Text

Amends 79,66 & 51 to Licenses NPF-41,NPF-51 & NPF-74 & SE, Respectively,Implement Recommended Changes from GL 93-05, Line-Item TS Improvements to Reduce SR for Testing During Power Operation
	ML17311A258
Person / Time
Site:	Palo Verde
Issue date:	09/02/1994
From:	Quay T; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML17311A259	List: ML17311A258; ML17311A261;
References
	GL-93-05, GL-93-5, NUDOCS 9409140090
	Download: ML17311A258 (74)
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D;C. 20555-0001 RIZONA PUBLIC SERVICE COMPANY ET AL.

DOCKET NO.

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

1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

79 License No.

NPF-41 The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by the Arizona Public Service Company (APS or the licensee) 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 California Public Power Authority dated January 4,

1994, complies 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 application, 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 acti.vities 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; 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.

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-41 is hereby amended to read as follows:

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(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 79, 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, except where otherwise stated in specific license conditions.

This license amendment is effective as of the date of issuance and must be.fully implemented no later than 45 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications T

odore R.

qua

, Director Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Date of Issuance:

September 2,

1994

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ATTACHMENT TO LICENSE AMENDMENT MENDMENT NO.

79 TO FACILITY OPERATING LICENSE NO.

NPF-41 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.

Remove 3/4 1-16 3/4 3-40 3/4 3-41 3/4 4-20 3/4 5-4 3/4 6-16 3/4 7-4 3/4 7-5 3/4 10-1 Insert 3/4 1-16 3/4 3-40 3/4 3-41 3/4 4-20 3/4 5-4 3/4 6-16 3/4 7-4 3/4 7-5 3/4 10-1

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I EACTIVITY CONTROL SYST HS LIHITING CONDITION FOR OPERATION Continued

~C ION:

(Continued) b)

The SHUTDOWN HARGIN requirement of Specification 3.1.1.2 is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Otherwise, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

d.

With one full-length CEA inoperable due to causes other than addressed by ACTION a.,

above, but within its above specified align-ment requirements, operation in HODES 1 and 2 may continue pursuant to the requirements of Specification 3.1.3.6.

e.

With one part-length CEA inoperable and inserted in the core, operation may continue provided the alignment of the inoperable part length CEA is maintained within 6.6 inches (indicated position) of all other part-length CEAs in its group and the CEA is maintained pursuant to the requirements of Specification 3. 1.3.7.

SURVEILLANCE RE UIREHENTS

4. 1.3. 1. 1 The position of each full-length and part-length CEA shall be deter-mined to be within 6.6 inches (indicated position) of all other CEAs in its group at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when one CEAC is inoperable or when both CEACs are inoperable, then verify the individual CEA positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4. 1.3. 1.2 Each full-length CEA not fully inserted and each part-length CEA which is inserted in the core shall be determined to be OPERABLE by movement of at least 5 inches in any one direction at least once per 92 days.*

With the exception that CEA 864 is exempt from this surveillance requirement for the remainder of Cycle 2 operations (i.e., until restart from the second refueling outage).

PALO VERDE UNIT 1 3/4 1-16 AHENDHENT NO. $4, 79

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INSTRUMENT 1.

Area Monitors TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS CHANNEL MODES FOR WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE E<<

I E I

~IRK II I'.

Fuel Pool Area RU-31 B.

New Fuel Area RU-19 C.

Containment Power Access Purge Exhaust RU-37

& RU-38 D.

Containment RU-148 RU-149 E.

Main Steam RU-139 A&B RU-140 A&B 2.

Process Monitors A.

Containment Building Atmosphere RU-1 1)

Particulate 2)

Gaseous p¹ P¹¹¹,W¹¹ 1,2,3,4 1,2,3,4 1,2,3,4 1,2,3,4 B.

Control Room Ventilation Intake RU-29

& RU-30 3.

Post Accident Sampling System N.A.

All MODES M*"*

1,2,3

With fuel in the storage pool or building.

- With irradiated fuel in the storage pool.

- - The functional test should consist of, but sampling capabilities.

¹If purge is in service for greater than 12

¹¹When purge system is in operation.

¹¹¹The functional test should consist of, but isolation capability by the insertion of a not be limited to, a verification of system

hours, perform once per 12-hour period.

not be limited to, a verification of system simulated alarm condition.

