Text

Amend 21 to License NPF-41,revising Tech Specs as Listed, Including Rev of Notations 2 & 3 in Table 2.2-1 to Be Applicable to Modes 3 & 4 Instead of Modes 3-6
	ML17300B045
Person / Time
Site:	Palo Verde
Issue date:	09/04/1987
From:	Knighton G; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML17300B046	List: ML17300B045; ML17300B047;
References
	NUDOCS 8709100513
	Download: ML17300B045 (16)
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0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ARIZONA PUBLIC SERVICE COMPANY ET AL.

DOCKET NO.

STN 50-528 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.

1 AMENIDMENT TO FACILITY OPERATING LICENSE Amendment No. 21 License No. NPF-41 1.

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

A.

The applications for amendment, dated May 11 and May 28,

1987, by the Arizona Public Service Company (APS) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric Company, Southern California Edison Company, 'Public Service Company of New Mexico, Los Angeles Department of Water and

Power, and Southern Ca1ifornia Public Power Authority (licensees),

comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the applications, the provisions of Act, and the 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 amendment will not be inimical to the common defense and security or to the health and safety of the public; 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.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-41 is hereby amended to read as follows:

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(2)

Tech...;-", <n~cifications and Environmental Protection Plan

'hj Technical Specifications contained in Appendix A, as revised through Amendment No. 21, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license.

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

3.

This license amendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Enclosure:

Changes to the Technical Specifications Date of Issuance:

September 4,

1987 George nighton, Dt'rector Projec Directorate V

Division of Reactor Projects - III, IV, V and Special Projects

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ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO. 21 TO 'FACILITY OPERATING LICENSE NO. NPF-41 J

l

,4.

n DOCKET NO. STN,50-528 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.

Also to be replaced are the following overleaf pages to the amended pages.

Amendment Pa es 2-5 3/4 3-23 3/4 3-41 3/4 9-1 3/4 10-1 Overleaf Pa es 2-6 3/4 3-24 3/4 3-42 3/4 9-2 3/4 10-2

E t

TABLE 2. 2-1 (Continued)

REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS TABLE NOTATION>

Trip mhy be manually bypassed above 10- X of RATt."D THERMAL POWER; bypass shaTT be automatically removed when THERMAL POWER is less than or equal to 10-4X of RATED THERMAL POWER.

(2)

(3)

(4)

(5)

In MODES 3-4, value may be decreased manually, to a minimum of 100 psia, as Pressurizer pressure is reduced, provided the margin between the pres-surizer pressure and this value is maintained at less than or equal to 400 psi; the setpoint shall be increased automatically as pressurizer pressure is increased until the trip setpoint is reached.

Trip may be manually bypassed below 400 psia; bypass shall be automatically removed whenever pressurizer pressure is greater than or equal to 500 psia.

In MODES 3-4, value may be decreased manually as steam generator pressure is reduced, provided the margin between the steam generator pressure and this value is maintained at less than or equal to 200 psi; the setpoint shall be increased automatically as steam generator pressure is increased until the trip setpoint is reached.

X of the distance between steam generator upper and lower level wide range instrument nozzles.

As stored within the Core Protection Calculator (CPC).

Calculation of the trip setpoint includes measurement, calculational and processor uncer-

tainties, and dynamic allowances.

Trip may be manually bypassed below 3X of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is greater than or equal to 1X of RATED THERMAL POWER.

The approved DNBR limit is 1.231 which includes a partial rod bow penalty compensation.

If the fuel burnup exceeds that for which an increased rod bow penalty is required, the DNBR limit shall be, adjusted.

In this case a

DNBR trip setpoint of 1.231 is allowed provided that 'the difference is com-pensated by an increase in the CPC addressable constant BERR1 as follows:

0 d

(Yo POL)

BERR1

= BERRl ld [1+

100 x

d (

DNBR) where BERR1 ld is the uncompensated value of BERR1; RB is the fuel rod 01 d bow penalty in Yo DNBR; RB is the fuel rod bow penalty in X DNBR already accounted for in the DNBR limit; POL is the power operating limit; and d (X POL)/d (X DNBR) is the absolute value of the most adverse derivative of POL with respect to DNBR.

