ML20101L071

Amends 49 & 35 to Licenses NPF-87 & NPF-89,respectively, Revising Core Safety Limit Curves & Revised Overtemperature Reactor Trip Setpoints

ML20101L071
Person / Time
Site:	Comanche Peak
Issue date:	04/01/1996
From:	Polich T NRC (Affiliation Not Assigned)
To:
Shared Package
ML20101L074	List: ML20101L071 ML20101L076
References
NUDOCS 9604030228
Download: ML20101L071 (16)

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j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066-0001

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TEXAS UTILITIES ELECTRIC COMPANY COMANCHE PEAK STEAM ELECTRIC STATION. UNIT 1 DOCKET N0. 50-445 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 49 License No. NPF-87 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Texas Utilities Electric Company (TV Electric, the licensee) dated November 21, 1995 (TXX-95288), as supplemented by letters dated December 15, 1995 (TXX-95306), and February 2, 1996 (TXX-96040), complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, as-amended, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance:

(i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this license ai.,endment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

9604030228 960401 PDR ADOCK 05000445 P

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. 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-87 is hereby amended to read as follows:

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, both of which are attached hereto, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

The license amendment is effective as of its date of issuance to be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION C/M Timothy J. Polich, Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

April 1, 1996

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4 UNITED STATES g

,g NUCLEAR REGULATORY COMMISSION

'f WASHINGTON. D.C. 2068H001 l

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TEXAS UTILITIES ELECTRIC COMPANY COMANCHE PEAK STEAM ELECTRIC STATION. UNIT ?

DOCKET NO. 50-446 AMENDMENT TO FACILITY OPERATING LICENSE l

Amendment No. 35 License No. NPF-89 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Texas Utilitics Electric Company (TV Electric, the licensee) dated November 21, 1995 (TXX-95288), as supplemented by letters dated December 15, 1995, (TXX-95306), and February 2, 1996 (TXX-96040), complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

i and the Commission's rules and regulations set forth in 10 CFR Chapter I-B.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance:

(i) that the activities authorized by this amendment can be conducted without endangerieg the health and safety of the public, and (ii) that such activitlcs will be conducted in compliance with the Commission's regulations; D.

The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and

)

E.

The issuance of this amendaait is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

. 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-89 is hereby amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan i

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.

TU Electric shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance to be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION Timothy J. Polich, Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

April 1, 1996 i

i i

i i

i l

i l

l i

l ATTACHMENT TO LICENSE AMENDMENT NOS.49 AND 35 FACILITY OPERATING LICENSE NOS. NPF-87 AND NPF-89 DOCKET NOS. 50-445 AND 50-446 l

r Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain marginal lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.

REMOVE INSERT 2-3 2-3 2-6 2-6 2-9 2-9 2-11 2-11 B 2-7 B 2-7 3/4 2-12 3/4 2-12

-r

-.r e

i UNIT 2 REACTOR CORE SAFETY LIMITS RCS TAVG (P) 670 I

~

UNACCEPTABLE OPERATION

~

P = 2385 PSIG 650 -

i P = 2235 PSIG 640 -

I I

630 -

l l

1 l

i P = 1985 PSIG 620 -

)

P = 1845 PSIG 610 -

600 -

590 -

I ACCEPTABLE 580 i

l OPERATION i

570

(

560.

1 i

1 i

550 i

3 i

0 20 40 60 80 100 120 PERCENT OF RATED THERMAL POWER i

FIGURE 2.1-lb UNIT 2 REACTOR CORE SAFETY LIMITS l

l l

COMANCHE PEAK - UNITS 1 AND 2 2-3 Unit 1 - Amendment No. 44, 49 Unit 2 - Amendment No.

35

TABLE 2.2-1 REACTOR TRIP SYSTEN INSTRIMENTATION TRIP SETPOINTS FUNCTIONAL UKIT TRIP _SETP01MT ALL0l@BLE VALUE 1.

