ML080580005
| ML080580005 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 04/03/2008 |
| From: | NRC/NRR/ADRO/DORL/LPLIV |
| To: | |
| Singal, Balwant, 415-3016, NRR/DORL/LPL4 | |
| Shared Package | |
| ML080580003 | List: |
| References | |
| TAC MD6561, TAC MD6562 | |
| Download: ML080580005 (19) | |
Text
(3) Luminant Generation Company LLC, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time, special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, and described in the Final Safety Analysis Report, as supplemented and amended; (4) Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use, at any time, any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required, any byproduct, source, and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6) Luminant Generation Company LLC, 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 facility.
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 Luminant Generation Company LLC is authorized to operate the facility at reactor core power levels not in excess of 3458 megawatts thermal in accordance with the conditions specified herein.
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A as revised through Amendment No. 145 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. Luminant Generation Company LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Unit 1 Amendment No. 145
(3) Luminant Generation Company LLC, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time, special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, and described in the Final Safety Analysis Report, as supplemented and amended; (4) Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use, at any time, any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required, any byproduct, source, and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6) Luminant Generation Company LLC, 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 facility.
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 Luminant Generation Company LLC is authorized to operate the facility at reactor core power levels not in excess of 3458 megawatts thermal in accordance with the conditions specified herein.
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A as revised through Amendment No. 145 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. Luminant Generation Company LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Antitrust Conditions DELETED Unit 2 Amendment No. 145
Rod Group Alignment Limits 3.1.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify individual rod positions within alignment limit. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> SR 3.1.4.2 Verify rod freedom of movement (trippability) 92 days by moving each rod not fully inserted in the core 10 steps in either direction.
SR 3.1.4.3 Verify rod drop time of each rod, from the Prior to reactor fully withdrawn position, is 2.7 seconds from the criticality after beginning of decay of stationary gripper coil voltage to each removal of dashpot entry, with: the reactor head
- a. Tavg 500qF; and
- b. All reactor coolant pumps operating.
COMANCHE PEAK - UNITS 1 AND 2 3.1-10 Amendment No. 64, 145
RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 1 of 7)
Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE(a)
- 1. Manual 1,2 2 B SR 3.3.1.14 NA Reactor Trip 3(b), 4(b), 5(b) 2 C SR 3.3.1.14 NA
- 2. Power Range Neutron Flux
- a. High 1,2 4 D SR 3.3.1.1 d 109.6% RTP(q)(r)#
SR 3.3.1.2 SR 3.3.1.7 SR 3.3.1.11 SR 3.3.1.16
- b. Low 1(c), 2 4 E SR 3.3.1.1 d 25.6% RTP(q)(r)#
SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.16
- 3. Power Range 1,2 4 E SR 3.3.1.7 d 6.3% RTP Neutron Flux Rate SR 3.3.1.11 with time constant High Positive Rate t 2 sec
- 4. Intermediate 1(c), 2(d) 2 F,G SR 3.3.1.1 d 31.5% RTP Range Neutron SR 3.3.1.8 Flux SR 3.3.1.11 (continued)
(a) The Allowable Value defines the limiting safety system setting except for Trip Functions 2a, 2b, 6, 7, and 14 (the Nominal Trip Setpoint defines the limiting safety system setting for these Trip Functions). See the Bases for the Nominal Trip Setpoints.
(b) With Rod Control System capable of rod withdrawal or one or more rods not fully inserted.
(c) Below the P-10 (Power Range Neutron Flux) interlock.
(d) Above the P-6 (Intermediate Range Neutron Flux) interlock.
(q) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found acceptance criteria band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(r) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the Nominal Trip Setpoint or a value that is more conservative than the Trip Setpoint; otherwise, the channel shall be declared inoperable. The Nominal Trip Setpoint, the methodology used to determine the as-found tolerance and the methodology used to determine the as-left tolerance shall be specified in the Technical Specification Bases.
- For Unit 1, through Cycle 13, the ALLOWABLE VALUE for the Power Range Neutron Flux - High remains at 110.8%
RTP and the Power Range Neutron Flux - Low remains at 27.7% RTP.
