ML062700274

TS-310 - Sequoyah, Units 1 and 2, Amendment, Nominal Trip Setpoints for Reactor Protection System and Engineered Safety Features (TS-02-01)

ML062700274
Person / Time
Site:	Sequoyah
Issue date:	09/13/2006
From:	Office of Nuclear Reactor Regulation
To:
Pickett D, NRR/DORL, 415-1364
Shared Package
ML062280122	List: ML062700274
References
Download: ML062700274 (22)

Text

(4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required, any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis, instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the Sequoyah and Watts Bar Unit 1 Nuclear Plants.

C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level The Tennessee Valley Authority is authorized to operate the facility at reactor core power levels not in excess of 3455 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. , are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3) Initial Test Program The Tennessee Valley Authority shall conduct the post-fuel-loading initial test program (set forth in Section 14 of Tennessee Valley Authority's Final Safety Analysis Report, as amended), without making any major modifications of this program unless modifications have been identified and have received prior NRC approval. Major modifications are defined as:

a. Elimination of any test identified in Section 14 of TVA's Final Safety Analysis Report as amended as being essential;

b. Modification of test objectives, methods or acceptance criteria for any test identified in Section 14 of TVA's Final Safety Analysis Report as amended as being essential;

c. Performance of any test at power level different from there described; and Facility Operating License No. DPR-77 Amendment No. 310

SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.2 LIMITING SAFETY SYSTEM SETTINGS REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS 2.2.1 The reactor trip system instrumentation and interlocks setpoints shall be set consistent with the Nominal Trip Setpoint values shown in Table 2.2-1.

APPLICABILITY: As shown for each channel in Table 3.3-1.

ACTION:

With a reactor trip system instrumentation or interlock setpoint less conservative than the value shown in the Allowable Values column of Table 2.2-1, declare the channel inoperable and apply the applicable ACTION statement requirement of Specification 3.3.1 until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Nominal Trip Setpoint value.

SEQUOYAH - UNIT 1 2-4 Amendment No. 12, 310

TABLE 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT NOMINAL TRIP SETPOINT ALLOWABLE VALUES

1. Manual Reactor Trip Not Applicable Not Applicable

2. Power Range Neutron Low Setpoint - 25% of RATED Low Setpoint - < 27.4% of RATED Flux THERMAL POWER THERMAL POWER High Setpoint - 109% of RATED High Setpoint - < 111.4% of RATED I THERMAL POWER THERMAL POWER

3. Power Range Neutron 5% of RATED THERMAL < 6.3% of RATED THERMAL Flux High Positive POWER with a time constant > 2 POWER with a time constant > 2 Rate second second

4. Power Range Neutron Flux, 5% of RATED THERMAL < 6.3% of RATED THERMAL High Negative Rate POWER with a time constant > 2 POWER with a time constant > 2 second second

5. Intermediate Range, Neutron 25% of RATED THERMAL *45.20% of RATED THERMAL Flux POWER POWER

6. Source Range Neutron Flux 105 counts per second

• 1.45 x 105 counts per second

7. Overtemperature AT See Note 1 See Note 3

8. Overpower AT See Note 2 See Note 4

9. Pressurizer Pressure--Low 1970 psig _ 1964.8 psig

10. Pressurizer Pressure-High 2385 psig < 2390.2 psig

11. Pressurizer Water Level-High 92% of instrument span <_92.7% of instrument span

12. Loss of Flow 90% of design flow per loop* > 89.6% of design flow per loop*

• Design flow is 90,045 (87,000 X 1.035) gpm per loop.

SEQUOYAH - UNIT 1 2-5 Amendment No. 44, 141, 185, 221, 223, 310

TABLE 2.2-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT NOMINAL TRIP SETPOINT ALLOWABLE VALUES I

13. Steam Generator Water Level--Low-Low

a. RCS Loops AT Equivalent RCS Loop AT variable input RCS Loop AT variable input < I to Power < 50% RTP 50% RTP nominal trip setpoint + 2.5% RTP I Coincident with Steam Generator Water Level -- Low-Low (Adverse) 15.0% of narrow range instrument span

> 14.4% of narrow range instrument span I

and Containment Pressure (EAM) 0.5 psig < 0.6 psig or Steam Generator Water Level -- Low-Low (EAM) 10.7% of narrow range instrument span

> 10.1% of narrow range instrument span I

with A time delay (Ts) if one Ts (Note 5) < (1.01) Ts (Note 5)

