ML032730666

TS Pages - Palo Verde Amendment 149

ML032730666
Person / Time
Site:	Palo Verde
Issue date:	09/29/2003
From:	NRC/NRR/DLPM
To:
Donohew J N, NRR/DLPM,415-1307
Shared Package
ML032731029	List: ML032720538 ML032730666
References
TAC MB3696
Download: ML032730666 (9)

Text

(8)(a) Arizona Public Service Company is authorized to transfer all or a portion of its 29.1% ownership share in Palo Verde, Unit 2 to certain equity investors identified in its submissions of August 6, August 8 and December 5, 1986, and at the same time to lease back from such purchasers such interest sold in the Palo Verde, Unit 2 facility. The term of the lease is for approximately 29-2 years subject to a right of renewal. Additional sale and leaseback transactions of all or a portion of APS's remaining ownership share in Palo Verde, Unit 2 are hereby authorized until June 30, 1987. Any such sale and lease back transaction is subject to the representations and conditions set forth in the aforementioned application of May 2, 1986, and the subsequent submittals dated July 30, August 2, August 6, August 7, August 8, August 13, October 16 and December 5, 1986, as well as the letters of the Director of the Office of Nuclear Reactor Regulation dated August 15, and December 11, 1986, consenting to such transactions.

Specifically, the lessor and anyone else who may acquire an interest under this transaction are prohibited from exercising directly or indirectly any control over the licensees of the Palo Verde Nuclear Generating Station, Unit 2. For purposes of this condition the limitations in 10 CFR 50.81, "Creditor Regulations," as now in effect and as they may be subsequently amended, are fully applicable to the lessor and any successor in interest to the lessor as long as the license for Palo Verde, Unit 2 remains in effect; this financial transaction shall have no effect on the license for the Palo Verde nuclear facility throughout the term of the license.

(b)

Further, the licensees are also required to notify the NRC in writing prior to any change in: (i) the terms or conditions of any lease agreements executed as part of this transaction; (ii) the ANPP Participation Agreement, (iii) the existing property insurance coverage for the Palo Verde nuclear facility, Unit 2 as specified in licensee counsel's letter of November 26, 1985, and (iv) any action by the lessor or others that may have an adverse effect on the safe 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 Arizona Public Service Company (APS) is authorized to operate the facility at reactor core power levels not in excess of 3990 megawatts thermal (100% power) in accordance with the conditions specified herein.

Amendment No. 6, 94, 428 149

Definitions 1.1 1.1 Definitions (continued)

RATED THERMAL POWER (RTP)

REACTOR PROTECTIVE SYSTEM (RPS) RESPONSE TIME SHUTDOWN MARGIN (SM)

RTP shall be a total reactor core heat transfer rate to the reactor coolant of 3876 MWt for Units 1 and 3. and 3990 MWt for Unit 2.

The RPS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its RPS trip setpoint at the channel sensor until electrical power to the CEAs drive mechanism is interrupted.

The response time may be measured by means of any series of sequential. overlapping. or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.

SDM shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming:

a. All full length CEAs (shutdown and regulating) are fully inserted except for the single CEA of highest reactivity worth. which is assumed to be fully withdrawn.

With any full length CEAs not capable of being fully inserted, the withdrawn reactivity worth of these CEAs must be accounted for in the determination of SDM and

b. There is no change in position.

part length CEA (continued)

PALO VERDE UNITS 1 AND 3 PALO VERDE UNIT 2 AMENDMENT NO.

. 135 AMENDMENT NO. 435 149 1.1-6

RPS Instrumentation -

Operating 3.3.1 Table 3.3.1-1 (page 1 of 3)

Reactor Protective System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED SURVEILLANCE FUNCTION CONDITIONS REOUIREMENTS ALLOWABLE VALUE

1. Variable Over Power 1.2

2. Logarithmic Power Level -

High(a) 2

3. Pressurizer Pressure - High 1.2 SR 3.3.1.1 SR 3.3.1.4 SR 3.3.1.6 SR 3.3.1.7 SR 3.3.1.8 SR 3.3.1.9 SR 3.3.1.13 SR 3.3.1.1 SR 3.3. 1.7 SR 3.3.1.9 SR 3.3.1.12 SR 3.3.1.13 SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.9 SR 3.3.1.13 SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.9 SR 3.3.1.12 SR 3.3.1.13 SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.9 SR 3.3.1.13 SR 3.3.1.1 SR 3.3. 1.7 SR 3.3.1.9 SR 3.3.1.13 Ceiling s 111.0S RTP Band S 9.91 RTP Incr. Rate S 11.01/min RTP Decr. Rate >

/sec RTP s 0.011S NRTP S 2388 psia 2 1821 psia 5 3.2 psIg Units 1 and 3:

890 psia Unit 2:

955 psia

4.