Manual Reactor Trip N.A.

N.A 2.

Power Range Neutron Flux a.

High Setpoint

$109% of RTP*

s111.7% of RTP*

i b.

Low Setpoint s25% of RTP*

s27.7 of RTP*

i i

3.

Power Range, Neutron Flux, 55% of RTP* with 56.3% of RTP* with i

High Positive Pate a time constar.t a time constant i

22 seconds 22 seconds 4.

Not Used 5.

Intermediate Range, s25% of RTP*

531.5 of RTP*

Neutron Flux i

5 5

6.

Source Range, Neutron Flux s10 cps sl.4 x 10 cps 7.

Overtemperature N-16 See Note 1 See Note 2 l

RTP = RATED THERNAL POWER i

I COMANCHE PEAK - UNIT I AND 2 2-5 Unit 1 - Amendment No. 2,14.21,3",41 t

Unit 2 - Amendment No. h46,27 L

6

TABLE 2.2-1 (Continued)

TABLE NOTATIONS NOTE 1: Overtemperature N-16

+

[1+rs T,-T,*] + K3 (P-P') - f, (aq)

N K -K i 2 a

Where:

N Measured N-16 Power by ion chambers, T,

Cold leg temperature, *F, Tl 560.5'F for Unit 1, 560.8'F for Unit 2 - Reference T, at RATED THERMAL POWER, l

K 1.150, i

K, 0.0134/*F for Unit 1 0.013e/ r for Unit 2 i

1+71 The function generated by the lead-lag controller for 1

1+T52 T, dynamic compensation, Time constants utilized in the lead-lag controller for r,72 i

T,, r 210 s, and r, s 3 s, i

K3 0.000719/psig for Unit 1 l

=

0.000720/psig for Unit 2 1

COMANCHE PEAK - UNIT 1 AND 2 2-9 Unit 1 - Amendment No. 44r42, 49 Unit 2 - Amendment No. 7, 35

TABLE 2.2-1 (Continued)

TABLE NOTATIONS (Continued)

NOTE 1:

(Continued)

For Unit 2 (1) for q - q, between -65% and +2.5%, f (aq) = 0, where q RATED, THERMAL POWER in the top and bo,ttom halves of the, and q, are percent l

core respectively, and q, + q, is total THERMAL POWER in percent of RATED THERMAL POWER, (ii) for each percent that the magnitude of q - q, exceeds -65%, the N-16 Trip Setpoint shall be automatically reduced by 1.86% of its value at RATED THERMAL POWER, and (iii) for each percent that the magnitude of q

-q exceeds +2.5%, the N-16 Trip Setpoint shall be automatically reduced by 1.,65% of its value at RATED THERMAL 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 1.88% of span for Unit 2.

l COMANCHE PEAK - UNIT 1 AND 2 2-11 Unit 1 - Amendment No. li,21,il, 49 Unit 2 - Amendment No. hB7, 35

l LIMITING SAFETY SYSTEM SETTINGS 1

BASES l

I Undervoltaae and Underfreauency - Reactor Coolant Pumo Busses The Undervoltage and Underfrequency Reactor Coolant Pump Bus trips provide core protection against DNB as a result of complete loss of forced coolant i

flow.

The specified setpoints assure a Reactor trip signal is generated before the Low Flow Trip Setpoint is reached. Time delays are incorporated in the Underfrequency and Undervoltage trips to prevent spurious Reactor trips from momentary electrical power transients. On decreasing power the Undervoltage l

j and Underfrequency Reactor Coolant Pump Bus trips are automatically blocked by P-7 (a power level of approximately 10% of RATED THERMAL POWER with a turbine first stage chamber pressure at approximately 10% of full power equivalent);

and on increasing power, reinstated automatically by P-7.

i Turbine Trio A Turbine trip initiates a Reactor trip. On decreasing power the Reactor trip from the Turbine trip is automatically blocked by P-9 (a power level of approximately 50% of RATED THERMAL POWER); and on increasing power, reinstated automatically by P-9.

