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. 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.
145 145 (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. 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.
145 145
Rod Group Alignment Limits 3.1.4 COMANCHE PEAK - UNITS 1 AND 2 3.1-10 Amendment No. 64 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify individual rod positions within alignment limit.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.1.4.2 Verify rod freedom of movement (trippability) by moving each rod not fully inserted in the core 10 steps in either direction.
92 days SR 3.1.4.3 Verify rod drop time of each rod, from the fully withdrawn position, is 2.7 seconds from the beginning of decay of stationary gripper coil voltage to dashpot entry, with:
- a. Tavg 500qF; and Prior to reactor criticality after each removal of the reactor head
, 145
- b. All reactor coolant pumps operating.
RTS Instrumentation 3.3.1 COMANCHE PEAK - UNITS 1 AND 2 3.3-15 Amendment No. 89 Table 3.3.1-1 (page 1 of 7)
Reactor Trip System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE(a)
- 1. Manual Reactor Trip
, 145 1,2 3(b), 4(b), 5(b) 2 2
B C
- 2. Power Range Neutron Flux
- a.
High
- b.
Low 1,2 1(c), 2 4
4 D
E SR 3.3.1.1 SR 3.3.1.2 SR 3.3.1.7 SR 3.3.1.11 SR 3.3.1.16 SR 3.3.1.1 SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.16 d 109.6% RTP(q)(r)#
d 25.6% RTP(q)(r)#
- 3.
Power Range Neutron Flux Rate High Positive Rate 1,2 4
E SR 3.3.1.7 SR 3.3.1.11 d 6.3% RTP with time constant t 2 sec
- 4. Intermediate Range Neutron Flux 1(c), 2(d) 2 F,G SR 3.3.1.1 SR 3.3.1.8 SR 3.3.1.11 d 31.5% RTP (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.
RTS Instrumentation 3.3.1 COMANCHE PEAK - UNITS 1 AND 2 3.3-16 Amendment No. 89 Table 3.3.1-1 (page 2 of 7)
Reactor Trip System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE(a)
- 5. Source Range Neutron Flux 2(e) 3(b), 4(b), 5(b) 2 I,J
, 145 2
J,K SR 3.3.1.1 SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.11 d 1.4 E5 cps d 1.4 E5 cps
- 6.
Overtemperature N-16 1,2 4
E SR 3.3.1.1 SR 3.3.1.2 SR 3.3.1.3 Refer to Note 1(q)(r)
SR 3.3.1.6 SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16
- 7. Overpower N-16 1,2 4
E SR 3.3.1.1 SR 3.3.1.2 SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16 d 112.8% RTP (q)(r)##
- 8. Pressurizer Pressure
- a.
Low
- b.
High 1(g) 1,2 4
4 M
E t 1863.6 psig (Unit 1) t 1865.2 psig (Unit 2) d 2400.8 psig (Unit 1) d 2401.4 psig SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16 SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.10 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.
RTS Instrumentation 3.3.1 COMANCHE PEAK - UNITS 1 AND 2 3.3-17 Amendment No. 64 Table 3.3.1-1 (page 3 of 7)
Reactor Trip System Instrumentation
, 131, 145 FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE(a)
- 9. Pressurizer Water Level - High 1(g) 3 M
SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.10 d 93.9% of instrument span
- 10. Reactor Coolant Flow - Low 1(g) 3 per loop M
SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16 t 88.6% of indicated loop flow (Unit 1) t 88.8% of indicated loop flow (Unit 2)
- 11. Not Used
- 12. Undervoltage RCPs 1(g) 1 per bus M
SR 3.3.1.9 SR 3.3.1.10 SR 3.3.1.16 t 4753 V
- 13. Underfrequency RCPs 1(g) 1 per bus M
SR 3.3.1.9 SR 3.3.1.10 SR 3.3.1.16 t 57.06 Hz
- 14. Steam Generator (SG) Water Level Low-Low (l) 1, 2 4 per SG E
SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.16 t 37.5%### of narrow range instrument span (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.
RTS Instrumentation 3.3.1 COMANCHE PEAK - UNITS 1 AND 2 3.3-18 Amendment No. 64 Table 3.3.1-1 (page 4 of 7)
Reactor Trip System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE(a)
- 16. Turbine Trip
- a.
Low Fluid Oil Pressure
- b.
Turbine Stop Valve Closure 1(j)
O 3
t 46.6 psig SR 3.3.1.10 SR 3.3.1.15 SR 3.3.1.10 SR 3.3.1.15 1(j)
P 4
t 1% open SR 3.3.1.14
- 17. Safety Injection (SI) Input from Engineered Safety Feature Actuation System (ESFAS) 1,2 2 trains Q
NA
, 145
- 18. Reactor Trip System Interlocks
- a.
Intermediate Range Neutron Flux, P-6
- b.
Low Power Reactor Trips Block, P-7
- c.
Power Range Neutron Flux, P-8
- d.
Power Range Neutron Flux, P-9
- e.
Power Range Neutron Flux, P-10
- f.