COMANCHE PEAK - UNITS 1 AND 2 3.3-15 Amendment No. 89, 145
RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 2 of 7)
Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE(a)
- 5. Source Range 2(e) 2 I,J SR 3.3.1.1 d 1.4 E5 cps Neutron Flux SR 3.3.1.8 SR 3.3.1.11 3(b), 4(b), 5(b) 2 J,K SR 3.3.1.1 d 1.4 E5 cps SR 3.3.1.7 SR 3.3.1.11
- 6. Overtemperature 1,2 4 E SR 3.3.1.1 Refer to Note 1(q)(r)
N-16 SR 3.3.1.2 SR 3.3.1.3 SR 3.3.1.6 SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16
- 7. Overpower 1,2 4 E SR 3.3.1.1 d 112.8% RTP N-16 SR 3.3.1.2 (q)(r)##
SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16
- 8. Pressurizer Pressure
- a. Low 1(g) 4 M SR 3.3.1.1 t 1863.6 psig SR 3.3.1.7 (Unit 1)
SR 3.3.1.10 t 1865.2 psig SR 3.3.1.16 (Unit 2)
- b. High 1,2 4 E SR 3.3.1.1 d 2400.8 psig SR 3.3.1.7 (Unit 1)
SR 3.3.1.10 d 2401.4 psig SR 3.3.1.16 (Unit 2)
(continued)
(a) The Allowable Value defines the limiting safety system setting except for Trip Functions 2a, 2b, 6, 7, and 14 (the Nominal Trip Setpoint defines the limiting safety system setting for these Trip Functions). See the Bases for the Nominal Trip Setpoints.
(b) With Rod Control System capable of rod withdrawal or one or more rods not fully inserted.
(e) Below the P-6 (Intermediate Range Neutron Flux) interlock.
(g) Above the P-7 (Low Power Reactor Trips Block) interlock.
(q) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found acceptance criteria band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(r) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the Nominal Trip Setpoint or a value that is more conservative than the Trip Setpoint; otherwise, the channel shall be declared inoperable. The Nominal Trip Setpoint, the methodology used to determine the as-found tolerance and the methodology used to determine the as-left tolerance shall be specified in the Technical Specification Bases.
- For Unit 1, through Cycle 13, the ALLOWABLE VALUE for Overpower N16 remains at 112.9% RTP.
COMANCHE PEAK - UNITS 1 AND 2 3.3-16 Amendment No. 89, 145
RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 3 of 7)
Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE(a)
- 9. Pressurizer Water 1(g) 3 M SR 3.3.1.1 d 93.9% of Level - High SR 3.3.1.7 instrument span SR 3.3.1.10
- 10. Reactor Coolant 1(g) 3 per loop M SR 3.3.1.1 t 88.6% of indicated Flow - Low SR 3.3.1.7 loop flow (Unit 1)
SR 3.3.1.10 t 88.8% of indicated SR 3.3.1.16 loop flow (Unit 2)
- 11. Not Used
- 12. Undervoltage 1(g) 1 per bus M SR 3.3.1.9 t 4753 V RCPs SR 3.3.1.10 SR 3.3.1.16
- 13. Underfrequency 1(g) 1 per bus M SR 3.3.1.9 t 57.06 Hz RCPs SR 3.3.1.10 SR 3.3.1.16
- 14. Steam Generator 1, 2 4 per SG E SR 3.3.1.1 t 37.5%### of (SG) Water Level SR 3.3.1.7 narrow range Low-Low (l) SR 3.3.1.10 instrument span SR 3.3.1.16 (Unit 1)(q)(r) t 34.9% of narrow range instrument span (Unit 2) (q)(r)
- 15. Not Used.
(continued)
(a) The Allowable Value defines the limiting safety system setting except for Trip Functions 2a, 2b, 6, 7, and 14 (the Nominal Trip Setpoint defines the limiting safety system setting for these Trip Functions). See the Bases for the Nominal Trip Setpoints.
(g) Above the P-7 (Low Power Reactor Trips Block) interlock.
(l) The applicable MODES for these channels in Table 3.3.2-1 are more restrictive.
(q) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found acceptance criteria band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(r) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the Nominal Trip Setpoint, or a value that is more conservative than the Trip Setpoint; otherwise, the channel shall be declared inoperable. The Nominal Trip Setpoint, the methodology used to determine the as-found tolerance and the methodology used to determine the as-left tolerance shall be specified in the Technical Specification Bases.
- For Unit 1, through Cycle 13, the ALLOWABLE VALUE for Steam Generator Water Level Low-Low remains at 36% of narrow range instrumentation.