Steam Generator is affected or A time delay (TM) if two or TM (Note 5) < (1.01) Tm (Note 5) more Steam Generators are affected

b. RCS Loop AT Equivalent to Power > 50% RTP Coincident with Steam Generator Water Level -- Low-Low (Adverse) 15.0% of narrow range instrument span

> 14.4% of narrow range instrument span I

and Containment Pressure (EAM) 0.5 psig < 0.6 psig I

or I Steam Generator Water 10.7% of narrow range 10.1% of narrow range Level -- Low-Low (EAM) instrument span instrument SEQUOYAH - UNIT 1 15 1 2-6 Amendment No. 16, 85, 136, 141, ,310

TABLE 2.2-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT NOMINAL TRIP SETPOINT ALLOWABLE VALUES I

14. Deleted

15. Undervoltage-Reactor 5022 volts-each bus _ 4739 volts-each bus Coolant Pumps

16. Underfrequency-Reactor 56.0 Hz - each bus > 55.9 Hz - each bus Coolant Pumps

17. Turbine Trip A. Low Trip System 45 psig _ 43 psig

• Pressure B. Turbine Stop Valve 1% open _ 1% open Closure

18. Safety Injection Input Not Applicable Not Applicable from ESF

19. Intermediate Range Neutron Flux - (P-6) Enable Block 1 x 10"4% of RATED THERMAL - 6 x 10"5% of RATED I POWER THERMAL POWER Source Range Reactor Trip

20. Power Range Neutron Flux 10% of RATED THERMAL < 12.4% of RATED (not P-1 0) Input to Low Power POWER THERMAL POWER Reactor Trips Block P-7

• The allowable value for the Turbine Trip - Low Trip System Pressure is > 39.5 psig and expires at the end of the Unit 1 Cycle 15 Operating Cycle.

SEQUOYAH - UNIT 1 2-6a Amendment No. 16, 85, 136, 141, 307, 310

TABLE 2.2-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT NOMINAL TRIP SETPOINT ALLOWABLE VALUES I

21. Turbine Impulse Chamber Pressure - 10% Turbine Impulse < 12.4% Turbine (P-13) Input to Low Power Reactor Pressure Equivalent Impulse Pressure Trips Block P-7 Equivalent

22. Power Range Neutron Flux - (P-8) Low 35% of RATED THERMAL <37.4% of RATED Reactor Coolant Loop Flow, and POWER THERMAL POWER Reactor Trip

23. Power Range Neutron Flux - (P-10) - 10% of RATED THERMAL > 7.6% of RATED Enable Block of Source, Intermediate, POWER THERMAL POWER and Power Range (low setpoint)

Reactor Trips

24. Reactor Trip P-4 Not Applicable Not Applicable

25. Power Range Neutron Flux - (P-9) - 50% of RATED THERMAL

• 52.4% of RATED Blocks Reactor Trip for Turbine Trip POWER THERMAL POWER Below 50% Rated Power NOTATION NOTE 1:

Overtemperature AT "1+ r5S)

G1 + I'4_S <- ATo fKi - K2- I*I + T2S)[

Z isl [T -- T']'] + K K3 (p - p,) - f. (AI)}

Where:

1 + T'S - Lead-lag compensator on measured AT 1 + r'S 1 4 , 'r5 Time constants utilized in the lead-lag controller for AT, T4 > 5 secs, T< *3 sec.

ATo - Indicated AT at RATED THERMAL POWER K 21 _< 1.15 K2 >_ 0.011 SEQUOYAH - UNIT 1 2-7 Amendment No. 19, 114, 141,211, 310

TABLE 2.2-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS NOTATION (Continued)

NOTE 1: (Continued) 1 + znS = The function generated by the lead-lag controller for Tavg dynamic compensation 1 + "'*S T1, & Z2 Time constants utilized in the lead-lag controller for Tavg, T, 33 secs., Z2 < 4 secs.

T = Average temperature OF Tv -< 578.2 0F (Tavg at RATED THERMAL POWER)

K3 = 0.00055 P Pressurizer pressure, psig Pf = 2235 psig (Nominal RCS operating pressure)

S Laplace transform operator (sec1) and f, (Al) is a function of the indicated difference between top and bottom detectors of the power-range nuclear ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that:

(i) for qt - qb between QTNL* and QTPL* f, (Al) = 0 (where qt and qb are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and qt + qb is total THERMAL POWER in percent of RATED THERMAL POWER).