PALS 'VERDE - UNIT 1 AMENDMENT ND. 21

TABLE 2.2-1 (Continued)

REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS TABLE NOTATIONS (Continued)

(6)

RATE.'is the maximum rate of decrea of,4;;.-.l;rip setpoint.

There are no restr"ictions on the rate at which i,'i-. q'~pAnt can increaqe.

FLOOk is the minimum value of the trip'setpoint.

SANWis the amount by which the trip setpoint is below the input signal

~un ess limited by Rate or Floor.

Setpoints are based on steam generator differential pressure.

(7)

The setpoint nay be altered to disabTe trip function during testing

-pursuant to Specification 3;10.3.

(8)

RATE is the maximum rate of increase of the trip setpoint.

(The rate at wWwsch the setpoint can decrease is no slower than five percent per second.)

CEILING is the maximum value of the trip setpoint.

SKNl~s the amount by which the trip setpoint is above the steady state input signal unless limited by the rath or the ceiling.

(9)

X of'the distance between steam generator upper and lower level narrow range instrument nozzles.

PALO VERDE - UNIT 1 2-6 ANENDNENT ND. 19

TABLE 3.3-3 Continued) t>ij TABLE NOTATIONS (a)

In MODES 3-4, the value may be decreased manually, to a minimum of 100 psia, as pressurizer pressure is reduced, provided the margin betwoen the pressut'izer press'ure a'n8'this value "is maintained at less tn;"" or equal to 400 psi;,the setpoint shall'e increased automatically as pressurizer pres~e is increased until the trip setpoint is reached.

Trip may be manually bypassed below 400 psia; bypass shall be automatically removed whenever pressurizer pressure is greater than or equal to 500 psia.

(b)

In MODES 3-4, the value may be decreased manually as steam generator pressure is reduced, provided the margin between the steam generator pressure and this value is maintained at less than or equal to 200 psi; the setpoint shall be increased automatically as steam generator pressure is increased until the trip setpoint is reached.

(c)

Four channels

provided, arranged in a selective two-out-of-four configuration (i.e., one-out-of-.two taken twice).

(d)

The proper two-out-of-four combination.

The provisions of Specification 3.0.4 are not applicable.

After the initial criticality of Unit 2 or Unit 3.

ACTION STATEMENTS ACTION 12-ACTION 13 "

With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

With the number of channels OPERABLE one less than the Total Number of Channels, STARTUP and/or POMER OPERATION may continue provided the inoperable channel is placed in the bypassed or tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

If the inoperable channel is

bypassed, the desirability of maintaining this channel in the bypassed condition shall be reviewed in accordance with Specification 6.5.1.6.h.

The channel shall be returned to OPERABLE status no later than during the next COLD SHUTDOWN.

Mith a channel process measurement circuit that affects multiple functional units inoperable or in test, bypass or trip all associated functional units as listed below.

Process Measurement Circuit 1.

Steam Generator Pressure Steam Generator Pressure

- Low Low Steam Generator Level 1-Low (ESF)

Steam Generator Level 2-Low (ESF) 2.

Steam Generator Level (Wide Range)

Steam Generator Level - Low (RPS)

Steam Generator Level 1-Low (ESF)

Steam Generator Level 2-Low (ESF)

PALO VERDE UNIT 1 3/4 3-23 AMENDMENT NO. 21

2.

Steam Generator Level -

Low (Wide Range)

Steam Generator Level - Low (RPS)

Steam Generator Level 1 -

Low (ESF)

Steam Generator Level 2 - Low (ESF)

STARTUP and/or POWER OPERATION may continue until the performance of the next required CHANNEL FUNCTIONAL TEST.