COMANCHE PEAK - UNITS 1 AND 2 3.3-17 Amendment No. 64, 131, 145
RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 4 of 7)
Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE(a)
- 16. Turbine Trip
- 17. Safety 1,2 2 trains Q SR 3.3.1.14 NA Injection (SI) Input from Engineered Safety Feature Actuation System (ESFAS)
- 18. Reactor Trip System Interlocks
- a. Intermediate 2(e) 2 S SR 3.3.1.11 t 6E-11 amp Range SR 3.3.1.13 Neutron Flux, P-6 1 1 per train T SR 3.3.1.5 NA
- b. Low Power Reactor Trips Block, P-7 1 4 T SR 3.3.1.11 d 50.7% RTP
- f. Turbine First SR 3.3.1.13 power Stage Pressure, P-13 (continued)
(a) The Allowable Value defines the limiting safety system setting except for Trip Functions 2a, 2b, 6, 7, and 14 (the Nominal Trip Setpoint defines the limiting safety system setting for these Trip Functions). See the Bases for the Nominal Trip Setpoints.
(e) Below the P-6 (Intermediate Range Neutron Flux) interlock.
(j) Above the P-9 (Power Range Neutron Flux) interlock.
COMANCHE PEAK - UNITS 1 AND 2 3.3-18 Amendment No. 64, 145
RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 5 of 7)
Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE(a)
- 19. Reactor Trip 1,2 2 trains R SR 3.3.1.4 NA Breakers(RTBs)(k) 3(b), 4(b), 5(b) 2 trains C SR 3.3.1.4 NA
- 20. Reactor Trip 1,2 1 each per U SR 3.3.1.4 NA Breaker RTB Undervoltage and Shunt Trip Mechanisms(k) 3(b), 4(b), 5(b) 1 each per C SR 3.3.1.4 NA RTB
- 21. Automatic Trip 1,2 2 trains Q SR 3.3.1.5 NA Logic 3(b), 4(b), 5(b) 2 trains C SR 3.3.1.5 NA (continued)
(a) The Allowable Value defines the limiting safety system setting except for Trip Functions 2a, 2b, 6, 7, and 14 (the Nominal Trip Setpoint defines the limiting safety system setting for these Trip Functions). See the Bases for the Nominal Trip Setpoints.
(b) With Rod Control System capable of rod withdrawal or one or more rods not fully inserted.
(k) Including any reactor trip bypass breakers that are racked in and closed for bypassing an RTB.
COMANCHE PEAK - UNITS 1 AND 2 3.3-19 Amendment No. 64, 145
RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 6 of 7)
Reactor Trip System Instrumentation Note 1: Overtemperature N-16 (For Unit 1 Cycle 13, see Note 2)
The Overtemperature N-16 Function Allowable Values shall not exceed the following setpoint by more than 0.5% N-16 span for N-16 input, 0.5% Tcold span for Tcold input, 0.5% pressure span for pressure input, and 0.5% q span for q input.
1 T1S o º 1 Q setpoint K1 K 2 << Tc Tc >> K3 PP f1 q
¬ 1 T2 S 1/4 Where:
Qsetpoint = Overtemperature N-16 trip setpoint, K1 =
- K2 = */oF K3 = */psig TC = Measured cold leg temperature, oF T cq = Indicated reference TC at RATED THERMAL POWER, *oF P = Measured pressurizer pressure, psig P1 t
- psig (Nominal RCS operating pressure) s = the Laplace transform operator, sec-1.
1,2 = Time constants utilized in lead-lag controller for Tc, 1 t
- sec, and 2 d
- sec f1(q) =
- {(qt - qb) - *%} when (qt - qb) t *% RTP
- as specified in the COLR (continued)
COMANCHE PEAK - UNITS 1 AND 2 3.3-20 Amendment No. 67, 145
RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 7 of 7)
Reactor Trip System Instrumentation Note 2: The Overtemperature N-16 Function Allowable Value shall not exceed the following setpoint by more than 1.72% of span.
1 T1S o º 1 Q setpoint K1 K 2 << Tc Tc >> K3 PP f1 q
¬ 1 T2 S 1/4 Where:
Qsetpoint = Overtemperature N-16 trip setpoint, K1 =
- K2 = */oF K3 = */psig TC = Measured cold leg temperature T cq = Indicated reference TC at RATED THERMAL POWER, *oF P = Measured pressurizer pressure, psig P1 t
- psig (Nominal RCS operating pressure) s = the Laplace transform operator, sec-1.
