ML052510061

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Tech Spec Pages for Amendment Nos. 304 and 294, Turbine Trip in Reactor Trip System Instrumentation
ML052510061
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 09/02/2005
From:
NRC/NRR/DLPM
To:
Pickett D, NRR/DLPM, 415-1364
Shared Package
ML052520073 List:
References
TAC MC6879, TAC MC6880
Download: ML052510061 (10)


Text

TABLE 3. 3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION TOTAL NO.

OF CHANNELS CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE APPLICABLE MODES FUNCTIONAL UNIT ACTION

12.

Loss of Flow - Single Loop (Above P-8) 31loop 2/loop in any operating loop 2/loop in each operating loop 1

6

13.

Loss of Flow - Two Loops (Above P-7 and below P-8)

14.

Main Steam Generator Water Level-Low-Low 3/loop 2/loop in two operating loops 21loop in each operating loop 1

6 A.

Steam Generator Water Level-Low-Low (Adverse)

B. Steam Generator Water Level-Low-Low (EAM) 3/Stm. Gen.

3/Stm. Gen.

2/Stm. Gen.

in any operating Stm. Gen 2/Stm. Gen.

in any operating Stm. Gen.

2/Stm. Gen.

in each Operating Stm. Gen.

2/Stm. Gen.

in each operating Stm. Gen.

1,2 1,2 9

9 C. RCS Loop AT D. Containment Pressure (EAM)

15.

Deleted

16.

Undervoltage-Reactor Coolant Pumps

17.

Underfrequency-Reactor Coolant Pumps

18.

Turbine Trip A.

Low Fluid Oil Pressure B. Turbine Stop Valve Closure 4 (I/loop) 2 3

1,2 1,2 10 11 4

2 3

4-1/bus 4-1/bus 2

2 3

3 1

6 1

6 3

4 2

4 2

4 I

  • I **

61 7

1 SEQUOYAH - UNIT I 314 3-3 Amendment No. 141, 301,304

TABLE 3.3-1 (Continued)

TABLE NOTATION With the reactor trip system breakers In the closed position, the control rod drive system capable of rod withdrawal, and fuel in the reactor vessel.

    • Above the P-9 (Power Range Neutron Flux) interlock.
  1. Source Range outputs may be disabled above the P-6 (Block of Source Range Reactor Trip) setpoint.

ACTION STATEMENTS I

ACTION 1 ACTION 2 With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the reactor trip breakers.

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and POWER OPERATION may proceed provided the following conditions are satisfied:

a.

The Inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1.1.

c.

The QUADRANT POWER TILT RATIO is monitored in accordance with Technical Specification 3.2.4.

SEQUOYAH - UNIT 1 3/4 3-5 Amendment Nos. 47, 135,136, 141, 213, 301, 304

TABLE 3.3-1 (Continued)

ACTION 3-With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a.

Below the P-6 (Block of Source Range Reactor Trip) setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint.

b.

Above the P-6 (Block of Source Range Reactor Trip) setpoint, but below 5% of RATED THERMAL POWER, restore the Inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 5% of RATED THERMAL POWER.

c.

Above 5% of RATED THERMAL POWER, POWER OPERATION may continue.

d.

Above 10% of RATED THERMAL POWER, the provisions of Specification 3.0.3 are not applicable.

ACTION 4-With the number of OPERABLE channels one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a.

Below the P-6 (Block of Source Range Reactor Trip) setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint.

b.

Above the P-6 (Block of Source Range Reactor Trip) setpoint, operation may continue.

ACTION 5-ACTION 6 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a.

The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1.1.

ACTION 7-With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP andlor POWER OPERATION may proceed provided the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or THERMAL POWER is reduced to less than P-9 within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

SEQUOYAH - UNIT 1 3/4 3-6 Amendment No. 47, 141, 304

TABLE 4.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS MODES IN CHANNEL WHICH CHANNEL CHANNEL.

FUNCTIONAL.

SURVEILLANCE FUNCTIONAL UNIT

15.

Deleted

16.

Undervoltage - Reactor Coolant Pumps

17.

Underfrequency - Reactor Coolant Pumps

18.

Turbine Trip A.

Low Fluid Oil Pressure B. Turbine Stop Valve Closure

19.

