ML020790012
ML020790012 | |
Person / Time | |
---|---|
Site: | South Texas ![]() |
Issue date: | 03/19/2002 |
From: | NRC/NRR/DLPM |
To: | |
References | |
TAC MB2138, TAC MB2139 | |
Download: ML020790012 (23) | |
Text
TABLE 3.3-1 (Continued)
REACTOR TRIP SYSTEM INSTRUMENTATION H MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE Cf FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION
- 13. Reactor Coolant Flow--Low
- a. Single Loop (Above P-8) 3/loop 2/loop in any 2/loop in each I 6 operating loop operating loop
- b. Two Loops (Above P-7 and 3/loop 2/loop in two 2/loop each I 6 below P-8) operating loops operating loop
- 14. Steam Generator Water 4/stm. gen. 2/stm. gen. in 3/stm. gen. 1,2 6 Level--Low-Low any operating each operating stm. gen. stm. gen.
- 15. Undervoltage--Reactor Coolant 4-I/bus 2 3 6 I
Pumps (Interlocked with P-7)
- 16. Underfrequency--Reactor 4-1/bus 2 3 6 I
Coolant Pumps (Interlocked with P-7)
- 17. Turbine Trip (Interlocked with P-9)
- a. Low Emergency Trip Fluid 3 2 2 I I I 6 Pressure
- b. Turbine Stop Valve Closure 4 2 3 00 1 6 zz 00 r\)c.)
(no',
TABLE 3.3-1 (Continued)
REACTOR TRIP SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE H> OPERABLE MODES FUNCTIONAL UNIT OF CHANNELS TO TRIP ACTION
!T
(:/ 18. Safety Injection Input from 1,,-, ESFAS 2 2 1,2 9A H-
- 19. Reactor Trip System Interlocks
- a. Intermediate Range Neutron Flux, P-6 2 I 2 8
- b. Low Power Reactor Trips Block, P-7 P-10 Input 4 2 3 8 1
or P-13 Input 2 I 2 8
- c. Power Range Neutron Flux, P-8 4 3 8
- d. Power Range Neutron 4 3 8 Flux, P-9 2
- e. Power Range Neutron 2 C 0 4 3 1,2 8 Flux, P-10
- f. Turbine Impulse Chamber Pressure, P-13 2 1 2 1 8 2 I 2 1,2 9,12
- 20. Reactor Trip Breakers 2 1 2 3*, 4*, 5* 10 oPp i.. .i .,
TABLE 3.3-1 (Continued)
REACTOR TRIP SYSTEM INSTRUMENTATION
(.0 (0
0 MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION
- 21. Automatic Trip and Interlock 2 1 2 1,2 9A Logic 2 2 3*, 4*, 5* 10
,.0 tU 4:*
0 CD z z N"1)
U1o.M
TABLE 3.3-1 (Continued*
TABLE NOTATIONS
- When the Reactor Trip System breakers are in the closed position and the Control Rod Drive System is capable of rod withdrawal.
- Below the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.
- Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.
ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels one less than 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 />.
ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP andlor POWER OPERATION may proceed provided the following conditions are satisfied:
- a. For Functional Units with installed bypass test capability, Note: A channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing per Specification 4.3. 1. 1. provided no more than one channel is in bypass at any time.
I. The inoperable channel may be placed in bypass, and must be placed in the tripped condition within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. and
- 2. Either, THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER and the Power Range Neutron Flux Trip Setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per Specification 4.2.4.2.
- b. For Functional Units with no installed bypass test capability,
- 1. The inoperable channel is placed in the tripped condition within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and
- 2. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1, and
- 3. Either, THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER and the Power Range Neutron Flux Trip Setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per Specification 4.2.4.2.
3/4 3-6 Unit 1 - Amendment No. 136 SOUTH TEXAS - UNITS 1 & 2 Unit 2 - Amendment No. 125
TABLE 3.3-1 (Continued)
ACTION STATEMENTS (Continued)
ACTION 3 - With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:
- a. Below the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint, and
- b. Above the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint but below 10% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 10% of RATED THERMAL POWER.