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INSTRUMENTATION INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The incore detection system shall be OPERABLE with:

a.

At least 75K of all incore detector locations, and 75X of all detec-tors, 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 contain-ing a fixed detector string with a minimum of three OPERABLE rhodium detectors or an OPERABLE movable incore detector capable of mapping the location.

ityytittditity: Iit tt I

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a 0 AZIMUTHAL POWER TILT, b.

Radial Peaking Factors, c ~

Local Power Density, d.

DNB Margin.

~CT ION:

a 0 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 a ~

b.

The incore detection system shall be demonstrated OPERABLE:

By performance of a CHANNEL CHECK within 7 days prior to its use for I

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 I 3/4 3-41

'AMENDMENT NO.~ 7g

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I EEACTGR~CANT Y TEN SURVEILLANCE RE UIREMENTS Continued b.

Monitoring the containment sump inventory and discharge at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c.

Performance of a Reactor Coolant System water inventory balance at least once per 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months s**.

d.

Monitoring the reactor head flange leakoff system at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.4.5.2.2 Each Reactor Coolant System pressure isolation valve specified in Table 3.4-1 shall be demonstrated OPERABLE by verifying leakage to be within its limit**:

a.

At least once per 18 months, b.*

Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 7 days or more and if leakage testing has not been performed in the previous 9 months, c.

Prior to returning the valve to service following ma'intenance, repair or replacement work on the valve, d.*

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following valve actuation due to automatic or manual action or flow through the valve, e.*

Within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months following a system response to an Engineered Safety Feature actuation signal.

The provisions of Specifications 4.4.5.2.2.b, 4.4.5.2.2.d, and 4.4.5.2.2.e are not applicable for valves UV 651, UV 652, UV 653 and UV 654 due to position indication of valves in the control room.

- The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4.

PALO VERDE - UNIT 1 3/4 4-20 AMENDMENT NO. ~79-

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EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:

a.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the following valves are in the indicated positions with the valves key-locked shut:

Valve Number Valve Function Valve Position 1.

SIA HV-604 1.

HOT LEG INJECTION 1.

SHUT 2.

SIC HV-321 2.

HOT LEG INJECTION 2.

SHUT 3.

SIB HV-609 3.

HOT LEG INJECTION 3.

SHUT 4.

SID HV-331 4.

HOT LEG INJECTION 4.

SHUT b.

At least once per 31 days by:

l.

Verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked,

sealed, or otherwise secured in position, is in its correct position, and 2.

Verifying that the ECCS piping is full of water by venting the accessible discharge piping high points.

C.

By a visual inspection which verifies that no:loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions.

This visual inspection shall be performed:

1.

For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and 2.

At least once daily of the affected areas within containment by containment entry and during the final entry when CONTAINMENT INTEGRITY is established.

d.

At least once per 18 months by:

PALO VERDE UNIT 1

3/4 5-4 AMENDMENT NO.

79

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Coi)TAINMENT SYSTEMS 3 4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2. 1 Two independent containment spray systems shall be OPERABLE with each spray system capable of taking suction from the RWT on a containment spray actuation signal and automatically transferring suction to the containment sump on a recirculation actuation signal.

Each spray system flow path from the containment sump shall be via an OPERABLE shutdown cooling heat exchanger.

APPLICABILITY:

MODES 1, 2, 3, and 4*.

ACTION:

With one containment spray system inoperable, restore the inoperable spray system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-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 .,

restore the inoperable spray system to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE RE UIREMENTS 4.6.2. 1 Each containment spray system shall be demonstrated OPERABLE:

At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path is positioned to take suction from the RWT on a containment spray actuation (CSAS) test signal.

b.

C.

By verifying that each pump develops an indicated differential pressure of greater than or equal to 257 psid at greater than or equal the minimum allowable recirculation flowrate when tested pursuant to Specification 4.0.5.

At least once per 31 days by verifying that the system piping is full of water to the 60 inch level in the containment spray header

(>115 foot level).

d.

At least once per 18 months, during shutdown, by:

2.

Verifying that each automatic valve in the flow path actuates to its correct position on a containment spray actuation (CSAS) and recirculation actuation (RAS) test signal.