SEQUOYAH - UNIT 1 2-8 Amendment No. 19, 141, 211, 223,310

TABLE 2.2-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS NOTATION (Continued)

NOTE 1: (Continued)

(ii) for each percent that the magnitude of (qt - qb) exceeds QTNL*, the AT nominal trip I setpoint shall be automatically reduced by QTNS of its value at RATED THERMAL POWER.

(iii) for each percent that the magnitude of (qt - qb) exceeds QTPL, the AT nominal trip setpoint shall be automatically reduced by QTPS* of its value at RATED THERMAL POWER.

NOTE 2:

Overpower AT 1 +  ;'sD < ATo K4 - K 5 ( I3S') T-K (T-rT) - f2 (AI) 6 Where: 1+ ,S as defined in Note 1 14+ F9 T = as defined in Note 1 AT 0 as defined in Note 1 K4 1.087 K5 _> 0.02/°F for increasing average temperature and 0 for decreasing average temperature T3S = The function generated by the rate-lag controller for Tavg 1 + 'r3S dynamic compensation QTNL, QTPL, QTNS, and QTPS are specified in the COLR per Specification 6.9.1.14.

SEQUOYAH - UNIT 1 2-9 Amendment No. 19, 114,141, 211, 223,310

\

TABLE 2.2-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS NOTATION (Continued)

NOTE 2: (Continued)

T Time constant utilized in the rate-lag controller for Tavg, Z >_10 secs.

3 K __ 0.0011 for T > T" and K >__ 0 for T __T" 6 6 T = as defined in Note 1 T1" Indicated Tvg at RATED THERMAL POWER (Calibration temperature for AT instrumentation, < 578.2°F)

S as defined in Note 1 and f 2(AI) is a function of the indicated difference between top and bottom detectors of the power-range nuclear ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that:

(i) for qt - qb between QPNL* and QPPL* f 2(AI) = 0 (where qt and qb are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and qt + qb is total THERMAL POWER in percent of RATED THERMAL POWER).

(ii) for each percent that the magnitude of (qt - qb) exceeds QPNL* the AT nominal trip setpoint shall be automatically reduced by QPNS* of its value at RATED THERMAL POWER.

(iii) for each percent that the magnitude of (qt - qb) exceeds QPPL* the AT nominal trip setpoint shall be automatically reduced by QPPS* of its value at RATED THERMAL POWER.

NOTE 3: The channel's maximum trip setpoint shall not exceed its computed nominal trip setpoint by more than 1.9 percent AT span.

NOTE 4: The channel's maximum trip setpoint shall not exceed its computed nominal trip setpoint by more than 1.7 percent AT span.

• QPNL, QPPL, QPNS, and QPPS are specified in the COLR per Specification 6.9.1.14.

SEQUOYAH - UNIT 1 2-10 Amendment No. 19, 141,211,223,310

INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2.1 The Engineered Safety Feature Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Nominal Trip Setpoint column of Table 3.3-4.

APPLICABILITY: As shown in Table 3.3-3.

ACTION:

a. With an ESFAS instrumentation channel or interlock trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Nominal Trip Setpoint value.

b. With an ESFAS instrumentation channel or interlock inoperable, take the ACTION shown in Table 3.3-3.

SURVEILLANCE REQUIREMENTS 4.3.2.1.1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-2.

4.3.2.1.2 The logic for the interlocks shall be demonstrated OPERABLE during the automatic actuation logic test. The total interlock function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by interlock operation.

4.3.2.1.3 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be verified to be within the limit at least once per 18 months. Each verification shall include at least one train such that both trains are verified at least once per 36 months and one channel per function such that all channels are verified at least once per N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the "Total No. of Channels" Column of Table 3.3-3.

SEQUOYAH - UNIT 1 3/4 3-14 Amendment No. 190, 251, 310

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TOTAL NO. MINIMUM OF CHANNELS CHANNELS APPLICABLE.