1,2 = Time constants utilized in lead-lag controller for Tc, 1 t
- sec, and 2 d
- sec f1(q) =
- {(qt - qb) - *%} when (qt - qb) t *% RTP
- as specified in the COLR COMANCHE PEAK - UNITS 1 AND 2 3.3-20a Amendment No. 145
ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 1 of 6)
Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE(a)
- 1. Safety Injection
- a. Manual 1, 2, 3, 4 2 B SR 3.3.2.8 NA Initiation
- b. Automatic 1, 2, 3, 4 2 trains C SR 3.3.2.2 NA Actuation Logic SR 3.3.2.4 and Actuation SR 3.3.2.6 Relays
- c. Containment 1, 2, 3 3 D SR 3.3.2.1 d 3.8 psig Pressure -- SR 3.3.2.5 High 1 SR 3.3.2.9 SR 3.3.2.10
- d. Pressurizer 1, 2, 3(b) 4 D SR 3.3.2.1 t 1803.6 psig Pressure -- SR 3.3.2.5 Low SR 3.3.2.9 SR 3.3.2.10
- e. Steam Line 1, 2, 3(b) 3 per steam D SR 3.3.2.1 t 594.0 psig(c)
Pressure line SR 3.3.2.5 (Unit 1)
Low SR 3.3.2.9 t 578.4 psig(c)
SR 3.3.2.10 (Unit 2)
- a. Manual 1, 2, 3, 4 2 per train, B SR 3.3.2.8 NA Initiation 2 trains
- b. Automatic 1, 2, 3, 4 2 trains C SR 3.3.2.2 NA Actuation Logic SR 3.3.2.4 and Actuation SR 3.3.2.6 Relays
- c. Containment 1, 2, 3 4 E SR 3.3.2.1 d 18.8 psig Pressure SR 3.3.2.5 High -- 3 SR 3.3.2.9 SR 3.3.2.10 (continued)
(a) The Allowable Value defines the limiting safety system setting except for functions 5b and 6c (the Nominal Trip Setpoint defines the limiting safety system setting for these Trip Functions). See the Bases for the Nominal Trip Setpoints.
(b) Above the P-11 (Pressurizer Pressure) interlock and below P-11, unless the Function is blocked.
(c) Time constants used in the lead/lag controller are 1t 10 seconds and 2 d 5 seconds. For Unit 1, Cycle 13 1t 50 seconds.
COMANCHE PEAK - UNITS 1 AND 2 3.3-29 Amendment No. 64, 145
ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 2 of 6)
Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE(a)
- 3. Containment Isolation
- a. Phase A Isolation (1) Manual 1, 2, 3, 4 2 B SR 3.3.2.8 NA Initiation (2) Automatic 1, 2, 3, 4 2 trains C SR 3.3.2.2 NA Actuation SR 3.3.2.4 Logic and SR 3.3.2.6 Actuation Relays (3) Safety Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
Injection
- b. Phase B Isolation (1) Manual 1, 2, 3, 4 2 per train, B SR 3.3.2.8 NA Initiation 2 trains (2) Automatic 1, 2, 3, 4 2 trains C SR 3.3.2.2 NA Actuation SR 3.3.2.4 Logic and SR 3.3.2.6 Actuation Relays (3) Contain- 1, 2, 3 4 E SR 3.3.2.1 d 18.8 psig ment SR 3.3.2.5 Pressure SR 3.3.2.9 High -- 3 (continued)
(a) The Allowable Value defines the limiting safety system setting except for functions 5b and 6c (the Nominal Trip Setpoint defines the limiting safety system setting for these Trip Functions). See the Bases for the Nominal Trip Setpoints.