Subsequent STARTUP and/or POWER OPERATION may continue if one channel is restored to OPERABLE status.

and the provisions of ACTION 14 are satisfied.

TABLE 3;3-3 (Continued)

ACTION STATEMENTS:,(Continued)

ACTION 14 -,With the number of charinel.INOPERABLE one less. than the Minimum

Channels

OPERABLE, STARTUf,""ind'/'or POWER OPERATION may continue jprovided the following'Ynditions 'are satisfied:

a.

Verify that one of the inoperable channels has been bypassed and place the other inoperable channel in the tripped condition within*1 hour.

b.

~ iAll functional units affected:by the bypassed/tripped

" channel shall also'be placed in the bypassed/tripped condition as listed. below:

Process Measurement Circuit, Functional Unit.Bypassed/Tripped 1.

, Steam Generator Pressure Steam Generator Pressure

- Low Low Steam Generator Level 1 - Low (ESF)

Steam Generator Level 2 - Low (ESF)

ACTION 15 =,

ACTION'16-ACTION 17-ACTION 18 "

With the number of OPERABLE channels one less than the Total

,:Number of Channels, restore.the inoperable channel. to OPERABLE

.status within.48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . or. be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .,and.in HOT SHUTDOWN w'ithin the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

With the number of OPERABLE channels one loess than the Total Number of Channels, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ;

however, one channel may be bypassed for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for surveillance testing provided the other channel is OPERABLE.

With the number of OPERABLE channels one less than the Minimum Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6.hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

With the number of OPERABLE channels one less than the Minimum Number of Channels, operation may continue for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

After 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months operation may continue provided at least 1 train of essential filtration is in operation, otherwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

3/4 9"24 "'

'NSTRUMENTATION INCORE DETECTORS LIMITING CONDITION FOR OPERATION.

3.3.3.2

'fhe incore detection system shall be OPERABLE with:

a.

At least 75/o of all incore detector locations, and 75K of all detectors, with at least one detector in each quadrant at each level; and b.

A minimum of six tilt estimates, with at least one at each of three levels.

An OPERABLE incore detector location shall consist of a fuel assembly containing a fixed detector string with a minimum of four OPERABLE rhodium detectors or an OPERABLE movable incore detector capable of mapping the location.

APPLICABILITY:

When the incore detection system is used for monitoring:

a ~

AZIMUTHAL POWER TILT, b.

Radial Peaking Factors, C.

Local Power Density, d.

DNB Margin.

ACTION:

a.

With the incore detection system inoperable, do not use the system for the above applicable monitoring or calibration functions.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.3.3.2 The incore detection system shall be demonstrated OPERABLE:

a.

b.

By performance of a CHANNEL CHECK within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to its use if the system has just been returned to OPERABLE status or if 7 days or more have clasped since last use and at least once per 7 days thereafter when required for monitoring the AZIMUTHAL POWER TILT, radial peaking factors, local power density or DNB margin:

At least once per 18 months by performance of a CHANNEL CALIBRATION operation which exempts the neutron detectors but includes all electronic components.

The fixed incore neutron detectors shall be calibrated prior to installation in the reactor core.

PALO VERDE UNIT 3.

3/4 3-41 AMENDMENT MD. 2l

INSTRUMENTATION.:.

SEISMIC INSTRUMENTATION E

LIMITING CONDITION FOR OPERATION" 3.3.3.3 The seismic. monitoring instrumentation shown, in Table 3.3-7 shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

With one or,.more seismic monitoring instruments inoperable.for, more than:30.,days, prepare

.and submit a Special Report to the Commission pursuant to,Specification 6.9.2 within the next. 10 days outlining the cause of the malfunction and the plans for restoring the instrument(s).to OPERABLE status.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.3.3.3. 1 Each of the above seismic monitoring instruments shalT':be

.demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL

-CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown.in.'able 4.3-4.