Safety Iniection Inout from ESF If a Reactor trip has not already been generated by the Reactor Trip System instrumentation, the ESF automatic actuation logic channels will initiate a Reactor trip upon any signal which initiates a Safety Injection. The ESF instrumentation channels which initiate a Safety Injection signal are shown in Table 3.3-2.

COMANCHE PEAK - UNITS 1 AND 2 B 2-7 Unit 1 - Amendment No. 49 Unit 2 - Amendment No. 35

UNIT 2 REACTOR CORE SAFETY LIMITS t

RCS TAVG (F) 670 J

UNACCEPTABLE I

l 660 -

OPERATION

~

P = 2385 PSIG 650 -

P = 2235 PSIG i

630 -

j i

P = 1985 PSIG 620 -

P = 1845 PSIG 610 -

600 -

l 590 -

ACCEPTABLE 580 I

OPERATION

)

570 l

l I

560,

I i

550 3

i i

0 20 40 60 80 100 120 PERCENT OF RATED THERMAL POWER i

FIGURE 2.1-lb UNIT 2 REACTOR CORE SAFETY LIMITS COMANCHE PEAK - UNITS 1 AND 2 2-3 Unit 1 - Amendment NO. H, 49 Unit 2 - Amendment NO.

35 1

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 Interlock Setpoints shall be set consistent with the Trip Setpoint values shown in Table 2.2-1.

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

ACTION:

a.

With a Reactor Trip System Instrumentation or Interlock Setpoint less conservative than the value shown in the Trip Setpoint column but more conservative than the value shown in the Allowable Value column of Table 2.2-1, adjust the setpoint consistent with the Trip Setpoint value.

b.

With the 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 l the channel is restored to OPERABLE status with its setpoint adjusted consistent with the Trip Setpoint value.

1 COMANCHE PEAK - UNITS 1 AND 2 2-4 Unit 1 - Amendment No. 41 Unit 2 - Amendment No. 27

TABLE 2.2-1 f

REACTOR TRIP SYSTEN INSTRIMENTATION TRIP SETPOINTS t

FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE 1.

Manual Reactor Trip N.A.

M.A 2.

Power Range, Neutron Flux a.

High Setpoint

$1095 of RTP*

s111.7% of RTP*

l b.

Low Setpoint 525% of RTP*

$27.7 of RTP*

t 3.

Power Range, Neutron Flux, 55% of RTP* with s6.3% of RTP* with High Positive Rate a time constant a time constant i

22 seconds 22 seconds fi 4.

Not Used t

5.

Intermediate Range, s25% of RTP*

s31.5 of RTP*

i Neutron Flux 5

5 6.

Source Range, Neutron Flux s10 cps 51.4 x 10 cps 7.

Overtemperature N-16 See Note 1 See Note 2 l

RTP = RATED THERNAL POWER I

t 4

COMANCHE PEAK - UNIT 1 AND 2 2-5 Unit I - Amendment No. 2,14,21,3a,41 Unit 2 - Amendment No. h46,27

TABLE 2.2-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS i

1 EUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE i

8.

Overpower N-16 s112% of RTP*

sll4.5% of RTP*

9.

Pressurizer Pressure-Low

a. Unit 1 21880 psig 21863.6 psig

b. Unit 2 21880 psig 21865.2 psig

10. Pressurizer Pressure-High

a. Unit I s2385 psig

$2400.8 psig

b. Unit 2 s2385 psig s2401.4 psig j

11.