ACTION 4 With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, suspend all operations involving positive reactivity changes. Limited plant cooldown or boron dilution is allowed provided the change is accounted for in the calculated SHUTDOWN MARGIN.
ACTION 5 With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, suspend all operations involving positive reactivity changes. Plant temperature changes or boron dilution is allowed provided the change is accounted for in the calculated SHUTDOWN MARGIN.
ACTION 6 - 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. For Functional Units with installed bypass test capability, the inoperable channel may be placed in bypass, and must be placed in the tripped condition within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Note: A channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing per Specification 4.3.1.1, provided no more than one channel is in bypass at any time.
- b. For Functional Units with no installed bypass test capability,
- 1. The inoperable channel is placed in the tripped condition within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and
- 2. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1.
SOUTH TEXAS - UNITS 1 & 2 3/4 3-7 Unit I - Amendment No. 136 Unit 2 - Amendment No. 125
TABLE 3.3-1 (Continued)
ACTION STATEMENTS (Continued)
ACTION 7 (Not Used)
ACTION 8 With less than the Minimum Number of Channels OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> determine by observation of the associated permissive annunciator window(s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.
ACTION 9 With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERABLE.
ACTION 9A With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or be in at least 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 />; however, one 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 per Specification 4.3.1.1, provided the other channel is OPERABLE.
ACTION 10 - With the number of OPERABLE channels one less than 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 open the Reactor Trip System breakers within the next hour.
ACTION 11 - (Not Used)
ACTION 12- With one of the diverse trip features (undervoltage or shunt trip attachment) inoperable, restore it 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 declare the breaker inoperable and apply ACTION 9. The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status.
SOUTH TEXAS - UNITS 1 & 2 3/43-8 Unit 1 - Amendment No. 136 Unit 2 - Amendment No. 125
0 H TABLE 4.3-1 7ri REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS TRIP ANALOG ACTUATING MODES FOR CHANNEL DEVICE WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTJUATION SURVEILLANCE CHECK CALIBRATION TEST (19) TEST LOGIC TEST IS REQUIRED FUNCTIONAL UNIT I. Manual Reactor Trip N.A. N.A. N.A R (14) N.A. 1, 2, 3Y, 4*, 5'
- 2. Power Range, Neutron Flux S D(2, 4), Q(17) N.A. N.A. 1,2
- a. High Setpoint M(3, 4),
Q(4, 6),
R(4, 5)
S R(4) S/u (I) N.A. N.A. 1***, 2
- b. Low Setpoint N.A. R(4) Q(17) N.A. N.A. 1,2
- 3. Power Range, Neutron Flux, High Positive Rate
- 4. Deleted
- 5. Intermediate Range, Neutron S R(4, 5) S/U (I) N.A. N.A. 1***, 2 Flux
- 6. Source Range, Neutron Flux S R(4, 5) S/u (1),
Q(9) (17) N.A. N.A. 2"*, 3, 4, 5 S R(4) Q(12,17) N.A. N,A. 3,4,5
- 7. Extended Range, Neutron Flux R Q(17) N.A. N.A. 1,2 I I
- 8. Overtemperature AT S S R Q(17) N.A. N.A. 1,2
- 9. Overpower AT Q (17) N.A. N.A. 1
- 10. Pressurizer Pressure--Low S R zz" 00.
_j
TABLE 4.3-1 (Continued)
REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS t1 TRIP ANALOG ACTUATING MODES FOR CHANNEL DEVICE WI-HICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE TEST (19) TEST LOGIC TEST IS REQUIRED)
FUNCTIONAL UNIT CHECK CALIBRATION (A
- 11. Pressurizer Pressure
--High S R Q(17) N.A. N.A. 1,2
- 12. Pressurizer Water Level
--High S R Q(17) N.A. N.A. 1
- 13. Reactor Coolant Flow S R N.A.
--Low Q(17, 18) N.A.
- 14. Steam Generator Water R Q(17, 18) N.A. N.A.
Level--Low-Low S 1,2
- 15. Undervoltage - Reactor N.A. R N.A. Q(17) N.A.
Coolant Pumps
- 16. Underfrequency - Reactor N.A. R N.A. Q(17) N.A.