FUNCTIONAL UNIT CHANNELS TO TRIP OPERABLE MODES ACTION

e. Loss of Power Start

1. Voltage Sensors 3/shutdown 2/shutdown 3/shutdown 1,2,3 35 board board board**

2. Load Shed Timer 2/shutdown 1/shutdown 1/shutdown I board board board** 1,2,3 35

f. Trip of Main 1/pump 1/pump 1/pump 1,2 20 Feedwater Pumps Start Motor-Driven Pumps and Turbine Driven Pump

g. Auxiliary Feedwater 3/pump 2/pump 3/pump 1,2,3 21 Suction Pressure- Low

h. Auxiliary Feedwater Suction Transfer Time Delays

1. Motor-Driven Pump 1/pump 1/pump 1/pump 1,.2,3 21

2. Turbine-Driven Pump 2/pump 1/pump 2/pump 1,2,3 21

• • Unit 1 shutdown boards only SEQUOYAH - UNIT I 3/4 3-20 Amendment No. 41, 129, 182, 188, 207,301, 310

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS_ APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

7. LOSS OF POWER

a. 6.9 kv Shutdown Board --

Loss of Voltage

1. Voltage Sensors 3/shutdown 2/shutdown 3/shutdown 1,2,3,4 34 5###,6###

board board board

2. Diesel Generator 2/shutdown 1/shutdown 1/shutdown 1,2,3,4 34 1 Start and Load board board board 5#, 6#

Shed Timer

b. 6.9 kv Shutdown Board Degraded Voltage

1. Voltage Sensors 3/shutdown 2/shutdown 3/shutdown 1, 2, 3, 4 34 board board board 5####, 6#

2. Diesel Generator 2/shutdown 1/shutdown 1/shutdown 1,2,3,4 34 Start and Load Shed board board board 5# , 6#

Timer

3. SI/Degraded Voltage 2/shutdown 1/shutdown 1/shutdown 1,2,3,4 34 Logic Enable Timer board board board

8. ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INTERLOCKS

a. Pressurizer Pressure- 3 2 2 1,2,3 22a P-1 1/Not P-11

b. Deleted

c. Steam Generator Level 3/loop 2/loop any 3/loop 1,2 22c P-14 loop SEQUOYAH - UNIT 1 3/4 3-21 Amendment No. 41, 129, 141, 160, 182, 188, 207, 310

TABLE 3.3-3 (Continued)

ACTION 21 - With less than the Minimum Number of Channels OPERABLE, declare the associated auxiliary feedwater pump inoperable, and comply with the ACTION requirements of Specification 3.7.1.2.

ACTION 22 - With less than the Minimum Number of Channels OPERABLE, declare the interlock inoperable and verify that all affected channels of the functions listed below are OPERABLE or apply the appropriate ACTION statement(s) for those functions.

Functions to be evaluated are:

a. Safety Injection Pressurizer Pressure Steam Line Pressure Negative Steam Line Pressure Rate

b. Deleted

c. Turbine Trip Steam Generator Level High-High Feedwater Isolation Steam Generator Level High-High ACTION 23 - With the number of OPERABLE channels one less than the Total Number of Channels, 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 />; 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 4.3.2.1.1.

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 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 />.

ACTION 25 - 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 34 - a. With the number of OPERABLE channels one less than the Total Number of Channels for voltage sensors, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or enter applicable Limiting Condition(s) For Operation and Action(s) for the associated diesel generator set made inoperable by the channel.

b. With the number of OPERABLE channels less than the Total Number of Channels by more than one for voltage sensors or timers, restore all but one channel to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or enter applicable Limiting Condition(s) For Operation and Action(s) for the associated diesel generator set made inoperable by the channels.

SEQUOYAH - UNIT 1 3/4 3-23 Amendment No. 12, 63, 129, 141, 160, 182, 188, 207, 310

\

TABLE 3.3-3 (Continued)

ACTION 35 - a. With the number of OPERABLE channels one less than the Total Number of Channels for voltage sensors, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or enter applicable Limiting Condition(s) For Operation and Action(s) for the associated auxiliary feedwater pump made inoperable by the channel.

b. With the number of OPERABLE channels less than the Total Number of Channels by more than one for voltage sensors or timers, restore all but one channel to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or enter applicable Limiting Condition(s) For Operation and Action(s) for the associated auxiliary feedwater pump made inoperable by the channels.

ACTION 36 - 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. For the affected protection set, the Trip Time Delay for one affected steam generator (Ts) is adjusted to match the Trip Time Delay for multiple affected steam generators (TM) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

c. 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 4.3.2.1 .1.

ACTION 37 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided that within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, for the affected protection set, the Trip Time Delays (Ts and TM) threshold power level for zero seconds time delay is adjusted to 0% RTP.

ACTION 38 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided that within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, for the affected protection set, the Steam Generator Water Level - Low-Low (EAM) channels trip setpoint is adjusted to the same value as Steam Generator Water Level - Low-Low (Adverse).