Pressurizer Water Level-High 592% of instrument 593.9% of instrument span span

12. Reactor Coolant Flow-Low 4

a. Unit 1 290% of instrument 288.6% of instrument span span

b. Unit 2 290% of instrument 288.8% of instrument span span i

i 1

RTP = RATED THERMAL POWER l

COMANCHE PEAK - UNIT 1 AND 2 2-6 Unit 1 - Amendment No. I',21,?1, 49 Unit 2 - Amendment No h N,

35

TABLE 2.2-1 (Continued)

TABLE NOTATIONS NOTE 1: Overtemperature N-16 1 + r,s K,-K2[1+rs T,-T,*] + K3 (P-P') - f, (aq)

N

=

a Where:

N Measured N-16 Power by ion chambers,

=

T, Cold leg temperature, "F,

=

T*

560.5'F for Unit 1, 560.8"F for Unit 2 - Reference T, at RATED THERMAL POWER, l

{

=

t K,

1.150,

=

K2 0.0134/*F for Unit 1 0.0138/*F for Unit 2 l

1+rl The function generated by the lead-lag controller for i

1+Ts2 T, dynamic compensation, Time constants utilized in the lead-lag controller for r,,

r2 i

T,, r, 210 s, and 72s3s, K3 0.000719/psig for Unit 1 l

=

0.000720/psig for Unit 2 COMANCHE PEAK - UNIT 1 AND 2 2-9 Unit 1 - Amendment No. 44rM, 49 Unit 2 - Amendment No. 7, 35

i i

2 i

I TABLE 2.2-1 (Continued)

M 1

5 TABLE NOTATIONS (Continued) y NOTE 1:

(Continued)

E P

Pressurizer pressure, psig, e

i 3

P 2

2235 psig (Nominal RCS operating pressure),

S Laplace transform operator, s,

$E and f aq is a function of the indicated difference between top and bottom halves of deteck(ors)of the power-range neutron ion chambers; with gains 3

j measured instrument response during plant STARTUP tests such that:

l For Unit 1 (1) for q - q, between -65% and +4%, f (aq) - 0, where q and q are percent l

4 RATED, THERMAL POWER in the top and bottom halves of lhe cor,e resp i

my, and q, + q, is total THERMAL POWER in percent of. RATED THERMAL POWER, o

(ii) for each percent that the magnitude of q - q, exceeds -65%, the N-16 Trip Setpointshallbeautomaticallyreducedby1.81%ofitsvalueatRATED THERMAL POWER, and i

S gg (iii) for each percent that the magnitude of q

[

Setpointshallbeautomaticallyreducedby2.26%ofitsvalueatRATED-q, exceeds +4%, th THERMAL POWER.

e i

7 i

i

TABLE 2.2-1 (Continued)

TABLE NOTATIONS (Continued)

NOTE 1:

(Continued)

For Unit 2 (1) for q

-q between -65% and +2.5%, f (aq) = 0, where q and q are percent l

RATED,THER, MAL POWER in the top and bo,ttom halves of the, core,respectively, and q, + q, is total THERMAL POWER in percent of RATED THERMAL POWER, (ii) for each percent that the magnitude of q

-q exceeds -65%, the N-16 Trip Setpoint shall be automatically reduced by 1.,86% of its value at RATED THERMAL POWER, and (iii) for each percent that the magnitude of q

-q exceeds +2.5%, the N-16 Trip Setpoint shall be automatically reduced by 1.,65% of its value at RATED THERMAL 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 1.88% of span for Unit 2.

l i

i 1

COMANCHE PEAK - UNIT 1 AND 2 2-11 Unit 1 - Amendment No. 11,21,11, 49 Unit 2 - Amendment No. h27, 35

LIMITING SAFETY SYSTEM SETTINGS BASES Undervoltaae and Underfreauency - Reactor Coolant Pumo Busses The Undervoltage and Underfrequency Reactor Coolant Pump Bus trips provide core protection against DNB as a result of complete loss of forced coolant flow. The specified setpoints assure a Reactor trip signal is generated before the Low Flow Trip Setpoint is reached. Time delays are incorporated in the Underfrequency and Undervoltage trips to prevent spurious Reactor trips from momentary electrical power transients. On decreasing power the Undervoltage l

and Underfrequency Reactor Coolant Pump Bus trips are automatically blocked by P-7 (a power level of approximately 10% of RATED THERMAL POWER with a turbine first stage chamber pressure at approximately 10% of full power equivalent);

and on increasing power, reinstated automaticaily by P-7.