Coolant Pumps
- 17. Turbine Trip
- a. Low Emergency Trip N.A. R N.A. S/U(1, 10) N.A.
Fluid Pressure N.A. R N.A. S/U(l, 10) N.A.
- b. Turbine Stop Valve Closure i 0 N.A. N.A. N.A. 1,2
- 18. Safety Injection Input N.A. R from ESFAS o
0 0 I-... I.-.
1-* 1-
TABLE 4.3-1 (Continued) 0 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS TRIP ACTUATING MODES ANALOG DEVICE WHICH FOR tr. CHANNEL OPERATIONAL SURVEILLANCE OPERATIONAL ACTUATION CHANNEL CHANNEL TEST LOGIC TEST IS REQUIRED CHECK CALIBRATION TEST (19)
FUNCTIONAL UNIT
- 19. Reactor Trip System Interlocks tQ
- a. Intermediate Range Neutron Flux, P-6 N.A. R(4) R N.A. N.A. 2**
- b. Low Power Reactor R N.A. N.A.
N.A. R(4)
Trips Block, P-7
- c. Power Range Neutron R N.A. N.A.
N.A. R(4)
Flux, P-8
- d. Power Range Neutron R N.A. N.A.
N.A. R(4)
Flux, P-9
- e. Power Range Neutron R N.A. N.A. 1,2 N.A. R(4)
Flux, P-10
- f. Turbine Impulse Chamber N.A.
N.A. R R N.A. 1 Pressure, P-13 N.A. Q(7, 11) N.A.
N.A. N.A. 1, 2, 3*, 4*, 5*
- 20. Reactor Trip Breaker N.A. N.A. N.A. Q(7)
N.A. 1, 2, 3* 4*, 5*
- 21. Automatic Trip and Interlock Logic I I N.A. Q(15), R(16) N.A. 1, 2, 3", 4*, 5*
N.A.
- 22. Reactor Trip Bypass Breaker N.A.
Ct.-D zz 00
TABLE 4.3-1 (Continued)
TABLE NOTATIONS (Continued)
(10) Setpoint verification is not applicable.
(11) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.
(12) OPERABILITY shall be verified by a check of memory devices, input accuracies. Boron Dilution Alarm setpoints, output values, and software functions.
(13) (Not used)
(14) The TRIP ACTUATING DEVICE OPERATIONAL 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).
(15) Local manual shunt trip prior to placing breaker in service.
(16) Automatic undervoltage trip.
(17) Each channel shall be tested at least every 92 days on a STAGGERED TEST BASIS.
(18) The surveillance frequency and/or MODES specified for these channels in Table 4.3-2 are more restrictive and, therefore, applicable.
(19) For channels with bypass test instrumentation, input relays are tested on an 18-month (R) frequency.
SOUTH TEXAS - UNITS 1 & 2 3/4 3-15 Unit I - Amendment No. 37,46, 136 Unit 2 - Amendment No. 29,-56, 1125
TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION H
MINIMUM TOTAL NO. CHANNELS Cl IANNELS APPLICABLE 3 OF CHANNELS TO TRIP OPERABLE MODES ACTION FUNCTIONAL UNIT
,.I1
- 1. Safety Injection (Reactor Trip, Feedwater Isolation, Control Room Emergency Ventilation, t,, Start Standby Diesel Generators, Reactor Containment Fan Coolers, and Essential Cooling Water).
- a. Manual Initiation 2 2 1,2,3,4 19 I
- b. Automatic Actuation Logic 2 2 1,2,3,4 14 W
40 1,2,3,4 14
- c. Actuation Relays 3 2 3 00
- d. Containment Pressure- 3 2 2 1,2,34 20 High-I
- e. Pressurizer Pressure--Low 4 1,2, 3# 20
- f. Compensated Steam Line 3/steam line 2/steam line 2/steam line 1,2, 3# 20 Pressure-Low any steam line in each steam line 0° Z 0 0-..