4.3.3.3.2 Each'of the abov'e seismicmonito'ring"insti uments actuated during a

.seismic event (greater than or equal to 0. 02g) shall have a

CHANNEL CALIBRATION performed within 5 days.

Data shall be retrieved from actuated tnstruments and analyzed to determine the magnitude of the vibratory ground motion.

A Special Report shall be prepared and submitted to the Commission pursuant to Specifi-cation 6.9.2 within 10 days describing the magnitude, frequency

spectrum, and resultant effect upon facility features important to safety.

'3/4.9 REFUELING OPERATIONS 3/4.9. 1 BORON CONCENTRATION LIMITING CONDITION FOR OPERATION f'<i;gl. ~g (

Q't xie~

3.9.1 Withe the reactor ve'ssel-head closure bolts less than fully tensioned or with the. head

removed, the boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions is met:

a.

Either a Keff of 0.95 or less, or b.

A boron concentration of greater than or equal to 2150 ppm.

APPLICABILITY:

MODE 6".

ACTION:

With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue boration at greater than or equal to 26 gpm of a solution containing

> 4000 ppm boron or its equivalent until K ff is reduced to less than or equal to 0.95 or the boron concentration is restored to greater than or equal to 2150 ppm, whichever is the more restrictive.

SURVEILLANCE RE UIREMENTS 4.9. l. 1 The more restrictive of the above two reactivity conditions shall be determined prior to:

a.

Removing or unbolting the reactor vessel

head, and b.

Withdrawal of any full-length CEA in excess of 3 feet from its fully inserted position within the reactor pressure vessel.

4.9. 1.2 The boron concentration of the Reactor Coolant System and the refueling canal shall be determined by chemical analysis at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

The reactor shall be maintained in MODE 6 whenever fuel is in the reactor vessel with the reactor vessel head closure bolts less than fully tensioned or with the head removed.

PALO VERDE UNIT 3.

3/4 9-1 AMENDMENT ND. 2l

REFUELING OPERATIONS 3/4.9. 2 INSTRUMENTATION

, LIMITING CONDITION,.FOR OPE i,;fiOix

~'

l 3.9.2 As a minimum, two source range neutron flux monitors shall be OPERABLE and operating, each with continuous visual indication in the control room and one with audible indication in the containment and control room.

APPLICABILITY:

MODE 6.

ACTION:

a ~

With one of the above required monitors inoperable or not operating, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

With both of the above required monitors inoper able or not operating, determine the boron concentration of the Reactor Coolant System at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE RE UIREMENTS 4.9.2 Each source range neutron flux monitor shall be demonstrated OPERABLE by performance of:

a.

A CHANNEL CHECK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , b.

A CHANNEL FUNCTIONAL TEST within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to the initial start of CORE ALTERATIONS, and c.

A CHANNEL FUNCTIONAL TEST at least once per 7 days.

"9/4 9"2

'3/4. 10 SPECIAL TEST EXCEPTIONS 3/4. 10. 1 SHUTDOWN MARGIN LIMITING CONDITION FOR OPERATION 3.10.1 The. SHUTDOWN MARGIN requ'i.

~".."".

~:

Sp~ ification 3.1.1.1 may be suspended fpr measurement of CEA worth a'nd shutdown margin provided reactivity equivalent-to at least the highest estimated CEA worth is available for trip insertion from OPERABLE CEA(s), or the reactor is subcritical by at least the reactivity equivalent of the highest CEA worth.

APPLICABILITY:

MODES 2, 3* and 4*8.

ACTION:

b.

With any full-length CEA not fully inserted and with less than the above reactivity equivalent available for trip insertion, immedi-ately initiate and continue boration at greater than or equal to 26 gpm of a solution containing greater than or equal to 4000 ppm boron or its equivalent until the SHUTDOWN MARGIN required by Specification

3. 1. 1. 1 is restored.

