperative 2.
CHANNEL CHECK S/u(b),
S S/U(c),
W S
W N.A.
W N.A.
2 3, 4, 5
2, 3, 4, 5
S/U(b),
S S/U(c),
M S
M SA SA 2
3, 5
CHANNEL OPERATIONAL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH TEST CALIBRATION SURVEILLANCE RE UIRED d.
Inoperative N.A.
b.
Flow Biased Simulated Thermal Power - Upscale S,D(g) c.
Fixed Neutron Flux-Upscal e S/U(c),
g S/u(c),
q M(d), SA N.A.
1, 2, 3, 5
M(d)(e), PA, R(h) 1 C4a lD f+
O 3.
Reactor Vessel Steam Dome Pressure - High 4.
Reactor Vessel Water Level-Low, Level 3
5.
Hain Steam Line Isolation Valve - Closure 6.
DELETED 7.
Primary Containment Pressure - High nl,8.
N.A.
N.A.
1, 2
1 2
1 j 2
h
/
- .g tg
~
CONTROLLED COPY TABLE 3.3.2-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION ACTION STATEMENTS ACTION 22 ACTION 25 a
be placed in an inoperable status for up to 6 ho required surveil ance n
e tripped co-dition provided at r
ERABLE channe sn monltorin that arameter.
(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 RMCU-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.
'ACTION 20 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 SHUTDOMN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 21 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 hours2.777778e-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.
ACTION 23 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 />.
ACTION 24 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 SHUTDOMN 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 />.
ACTION 26 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.
goZ-8 S-i~o TABLE NOTATIONS y
BOX 0 g.ea v/cps
- Hay be bypassed with reactor steam pressure 037 psig and all turbine stop valves closed.
"*Mhen handling irradiated fuel in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
gDuring CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
MASHINGTON NUCLEAR - UNIT 2 3/4 3-15 Amendment No.
$8, 99, 112
In ert for a e
/4 3-15 (a)
When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into the associated Limiting Conditions For Operation/Action statement may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated function maintains the isolation capability.
TABLE 3.3.3-1 (Continued)
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION C
I TRIP FUNCTION C.
DIVISION 3 TRIP SYSTEM 1.
HPCS SYSTEM MINIMUM OPERABLE APPLICABLE CHANNELS PER OPERATIONAL TRIP SYSTEM a CONDITIONS ACTION CA I
CO as<<+
F,~,J.
C ao b.
C.
d.
e.f.
g.
2(b) 2(b) 2(c) 2(d) 2(d) 11/division MINIMUM TOTAL NO.
CHANNELS CHANNELS OF CHANNELS TO TRIP OPERABLE Reactor Vessel Water Level - Low, Low, Level 2
Drywell Pressure - High Reactor Vessel Water Level-High, Level 8 Condensate Storage Tanks Level-Low Suppression Pool Water Level-High HPCS System Flow Rate-Low (Minimum Flow)
Manual Initiation 3
4*
5*
1, 2, 3, 4*, 5*
APPLICABLE OPERATIONAL CONDITIONS 30 30 32 36 31 34 ACTTON LOSS OF POWER 1.
4.16 kV Emergency Bus Under-voltage (Loss of Voltage) 2/bus 2.
- 4. 16 kV Emergency Bus Under-voltage (Degraded Voltage 3/bus Division 1 and 2}
3.
- 4. 16 kV Emergency Bus Undervoltage (Degraded Voltage Division 3}
2/bus 2/bus TABLE NOTATIONS 1/bus 2/bus 2/bus 1, 2, 3, 4"+, 5""
37 2/bus 1, 2, 3, 4+*; 5++
38 2/bus 1, 2, 3, 4**, 5~
38 d 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 /> durin s urves 1 lance without placln e
ion rovided at least one ne an the same trip system is monitoring that parame er.
CL O
(b)
(c)
(d)
Also activates the associated division diesel generator.
Provides signal to close HPCS pump discharge valve only on 2-out-of-2 logic, Provides signal to HPCS pump suction valves only.
When the system is required to be OPERABLE per Specification 3.5.2 or 3.5.3.
Required when ESF equipment is required to be OPERABLE.
Not required to be OPERABLE when reactor steam dome pressure is less than or equal to 128 psig.
Inse f r a e 43-28 (a)
When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into the associated Limiting Conditions For Operation/Action statement may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated function or the redundant function maintains ECCS initiation capability.
TABLE 3.3.4.1-1 ASS RECIRCULATION PUMP TRIP SYSTEH INSTRUMENTATION TRIP FUNCTION Reactor Vesse1 Water Level-Low Low, Leve1 2
l.
2.
Reactor Vesse1 Pressure
- High HINIHUH OPERABLE CHANNELS PER TRIP SYSTEH a
'a)
I
~ c ne'I.
y h ac In a nn ah st~ns~nr+~2 hpttrspn r~ei~r s~vpyt~l Qr ded e o r c ne1 'P B
MnsNC'+
When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into the associated Limiting Conditions I:or Operation/Action Statement'may be delayed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> provided the associated function maintains I
ATWS-RPT trip capability.
0
- ~
I P
I
TABLE 3. 3.4.2-1 END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUHENTATION TRIP FUNCTION 1.
Turbine Throttle Valve - Closure 2.
Turbine Governor Valve - Fast Closure MINIMUM OPERABLE CHANNELS PER TRIP SYSTEM a 2(b) 2(b)
)A+ri yam m~abe~a~
i~an+nogera~e phd~ fdr~Ptf/tpup4 fear r~iPt pd s~ydfPf~ pd~g fh thy other trip system is OPERAM.'E.
(b)Thi Inction shall be automatically bypassed when turbine first stage pressure is less than or equal to 165 psig, equivalent to THERMAL POWER less than 30K of RATED THERMAL POWER.
rodin'e~ ~y
~Z-W3 -lao.
dd~d v/v/vz (a)
%hen a channel is placed in an inoperable status solely for performance of required Surveillances, entry into the associated Limiting Conditions For Operation/Action
~
Statement may be delayed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> provided the associated function maintains EOC-RPT trip capability.
FUNCTIONAL UNITS TABLE 3.3.5-1 REACTOR CORE ISOLATION COOLING SYSTEH ACTUATION INSTRUHENTATION HINIHUH OPERABLE CHANNELS PER TRIP SYSTEH a ACTION a.
Reactor Vessel Water Level - Low Low, Level 2
b.
Reactor Vessel Water Level - High, Level 8
c.
Condensate Storage Tank Mater Level Low Low d.
Hanual Initiation 2(b) 2(c) 1(d) 50 51 52 53 P'c ann m
b la d 'n
'p p
ci e tr p st ip am t p s te is tt n
th (b)
One trip system with two-out-of-two (c)
One trip system with one-out-of-two logic.
(d)
One trip system with one channel.
(a)
When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into the associated Limiting Conditions For Operation/Action Statement may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated function maintains RCIC initiation capability.
IJ d
I
,l I