N)
Cn,
TABLE 3.3-3 (Continued) 0 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION
-H MINIMUM H TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 3.d. RCP Seal Injection Isolation (Continued)
- 2) Charging Header 1 I I 1,2,3,4 16 Pressure - Low Coincident with Phase See item 3.a. above for Phase "A" Isolation initiating functions and requirements "A" Isolation
- 4. Steam Line Isolation
- a. Manual Initiation
- 1) Individual 2/steam line 1/steam line 2/operating 1,2,3 24 steam line
- 2) System 2 1 2 1,2,3 23 2 1 2 1,2,3 22
- b. Automatic Actuation Logic and Actuation Relays
- c. Steam Line Pressure 3/steam line 2/steam line 2/ steam line 20 Negative Rate--High any steam line in each steam line I I d. Containment Pressure 3 2 2 1,2,3 20 High-2
- e. Compensated Steam Line 3/steam line 2/steam line 2/steam line 1, 2, 3# 20 oCt Pressure - Low any steam line in each steam 00t' line Tz 0_.a -.
TABLE 3.3-3 (Continued)
TABLE NOTATIONS
- Function is actuated by either actuation train A or actuation train B.
Actuation train C is not used for this function.
"****Automaticswitchover to containment sump is accomplished for each train using the corresponding RWST level transmitter.
- Trip function may be blocked in this MODE below the P-II (Pressurizer Pressure Interlock)
Setpoint.
- During CORE ALTERATIONS or movement of irradiated fuel within containment.
- Trip function automatically blocked above P-11 and may be blocked below P-I l when Low Compensated Steamline Pressure Protection is not blocked.
ACTION STATEMENTS ACTION 14- With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or be in at least 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 in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; however, one 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 per Specification 4.3.2.1, provided the other channel is OPERABLE.
ACTION 15- (Not Used)
ACTION 16 - With the Charging Header Pressure channel inoperable:
a) Place the Charging Header Pressure channel in the tripped condition within one hour and b) Restore the Charging Header Pressure channel to operable status within 7 days or be in at least 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 in Cold Shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
ACTION 17 With the number of OPERABLE channels one less than the Total Number of Channels, place the inoperable channel in the bypassed condition within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or be in at least 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 in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. One additional channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing per Specification 4.3.2.1.
ACTION 18- With less than the Minimum Channels OPERABLE requirement, operation may continue provided the containment purge supply and exhaust valves are maintained closed.
Unit 1 - Amendment No.
SOUTH TEXAS - UNITS 1 & 2 3/4 3-26 Unit 1 - Amendment No. 4-4, 136 4125 Unit 2 - Amendment No.
TABLE 3.3-3 (Continued)
ACTION STATEMENTS (Continued)
ACTION 19 With the number of OPERABLE channels one less than 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 at least 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 in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
ACTION 20 - 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. For Functional Units with installed bypass test capability, the inoperable channel may be placed in bypass, and must be placed in the tripped condition within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Note: A channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing per Specification 4.3.2.1. provided no more than one channel is in bypass at any time.
- b. For Functional Units with no installed bypass test capability,
- 1. The inoperable channel is placed in the tripped condition within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and
- 2. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels per Specification 4.3.2.1.
ACTION 21 With less than the Minimum Number of Channels OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> determine by observation of the associated permissive annunciator window(s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.
ACTION 22 With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or be in at least 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 in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one 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 per Specification 4.3.2.1 provided the other channel is OPERABLE.
ACTION 23 - With the number of OPERABLE channels one less than the Total Number of Channels, 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 at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
136 SOUTH TEXAS - UNITS 1 & 2 3/4 3-27 Unit 22 -- Amendment Unit No. 44,'25125 Amendment No.
TABLE 3.3-3 (Continued)
ACTION STATEMENTS (Continued)
ACTION 24 With the number of OPERABLE channels one less than the Total Number of Channels, 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 declare the associated valve inoperable and take the ACTION required by Specification 3.7.1.5.
ACTION 25 With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or be in at least 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 />; however, one 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 per Specification 4.3.2.1 provided the other channel is OPERABLE.
ACTION 26 With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, declare the affected Auxiliary Feedwater Pump inoperable and take ACTION required by Specification 3.7.1.2.
ACTION 27 For an inoperable channel, declare its associated ventilation train inoperable and apply the actions of Specification 3.7.7.
ACTION 28 With the number of OPERABLE channels less than the Minimum Channels OPERABLE requirement, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain operation of the Control Room Makeup and Cleanup Filtration System (at 100% capacity) in the recirculation and makeup filtration mode.
