Text

Proposed Tech Specs,Incorporating Revised Core Safety Limit Curves & Revised N-16 Overtemp Reactor Trip Setpoints, Resulting from Reload Analyses for CPSES Unit 2,Cycle 3
	ML20094N901
Person / Time
Site:	Comanche Peak
Issue date:	11/21/1995
From:	; TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	;
Shared Package
ML20094N899	List: ML20094N901; TXX-9528, LAR 95-008 to License NPF-87 & NPF-89,incorporating Revised Core Safety Limit Curves & Revised N-16 Overtemp Reactor Trip Setpoints,Resulting from Reload Analyses for CPSES Unit 2,Cycle 3;
References
	NUDOCS 9511280219
	Download: ML20094N901 (7)
	v • d • e

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I ATTACHMENT 3 to TXX 95288 AFFECTED TECHNICAL SPECIFICATION PAGES I

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l 9511280219 951121 PDR ADOCK 05000445 -

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Attachment 3 to TXX 95288 Page 1 of 6 l

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660 650 P = _. P.4 ,

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550 0 40 60 80 100 \ 120 PERCENT OF RATED THERMAL POWER TIGIME 2.1-lb UNIT 2 REACTOR CORE SAFETY LIMITS COMANCHE PEAK - UNITS 1 AND 2 23 Unit 1 - Amendment No. 14

Attachment 3 to TXX 95288 Page 2 of 6 RCS - TAVG (F) 670

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OPERATION

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l ACCEPTABLE 580

_ OPERATION 570 560 550 ,

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, PERCENT OF RATED THERMAL POWER

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.. to TXX-95288 Page 3 of 6 .

TABLE 2.2-1 (Continued)

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REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE

8. Overpower N-16 5112% of RTP* 1114.5% of RTP*

9. Pressurizer Pressure-Low

a. Unit 1 11880 psig t1863.6 psig

b. Unit 2 11880 psig E1865.2 psig i

10. Pressurizer Pressure-High

a. Unit 1 12385 psig 12400.8 psig

b. Unit 2 52385 psig 12401.4 psig

11. Pressurizer Water Level-High 192% of 193.9% of instrument span instrument span ,

12. Reactor Coolant Flow-Low

a. Unit 1 190% of-+eepG nstrumentispan) 188.6% of-leep-;iinstrument'Jpan; design flow" dcsign ficw " i

b. Unit 2 190% of-leeMfnstrumentXspanj 188.8% of-leepiin,strtimentDpanj

ini;u; ;;;surcd eini;;; ;cesured fi cw"' fl ow"'

RTP = RATED THERMAL POWER

" Loop design flow = 00.050 spa.

- ' Loop einieu; ;casured flow = 00.500 sp;.

COMANCHE PEAK - UNIT 1 AND 2 2-6

to TXX-95288 Page 4 of 6 i

TABLE 2.2-1 (Continued)

TABLE NOTATIONS NOTE 1: Overtemperature N-16 N=K - 1 K, [ 1+ 1 1 T c - T c"] + K3 (P-P ) -f1 (aq) 1 2

1+ 1,s Where:

N = Measured N-16 Power by ion chambers, Tc =

Cold leg temperature. *F.

T' c

560,5 F for Unit 1, 550.3560;8 F for Unit 2 - Reference T at RATED c THERNAL POWER, K1 = 1.150, K2

0.0134/*F for Unit 1 0.0150550.0138/*F for Unit 2 1+ 11 1

- The function generated by the lead-lag controller for Tc ,

1+ 1,5 dynamic compensation, 11, 12 - Time constants utilized in the lead-lag controller for Tc .1 1 > 10s, and I, s 3s, K3 = 0.000719/psig for Unit 1

&-000B980;00_0720/psig for Unit 2 COMANCHE PEAK - UNITS 1 AND 2 2-6

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Attachment 3 to TXX-95288 Page 5 of 6 TABLE 2.2-1 (Continued) !

. TABLE NOTATIONS (Continued)

NOTE 1: (Continued)

For Unit 2 (i) for qt - q, between -5065% and +5:52:5%. f (a q) = 0, where q, and q, are percent t

i RATED THERMAL POWER in the top and bottom halves of the core respectively.

and qt + g, is total THERMAL POWER in percent of RATED THERMAL POWER. ,

(ii) for each percent that the magnitude of q, - q, exceeds -5265%. the N-16 Trip Setpoint shall be automatically reduced by 2-151!86% of its value at RATED THERMAL '

POWER, and (iii) for each percent that the magnitude of q, - q, exceeds +5:52;5%. the N-16 Trip Setpoint shall be automatically reduced by 2:171:65% of its value at RATED THERMAL i POWER. !

! NOTE 2: The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 3.51% .

of span for Unit 1 or Br851188% of span for Unit 2. ;

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t l COMANCHE PEAK - UNITS 1 AND 2 2-9 [

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Attachment 3 to TXX-95288 Page 6 of 6 POWER DISTRIBUTION LIMITS 3/4.2.5 DNB PARAMETERS LIMITING CONDITION FOR OPERATION 3.2.5 The following DNB-related parameters shall be maintained within the stated limits:

a. Indicated Reactor Coolant System T.,,5 592*F

b. Indicated Pressurizer Pressure 1 2219 psig*

c. Indicated Reactor Coolant System (RCS) Flow 1 403,400 gpm** for Unit 1 2 305.200 gpm** for Unit 2 APPLICABILITY: MODE 1. 408[000 ACTION:

With any of the above parameters exceeding its limit, restore the parameter to within its limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SURVEILLANCE REQUIREMENTS 4.2.5.1 Each of the above parameters shall be verified to be within its limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.2.5.2 The RCS total flow rate shall be verified to be within its limits at least once per 31 days by plant computer indication or measurement of the RCS elbow tap differential pressure transmitters' output voltage.

4.2.5.3 The RCS loop flow rate indicators shall be subjected to a CHANNEL CALIBRATION at least once per 18 months. The channels shall be normalized based on the RCS flow rate determination of Surveillance Requirement 4.2.5.4.

4.2.5.4 The RCS total flow rate shall be determined by precision heat balance measurement after each fuel loading and prior to operation above 85% of RATED THERMAL POWER. The feedwater pressure and tcoperature, the main steam pressure, and feedwater flow differential pressure instruments shall be calibrated within 90 days of performing the calorimetric flow measurement.

Limit not applicable during either a THERMAL POWER ramp in excess of 5% of RATED THERMAL POWER per minute or a THERMAL POWER step in excess of 10% of RATED THERMAL POWER.

- Includes a 1.8% flow measurement uncertainty.

COMANCHE PEAK UNITS 1 AND 2 3/4 2 12

ML20094N901

Text

560,5 F for Unit 1, 550.3560;8 F for Unit 2 - Reference T at RATED c THERNAL POWER, K1 = 1.150, K2

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