Verifying that upon a recirculation actuation test signal, the containment sump isolation valves open and 'that a recirculation mode flow path via an OPERABLE shutdown cooling heat exchanger is established.

Only when shutdown cooling is not in operation.

PALO VERDE - UNIT 1

3/4 6-15 AMENDMENT NO.

27

CONTAINMENT SYSTEMS SURVEILLANCE RE UIRf:MEINTS~Continued~

3.

Verif'ying that each spray pumpistarts,automatically on a safety injection actuation (SIAS) and on a cohtliniment spray actuation (CSAS) test signa'll.

e.

At least oncih pier 10 years by performing an air or smioke flow test

-through each spray header and 'verifying each spray nozzle is unobstructed.

PALO VERDE UNIT 1 3/4 6i-16 AMENDMENT NO.

PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7. 1.2 At least three independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:

,a.

Two feedwater

pumps, each capable of being powered from separate OPERABL'E emergency

busses, and b.

One feedwater pump capable of being powered from an OPERABLE steam supply system.

APPLICABILITY:

MODES 1, 2, 3, and 4*.

ACTION:

a.

With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With two auxiliary feedwater pumps inoperable 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 within the fol.lowing 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxil,iary feedwater pump to OPERABLE status as soon as possible.

SURVEILLANCE RE UIREMENTS 4.7. 1.2 Each, auxiliary feedwater pump shall be demonstrated OPERABLE:

a

~

b.

At least once per 31 days:

1.

Verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked,

sealed, or otherwise secured in position, is in its correct position.

2.

Verifying that all manual valves in the suction lines from the primary AFW supply tank (condensate storage tank CTE-TOl) to each essential AFW pump, and the manual discharge line valve of each AFW pump are locked, sealed or otherwise secured in the open position.

At least once per 92 days on a

STAGGERED TEST BASIS by:

1.

Testing the turbine-driven pump and both motor-driven pumps pur-suant to Specification 4.0.5.

The provisions of Specification 4.0.4 are not applicable for the turbine-driven pump for entry into MODE 3.

Until the steam generators are no longer required for heat removal.

PALO VERDE UNIT 1

3/4 7-4 AMENDMENT NO.

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0 PLANT SYSTEMS SURVEILLANCE RE UIREMENTS c.

At least once per 18 months during shutdown by:

l.

Verifying that each automatic valve in the flow path actuates to its correct position upon receipt of an auxiliary feedwater actuation test signal.

2.

Verifying that

each, pump that starts automatically upon receipt of an auxiliary feedwater.

actuation test signal.will start automatically upon receipt of an auxiliary feedwater actuation test signal.

d.

Prior to startup following any refueling shutdown or cold shutdown of 30 days or longer, by verifying on a

STAGGERED TEST BASIS (by means of a flow test) that the normal flow path from the condensate storage tank to each of the steam generators through one of the essential auxiliary feedwater pumps delivers at least 650 gpm at 1270 psia or equivalent at the entrance of the steam generator.

e.

The.provisions of Speci.fication 4.0.4 are not applicable for entry into MODE 3 or MODE 4 for the turbine-driven pump.

PALO VERDE UNIT 1 3/4 7-5 AMENDMENT NO. ~ 79

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3 4.10 SPECIAL TEST E

PTIONS 3 4.10.1 SHUTDOWN MARGIN AND K.) -

CEA WORTH TESTS LIMITING CONDITION FOR OPERATION 3.10.1 The SHUTDOWN MARGIN and K., requirements of Specification 3.1.1.2 may be suspended for measurement of CEA worth and shutdown margin provided re-activity 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.

4 LIOAEILIE:

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4 4

ACTION:

a

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b.

With any full-length CEA not fully inserted and with less than the above reactivity equivalent available for trip insertion, 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 and K., required by Specification 3. 1. 1.2 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 solu-tion 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 50% withdrawn position within 7 days prior to reducing the SHUTDOWN MARGIN to less than the limits of Specification 3.1.1.2.

