ML20211P695
| ML20211P695 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 02/19/1987 |
| From: | GULF STATES UTILITIES CO. |
| To: | |
| Shared Package | |
| ML20211P639 | List: |
| References | |
| NUDOCS 8703020417 | |
| Download: ML20211P695 (4) | |
Text
_ _ _ _ _ _.__ -_________ __
TABLE 4.3.1.1-1 i
l
- 5i REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS t
=
f CHANNEL OPERATIONAL R
E CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH FUNCTIONAL UNIT CHECK TEST CALIBRATION (a)
SURVEILLANCE REQUIRED 1.
l a.
Neutron Flux - High S/U.S,(b)
S/U(c),W R
2 S
W R
3,4,5 b.
Inoperative NA W
NA 2,3,4,5 II) 2.
Average Power Range Monitor:
j a.
Neutron Flux - High, S/U,5,(b)
S/U(C),W SA 2
i Setdown S
W SA 3,4,5 1
I
)
Thermal Power - High S,0(h) 3fg(c),y g(d)(e), 33(o)g(i)
I b.
Flow Blased Simulated w
7 4
c.
Neutron Flux - High 5
S/U
,W W(d), 3g 3
IC) d.
Inoperative NA W
NA 1,2,3,4,5
.1 I3) 3.
Reactor Vessel Steam Dome R(g)
- 1. 2 Pressure - High S
M 4.
I9) 1, 2 Low, Level 3 S
M R
5.
I9) 1 High, Level 8 S
M R
6.
Main Steam Line Isolation Valve.- Closure NA M
R 1
7.
Main Steam Line Radiation -
1,2(d)
High S
M R
IU) 1, 2 8.
Drywell Pressure - High S
M R
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TABLE 4.3.1.1-1 (Continued) h REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS I
E*
The LPRMs shall be calibrated at least once per 1000 effective full power hours (EFPH) g (f) using the TIP system.
Calibrate Rosemount trip unit setpoint at least once per 31 days.
(g)
Verify measured drive flow to be less than or equal to established drive flow at the existing flow h
(h) 1 control valve position.
This calibration shall consist of verifying the simulated thermal power time constant to be less i
-8 H
(1) than 6.6 seconds.
This function is not required to be OPERABLE when the reactor pressure vessel head is removed l
(j) per Specification 3.10.1.
(k) With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
(1) This function is not required to be OPERABLE when DRYWELL INTEGRITY is not required per Specification 3.10.1 j
(m) Verify the Turbine 8ypass Valves are closed when THERMAL POWER is greater than l
or equal to 40X RATED THERMAL POWER.
m
}
The CHAf00EL FUNCTIONAL TEST and CHANNEL CALIBRATION shall include the turbine (n) l l
4 first stage pressure instruments.
l (oS The CHANNEL CAtlBRATIOSJ 3 hall enJotje ne.[lw refereme 4runsm Her3 Oese.
S'O * "' Ne's shalf be calib ralegj ee4 (ca3+ ong,
p,, g g
__4 g,.
TABLE 4.3.6-1 CONTROL R00 BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS g
CHANNEL OPERATIONAL 55 CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH TRIP FUNCTION CHECK TEST CALIBRATION (,)
SURVEILLANCE REQUIRED E
1.
R00 PATTERN CONTROL SYSTEM II) a.
Low Power Setpoint S
S/
d)(e) 34 1, 2 II)
S/
b.
High Power Setpoint S
d)(e) gg#
y 2.
APRM l
a.
Flow Biased Neutron Flux -
Upscale NA S/U(b) g 34(y 7
b.
Inoperative NA S/U
,M NA 1,2,5 SA I
w S/U(b)',H
)
c.
Downscale NA S/U M
SA 2, 5 d.
Neutron Flux - Upscale, Startup NA w
h 3.
SOURCE RANGE MDNITORS b) W NA 2, 5 S/U(ID}'W I
a.
Detector not full in NA M
2, 5 S/U(b)*
b.
Upscale NA (5
c.
Inoperative NA S/U Downscale NA S/UID)',W SA 4.
INTERMEDIATE RANGE MDNITORS S/U((b) W NA 2, 5 I
a.
Detector not full in NA b),
SA 2, 5 b.
Upscale NA S/UID},W c.
Inoperative NA-S/U W
NA 2, 5 d.
Downscale NA S/UI ),W SA 2, 5 5.
SCRAM DISCNARGE VOLUME a.
Water Level-High NA M
R 1, 2, 5*
6.
REACTOR COOLANT SYSTEM RECIRCULATION FLOW l
a.
Upscale NA S/U(b) M SA 1
TABLE 4.3.6-1 (Continued)
CONTROL ROD 8 LOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS NOTES:
a.
Neutron detectors may be excluded from CHANNEL CALIBRATION.
b.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to startup, if not performed within the previous 7 days.
c.
Within one hour prior to control rod movement, unless performed within the preyious 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and as each power range above the RPCS low power setpoint is entered for the first time during any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period during power increase or decrease.
d.
At least once per 31 days while operation continues within a given power i
range above the RPCS low power setpoint.
e.
Includes reactor manual control multiplexing system input.
f.
Verify the Turbine Bypass valves are closed when THERMAL POWER is greater than 20% RATED THERMAL POWER.
I l
With any control rod withdrawn.
Not applicable to control rods removed 8
per Specification 3.9.10.1 or 3.9.10.2.
Calibrate trip unit setpoint once per 31 days.
S.
Th e.
CHANNEL call 8 EAT 10M shall excliade -Se -Ilow rekrence.
l fras=Hes. %csc basm#ers shall l:e. calarsfed at least once per IB monus.
i i
l RIVER BEND - UNIT 1 3/4 3-64
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