Safety Injection Input from ESF CHECK CALIBRATION TEST IS REQUIRED 20.

Reactor Trip Breaker

21.

Automatic Trip Logic

22.

Reactor Trip System Interlocks A.

Intermediate Range Neutron Flux, P-6 B.

Power Range Neutron Flux, P-7 C. Power Range Neutron Flux, P-8 D. Power Range Neutron Flux, P-1 0 E. Turbine Impulse Chamber Pressure, P-13 F.

Power Range Neutron Flux, P-9 G.

Reactor Trip, P4

23.

Reactor Trip Bypass Breaker NA.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

NA.

NA.

NA.

N.A.

N A.

NA.

N.A.

N.A.

R R

N.A.

N.A.

N.A.

N.A.

N.A.

R N.A.

R R

R R

N.A.

N.A.

Q Q

S/U(1)

S/U(1)

R M(5) and S/U(1)

M(5)

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

R M(1 0)R(1 1) 1 **

1**

1,2 1

I 1, 2, and

  • 1, 2, and
  • 2, and
  • I 1

1, 2 1

1, 2, and

  • 1, 2, and
  • I I

SEQUOYAH - UNIT 1 3/4 3-12 Amendment No. 54, 63,141, 304

TABLE 4.3-1 (Continued)

NOTATION With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.

Above the P-9 (Power Range Neutron Flux) interlock.

(1)

If not performed In previous 31 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 FLUX DIFFERENCE above 15% of RATED THERMAL POWER. Recalibrate if the absolute difference greater than or equal to 3 percent. The frequency of this surveillance is every 31 EFPD. This surveillance is not required to be performed until 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after thermal power is > 15% RTP.

(4)

Deleted.

(5)

Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS. The test shall independently verify the OPERABILITY of the undervoltage and automatic shunt trip circuits.

(6)

Neutron detectors may be excluded from CHANNEL CALIBRATION.

(7)

Below P-6 (Block of Source Range Reactor Trip) setpoint.

(8)

Deleted.

(9)

The CHANNEL FUNCTIONAL TEST shall Independently verify the operability of the undervoltage and shunt trip circuits for the manual reactor trip function.

(10)

Local manual shunt trip prior to placing breaker in service. Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(11)

Automatic and manual undervoltage trip.

SEQUOYAH - UNIT 1 314 3-13 Amendment No. 54,114,141, 199, 304

TABLE 3.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION FUNCTIONAL UNIT

16.

Undervoltage-Reactor Coolant Pumps

17.

Underfrequency-Reactor Coolant Pumps

18.

Turbine Trip A.

Low Fluid Oil Pressure B. Turbine Stop Valve Closure

19.

Safety Injection Input from ESF

20.

Reactor Trip Breakers A. Startup and Power Operation TOTAL NO.

OF CHANNELS 4-1/bus 4-1 (bus 3

4 2

2 CHANNELS TO TRIP 2

2 2

4 1

1 MINIMUM CHANNELS OPERABLE 3

3 2

4 2

2 APPLICABLE MODES 1

1**

1**

1,2 1', 2 ACTION 6

6 6

7 I

I 12 12, 15 Shutdown

21.

Automatic Trip Logic A. Startup and Power Operation B. Shutdown

22.

Reactor Trip System Interlocks A. Intermediate Range Neutron Flux, P-6 B. Power Range Neutron Flux, P-7 2

2 2

2 4

I 1

2 2

2 2

2 3

3*,4* and 5*

1, 2 3*,4* and 5*

2, and*

1 16 12 16 8a 8b SEQUOYAH - UNIT 2 3/4 3-3a Amendment No. 46, 48, 132, 290,294

TABLE 3.3-1 (Continued)

TABLE NOTATION With the reactor trip system breakers in the closed position, the control rod drive system capable of rod withdrawal, and fuel in the reactor vessel.

    • Above the P-9 (Power Range Neutron Flux) Interlock.

Source Range outputs may be disabled above the P-6 (Block of Source Range Reactor Trip) setpoint.

ACTION STATEMENTS I

ACTION I ACTION 2 With the number of OPERABLE channels one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be In HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the reactor trip breakers.

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a.

The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b.

The Minimum Channels OPERABLE requirement Is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1.1.

c.