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

PALO VERDE UNIT 1

3/4 10-1 AMENDMENT NO. K., ~,~ 7g

SP ST XCEP'll'IONS 3 4.10.2 MODERATOR TEMF'ERATUIRE COiEFF OWER DIST BUT ON ~NIlS ENT G

OUP HEIGN S'RT 0 N

LIMITING CONDITION FOR OPERATION

3. 10.2 The moderator temperature coefficient

,group height

,insertion, and power distribution limits of Specifications 0.1.123,i 3.1.3.1, 3.1.3.5,

3. 1.3.6, 3.1.3.7, 3.2.2, 3.2.3, 3.2.7, and the Minimum Channe'ls OPERABLE requirement of 1.C.1 (CEA Calculators) of Table 3.3-1 may b0 suspended during the performance of PHYSICS TESTS provided:

'a ~

The THERMAL POWER is restricted to'th'e test poser plateau which shall not e'xceed

'B5X oF RATED THERMAL POWER, and b.

The limits of Specification-3.2.1 0re m5intained and determined as specified in Specification 4. 10.2.2 below.

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ACTION:

With any of the limits of.?pecification 3.2.i bieitig exceeded while the requirei ments of Specifications 3.]I.1.3,, 3.1.3.1, 3.1.3.5, 3L1.8.5, 3.1.3.7, 3.,2.2, 3.2.3, 3.2.7, and the Minimum Channels OPERABLE requireaenit of I.C.1 (CEA Calculators) of Table 3.3-1 are suspended, eithiar:

a.

Reduce THERMAL POWER sufficiently to satisfy the require'ments of Specification 3.2. 1, or b.

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

~RETELL E

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4. 10.2. 1 The THERMAL POWER shall be determi6edi at least once per hour during PHYSICS TESTS in which the requirements of SpecIfications 3.]L. 1.33 3. 1.3. I, 3.1.3.5, 3.1.3.6, 3.13.7, 3.2.2, 3.2.3 3.2.7, or the INinimum Channels OPERABLE requirement of I.C. 1 (C',EA Calculator's) of Table 3.3-1 are suspended'nd shall be verified to be within the test power 'plateau.

4.10.2.2 The linear heat rate sha'll be detetmined'o be arithin the limits o'f

'pecification 3.2.1 by monitoring 'it continuously with the Incore Detector Monitoring System pur. uant to the requirementls of Specifications 4.2.1.2 and 3.3.3.2 during PHYSICS TESlS above 20X of RATED THEfML POWER in which the requirements of Specifications

3. le1.3, 3. 1.3.1 3.1.3.5, 3.1.3.6, 3.1.3.7, 3.2.2, 3.2.3, 3.2.7, or the, Minimum Channels OPl;RABLi: rIaquirements of I.C.1 (CEA Calculators) of Table 3.3-1 are suspended.

PALO VERDE UNIT 1 3/4 10-2 AMENDMENT NO.

27

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 RIZONA PUBLIC SERVICE COMPANY ET AL.

DOCKET NO.

STN 50-529 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

66 License No.

NPF-51 The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by the Arizona Public Service Company (APS or the licensee) 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 California Public Power Authority dated January 4,

1994, complies 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 Part I; B.

The facility will operate in. conformity with the application, 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 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 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 attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-51 is hereby amended to read as follows:

J II/

3.

(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 66, 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, except where otherwise stated in specific license conditions.

This license amendment is effective as of the date of issuance and must be fully implemented no later than 45 days from the, date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications T eodore R. quay, Director Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Date of Issuance:

September 2,

1994

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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.

66 TO FACILITY OPERATING LICENSE NO.

NPF-51 DOCKET NO.

STN 50-529 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.

Remove 3/4 1-16 3/4 3-40 3/4 3-41 3/4 4-20 3/4 5-4 3/4 6-16 3/4 7-4 3/4 7-5 3/4 10-1'nsert 3/4'-16 3/4 3-40 3/4 3-41 3/4 4-20 3/4 5-4 3/4 6-16 3/4 7-4 3/4 7-5 3/4 10-1

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REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION Continued ACTION:

(Continued) b)

The SHUTDOWN MARGIN requirement of Specification 3. 1. 1.2 is determined at least once per,12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Otherwise, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

d

~

e.

With one full-length CEA inoperable due to causes other than addressed by ACTION a

, above, but within its above specified align-ment requirements, operation in MODES 1 and 2 may continue pursuant to the requirements of,Specification 3. 1.3,6.