Pressurizer Pressure - Low 1.2

5. Containment Pressure - High 1.2

6. Steam Generator I Pressure - Low 1.2 I

7. Steam Generator 2 Pressure - Low 1.2 SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.9 SR 3.3.1.13 Units I and 3: 2 890 psia Unit 2:

955 psia I

(continued)

(a) Trip may be bypassed when logarithmic power is > IE-4S NRTP.

Bypass shall when logarithmic power s s E-4* NRTP.

be automatically removed PALO VERDE UNITS 1 AND 3 PALO VERDE UNIT 2 AMENDMENT NO. -41.

119 AMENDMENT NO. 49 149 3.3.1-8

RPS Instrumentation - Shutdown 3.3.2 Table 3.3.2-1 Reactor Protective System Instrumentation Shutdown FUNCTI ON

1. Logarithmic Power Level-Highcd)

2. Steam Generator 11 Pressure-Low'b)

3. Steam Generator 12 Pressure-Low(bl APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS 3(a) 4 5a 313)

~~3(a)

SURVEILLANCE REOUIREMENTS SR 3.3.2.1 SR 3.3.2.2 SR 3.3.2.3 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.1 SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.1 SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.5 ALLOWABLE VALVE

< 0.011X RTP(C)

Units I and 3:

890 psia Unit 2: 2 955 psia Units I and 3: 2 890 psia Unit 2: 2 955 psia I

I (a)

With any Reactor Trip Circuit Breakers (RTCBs) closed and any control element assembly capable of being withdrawn.

(b)

The setpoint may be decreased as steam pressure s reduced. provided the margin between steam pressure and the setpoint is maintained 200 psig. The setpoint shall be automatically increased to the normal setpoint as steam pressure Is increased.

(c)

The setpoint must be reduced to r IE-4Z NRTP when less than 4 RCPs are running.

(d)

Trip may be bypassed when logarithmic power is IE-4: NRTP.

Bypass shall be automatically removed when logarithmic power is 5 IE-4Z NRTP.

PALO VERDE UNITS 1 AND 3 PALO VERDE UNIT 2 AMENDMENT NO. All 119 AMENDMENT NO. 41-9 149 3.3.2-5

ESFAS Instrumentation 3.3.5 Table 3.3.5-1 (page of 1)

Engineered Safety Features Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED FUNCTION CONDITIONS ALLOWABLE VALUE

1. Safety Injection Actuation Signal

a. Contairmrent Pressure - High 1.2.3

< 3.2 psig

b. Pressurizer Pressure - Low(a) 2 1821 psia

2. Containment Spray Actuation Signal

a. Contairinment Pressure - High High 1.2.3 s.9 psig

3. ContaInment Isolation Actuation Signal

a. Contairrent Pressure - Hiq 1.2.3 3.2 psig

b. Pressurizer Pressure - Low a) 1821 psa

4. Main Steam Isolation Sgnal(C)

a. Steam Generator #1 Pressure-tow(b) 1.2.3 Units l and 3: 2 890 psla Unit 2: 2 955 psia

b. Steam Generator 2 Pressure-Low(b)

Units 1 and 3: 2 890 psia Unit 2: ? 955 psia

c. Steam Generator A1 Level-High s 91.S C. Steam, Generator 2 Level-High S 91.5t

e. Contairment Pressure-High S 3.2 psig

5. Recirculation Actuation Signal

a. Refueling Water Storage Tank Level-Low 1.2.3 2 6.9 and s 7.9:

6. Auxiliary Feeawater Actuation Signal SG 1 (AFAS-)

a. Steam Generator fl Level-Low 1.2.3 2 25.3

b. SG Pressure Difference-High S 192 psid

7. Auxiliary Feed.ater Actuation Signal SG #2 (AFAS-2)

a. Steam Generator 2 Level-Low 1.2.3 2 25.35

b. SG Pressure Dfference-High s 192 psid (a)

The setpoint may be decreased to a minimum value of 100 psia. as pressurizer pressure is reduced.

provided the margin between pressurizer pressure and the setpoint is maintained 400 psia or 2 140 psia greater than the saturation pressure of the RCS cold leg when the RCS cold leg temperature is 2 45°F.

Trips may be bypassed when pressurizer pressure is 400 psia.

