ML17326B434
| ML17326B434 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/31/1988 |
| From: | INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | |
| Shared Package | |
| ML17326B433 | List: |
| References | |
| NUDOCS 8809070510 | |
| Download: ML17326B434 (7) | |
Text
TABLE 3.3-1 Continued+
DESIGNATION P-7 COVDITIOV A'.:D SETPOIVT With 2 of 4 Power Range Neutron Flux Channe ls greater than or equal to 11~ of RATED THER.'LAL POWER or 1 of
> ".urbane First S tage Pressure channels greater than or equal "o 37 psig.
FUNCTION P-7 prevents or defeats the automatic block of reactor trip on:
Low flow in more than one primary coolant loop, reactor coolant pump under-voltage and under-frequency, turbine trip, pressurizer low pressure, and pressurizer high level.
Low flow in a particular loop can be evidenced by either a detected low flow or by the opening of the reactor coolant pump breaker.
P-8 P-10 With 2 of 4 Power Range Neutron Flux channels greater than or equal to 31% of RATED THERMAL POWER.
With 3 of 4 Power Range Neutron Flux channels less than 9% of RATED THERMAL POWER.
P-8 prevents or defeats the automatic block of reactor trip caused by either a low coolant flow condition in a single loop or a reactor coolant pump breaker trip on a single loop.
P-10 prevents or defeats the manual block of:
Power range low setpoint reactor trip, Intermediate range reactor trip, and intermediate range rod StoPS.
Provides input to P-7.
D.
C.
COOK - UNIT 1 3/4 3-9 AMENDMENT NO.
8809070510 88083i PDR ADOCK 050003i5 P
PNU
TABLE 4.3-1 REACTOR TRIP SYSTE INSTR ENTATION SURVEILLANCE RE VIRENENTS nOO PC I
U CTIONAL V 1;
Manual Reactor Trip A. Shunt Trip Function B. Undervoltage Trip Function 2.
Power Range, Neutron Flux, CHANNEL CHANNEL MI-Tel CHANNEL FUNCTIONAL ST MODES IN MHICH SURVEILLANCF N.A.
N.A.
N.A.
N.A.
S/U(1) (10) 1', $,3*,4~,5*
S/U(l)(10) 1,2,3*,4*,5~
D(2,8),M(3,8)
M and S/U(l) 1, 2 and
- and Q(6,8) 3.
Power Range, Neutron Flux, High Positive Rate 4.
Power Range, Neutron Flux,
" High Negative Rate 5.
Intermediate
- Range, Neutron Flux N.A.
N.A.
R (6)
R (6)
R(6, 8)
S/U (1) 1, 2
1, 2
1, 2 and
- 6.
Source
- Range, Neutron Flux
'L 7.
Overtemperature hT 8.
Overpower hT 9.
Pressurizer Pressure Low
- 10. Pressurizer. Pressure High
- 11. Pressurizer Mater LevelHigh
- 12. Loss of Flow-Single Loop The provisions of Specification R(6, 14)
R(9)
R(9)
R+
R(8) 4.0.6 are applicable.
M( 14) and S/U (1)
M 2 ( I)
~
3 (7).
4 and 5
1, 2
1, 2
ls 2
1 1,
2
TABLE 3 3-Co t ued DESIGNATION CONDITION AND SETPO N
FUNCT ON P-7 With 2 of 4 Power Range Neutron Flux Channels 11% of RATED THERMAL POWER or 1 of 2 Pressure Before the First Stage channels
> 51 psig.
P-7 prevents or defeats the automatic block of reactor trip on:
Low flow in more.than one primary coolant loop, reactor coolant pum'p under-voltage and under-frequency, turbine trip, pressurizer low pressure, and pressurizer high level.
Low flow in a particular loop can be evidenced by either a
detected low flow or by the opening of the reactor coolant pump breaker.
P-8 P-10 With 2 of 4 Power Range Neutron Flux channels
> 31% of RATED THERMAL POWER.
With 3 of 4 Power Range Neutron Flux channels (
9% of RATED THERMAL POWER.
P-8 prevents or defeats the automatic block of reactor trip caused by either a low coolant flow condition in a single loop or a reactor coolant pump breaker trip on a single loop.
P-10 prevents or defeats the manual block of:
Power range low setpoint reactor trip, Intermediate range reactor trip, and intermediate range rod stops.