With one part-length CEA inoperable and inserted in the core, operation may continue:provided the alignment of the inoperable part length CEA is maintained within 6.6 inches (indicated position) of all other part-length CEAs in its group and the CEA is maintained pursuant to the requirements of Specification 3. 1.3.7.

SURVEILLANCE RE UIREMENTS

4. 1.3. 1. 1 The position of each full-length and part-length CEA shall be deter, mined to be within 6.6 inches (indicated position) of all'ther CEAs in its group at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when one CEAC is inoperable or when both CEACs are inoperable, then verify the individual CEA positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4 '.3. 1.2 Each full-length CEA not fully inserted and each part-length CEA which is inserted in the core shall be determined to be OPERABLE by movement of

,at least 5 inches in any one direction at least once per 92 d'ays..*

With the exception that CEAs 27 and 41 are exempt from this surveillance requirement until restart from the second refueling outage.

PALO VERDE UNIT 2 3/4 1-16 AMENDMENT NO. 39, ~66

0

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I

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INSTRUMENT 1.

Area Monitors TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS CHANNEL MODES FOR WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE EE I ALIRIIATII TE I

~IS RE IREE CrJ I

ED AD Fuel Pool Area RU-31 B.

New Fuel Area RU-19 C.

Containment Power Access Purge Exhaust RU-37

& RU-38 D.

Containment RU-148 RU-149 E.

Main Steam RU-139 A&B RU-140 A&B 2.

Process Monitors P¹¹¹,W¹¹ 1,2,3,4 1,2,3,4 A.

Containment Building Atmosphere RU-1 1)

Particulate 2)

Gaseous B.

'Control Room Ventilation Intake RU-29

& RU-30 3.

Post Accident Sampling System N.A.

1,2,3;4 1,2,3,4 Q

All MODES M***

1 2

3 m

C7 m

C7

With fuel in the storage pool or building.

- With irradiated fuel in the storage pool.

- - The functional test should consist of, but sampling capabilities.

¹If purge is in service for greater than 12

¹¹When purge system is in operation.

¹¹¹The functional test should consist of, but isolation capability by the insertion of a not be limited to, a verification of system

hours, perform once per 12-hour period.

not be limited to, a verification of system simulated alarm condition.

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INSTRUMENTATIO INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The incore detection system shall be OPERABLE with:

a.

At least 75X of all incore detector locations, and 75X of all detec-tors, 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 contain-ing a fixed detector string with a minimum of three 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.

~CTI ON:

'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 a ~

b.

The incore detection system shall be demonstrated OPERABLE:

By performance of a CHANNEL CHECK within 7 days prior to its use 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 2 3/4 3-41 AMENDMENT NO.

66

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'i t A

REACTOR. COOLANT SYSTEM SURVEILLANCE RE UIREMENTS Continued c.

Performance of a Reactor Coolant System water inventory balance at least once per 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months s**.

d.

Monitoring the reactor head flange leakoff system at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.4.5.2.2 Each Reactor Coolant System pressure isolation valve specified in Table 3.4-1 shall be demonstrated OPERABLE by verifying leakage to be within its limit**:

a.

At least once per 18 months, b.*

Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 7 days or more and if leakage testing has not been performed in the previous 9 months, c.

Prior to returning the valve to service following maintenance, repair or replacement work on the valve, d.*

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following valve actuation due to automatic or manual action or flow through the valve, e.*

Within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months following a system response to an Engineered Safety Feature actuation signal.

The provisions of Specifications 4 '.5.2.2.b, 4.4.5.2.2.d, and 4.4.5.2.2.e are not applicable for valves UV 651, UV 652, UV 653 and UV 654 due to position indication of valves in the control room.

- The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4.

PALO VERDE - UNIT 2 3/4 4-20 AMENDMENT NO.

66

0 I

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I

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:

a.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the following valves are in the indicated positions with the valves key-locked shut:

Valve Number Valve Function Valve Position 1.

SIA HV-604 1.

HOT LEG INJECTION 1.

SHUT 2.

SIC HV-321 2.

HOT LEG INJECTION 2.

SHUT 3.

SIB HV-609 3.

HOT LEG INJECTION 3.

SHUT, 4

~

SID HV-331 4.

