ML20073D998
| ML20073D998 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 04/26/1991 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20073D996 | List: |
| References | |
| NUDOCS 9104300009 | |
| Download: ML20073D998 (2) | |
Text
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TABLE 4.3.1.1-1
'23 E
e_
Io REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS
~ r-j CHANNEL OPERATIONAL q.
@8 G;
oo c'-
CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH O
2 FUNCTIONAL UNIT CHECK TEST CALIBRATION (a) SURVEILLANCE REQUIRED W-Se N*
1.
a.
Neutron Flux - High S/U,5,ID)
S/U, W R
2 8S
@g7 5
W R
3, 4, 5 x~
b.
Inoperative NA W
NA 2,3,4,S II)
D 2.
Average Power Range Monitor:
a.
-Neutron Flux - High, S/U.S,g)
S/U, W SA 2
Setdown S
W SA 3, 5 b.
- Flow Biased Simulated i
II)
W(d)(e), SA, R 1
Thermal Power - High Sy Q
w L
fd) c.
Neutron Flux --High 5
Q W
, SA 1
d.
Inoperative NA Q
NA 1, 2, 3, S 3.
Reactor Vessel Steam Dome f9) 1, 2 fi)
Pressure - High S
Q R
4.
I9) 1, 2 Low, Level 3 S
Q R
k 5.
f9) 1 R
High, Level 8 S
Q R
3 6.
Main Steam Line Isolation Valve - Closure NA Q
R 1
2?
7.
Main Steam Line Radiation -
fd)
High S
Q R
1, 2 R(9) 1, 2(k) 8.
Drywell Pressure - High 5
Q
,-=,
TABLE 4.3.1.1-1 (Continued)
REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS c3
- g-23, 7-5 CHANNEL OPERATIONAL i
c3.
CHANNEL-FUNCTIONAL CHANNEL CONDITIONS FOR WHICH
'CL
((
FUNCTIONAL UNIT CHECK TEST CALIBRATION SURVEILLANCE REQUIRED
$5 a
9.
" Scram Discharge Volume Water 55 Level - High r2 a.
Transmitter / Trip Unit S
Q R(9)
II) 1, 2, S b.
Float Switch NA Q
R 1, 2, S II)
I9) 10.
Turbine Stop Valve - Closure S
Q R
1 11.
Turbine Control Valve Fast Closure Valve Trip System Oil Pressure - Low S
Q R(9) 1 12.
Reactor Mode Switch Shutdown Position NA R
NA 1,2,3,4,5 13.
Manual Scram NA W
hA 1,2,3,4,5 Y
co (a) Neutron detectors may be excluded from CHANNEL CALIBRATION.
(b) The IRM and SRM channels shall be determined to overlap for at least 1/2 decade during each startup af ter entering OPERATIONAL CONDITION 2 and the IRM and APRM channels shall be deter-mined to overlap for at least 1/2 decade during each controlled shutdown, if not performed within the previous 7 days.
(c) [ DELETED]
(d) This calibration shall consist of the adjustment of the APRM channel to conform to the power values calculated by a heat balance during OPERATIONAL CONDITION 1 when TilERMAL POWER > 25% of RATED D(dated THERMAL POWER.
Adjust the APRM channel if the absolute difference is greater than 2% of RATED THERMAL POWER.
sr (e)1 This calibration shall consist of the adjustment of the APRM flow biased channel to conform to a g
! calibrated flow signal.
gt (f)
The LPRMs shall be calibrated at least once per 1000 MWD /T using the TIP system.
g (g)
Calibrate trip unit at least once per 92 days.
(h)'-Vcrify acc;ured drive #1cu to bc !cc: ther er equal to c;teblished drive '?cw at the existir.g '?ct cer-if trel valvc pc;ition.
(i) This calibration shall consist of verifying the 6 1 second simulated thermal power time constant.
f}
(j) Not applicable when the reactor pressure vessel head is unbolted or removed per Specification 3.10.1.
j (k) Not applicable whe. DRYWELL INTEGRITY is not required.
1 (1) Applicable with any control rod withdrawn.
Not applicable to control rods removed per Specifica-tion 3.9.10.1 or 3.9.10.2.
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