ACTION 29 For an inoperable channel, declare its associated ventilation train inoperable and apply the actions of Specification 3.7.8.
ACTION 30- With irradiated fuel in the spent fuel pool: With the number of OPERABLE channels less than the Minimum Channels OPERABLE requirement, fuel movement within the spent fuel pool or crane operation with loads over the spent fuel pool may proceed provided the FHB exhaust air filtration system is in operation and discharging through at least one train of HEPA filters and charcoal adsorbers.
SOUTH TEXAS - UNITS 1 & 2 3/4 3-28 Unit 1 - Amendment No. 1-2-5, 136 Unit 2 - Amendment No. -00, 113,125
W TABLE 4.3-2 0
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION
, SURVEILLANCE REQUIREMENTS H DIGITAL OR TRIP ANALOG ACTUATING MODES DEVICE WHICH FOR k) CHANNEL MASTER SLAVE OPERATIONAL OPERATIONAL RELAY RELAY SURVEILLANCE CHANNEL CHANNEL CHANNEL. ACTUATION TEST LOGIC TEST TEST TEST IS REQUIRED FUNCTIONAL UNIT CHECK CALIBRATION TEST (7)
- 1. Safety Injection (Reactor Trip, Feedwater Isolation, Control Room Emergency Ventilation, Start Standby Diesel Generators, Reactor Containment Fan Coolers, and Essential Cooling Water)
- a. Manual Initiation N.A. N.A. N.A. R NA, N.A. N.A. 1,2,3,4 N.A. N.A. Q(I) N.A. N.A. 1,2,3,4
- b. Automatic Actuation N.A. N.A.
Logic N.A. N.A. N.A. N.A. Q(6)
- c. Actuation Relays N.A. Q(4,5) 1,2,3,4 R N.A. N.A. N.A. N.A. 1,2,3,4
- d. Containment Pressure S Q High- I N.A. N.A. N.A. N.A.
- e. Pressurizer Pressure S R Q 1,2,3 Low N.A. N.A. N.A. N.A. 1,2,3
- f. Compensated Steam Line S R Q Pressure-Low I I
- zz:
0 o i....
I,.r Io'.
TABLE 4.3-2 (Continued) 0 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS H
1-Il DIGITAL OR TRIP ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR WlIICI I CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE CHANNEL CHECK CALIBRATION TEST (7) TEST LOGIC TEST TEST TEST IS REQUIRED FUNCTIONAL UNIT
- 2. Containment Spray N.A. N.A. N.A. 1,2,3,4
- a. Manual Initiation N.A. N.A. N.A. R N.A. N.A. N.A. N.A. Q(1) N.A. N.A. 1,2,3,4
- b. Automatic Actuation Logic N.A. N.A. N.A. N.A. N.A. Q(6) Q 1,2,3,4
- c. Actuation Relays S R Q N.A. N.A. N.A. N.A. 1,2,3
- d. Containment Pressure High-3
- 3. Containment Isolation
- a. Phase "A" Isolation N.A. N.A. N.A. R N.A. N.A. N.A. 1,2,3,4
- 1) Manual Initiation N.A. N.A. N.A. N.A. Q(I) N.A. N.A. 1,2,3,4
- 2) Automatic Actuation Logic N.A. N.A. N.A. N.A. N.A. Q(6) Q(4) 1,2,3,4
- 3) Actuation Relays
,- 4) Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.
- b. Containment Ventilation Isolation Q(I) N.A. N.A. 1,2,3,4 zz 1) Automatic Actuation N.A. N.A. N.A. N.A.
Logic N.A. N.A. N.A. N.A. N.A. Q(6) Q 1,2,3,4
- 2) Actuation Relays I-. j.
(no.3
I .
TABLE 4.3-2 (Continued) 0 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS Ut DIGITAL OR TRIP ANALOG ACTUATING MODES CHANNEL DEVICE M ASTER SLAVE FOR WHICH CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE cj FUNCTIONAL UNIT CHECK CALIBRATION TEST (7) TEST LOGIC TEST TEST TEST IS REQUIRED
- 3. Containment Isolation (Continued)
- 3) Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.