Provides input to P-7.
DE C.
COOK - UNIT 2 3/4 3-8 AMENDMENT NO.
~ ~
TAB 4
-1 Conti u d
~NOTAT10 With the reactor trip system breakers closed losed and the control rod drive system capable of rod withdrawal.
(1)
If not performed in previous 7 days.
(2)
Heat balance only, above 15% of RATED THERMAL POWER.
Adjust channel if absolute difference greater than 2 percent.
(3)
Compare incore to excore axial imbalance above 15% of RATED THERMAL POWER.
Recalibrate if absolute difference greater than or equal to 3 percent.
(4)
(5)
(6)
Manual ESF functional input check every 18 months.
Each train tested every other month.
Neutron detectors may be excluded from CHANNEL CALIBRATION.
(7)
Below P-6 (BLOCK OF SOURCE RANGE REACTOR TRIP) setpoint.
(S)
(9)
(10)
The provisions of Specification 4,0.4 are not applicable.
The provisions of Specification 4.0.4 are not applicable for f (AI) and f (~I) penalties.
(See also note 1 of Table 2,2-1) 1 2
The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip circuits for the Manual Reactor Trip Function.
The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit(s).
(11)
The CHANNEL FUNCTIONAL TEST shall independently verify the OPE1Vj3ILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.
(12)
Local manual shunt trip prior to placing breaker in service.
(13)
Automatic Undervoltage Trip.
(14)
The provisions of Specification 4.0.4 are not applicable when leaving MODE 1.
In such an event, the calibration and/or functional test shall be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after leaving MODE l.
D.
C.
COOK - UNIT 1 3/4 3-14 AMENDMENT NO.
TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS FUNCTIONAL UNIT 1.
Shunt Trip Function B.
Undervoltage Trip Function 2.
Power Range, Neutron Flux 3.
Power Range, Neutron Flux, High Positive Rate 4.
Power Range, Neutron Flux, High Negative Rate 5.
Intermediate
- Range, Neutron Flux 6 ~
Source
- Range, Neutron Flux CHANNEL CHECK N.A.
N.A.
N.A.
N.A.
CHANNEL CALIBRATION N.A.
N.A.
D(2,8),M(3,8) and Q(6,8)
R(6)
R(6)
R(6,8)
R(6,14)
CHANNEL FUNCTIONAL TEST S/U(1)(10)
S/U(1)(lo)
M and S/U(l)
S/U(l)
M(14) and S/U(1)
MODES IN WHICH SURVEILLANCE
~E(EUIRED
]
- 2. 3*, 4*, 5*
3*, 4*, 5*
1, 2 and
- 1, 2
1, 2
1, 2 and
- 2(>)
3(7) 4 and 5
7.
Overtemperature AT 8.
Overpower AT 9.
Pressurizer Pressure--Low
- 10. Pressurizer Pressure--High ll. Pressurizer Water Level--High 12.
Loss of Flow - Single Loop R(9)
R(9)
R(8) 1,-2 1,
2 1
2 1,
2
~
~
~
E g
I~
TABLE 4.3-1 Continued NOTATION (1)
(2)
(3)
With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.
If not performed in previous 7 days.
Heat balance only, above 15% of RATED THERMAL POWER.
Adjust channel if absolute difference
> 2 percent.
Compare incore to excore axial offset above 15% of RATED THERMAL POWER.
Recalibrate if absolute difference > 3 percent.
(4)
(5)
(6)
Manual ESF functional input check every 18 months.
Each train tested every other month.
Neutron detectors may be excluded from CHANNEL CALIBRATION.
(7)
Below P-6 (BLOCK OF SOURCE RANGE REACTOR TRIP) setpoint.
(8)
(9)
The provisions of Specification 4.0.4 are not applicable'.
The provisions of Specification 4.0.4 are not applicable for fl ( AI) and f2( A I) penalties.
(See also note 1 of Table 2.2-1)
(10)
The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip circuits for the Manual Reactor Trip Function.
The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit(s).
The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.
(12)-
(13)
(14)
Local manual shunt trip prior to placing breaker in service.
Automatic Undervoltage Trip.
The provisions of Specification 4.0.4 are not applicable when leaving MODE 1.
In such an event, the calibration and/or functional test shall be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after leaving MODE 1.
D.
C.
COOK - UNIT 2 3/4 3-13 Amendment No.