Bypass shall be automatically removed when pressurizer pressure is 2 00 psia.

The setpoint shall be automatically Increased to the normal setpoint as pressurizer pressure is increased.

(b) The setpoint ray be decreased as steam pressure is reduced. provided the margin between steam pressure ard the setpoint is aintained 200 psig. The setpoint shall be automatica ly increased to the normal setpoint as steam pressure is increased.

(c) The Main Steam Isolation Signal (SIS) Function (Steam Generator Pressure - Low. Steam Generator Level.

High and Containment Pressure - High signals) is not required to be OPERABLE when all associated valves isolated by the MSIS Function are closed.

PALO VERDE UNITS 1 AND 3 PALO VERDE UNIT 2 AMENDMENT NO. 117 AMENDMENT NO. Ail 149 3.3.5-4

RCS Pressure. Temperature and Flow DNB Limits 3.4.1 Figure 3.4.1-1, (Page 1 of 2)

Reactor Coolant Cold Leg Temperature vs. Core Power Level I

I Units 1 and 3 575 IL cc 570 M

565 560 L

-3 555 U

550 545 540

.9 (0,570)

(3Q~q5)

'\\11 ~~~~~~~~~~~~~

~~'

gwi cTaLo'ftfa I

I I~~~' I I

I I

I

\\

575 570 565 560 555 550 545 540 0

10 20 30 40 50 60 70 80 90 CORE POWER LEVEL, % OF RATED THERMAL POWER (3876 MWt)

Io(

1 PALO VERDE UNITS 1 AND 3 PALO VERDE UNIT 2 AMENDMENT NO. 117 AMENDMENT NO. 41-7 149 3.4.1-3

RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 Figure 3.4.1-1, (Page 2 of 2)

Reactor Coolant Cold Leg Temperature vs. Core Power Level Unit 2 U-0 C) 575 570 565 575 570 565 560

• l 555.

550 545 540 t560 555

~Z~\\

550 545 540 100 Th 0

I I

I I

I I

I I

I 10 20 30 40 50 60 70 80 90 CORE POWER LEVEL, % OF RATED THERMAL POWER (3990 M'lM)

PALO VERDE UNITS 1 AND 3 PALO VERDE UNIT 2 AMENDMENT NO.

117 AMENDMENT NO.

44g.

149 3.4.1-4

MSSVs 3.7.1 Table 3.7.1-1 (page 1 of 1)

Variable Overpower Trip Setpoint versus OPERABLE Main Steam Safety Valves MAXIMUM ALLOWABLE MINIMUM NUMBER OF MAXIMUM POWER VARIABLE OVERPOWER TRIP MSSVs PER STEAM

( RTP)

SETPOINT GENERATOR

(% RTP)

REQUIRED OPERABLE Units Units 1 and 3 Unit 2 1 and 3 Unit 2 10 100.0 100.0 111.0 111.0 9

98.2 90.0 108.0 99.7 8

87.3 80.0 97.1 89.7 7

76.4 68.0 86.2 77.7 6

65.5 56.0 75.3 65.7 PALO VERDE UNITS 1 AND 3 PALO VERDE UNIT 2 AMENDMENT NO. 117 AMENDMENT NO. 44.7 149 3.7.1-3

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.15 Safety Function Determination Program (continued)

b. A required system redundant to system(s) in turn supported by the inoperable supported system is also inoperable: or

c. A required system redundant to support system(s) for the supported systems (a) and (b) above is also inoperable.

The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program.

the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.

When a loss of safety function is caused by the inoperability of a single Technical Specification support system, the appropriate Conditions and Required Actions to enter are those of the support system.

5.5.16 Containment Leakage Rate Testing Program A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50. Appendix J. Option B. as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163. "Performance-Based Containment Leak-Test Program." dated September, 1995. as modified by the following exceptions:

The peak calculated containment internal pressure for the design basis loss of coolant accident. Pa. is 52.0 psig for Units 1 and 3.

and 58.0 psig for Unit 2. The containment design pressure is 60 Psig.

The maximum allowable containment leakage rate. La. at P. shall be 0.1 % of containment air weight per day.

Leakage Rate acceptance criteria are:

a. Containment leakage rate acceptance criterion is < 1.0 La.

During the first unit startup following testing in accordance with this program, the leakage rate acceptance are < 0.60 La for the Type B and C tests and 0.75 L for Type A tests.

(continued)

PALO VERDE UNITS 1 AND 3 AMENDMENT NO. 4-29, 137 PALO-VERDE UNIT 2 5.5-23 AMENDMENT NO. 4-149