SEQUOYAH - UNIT 1 3/4 3-23a Amendment No. 141,160, 182, 188, 207, 310

TABLE 3.3-4 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT NOMINAL TRIP SETPOINT ALLOWABLE VALUES I

1. SAFETY INJECTION, TURBINE TRIP AND FEEDWATER ISOLATION

a. Manual Initiation Not Applicable Not Applicable

b. Automatic Actuation Logic Not Applicable Not Applicable

c. Containment Pressure-High 1.54 psig < 1.6 psig

d. Pressurizer Pressure--Low 1870 psig > 1864.8 psig

e. Deleted

f. Steam Line Pressure-Low 600 psig steam line _ 592.2 psig steam pressure (Note 1) line pressure (Note 1)

SEQUOYAH - UNIT 1 3/4 3-24 Amendment No. 141, 310

TABLE 3.3-4 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT NOMINAL TRIP SETPOINT ALLOWABLE VALUES

2. CONTAINMENT SPRAY

a. Manual Initiation Not Applicable Not Applicable

b. Automatic Actuation Logic Not Applicable Not Applicable

c. Containment Pressure--High-High 2.81 psig <2.9 psig

3. CONTAINMENT ISOLATION

a. Phase "A" Isolation

1. Manual Not Applicable Not Applicable

2. From Safety Injection Automatic Not Applicable Not Applicable Actuation logic

b. Phase "B" Isolation

1. Manual Not Applicable Not Applicable

2. Automatic Actuation Logic Not Applicable Not Applicable

3. Containment Pressure-High-High 2.81 psig <2.9 psig I

c. Containment Ventilation Isolation

1. Manual Not Applicable Not Applicable

2. Automatic Isolation Logic Not Applicable Not Applicable SEQUOYAH - UNIT 1 3/4 3-25 Amendment No. 12, 141, 310

TABLE 3.3-4 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT NOMINAL TRIP SETPOINT ALLOWABLE VALUES

3. Containment Purge Air 8.5 x 10-3 VCi/c 8.5 x 10-3 gCi/cc Exhaust Monitor 8 Radioactivity-High

4. STEAM LINE ISOLATION

a. Manual Not Applicable Not Applicable

b. Automatic Actuation Logic Not Applicable Not Applicable

c. Containment Pressure- 2.81 psig < 2.9 psig High-High

d. Steam Line Pressure--Low 600 psig steam line pressure > 592.2 psig steam line pressure (Note 1) (Note 1)

e. Negative Steam Line 100.0 psi (Note 2) < 107.8 psi (Note 2)

Pressure Rate-High

5. TURBINE TRIP AND FEEDWATER ISOLATION

a. Steam Generator Water 81% of narrow range instrument *81.7% of narrow range I level-- High-High span each steam generator instrument span each steam generator

b. Automatic Actuation Logic N.A. N.A.

SEQUOYAH - UNIT 1 3/4 3-26 Amendment No. 63, 141,168, 310

TABLE 3.3-4 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT NOMINAL TRIP SETPOINT ALLOWABLE VALUES

6. AUXILIARY FEEDWATER

a. Manual Not Applicable Not Applicable

b. Automatic Actuation Logic Not Applicable Not Applicable

c. Main Steam Generator Water Level--Low-Low

i. RCS Loop AT Equivalent to RCS Loop AT variable input RCS Loop AT variable input <

Power < 50% RTP 50% RTP nominal trip setpoint +2.5% RTP Coincident with Steam Generator Water 15.0% of narrow range Ž14.4% of narrow range Level- Low-Low (Adverse) instrument span instrument span and Containment Pressure-EAM 0.5 psig _*0.6 psig or Steam Generator Water 10.7% of narrow range instrument span

_>10.1% of narrow instrument span I

Level--Low-Low (EAM) with I

A time delay (Ts) if one Ts (Note 5, Table 2.2-1) * (1.01) Ts (Note 5, Table 2.2-1)

Steam Generator is affected or A time delay (TM ) if two or TM (Note 5, Table 2.2-1) _ (1.01) TM (Note 5, Table 2.2-1) more Steam Generators are affected SEQUOYAH - UNIT 1 3/4 3-27 Amendment No. 29, 94, 141,151, 310

TABLE 3.3-4 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT NOMINAL TRIP ALLOWABLE VALUES SETPOINT ii. RCS Loop AT Equivalent to Power