The QUADRANT POWER TILT RATIO is monitored in accordance with Technical Specification 3.2.4.

SEQUOYAH - UNIT 2 314 3-5 Amendment No. 39, 122, 129, 132, 203, 290,294

TABLE 3.3-1 (Continued)

ACTION 3 With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a.

Below the P-6 (Block of Source Range Reactor Trip) setpoint, restore the Inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint.

b.

Above the P-6 (Block of Source Range Reactor Trip) setpoint, but below 5% of RATED THERMAL POWER, restore the Inoperable channel to OPERABLE status prior to Increasing THERMAL POWER above 5% of RATED THERMAL POWER.

c.

Above 5% of RATED THERMAL POWER, POWER OPERATION may continue.

d.

Above 10% of RATED THERMAL POWER, the provisions of Specification 3.0.3 are not applicable.

ACTION 4 With the number of OPERABLE channels one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a.

Below the P-6 (Block of Source Range Reactor Trip) setpoint, restore the Inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint.

b.

Above the P-6 (Block of Source Range Reactor Trip) setpoint, operation may continue.

ACTION 5 ACTION 6 With the number of OPERABLE channels one less than required by the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a.

The inoperable channel Is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1.1.

ACTION 7 With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or THERMAL POWER is reduced to less than P-9 within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

SEQUOYAH - UNIT 2 3/4 3-6 Amendment No. 39,132,294

TABLE 4.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES FOR CHANNEL CHANNEL.

FUNCTIONAL.

WHICH FUNCTIONAL UNIT

15.

Deleted

16.

Undervoltage - Reactor Coolant Pumps

17.

Underfrequency - Reactor Coolant Pumps

18.

Turbine Trip A.

Low Fluid Oil Pressure B.

Turbine Stop Valve Closure

19.

Safety Injection Input from ESF

20.

Reactor Trip Breaker

21.

Automatic Trip Logic

22.

Reactor Trip System Interlocks A.

Intermediate Range Neutron Flux, P-6 B.

Power Range Neutron Flux, P-7 C.

Power Range Neutron Flux, P-8 D.

Power Range Neutron Flux, P-1 0 E. Turbine Impulse Chamber Pressure, P-13 F.

Power Range Neutron Flux, P-9 G.

Reactor Trip, P-4

23.

Reactor Trip Bypass Breaker SEQUOYAH - UNIT 2 CHECK CALIBRATION TEST SURVEILLANCE IS REQUIRED N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

NA.

N.A.

N.A.

N.A.

N.A.

N. A.

R R

NA.

N.A.

N.A.

N.A.

N.A.

R N.A.

R R

R R

N..

N.A.

3/4 3-12 Q

Q 1

1 S/U(1)

S/U(1)

R M(5) and S/U(1)

M(5) 1**

1**

1, 2 1,2, and

  • 1, 2, and
  • I N.A.

2, and' N.A.

1 N.A.

1 N.A.

1,2 N.A.

1 N.A.

1 R

1,2,and*

M(1 0)R(11) 1, 2, and

  • Amendment Nos. 16, 46, 55, 132, 294

Table 4.3-1 (Continued)

NOTATION With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.

Above the P-9 (Power Range Neutron Flux) interlock.

(1)

If not performed in previous 31 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 FLUX DIFFERENCE above 15% of RATED THERMAL POWER. Recalibrate if the absolute difference greater than or equal to 3 percent. The frequency of this surveillance Is every 31 EFPD. This surveillance is not required to be performed until 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after thermal power is > 15% RTP.

(4)

Deleted.

(5)

Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS. The test shall independently verify the OPERABILITY of the undervoltage and automatic shunt trip circuits.

(6)

Neutron detectors may be excluded from CHANNEL CALIBRATION.

(7)

Below P-6 (Block of Source Range Reactor Trip) setpoint.

(8)

Deleted.

(9)

The CHANNEL FUNCTIONAL TEST shall independently verify the operability of the undervoltage and shunt trip circuits for the manual reactor trip function.

(10)

Local manual shunt trip prior to placing breaker in service. Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(11)

Automatic and manual undervoltage trip.

SEQUOYAH - UNIT 2 3/4 3-13 Amendment No. 46, 104, 132, 190,294