COMANCHE PEAK - UNITS 1 AND 2 3.3-30 Amendment No. 64, 145
ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 3 of 6)
Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE(a)
- 4. Steam Line Isolation
- a. Manual 1, 2(i), 3(i) 2 F SR 3.3.2.8 NA Initiation
- b. Automatic 1, 2(i), 3(i) 2 trains G SR 3.3.2.2 NA Actuation Logic SR 3.3.2.4 and Actuation SR 3.3.2.6 Relays
- c. Containment 1, 2(i), 3(i) 3 D SR 3.3.2.1 d 6.8 psig Pressure -- SR 3.3.2.5 High 2 SR 3.3.2.9 SR 3.3.2.10
- d. Steam Line Pressure (1) Low 1, 2(i), 3(b)(i) 3 per steam D SR 3.3.2.1 t 594.0 psig(c) line SR 3.3.2.5 (Unit 1)
SR 3.3.2.9 t 578.4 psig(c)
SR 3.3.2.10 (Unit 2)
(2) Negative 3(g)(i) 3 per steam D SR 3.3.2.1 d 178.7 psi(h)
Rate -- line SR 3.3.2.5 High SR 3.3.2.9 SR 3.3.2.10 (continued)
(a) The Allowable Value defines the limiting safety system setting except for functions 5b and 6c (the Nominal Trip Setpoint defines the limiting safety system setting for these Trip Functions). See the Bases for the Nominal Trip Setpoints.
(b) Above the P-11 (Pressurizer Pressure) Interlock and below P-11, unless the Function is blocked.
(c) Time constants used in the lead/lag controller are 1t 10 seconds and 2 d 5 seconds. For Unit 1, Cycle 13 1t 50 seconds.
(g) Below the P-11 (Pressurizer Pressure) Interlock; however, may be blocked below P-11 when safety injection on steam line pressure-low is not blocked.
(h) Time constant utilized in the rate/lag controller is t 50 seconds.
(i) Except when all MSIVs and their associated upstream drip pot isolation valves are closed and deactivated.
COMANCHE PEAK - UNITS 1 AND 2 3.3-31 Amendment No. 64, 145
ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 4 of 6)
Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE(a)
- 5. Turbine Trip and Feedwater Isolation
- a. Automatic 1, 2(j) 2 trains H SR 3.3.2.2 NA Actuation Logic SR 3.3.2.4 and Actuation SR 3.3.2.6 Relays
- b. SG Water 1, 2(j) 3 per SG(p) I SR 3.3.2.1 d 84.5%# of Level -- High SR 3.3.2.5 narrow range span High (P-14) SR 3.3.2.9 (Unit 1) (q)(r)
SR 3.3.2.10 d 82.0% of narrow range span (Unit 2) (q)(r)
- c. Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
(continued)
(a) The Allowable Value defines the limiting safety system setting except for functions 5b and 6c (the Nominal Trip Setpoint defines the limiting safety system setting for these Trip Functions). See the Bases for the Nominal Trip Setpoints.
(j) Except when all MFIVs and associated bypass valves are closed and de-activated or isolated by a closed manual valve.
(p) A channel selected for use as an input to the SG water level controller must be declared inoperable.
(q) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found acceptance criteria band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(r) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the Nominal Trip Setpoint, or a value that is more conservative than the Trip Setpoint; otherwise, the channel shall be declared inoperable. The Nominal Trip Setpoint, the methodology used to determine the as-found tolerance and the methodology used to determining the as-left tolerance shall be specified in the Technical Specification Bases.
- For Unit 1, through Cycle 13, the ALLOWABLE VALUE for the SG Water Level High-High remains at 86% of narrow range span.
COMANCHE PEAK - UNITS 1 AND 2 3.3-32 Amendment No. 64, 131, 145
ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 5 of 6)
Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE(a)
- a. Automatic 1, 2, 3 2 trains G SR 3.3.2.2 NA Actuation Logic SR 3.3.2.4 and Actuation SR 3.3.2.6 Relays (Solid State Protection System)
- b. Not Used.
- c. SG Water 1, 2, 3 4 per SG D SR 3.3.2.1 >37.5%## of Level Low-Low SR 3.3.2.5 narrow range span SR 3.3.2.9 (Unit 1) (q)(r)
SR 3.3.2.10 >34.9% of narrow range span (Unit 2) (q)(r)
- d. Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
- e. Loss of Offsite 1, 2, 3 1 per train F SR 3.3.2.7 NA Power SR 3.3.2.9 SR 3.3.2.10
- f. Not Used.
- g. Trip of all Main 1, 2 2 per AFW J SR 3.3.2.8 NA Feedwater pump Pumps
- h. Not Used.
(continued)
(a) The Allowable Value defines the limiting safety system setting except for functions 5b and 6c (the Nominal Trip Setpoint defines the limiting safety system setting for these Trip Functions). See the Bases for the Nominal Trip Setpoints.