Turbine Trio A Turbine trip initiates a Reactor trip.

On decreasing power the Reactor trip from the Turbine trip is automatically blocked by P-9 (a power level of approximately 50% of RATED THERMAL POWER); and on increasing power, reinstated automatically by P-9.

Safety In.iection Inout from ESF If a Reactor trip has not already been generated by the Reactor Trip System instrumentation, the ESF automatic actuation logic channels will initiate a Reactor trip upon any signal which initiates a Safety Injection.

The ESF instrumentation channels which initiate a Safety Injection signal are shown in Table 3.3-2.

COMANCHE PEAK - UNITS 1 AND 2 B 2-7 Unit 1 - Amendment No. 49 Unit 2 - Amendment No. 35 i

l i

l LIMITING SAFETY SYSTEM SETTINGS BASES i

l Reactor Trio System Interlocks The Reactor Trip System interlocks perform the following functions:

P-6 On increasing power, P-6 allows the manual block of the Source Range trip (i.e., prevents premature block of Source Range trip), provides i

a backup block for Source Range Neutron Flux doubl ng, and deener-gizes the high voltage to the detectors. On decreasing power, Source l

Range Level trips are automatically reactivated and high voltage l

restored.

j P-7 On increasing power, P-7 automatically enables Reactor trips on low flow in more than one reactor coolant loop, reactor coolant pump j

bus undervoltage and underfrequency, pressurizer low pressure and j

pressurizer high level.

On decreasing power, the above listed trips j

are automatically blocked.

j P-8 On increasing power, P-8 automatically enables the Reactor trip on low flow in one reactor coolant loop.

On decreasing power, the P-8 i

automatically blocks the reactor trip on low flow in one reactor i

coolant loop.

P-9 On increasing power, P-9 automatically enables Reactor trip on l

Turbine trip. On decreasing power, P-9 automatically blocks Reactor l

trip on Turbine trip.

1 P-10 On increasing power, P-10 allows the manual block of the Intermediate

{

Range trip and the Low Setpoint Power Range trip; and automatically blocks the Source Range trip and de-energizes the Source Range high l

voltage power.

On decreasing power, the Intermediate Range trip and the Low Setpoint Power Range trip are automatically reactivated.

Provides input to P-7.

j P-13 Turbine first stage chamber pressure provides input to P-7.

.i i

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i COMANCHE PEAK - UNITS 1 AND 2 8 2-8

POWER DISTRIBtJTION LIMITS SURVEILLANCE REQUIREMENTS 4.2.4.1 The QUADRANT POWER TILT RATIO shall be determined to be within the limit above 535 of RATED THERMAL POWER by:

a.

Calculating the ratio at least once per 7 days when the alarm is

OPERABLE, l

b.

Calculating the ratio at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the alarm is inoperable, and l

c.

Calculating the ratio at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when above 75%

l RATED THERMAL POWER with one Power Range channel inoperable.

i i

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I COMANCHE PEAK - UNITS 1 AND 2 3/4 2-11 Unit 1 - Amendment No. 36 Unit 2 - Amendment No. 22

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:

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

b.

Indicated Pressurizer Pressure 2 2219 psig*

Indicated Reactor Coolant System (RCS) Flow 2 403,400 gpm** for Unit 1 c.

2 408,000 gpm** for Unit 2 l

APPLICABILITY: MODE 1.

ACTION:

With any of the above parameters exceeding its limit, restore the parameter to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 5%

RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

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

i 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 temperature, the main steam pres-within 90 days of performing the calorimetric flow measurement.sure

• 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 Unit 1 - Amendment No. 14,21,10, 49 Unit 2 - Amendment No. h44, 35

-