- 4) RCB Purge S R Q N.A. N.A. N.A. N.A. 1,2,3,4,5*, 6*
Radioactivity-High
- 5) Containment Spray See Item 2. above for Containment Spray manual initiation Surveillance Requirements.
Manual Initiation
- 6) Phase "A" Isolation See Item 3. a. above for Phase "A" Isolation manual initiation Surveillance Requirements.
Manual Initiation
- c. Phase "B" Isolation
- 1) Automatic Actuation N.A. N.A. N.A. N.A. Q(I) N.A. N.A. 1,2,3,4 Logic
- 2) Actuation Relays N.A. N.A. N.A. N.A. N.A. Q(6) Q 1,2,3,4
- 3) Containment S R Q N.A. N.A. N.A. N.A. 1,2,3 Pressure--High-3
- 4) Containment Spray See Item 2. above for .Containment Spray manual initiation Surveillance Requirements.
Manual Initiation
-1"
- d. RCP Seal Injection Isolation
- 1) Automatic Actuation N.A. N.A. N.A. N.A. N.A. Q Q 1,2,3,4 Logic and Actuation Relays
- 2) Charging Header S R Q N.A. N.A. N.A. N A. 1,2,3,4 0'
Pressure - Low z*
0 o Coincident with See Item 3.a. above for Phase "A"surveillance requirements.
Phase "A" Isolation IN) W..
-, M..
TABLE 4.3-2 (Continued) zn ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 0
©n SURVEILLANCE REQUIREMENTS DIGITAL OR TRIP ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR WHICH CHANNEL CHANNEL CHANNEL OPERATIONAL. OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST (7) TEST LOGIC TEST TEST TEST IS REQUIREDI
- 4. Steam Line Isolation
- a. Manual Initiation N.A. N.A. N.A. R N.A. N.A. N.A. 1,2,3
- b. Automatic Actuation N.A. N.A. N.A. N.A. Q(I) Q(6) Q 1,2,3 Logic and Actuation Relays
- c. Steam Line Pressure S R Q N.A. N.A. N.A. N.A. 3 Negative Rate-High
- d. Containment Pressure S R Q N.A. N.A. N.A. N.A. 1,2.3 High-2
- e. Compensated Steam Line S R Q N.A. N.A. N.A. N.A. 1,2,3 Pressure-Low
- 5. Turbine Trip and Feedwater Isolation
- a. Automatic Actuation N.A. N.A. N.A. N.A. Q(I) Q(6) Q(4) 1,2,3 Logic and Actuation Relays
- b. Steam Generator Water S R Q N.A. N.A. N.A. N.A. 1,2,3 Level-High-High (P-14)
- c. Deleted
( n zz d. Deleted 00o e. Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.
W TABLE 4.3-2 (Continued) 0 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS DIGITAL OR TRIP ANALOG ACTUATING MODES CHANNEL: DEVICE MASTER SLAVE FOR WHICH C/) CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY REILAY SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST (7) TEST LOGIC TEST TEST TEST IS REOUIREI)
- 5. Turbine Trip and Feedwater Isolation (Continued)
- f. Tavg -Low Coincident S R Q N.A. N.A. N.A. N.A. 1,2,3 with Reactor Trip (P-4)
(Feedwater Isolation Only)
- a. Manual Initiation N.A. N.A. N.A. R N.A. N.A. N.A. 1,2,3
- b. Automatic Actuation N.A. N.A. N.A. N.A. Q(M) N.A. N.A. 1,2,3 Logic
- c. Actuation Relays N.A. N.A. N.A. N.A. N.A. Q(6) Q 1,2,3
- d. Steam Generator Water S R Q N.A. N.A. N.A. N.A 1,2,3 Level--Low-Low
- e. Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.
f, Loss of Power See Item 8. below for all Loss of Power Surveillance Requirements.
- 7. Automatic Switchover to L
Containment Sump 71 z,. z a. Automatic Actuation N.A. N.A. N.A. N.A. Q(6) Q(6) Q 1,2,3,4 0 0 Logic and Actuation Relays
- b. RWST Level--Low-Low S R Q N.A. N.A. N.A. N.A. 1,2,3,4 Coincident With:
Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.