(q) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found acceptance criteria band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(r) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the Nominal Trip Setpoint, or a value that is more conservative than the Trip Setpoint; otherwise, the channel shall be declared inoperable. The Nominal Trip Setpoint, the methodology used to determine the as-found tolerance and the methodology used to determine the as-left tolerance shall be specified in the Technical Specification Bases.
- For Unit 1, through Cycle 13, the ALLOWABLE VALUE for the SG Water Level Low-Low remains at 36% of narrow range span.
COMANCHE PEAK - UNITS 1 AND 2 3.3-33 Amendment No. 64, 131, 145
ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 6 of 6)
Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE(a)
- 7. Automatic Switchover to Containment Sump
- a. Automatic 1, 2, 3, 4 2 trains C SR 3.3.2.2 NA Actuation Logic SR 3.3.2.4 and Actuation SR 3.3.2.6 Relays
- b. Refueling 1, 2, 3, 4 4 K SR 3.3.2.1 t 31.9(b)%
Water Storage SR 3.3.2.5 instrument span Tank (RWST) SR 3.3.2.9 Level - Low SR 3.3.2.10 Low Coincident with Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
Safety Injection
- 8. ESFAS Interlocks
- a. Reactor Trip, 1, 2, 3 1 per train, 2 F SR 3.3.2.11 NA P-4 trains
- b. Pressurizer 1, 2, 3 3 L SR 3.3.2.5 d 1975.2 psig Pressure, P-11 SR 3.3.2.9 (Unit 1) d 1976.4 psig (Unit 2)
(a) The Allowable Value defines the limiting safety system setting except for functions 5b and 6c (the Nominal Trip Setpoint defines the limiting safety system setting for these Trip Functions). See the Bases for the Nominal Trip Setpoints.
(b) The Unit 1 RWST Level Low-Low Allowable Value will remain > 43.9% instrument span until completion of Cycle 12.
COMANCHE PEAK - UNITS 1 AND 2 3.3-34 Amendment No. 125, 129, 145
Pressurizer Safety Valves 3.4.10 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 Pressurizer Safety Valves LCO 3.4.10 Three pressurizer safety valves shall be OPERABLE with lift settings t 2410* psig and d 2485* psig.
APPLICABILITY: MODES 1, 2, and 3, MODE 4 with all RCS cold leg temperatures > 320qF
NOTE------------------------------------------------
The lift settings are not required to be within the LCO limits during MODES 3 and 4 for the purpose of setting the pressurizer safety valves under ambient (hot) conditions. This exception is allowed for 54 hours2.25 days <br />0.321 weeks <br />0.074 months <br /> following entry into MODE 3 provided a preliminary cold setting was made prior to heatup.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pressurizer safety A.1 Restore valve to 15 minutes valve inoperable. OPERABLE status.
B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> associated Completion Time not met. AND OR B.2 Be in MODE 4 with any 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> RCS cold leg Two or more pressurizer temperatures d 320qF.
safety valves inoperable.
- For Unit 1, through Cycle 13, the three pressurizer safety valve lift settings shall be > 2460 psig and < 2510 psig for the Limiting Condition for Operation.
COMANCHE PEAK - UNITS 1 AND 2 3.4-21 Amendment No. 64, 145
MSSVs 3.7.1 3.7 PLANT SYSTEMS 3.7.1 Main Steam Safety Valves (MSSVs)
LCO 3.7.1 Five MSSVs per steam generator shall be OPERABLE.
APPLICABILITY: MODES 1, 2, and 3 ACTIONS
NOTE----------------------------------------------------------------
Separate Condition entry is allowed for each MSSV.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more steam A. Reduce THERMAL POWER 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> generators with one MSSV to <68% RTP.
inoperable and the Moderator Temperature Coefficient (MTC) zero or negative at all power levels.
(continued)
COMANCHE PEAK - UNITS 1 AND 2 3.7-1 Amendment No. 64, 145
MSSVs 3.7.1 Table 3.7.1-1 (page 1 of 1)
OPERABLE Main Steam Safety Valves versus Maximum Allowable Power NUMBER OF OPERABLE MSSVs MAXIMUM ALLOWABLE POWER PER STEAM GENERATOR (% RTP) 4 d 61 3 d 43 2 d 26 COMANCHE PEAK - UNITS 1 AND 2 3.7-4 Amendment No. 64, 145