ML070350047

Technical Specifications, Issuance of Amendment Nos. 131 & 131 Technical Specification Changes Related to Unit 1 Steam Generator Replacement Project (TAC Nos. MD0187 & MD0188)

ML070350047
Person / Time
Site:	Comanche Peak
Issue date:	02/20/2007
From:	NRC/NRR/ADRO/DORL/LPLIV
To:
Thadani, M C, NRR/DORL/LP4, 415-1476
Shared Package
ML070350045	List: ML070350046 ML070350047
References
TAC MD0187, TAC MD0188
Download: ML070350047 (7)

Text

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 3 of 6)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE(a)

10. Reactor Coolant Flow - Low i (g) 3 per loop M

SR3.3.1.1 SR 3.3.1.7 SR3.3.1.10 SR 3.3.1.16

> 88.6% of indicated loop flow (Unit 1)

> 88.8% of indicated loop flow (Unit 2)

11. Not Used

12. Undervoltage RCPs

13. Underfrequency RCPs

14. Steam Generator (SG) Water Level Low-Low (I)

I(g) 1 per bus I(g) 1 per bus M

SR3.3.1.9 SR 3.3.1.10 SR 3.3.1.16 M

SR3.3.1.9 SR3.3.1.10 SR 3.3.1.16 E

SR 3.3.1.1 SR 3.3.1.7 SR3.3.1.10 SR 3.3.1.16 z 4753 V

> 57.06 Hz 1,2 4 per SG

> 36% of narrow range instrument span (Unit 1) (q)(r)

> 33.4% of narrow range instrument span (Unit 2)

I I

15. Not Used.

16. Turbine Trip

a.

Low Fluid Oil Pressure

b.

Turbine Stop Valve Closure 10) 10) 3 4

0 SR3.3.1.10 SR 3.3.1.15 P

SR3.3.1.10 SR 3.3.1.15

> 46.6 psig

> 1% open (continued)

(a) The Allowable Value defines the limiting safety system setting. See the Bases for the Trip Setpoints.

(g) Above the P-7 (Low Power Reactor Trips Block) Interlock.

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

(I) 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.

COMANCHE PEAK - UNITS I AND 2 3.3-17 Amendment No. 64, 131

RTS Instrumentation 3.3.1 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 1,20) 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

< 86% of Level - High SR 3.3.2.5 narrow range High (P-14)

SR 3.3.2.9 span (Unit 1) (q)(r)

SR 3.3.2.10

,583.5% of narrow range span (Unit 2)

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. See the Bases for the Trip Setpoints.

(j) Except when all MFIVs and associated bypass valves are dosed and de-activated or Isolated by a dosed 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 determine the as-left tolerance shall be specified in the Technical Specification Bases.

II COMANCHE PEAK - UNITS 1 AND 2 3.3-32 Amendment No.-64, 131

ERFAS 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)

6.

Auxiliary Feedwater

a.

Automatic Actuation Logic and Actuation Relays (Solid State Protection System) 1,2,3 2 trains G

SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 NA

b.

Not Used.

c.

SG Water Level Low-Low 1.2,3 4 per SG D

SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10 2ý 36% of narrow range span (Unit 1)(q)(r)

> 33.4% of narrow range span (Unit 2)

II

d.

Safety Injection

e.

Loss of Offsite Power Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

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

h.

Not Used.

1,2 2 per AFW pump J

SR 3.3.2.8 NA (continued)

(a) The Allowable Value defines the limiting safety system setting. See the Bases for the 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 setpolnt 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 Setpolnt; 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.

COMANCHE PEAK - UNITS 1 AND 2 3.3-33 Amendment No.-64, 131

RCS Loops -MODE 3

3.4.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 Verify required RCS loops are in operation.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.4.5.2 Verify steam generator secondary side water levels are 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

>38% (Unit 1) and Ž10% (Unit 2) for required RCS loops.

SR 3.4.5.3 Verify correct breaker alignment and indicated power are 7 days available to the required pump that is not in operation.

I COMANCHE PEAK - UNITS 1 AND 2 3.4-10 Amendment No.-64, 131

RCS Loops -MODE 4

3.4.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Verify one RHR or RCS loop is in operation.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.4.6.2 Verify SG secondary side water levels are k38% (Unit 1) 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and k10% (Unit 2) for required RCS loops.

SR 3.4.6.3 Verify correct breaker alignment and Indicated power are 7 days available to the required pump that Is not in operation.

I Amendment No.-&ý 131 COMANCHE PEAK - UNITS I AND 2 3.4-13

RCS Loops -

MODE 5, Loops Filled 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 RCS Loops -MODE 5, Loops Filled LCO 3.4.7 One residual heat removal (RHR) loop shall be OPERABLE and in operation, and either:

a. One additional RHR loop shall be OPERABLE; or

b. The secondary side water level of at least two steam generators (SGs) shall be >38% (Unit 1) and _10% (Unit 2).

NOTES

1. The RHR pump of the loop in operation may be removed from operation for < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period provided:

a. No operations are permitted that would cause introduction of coolant into the RCS with boron concentration less than required to meet the SDM of LCO 3.1.1; and

b. Core outlet temperature is maintained at least 10°F below saturation temperature.

2. One required RHR loop may be inoperable 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 provided that the other RHR loop is OPERABLE and in operation.

3. No reactor coolant pump shall be started with any RCS cold leg temperature < 350°F unless the secondary side water temperature of each SG is < 50*F above each of the RCS cold leg temperatures.

4. All RHR loops may be removed from operation during planned heatup to MODE 4 when at least one RCS loop is in operation.

APPLICABILITY:

MODE 5 with RCS loops filled COMANCHE PEAK - UNITS 1 AND 2 3.4-14 Amendment No. 495, 131

RCS Loops -MODE 5, Loops Filled 3.4.7 SURVEILLANCE FREQUENCY SR 3.4.7.2 Verify SG secondary side water level is >38% (Unit 1) 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and >10% (Unit 2) in required SGs.

SR 3.4.7.3 Verify correct breaker alignment and indicated power are 7 days available to the required RHR pump that is not in operation.

I COMANCHE PEAK - UNITS 1 AND 2 3.4-16 Amendment No.-64, 131