I-...
0 TABLE 4.3-2 (Continued)
.),
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION t-I SURVEILLANCE REQUIREMENTS DIGITAL OR TRIP C,-)
ANAL.OG ACTUATING MODES CHANNEL. DEVICE MASTER SItVE FOR WtIICI I CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE FUNCTIONAL UNIT CttECK CALIBRATION TEST (7) TEST LOGIC TEST TEST TEST IJS REQUIRED
- 8. Loss of Power
- b. 4.16 kV ESF Bus N.A. R N.A. Q N.A. N.A. N.A. 1,2,3,4 Undervoltage (Tolerable Degraded Voltage Coincident with SI)
- 9. Engineered Safety Features Actuation System Interlocks
- a. Pressurizer Pressure, P-1I N.A. R Q N.A. N.A. N.A. N.A. 1,2,3
- b. Low-Low Tvg, P-12 N.A. R Q N.A. N.A. N.A. N.A. 1,2,3
>23:,, c. Reactor Trip, P-4 N.A. N.A. N.A. R N.A. N.A. N.A. 1,2.3
- 10. Control Room Ventilation
- a. Manual Initiation N.A. N.A. N.A. R N.A. N.A. N.A. All (CL'
! I c-a.
W TABLE 4.3-2 (Continued)
I ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS DIGITAL TRIP ANALOG ACTUATING MODES CHANNEL. DEVICE MASTER SLAVE FOR WHICH CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE
(,- FUNCTIONAL UNIT CHECK CALIBRATION TEST (7) TEST LOGIC TEST TEST TEST IS REQUIRED
- 10. Control Room Ventilation (Continued)
- b. Safety Injection See Item I. above for all Safety Injection Surveillance Requirements.
- c. Automatic Actuation N.A. N.A. N.A. N.A. Q(6) N.A. N.A. All Logic and Actuation Relays
- d. Control Room Intake Air S R Q N.A. N.A. N.A. N.A. All Radioactivity-High 0.)
- e. Loss of Power S ee Items 8. above for all Loss of Power Surveillance Requirements.
00 I1. FHB HVAC
- a. Manual Initiation N.A. N.A. N.A. R N.A. N.A. N.A. 1,2,3,4, or with irradiated fuel in the spent fuel pool
- b. Automatic Actuation N.A. N.A. N.A. N.A. Q(6) N.A. N.A. 1,2, 3,4, Logic and Actuation or with irradiated Relays fuel in the spent fuel pool.
E3 0"
N,.
GO TABLE 4.3-2 (Continued) 0 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION Hz SURVEILLANCE REOUIREMENTS DIGITAL OR TRIP ANAL OG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR WHICH tor CHANNEL CHANNEL. CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE CHECK CALIBRATION TEST (7)
FUNCTIONAL UNIT
- 11. FHB HVAC (Continued)
TEST LOGIC TEST TEST TEST IS REQUIRED I
- c. Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.
- d. Spent Fuel Pool S R Q N.A. N.A. N.A. N.A. With irradiated Exhaust Radio fuel in spent fuel activity-High pool.
TABLE NOTATION (1) Each train shall be tested at least every 92 days on a STAGGERED TEST BASIS.
(2) Deleted (3) Deleted (4) Except relays K807, K814, K829 (Train B only), K831, K845, K852 and K854 (Trains B and C only) which shall be tested at least once per 18 months during refueling and during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless they have been tested within the previous 92 days.
(5) Except relay K815 which shall be tested at indicated interval only when reactor coolant pressure is above 700 psig.
(6) Each actuation train shall be tested at least every 92 days on a STAGGERED TEST BASIS. Testing of each actuation train shall include master relay testing of both logic trains. If an ESFAS instrumentation channel is inoperable due to failure of the Actuation Logic Test and/or Master Relay Test, increase the surveillance frequency such that each train is tested at least every 62 days on a STAGGERED TEST BASIS unless the failure carn be determined by performance of an engineering evaluation to be a single random failure.
0O (7) For channels with bypass test instrumentation, input relays are tested on an 18-month (R) frequency.
I
- During CORE ALTERATIONS or movement of irradiated fuel within containment.