ML20212B669
| ML20212B669 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 07/31/1986 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20212B660 | List: |
| References | |
| NUDOCS 8608070191 | |
| Download: ML20212B669 (3) | |
Text
__
TA8LE 3.3-2 (Continued) 9
~
Y REACTOR TRIP SYSTEN INSTRUMENTATION RESPONSE TIMES 5
i RESPONSE TINE FUNCTIONAL UNIT E
i y
12.
Low Reactor Coolant flow
< 1 second a.
Single Loop (Above P-8)
~E I second b.
Two Loops (Above P-7 and below P-8)
- 4. Linik 1..
4 3.5 eandS 5
13.
Steam Generator Water Level-Low-Low b, 0.ctib 2
... - * ~ ~ 2.0 seconds y
14.
Undervoltage-Reactor Coolant Pumps 5 1.5 seconds 15.
Underfrequency-Reactor Coolant Pumps 5 0.6 second j
l 16.
a.1 Control Valve EH Pressure - Low (Unit 1)
N.A.
N.A.
t' a.2 Stop Valve EH Pressure - Low (Unit 2)
N.A.
J b.
Turbine Stop Valve Closure l
T N.A.
l-17.
Safety Injection input from ESF 1
N.A.
18.
Reactor Trip System Interlocks i
N.A.
19.
Reactor Trip Breakers N.A.
j 20.
Automatic Trip and Interlock Logic i
i 8608070191 860731 PDR ADOCK 05000413 l
P PDR l
1 1
1
TABLE 4.3-1 (Continued)
KACTOR TRIP SYSTEN INSTRUMENTATION SullVEILLANCE KQUIREMENTS
-4 h
TRIP ANALOG.
ACTUATING Im0ES FOR e
CHANNEL DEVICE WICH E
CHAIRIEI CHAISIEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE e
U FUNCTICIIAL UNIT CECK CAlleRAT TEST TEST LOGIC TEST IS REQUIKO
^
/
o-13.
Steam Generator Water Level-S R (G)
M N.A.
N.A.
1, 2 m
Low-Low
'. A.
M N.A.
1 N
- 14. Undervoltage - Reactor Coolant N.A.
R Pumps
- 15. Underfrequency - Reactor N.A.
R N. 4.
M N.A.
1 Coolant Pumps y
16.
.1 Control Valve EN N.A.
R N.A.
S/U(1,10)
N.A.
If Y
Pressure - Low (Unit 1)
U a.2 Stop Valve EN Pressure N.A.
R N.A.
S/U(1,10)
N.A.
If
- Low (Unit 2) l b.
Turbine Stop Valve Closure N.A.
R N.A.
5/U(1,10)
N.A.
If l
i l
17.
Safety Injection Input from N.A.
N.A.
N.A.
R**
N.A.
1, 2 j
ESF 1
i
- 18. Reactor Trip System Interlocks i
a.
Intermediate Range l
fleutron Flux, P-6 N.A.
R(4)
M M.A.
M.A.
2ff i
I b.
Low Power Reactor l
Trips Block, P-7 N.A.
R(4)
M(8)
N.A.
N. A!'
1 c.
Power Range Neutron Flux, P-8 N.A.
R(4)
M(8)
N.A.
M.A.
I d.
Low Power Range fleutron Flux, P-9 N.A.
R(4)
M(8)
N.A.
N.A.
1
- 1his surveillance need not be performed until prior to entering STARTUP following the Unit I first refueling.
TABLE 4.3-1 (continued)
TABLE NOTATIONS Only if the Reactor Trip System breakers happen to be closed and the Control Rod Drive System is capable of rod withdrawal.
Above P-9 (Reactor Trip on Turbine Trip Interlock) Setpoint.
Below P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.
- Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.
(1)
If not performed in previous 7 days.
(2) Comparison of calorimetric to excore power indication above 15% of RATED THERMAL POWER.
Adjust excore channel gains consistent with calorimetric power if absolute difference is greater than 2%.
The provisions c,f Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
(3) Single point comparison of incore to excore axial flux difference above 15% of RATED THERMAL POWER.
Recalibrate if the absolute difference is greater than or equal to 3%.
The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
(4) Neutron detectors may be excluded from CHANNEL CALIBRATION.
(5) Detector plateau curves shall be obtained, evaluated and compared to manufacturer's data.
For the Intermediate Range and Power Range Neutron Flux channels the provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
(6)
Incore - Excore Calibration, above 75% of RATED THERMAL POWER.
The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
(7) Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.
(8) With power greater than or equal to the interlock setpoint the required ANALOG CHANNEL OPERATIONAL TEST shall consist of verifying that the interlock is in the required state by observing the permissive status I
light.
(9) Monthly surveillance in MODES 3*, 4*, and 5* shall also include verifi-cation that permissives P-6 and P-10 are in their required state for l
existing plant conditions by observation of the permissive status light.
Monthly surveillance shall include verification of the Baron Dilution Alarm Setpoint of less than or equal to one-half decade (square root of 10) t I
above background.
l (10) Setpoint verification it not applicable.
(11) At least once per 18 months and following maintenance or adjustment of the Reactor trip breakers, the TRIP ACTUATING DEVICE OPERATIONAL TEST shall include independent verification of the Undervoltage and Shunt trips.
(12) CHANNEL CALIBRATION shall include the RTD bypass loops flow rate.
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