Turbine First Stage
- Pressure, P-13 2(e) 1 1
1 1,2 1
2 1 per train 4
4 4
2 S
T T
T S
T SR 3.3.1.11 SR 3.3.1.13 SR 3.3.1.5 SR 3.3.1.11 SR 3.3.1.13 SR 3.3.1.11 SR 3.3.1.13 SR 3.3.1.11 SR 3.3.1.13 SR 3.3.1.10 SR 3.3.1.13 t 6E-11 amp NA d 50.7% RTP d 52.7% RTP t 7.3% RTP and d 12.7% RTP d 12.7% turbine power (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.
RTS Instrumentation 3.3.1 COMANCHE PEAK - UNITS 1 AND 2 3.3-19 Amendment No. 64, 145 Table 3.3.1-1 (page 5 of 7)
Reactor Trip System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE(a)
- 19. Reactor Trip Breakers(RTBs)(k) 1,2 3(b), 4(b), 5(b) 2 trains 2 trains R
C SR 3.3.1.4 SR 3.3.1.4 NA NA
- 20. Reactor Trip Breaker Undervoltage and Shunt Trip Mechanisms(k) 1,2 3(b), 4(b), 5(b) 1 each per RTB 1 each per RTB U
C SR 3.3.1.4 SR 3.3.1.4 NA NA
- 21. Automatic Trip Logic 1,2 3(b), 4(b), 5(b) 2 trains 2 trains Q
C SR 3.3.1.5 SR 3.3.1.5 NA 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.
RTS Instrumentation 3.3.1 COMANCHE PEAK - UNITS 1 AND 2 3.3-20 Amendment No. 67 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.
q
f P
P K
T T
S T
1 S
T 1
K K
Q 1
1 3
o c
c 2
1 2
1 setpoint
>>1/4
º
<<¬
Where:
Qsetpoint = Overtemperature N-16 trip setpoint, K1
=
K2
=
- /oF K3
=
- /psig TC =
Measured cold leg temperature, oF Tcq =
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) d *% RTP 0%
when *% RTP < (qt - qb) < *% RTP
- {(qt - qb) - *%}
when (qt - qb) t *% RTP
- as specified in the COLR (continued)
, 145
RTS Instrumentation 3.3.1 COMANCHE PEAK - UNITS 1 AND 2 3.3-20a Amendment No. 145 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.
q
f P
P K
T T
S T
1 S
T 1
K K
Q 1
1 3
o c
c 2
1 2
1 setpoint
>>1/4
º
<<¬
Where:
Qsetpoint = Overtemperature N-16 trip setpoint, K1
=
K2
=
- /oF K3
=
- /psig TC =
Measured cold leg temperature Tcq =
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) d *% RTP 0%
when *% RTP < (qt - qb) < *% RTP
- {(qt - qb) - *%}
when (qt - qb) t *% RTP
- as specified in the COLR
ESFAS Instrumentation 3.3.2 COMANCHE PEAK - UNITS 1 AND 2 3.3-29 Amendment No. 64 Table 3.3.2-1 (page 1 of 6)
Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE(a)
- 1.
Safety Injection
- a.
Manual Initiation 1, 2, 3, 4 2
B SR 3.3.2.8 NA
- b.
Automatic Actuation Logic and Actuation Relays 1, 2, 3, 4 2 trains C
SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 NA
- c.
Containment Pressure --
High 1 1, 2, 3 3
D SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10 d 3.8 psig
- d.
Pressurizer Pressure --
Low 1, 2, 3(b) 4 D
SR 3.3.2.1 t 1803.6 psig SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10
- e.
Steam Line Pressure Low 1, 2, 3(b) 3 per steam line D
SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10 t 594.0 psig(c)
(Unit 1) t 578.4 psig(c)
(Unit 2)
- 2.
- a.
Manual Initiation 1, 2, 3, 4 2 per train, 2 trains B
SR 3.3.2.8 NA
- b.
Automatic Actuation Logic and Actuation Relays 1, 2, 3, 4 2 trains C
SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 NA
- c.
Containment Pressure High -- 3 1, 2, 3 4
E SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10 d 18.8 psig (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.
, 145
ESFAS Instrumentation 3.3.2 COMANCHE PEAK - UNITS 1 AND 2 3.3-30 Amendment No. 64 Table 3.3.2-1 (page 2 of 6)
Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE(a)
- 3.
Containment Isolation
- a.
Phase A Isolation (1) Manual Initiation 1, 2, 3, 4 2
B SR 3.3.2.8 NA (2) Automatic Actuation Logic and Actuation Relays 1, 2, 3, 4 2 trains SR 3.3.2.2 SR 3.3.2.4 C
SR 3.3.2.6 NA (3) Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
- b.
Phase B Isolation (1) Manual Initiation 1, 2, 3, 4 2 per train, 2 trains B
SR 3.3.2.8 NA (2) Automatic Actuation Logic and Actuation Relays 1, 2, 3, 4 2 trains C
SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 NA (3) Contain-ment Pressure High -- 3 1, 2, 3 4
E SR 3.3.2.1 d 18.8 psig SR 3.3.2.5 SR 3.3.2.9 (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.