HOT LEG INJECTION 4.

SHUT.

b.

At least once per 31 days by:

1.

Verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked,

sealed, or otherwise secured in position, is in its correct position, and 2.

Verifying that the ECCS piping is full of water by venting the accessible discharge piping high points.

c

~

By a visual inspection which verifies that no loose debris (rags,

trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions.

This vi'sual inspection shall be performed:

1.

For all accessible areas of the containment prior to establishing CONTAINHENT INTEGRITY, and 2.

At least once daily of the affected areas within. containment by containment entry and during the final entry when CONTAINMENT INTEGRITY is established.

d.

At least once per 18 months by:

PALO VERDE - UNIT 2 3/4 5-4 AMENDMENT NO.

66

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CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS Continued 3.

Verifying that each spray pump starts automatically on a safety injection actuation (SIA) and on a containment spray actuation (CSA) test signal.

e.

At least once per 10 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.

PALO VERDE UNIT 2 3/4 6-16 AMENDMENT NO.~ 66

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PLANT SYSTEMS U ILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7. 1.2 At least three independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:

a.

Two feedwater

pumps, each capable of being powered from separate OPERABLE emergency

busses, and b.

One feedwater pump capable of being powered from an OPERABLE steam supply system.

OPPLIC L TT:

ECOLE I,. 2, I, 2

3

~CT ION:

a ~

b.

With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

With two auxiliary feedwater pumps inoperable 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 within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible.

SURVEILLANCE RE UIREHENTS 4.7. 1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE:

'a ~

b.

At least once per 31 days:

1.

Verifying that each valve (manual, power-operated, or automatic) in the, flow path that is not locked,

sealed, or otherwise secured in position, is in its correct position.

2.

Verifying that all manual valves in the suction lines from the primary AFW supply tank (condensate storage tank CTE-T01) to each essential AFW pump, and the manual discharge line valve of each AFW pump are locked, sealed or otherwise secured in the open position.

At least once per 92 days on a

STAGGERED TEST BASIS by:

1.

Testing the turbine-driven pump and both motor-driven pumps pur-suant to Specification 4.0.5.

The provisions of Specification 4.0.4 are not applicable for the turbine-driven pump for entry into NODE 3.

Until the steam generators are no longer required for heat removal.

PALO VERDE UNIT 2 3/4 7-4 AMENDMENT NO.~ 66

4

PLANT SYSTEMS SURVEILLANCE RE UIREMENTS C.

At least once per 18 months during shutdown by:

l.

Verifying that each automatic valve in the flow path actuates to its correct position upon receipt of an auxiliary feedwater actuation test signal.

2.

Verifying that each pump that starts automatically upon receipt of an auxiliary feedwater actuation test signal will start automatically upon receipt of an auxiliary feedwater actuation test signal.

.d.

e.

Prior to startup following any refueling shutdown or cold shutdown of.

30 days or longer, by veri'fying on a

STAGGERED TEST BASIS (by means of a flow test) that the normal flow path from the condensate storage tank to each of the steam generators through one of the essential auxiliary feedwater pumps delivers at least 650 gpm at 1270 psia or.

equivalent at the entrance of the steam generator.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or MODE 4 for the turbine-driven pump.

PALO VERDE UNIT 2 3/4 7-5 AMENDMENT NO. ~ ~,~

66

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~1 3 4.10 SPECIAL TEST PTIONS

~3 4.10.1 SHUTDOWN MARGIN AND K q

CEA WORTH TESTS LIMITING CONDITION FOR OPERATION

3. 10. 1 The SHUTDOWN MARGIN and K., requirements of Specification 3. 1. 1.2 may be suspended for measurement of CEA worth and shutdown margin provided reac-tivity 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*.

ACTION:

a

~

With any full-length CEA not fully inserted and with less than the above reactivity equivalent available for trip insertion, 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 and K., required by Specifica-tion 3. 1. 1.2 are restored.

b.

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 solu-tion containing greater than or equal to 4000 ppm boron or its equi-valent 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 50% withdrawn position within 7 days prior to reducing the SHUTDOWN MARGIN to less than the limits of Specification 3.1.1.1.