With all full-length CEAs fully inserted and the reactor subcritical by less than the above reactivity equivalent, immediately initiate and continue boration at greater than or equal to 26 gpm of a solution containing greater than or equal to 4000 ppm boron or its equivalent until the SHUTDOWN MARGIN required by Specification

3. 1. 1. 1 is restored.

SURVEILLANCE RE UIREMENTS

4. 10. 1. 1 The position of each full-length and part-length CEA required either partially or fully withdrawn shall be determined at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

4. 10.1.2 Each CEA not fully inserted shall be demonstrated capable of full insertion when tripped from at least the 50K withdrawn position within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to reducing the SHUTDOWN MARGIN to less than the limits of Specification

3. l. 1. l.

4. 10.1.3 When in MODE 3 or MODE 4, the reactor shall be determined to be subcritical by at least the reactivity equivalent of the highest estimated CEA worth or the reactivity equivalent of the highest estimated CEA worth is avail-able for trip insertion from OPERABLE CEAs at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months by con-sideration of at least the following factors:

a.

Reactor Coolant System boron concentration, b.

CEA position, c.

Reactor Coolant System average temperature, d.

Fuel burnup based on gross thermal energy generation, e.

Xenon concentration, and f.

Samarium concentration.

Operation in NODE 3 and MODE 4 shall be limited to 6 consecutive hours.

iimifed to low gower PHYSICS TESHNG at the 320'F plateau.

PALO VERDE UNIT 1 3/4 10-1 AMENDMENT NO. 21

SPECIAL TEST EXCEPTIONS 3/4. 10. 2 MODERATOR TEMPERATURE COEFFICIENT GROUP HEIGHT INSERTION AND POWER DISTRIBUTION LIMI S LIMITING CO DITION FOR 'OPERATION

3. 10.2 The moderator temperature coefficient, group height, insertion, and power distribution limits of Specifications

3. 1. 1.3, 3.1.3.1, 3.1.3.5,

3. l. 3. 6,

3. 2. 2, 3. 2. 3, 3. 2. 7, and the Minimum Channels OPERABLE requirement of I.C.1 (CEA Calculators) of Table 3.3-1 may be suspended during the performance of PHYSICS TESTS provided:

a.

The THERMAL POWER is restricted to the test power plateau which shall.not.exceed 85K of RATED THERMAL POWER, and b.

The limits.of Specification 3.2. 1 are 'maintained and determined as specified in Specification 4. 10.2.2 below.

APPLICABILITY:

MODES 1 and 2.

ACTION:

With any of the limits of Specification 3:2.1 being exceeded while the requirements of Specifications 3.1.1.3, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.2, 3.2.3, 3.2.7, and the Minimum Channels OPERABLE requirement of I.C.1 (CEA Calculators) of Table 3.9-1 are suspended, either:

a.

Reduce TKERMAL POWER sufficiently to satisfy the requirements of Specification 3.2. 1, or b.

Be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE RE UIREMENTS

4. 10.2.1 The THERMAL POWER shall be determined at least once per hour during PHYSICS TESTS in which the requirements of Specifications 3.1.1.3,

3. 1.3. 1,

3. 1.3. 5, 3. 1. 3. 6, 3. 2. 2, 3;2.3,

3. 2.7, or the Minimum Channels OPERABLE require-ment of I.C. 1 (CEA Calculators) of Table 3.3-1 are suspended and shall be verified to be within the test power plateau.

4. 10.2.2 The linear heat rate shall be determined to be within the limits of Specificati'on 3.2.1 by monitoring it continuously with the Incore Detector Monitoring System pursuant to the requirementy of Specifications 4.2. 1.3 and

3. 3. 3. 2 during PHYSICS TESTS above 20K of RATED THERMAL POWER in which the requirements of Specifications

3. l. 1.3,

3. 1.3. 1,

3. 1.3.5,

3. 1.3.6, 3.2.2, 3.2.3, 3.2.7 or the Minimum Channels OPERABLE requirement of I.C.3.

(CEA Calcuiators) ef Table 3.3-3. are suspended.

ML17300B045

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