, 145
ESFAS Instrumentation 3.3.2 COMANCHE PEAK - UNITS 1 AND 2 3.3-31 Amendment No. 64 Table 3.3.2-1 (page 3 of 6)
Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS SURVEILLANCE REQUIREMENTS CONDITIONS ALLOWABLE VALUE(a)
- 4.
Steam Line Isolation
- a.
Manual Initiation 1, 2(i), 3(i) 2 F
SR 3.3.2.8 NA
- b.
Automatic Actuation Logic and Actuation Relays 1, 2(i), 3(i) 2 trains G
NA SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6
- c.
Containment Pressure --
High 2 1, 2(i), 3(i) 3 D
SR 3.3.2.1 d 6.8 psig SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10
, 145
- d.
Steam Line Pressure (1) Low 1, 2(i), 3(b)(i) 3 per steam line D
SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10 t 594.0 psig(c)
(Unit 1) t 578.4 psig(c)
(Unit 2) 3(g)(i) 3 per steam line D
SR 3.3.2.1 (2) Negative Rate --
High d 178.7 psi(h)
SR 3.3.2.5 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.
ESFAS Instrumentation 3.3.2 COMANCHE PEAK - UNITS 1 AND 2 3.3-32 Amendment No. 64 Table 3.3.2-1 (page 4 of 6)
Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE(a)
- 5.
Turbine Trip and Feedwater Isolation
- a.
Automatic Actuation Logic and Actuation Relays 1, 2(j) 2 trains H
SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 NA d 84.5%# of narrow range span (Unit 1) (q)(r) d 82.0% of narrow range span (Unit 2) (q)(r)
- b.
SG Water Level -- High High (P-14) 1, 2(j) 3 per SG(p)
I SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10
, 131, 145
- 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.
ESFAS Instrumentation 3.3.2 COMANCHE PEAK - UNITS 1 AND 2 3.3-33 Amendment No. 64 Table 3.3.2-1 (page 5 of 6)
Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE(a)
- 6.
- a.
Automatic Actuation Logic and Actuation Relays (Solid State Protection System) 1, 2, 3 G
SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 NA 2 trains
- b.
Not Used.
- c.
SG Water Level Low-Low 1, 2, 3 4 per SG
, 131, 145 D
SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10
>37.5%## of narrow range span (Unit 1) (q)(r)
>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 Power 1, 2, 3 1 per train F
SR 3.3.2.7 SR 3.3.2.9 SR 3.3.2.10 NA
- f.
Not Used.
- g.
Trip of all Main Feedwater Pumps 1, 2 2 per AFW pump J
SR 3.3.2.8 NA
- 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.
ESFAS Instrumentation 3.3.2 COMANCHE PEAK - UNITS 1 AND 2 3.3-34 Amendment No. 125 Table 3.3.2-1 (page 6 of 6)
Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS SURVEILLANCE REQUIREMENTS CONDITIONS ALLOWABLE VALUE(a)
- 7.
Automatic Switchover to Containment Sump
- a.
Automatic Actuation Logic and Actuation Relays 1, 2, 3, 4 2 trains C
SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 NA
- b.
Refueling Water Storage Tank (RWST)
Level - Low Low 1, 2, 3, 4 4
K SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10 t 31.9(b)%
instrument span Coincident with Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
- 8.
ESFAS Interlocks
- a.
Reactor Trip, P-4 1, 2, 3 1 per train, 2 trains F
SR 3.3.2.11 NA
- b.
Pressurizer Pressure, P-11 1, 2, 3 3
L SR 3.3.2.5 d 1975.2 psig 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.
, 129, 145
Pressurizer Safety Valves 3.4.10 COMANCHE PEAK - UNITS 1 AND 2 3.4-21 Amendment No. 64 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 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 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 valve inoperable.
A.1 Restore valve to OPERABLE status.
15 minutes B. Required Action and associated Completion Time not met.
OR Two or more pressurizer safety valves inoperable.
B.1 Be in MODE 3.
AND B.2 Be in MODE 4 with any RCS cold leg temperatures d 320qF.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 12 hours 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.
, 145
MSSVs 3.7.1 COMANCHE PEAK - UNITS 1 AND 2 3.7-1 Amendment No. 64 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 generators with one MSSV inoperable and the Moderator Temperature Coefficient (MTC) zero or negative at all power levels.
A.
Reduce THERMAL POWER to <68% RTP.
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (continued)
, 145
MSSVs 3.7.1 COMANCHE PEAK - UNITS 1 AND 2 3.7-4 Amendment No. 64 Table 3.7.1-1 (page 1 of 1)
OPERABLE Main Steam Safety Valves versus Maximum Allowable Power NUMBER OF OPERABLE MSSVs PER STEAM GENERATOR MAXIMUM ALLOWABLE POWER
(% RTP) 4 3
2 d 61 d 43
, 145 d 26