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

PALO VERDE UNIT 2 3/4 10-1 AMENDMENT NO.~ ~,66

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I

+**y0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ARIZONA PUBLIC SERVICE COMPANY ET AL.

DOCKET NO.

STN 50-530 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.

3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

51 License No. NPF-74 The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by the Arizona Public Service Company (APS or the licensee) 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 California Public Power Authority dated January 4,

1994, complies 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 application, 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 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 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 attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No.

NPF-74 is hereby amended to read as follows:

0 0

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ei ig Ir

3.

(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 51, 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, except where otherwise stated in specific license conditions.

This license amendment is effective as of the date of issuance and must be fully implemented no later than 45 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Date of Issuance:

September 2,

1994

I~

~ ~

sli

MENDMENT NO.

ATTACHMENT TO LICENSE AMENDMENT TO FACILITY OPERATING LICENSE NO.

NPF-74 DOCKET NO.

STN 50-530 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.

Remove 3/4 1-16 3/4 3-40 3/4 3-41; 3/4 4-20 3/4 5-4 3/4 6-16 3/4 7-4 3/4 7-5 3/4 10-1 Insert 3/4 1-16 3/4 3-40 3/4 3-41 3/4 4-20 3/4 5-4 3/4 6-16 3/4 7-4 3/4'-5 3/4 10-1

0 0

kg ~"

~

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REAC IVI ON RO SYSTEMS LIMITING CONDITION FOR OPERATION Continued

~CTIOM:

(Continued) b)

The SHUTDOWN MARGIN requirement of Specification 3.1. 1.2 is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Otherwise, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

d.

e.

With one full-length CEA inoperable due to causes other than addressed by ACTION a.,

above, but within its above specified align-ment requirements, operation in MODES 1 and 2 may continue pursuant to the requirements of Specification 3.1.3.6.

With one part-length CEA inoperable and inserted in the core, operation may continue provided the alignment of the inoperable part length CEA is maintained within 6.6 inches (indicated position) of all other part-length CEAs in its group and the CEA is maintained pursuant to the requirements of Specification 3. 1.3.7.

SURVEILLANCE RE UIREMENTS

4. 1.3. 1. 1 The position of each full-length and.part-length CEA shall be deter-mined to be within 6.6 inches (indicated position) of all other CEAs in its group at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when one CEAC is inoperable or when both CEACs are inoperable, then verify the individual CEA

,positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4. 1.3. 1.2 Each full-length CEA not fully inserted and each part-length CEA which is inserted in the core shall be determined to be OPERABLE by movement of at least 5 inches in any one direction at least once per 92 days.

t PALO VERDE' UNIT 3 3/4.1-16 AMENDMENT NO. 48,-42-51

L

INSTRUMENT 1.

Area Honitors TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE RE UIREHENTS CHANNEL MODES FOR WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE E I AIIBII E

~EBIREB A.

Fuel Pool Area RU-31 B.

New Fuel Area RU-19 C.

Containment Power Access Purge Exhaust RU-37

& RU-38 D.

Containment RU-148 RU-149 E.

Hain Steam RU-139 A&B RU-140 A&B 2.

Process Honitors p¹ P¹¹¹,W¹¹ 1,2,3,4 1,2,3,4 A.

Containment Building Atmosphere RU-1 1)

Particulate 2)

Gaseous B.

Control Room Ventilation Intake RU-29

& RU-30 3.

Post Accident Sampling System N.A.

1,2,3,4 1,2,3,4 All MODES g***

1 2

3

With fuel in the storage pool or building.

- With irradiated fuel in the storage pool.

- - The functional test should consist of, but sampling capabilities.

¹If purge is in service for greater than 12

¹¹When purge system is in oper'ation.

¹¹¹The functional test should consist of, but isolation capability by the insertion of a not be limited to, a verification of system

hours, perform once per 12-hour period.

not be limited to, a verification of system simulated alarm condition.

II IK'l

~

INSTRUMENTATION INCORE DET C

ORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The incore detection system shall be OPERABLE with:

a.

At least 75X of all incore detector locations, and 75X of all detec-tors, 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 contain-ing a fixed detector string with a minimum of three OPERABLE rhodium detectors or an OPERABLE movable incore detector capable of mapping the location.

~PPLI I ITY:

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II

ML17311A258

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