> 50% RTP Coincident with Steam Generator Water 15.0% of narrow range _ 14.4% of narrow range I Level-- Low-Low (Adverse) instrument span instrument span and Containment Pressure (EAM) 0.5 psig < 0.6 psig or Steam Generator Water Level-- 10.7% of narrow range :10.1% of narrow range Low-Low (EAM) instrument span instrument span

d. S.I. See 1 above (all SI Setpoints)

e. Loss of Power Start

1. Voltage Sensors 5520 volts _ 5331 volts

2. Load Shed Timer 1.25 seconds > 1.00 second and < 1.50 seconds

f. Trip of Main Feedwater Pumps N.A. N.A.

g. Auxiliary Feedwater Suction Pressure- 3.21 psig (motor driven > 2.44 psig (motor driven pump)

Low pump) 13.9 psig (turbine driven > 12 psig (turbine driven pump)

(pump)

h. Auxiliary Feedwater Suction Transfer 4 seconds (motor driven < 4.4 seconds and Time Delays pump) > 3.6 seconds (motor driven pump) 5.5 seconds (turbine driven < 6.05 seconds and pump) > 4.95 seconds (turbine driven pump)

SEQUOYAH - UNIT 1 3/4 3-27a Amendment No. 29, 94, 129, 141, 151,182, 183, 188, 207, 219, 310

TABLE 3.3-4 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS NOMINAL.TRIP FUNCTIONAL UNIT SETPOINT ALLOWABLE VALUES

7. LOSS OF POWER

a. 6.9 kv Shutdown Board Undervoltage Loss of Voltage

1. Voltage Sensors 5520 volts > 5331 volts I

2. Diesel Generator Start and Load Shed 1.25 seconds _1.00 second and Timer < 1.50 seconds

b. 6.9 kv Shutdown Board-Degraded Voltage

1. Voltage Sensors 6456 volts _>6403.5 volts (dropout)

< 6595.5 volts (reset)

2. Diesel Generator Start and Load Shed 300 seconds < 370 seconds Timer

3. SI/Degraded Voltage Logic 9.5 seconds Ž7.5 seconds and Enable Timer < 11.5 seconds

8. ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INTERLOCKS

a. Pressurizer Pressure

1. Not P-11, Automatic Unblock of Safety Injection on Increasing Pressure 1970 psig <1975.2 psig

2. P-11, Enable Manual Block of Safety Injection on Decreasing Pressure 1962.psig > 1956.8 psig SEQUOYAH - UNIT 1 3/4 3-27b Amendment No. 33, 129, 141, 182, 188, 207, 219, 310

TABLE 3.3-4 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT NOMINAL TRIP SETPOINT ALLOWABLE VALUES

8. ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INTERLOCKS (Continued)

b. Deleted

c. Deleted

d. Steam Generator Level Turbine Trip, (See 5. above)

Feedwater Isolation P-14

9. AUTOMATIC SWITCHOVER TO CONTAINMENT SUMP

a. RWST Level -Low 130" from tank base < 132.71" and

_ 127.29" from tank base COINCIDENT WITH Containment Sump Level - High 30" above elev. 680' < 31.68" and

> 28.32" above elev. 680' AND Safety Injection (See 1 above for all Safety Injection Setpoints/Allowable Values)

b. Automatic Actuation Logic N.A. N.A.

Note 1: Time constants utilized in the lead-lag controller for Steam Pressure - Low are r,1 > 50 seconds and T2 < 5 seconds.

Note 2: Time constant utilized in the rate-lag controller for Negative Steam Line Pressure Rate - High is 'r _ 50 seconds.

SEQUOYAH - UNIT 1 3/4 3-28 Amendment No. 14, 63, 141,310

TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS. APPLICABLE ALARM/TRIP MEASUREMENT ACTION INSTRUMENT OPERABLE MODES SETPOINT RANGE

1. AREA MONITOR

a. Fuel Storage Pool 1 < 151 mR/hr 26 10 104 mR/hr Area

2. PROCESS MONITORS

< 8.5x 10-31'10-107 cpm

a. Containment Purge 1 1,2,3,4&6 28 Ci/cc Air

b. Containment

i. Gaseous Activity RCS Leakage 1 1, 2,3& 4 N/A 10-107 cpm 27 Detection ii. Particulate Activity 10 -107 cpm RCS Leakage 1 1,2,3&4 N/A 27 Detection 10-107 cpm

c. Control Room 2 ALL MODES < 400 cpm** 29 Isolation and during movement of irradiated fuel assemblies

• With fuel in the storage pool or building

• • Equivalent to 1.0 x 10-5 iCi/cc.

SEQUOYAH - UNIT 1 3/4 3-40 Amendment No. 12, 60, 112, 168, 256, 310