Text

Amends 65,51 & 38 to Licenses NPF-41,NPF-51 & NPF-74, Respectively,Reducing Allowable out-of-svc Time for One Train of Ecw Sys from 7 Days to 72 H
	ML17306B030
Person / Time
Site:	Palo Verde
Issue date:	10/01/1992
From:	Quay T; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML17306B031	List: ML17306B030; ML17306B032;
References
	NUDOCS 9210130247
	Download: ML17306B030 (30)
	v • d • e

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 9210i30247 92iOOi PDR ADOCK 05000528'DR RIZONA PUBLIC SERVICE COMPANY ET AL.

OCKET NO.

STN 50-528 PALO VERDE NUCLEAR G NERATING STATION UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 65 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 April 27,

1992, 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; 2.

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.

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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3.

(2)'echnical S ecifications and Environmental. Protection Plan The Technical Speci,fications-contained in Appendix A, as. revised through Amendment 'No. 65, and. the Environmental Protection Plan contained in Appendix B, are hereby incorporated into.this license.

APS'hall operate the facility in accordance with 'the Technical Specifications and the Environmen'tal Protection

Plan, except where otherwise stated in specific license conditions.'his 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 Date of Issuance:

October 1,

1992 Theodore R.

quay., Director Project Directorate V

Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.

65 TO FACILITY OPERATING LICENSE NO. NPF-41 OCK T TN 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 7-15 B 3/4 7-4 Insert 3/4,7-15 B,3/4 7-4

L

PLANT SYSTEMS 3/4.7.6 ESSENTIAL CHILLED.WATER SYSTEM LIMITING CONDITION, FOR OPERATION 3.7.6.

At least two independent essential chilled water loops shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and'4.

ACTION:

a.

With only one essential chilled water loop OPERABLE, restore at least two loops to OPERASLE status within 72'hours or be in at least NOT 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 .

b.

With only one essential chilled water system OPERABLE:

l.

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months verify that the normal HVAC system is providing space cooling to the vital power distribution rooms that depend on the inoperable essential chilled water system for space

cooling, and 2.

Within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months establish OPERABIL'ITY of the safe shutdown systems which do not depend on the inoperable essential chilled water system (one train each of boration, pressurizer heaters and auxiliary feedwater),

and 3.

Within. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months establish OPERABILITY of all required systems, subsystems,

trains, components, and devices. that depend on the remaining OPERABLE essential chilled water system for space cooling.

I'f these conditions are not satisfied within the specified time, 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 .

SURVEILLANCE RE UIREMENTS 4.7. 6. 1 At least two essential chilled water loops shall be demonstrated OPERABLE at least once per 31 days by verifying that each valve (manual, power-operated, or automatic) servicing safety-related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.

4.7.6.2 Once per 18 months during shutdown, verify that each valve (manual',

power-operated, or automatic) servicing safety-related equipment that is locked,

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

PALO VERDE -,UNIT 1 3/4 7-15 AMENDMENT NO. 65

PLANT SYSTEHS 3/4. 7. 7 CONTROL ROOH ESSENTIAL FILTRATION SYSTEM LIHITING CONDITION FOR OPERAT'ION 3.7.7 Two independent control room essential filtration systems shall~ be OPERABLE.

APPLICABILITY:,Al 1

MODES.

ACTION:

NODES 1, 2, 3, and 4:

With one control room essential fi'ltration syst)em inoperable, restore the',

inoperable system to OPERABLE st.atus within 7 days or be in at least, HAT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN wi'thin the following'0 hours0 days 0 hours 0 weeks 0 months .

MODES 5 and 6:

With one control'oom es! ential filtrktion system inoperable restore the inoperable system to,OPERABLlE status within 7 days or initiate and maintain o!peration of the remai'ning

'OPERABLE control room essential filtrat.ion system.

b.

With both control room essential filtkat'ion systems inoperab1ie, or with the OPERABLE control room eSsent)al, filtration system, required to be OPERABLE by ACTION a., not capable of being powered by an OPERABLE,iemergency power source, suspend, all<pperations involving CORE ALTEIRATIONS or positive rea/ti'viky Changes.

4.7.7 Each control room essential fi'Itration'ystem shall be demonstrated OPERABLE:

a ~

At least once per 31 days on a STAGGERED TEST BASIS by initidti6g,'rom the control room, flow thro!igh'He HEPA filters and charcoal adsorbers and verifying that the'y'te'm 6perakes for,at least'5 ainutes.

At least bnce per 18 months or (1) after any structural waintknhncIe on the HEPA filter or charcoal adsokbelr housings, or (2) foll'owing'ainting, fire, or chemical releksei.inl any ventilation zone communicating.~iith the system 'by:

PALO VERDE - UNIT 1 3/4 7-16 AHENDHENT I'0. 2>.

PLANT SYSTEMS BASES 3/4. 7. 1. 4'CTIVITY The limitations on secondary system specific. activity ensure that the resultant offsite radiation dose will be limited to a small fraction of 10 CFR Part 100 limits in the event of a steam line rupture.

This dose also includes the effects of a coincident 1 gpm primary-to-secondary tube leak in the steam generator of the affected steam line and a concurrent loss-of-offsite electrical power.

These values are consistent with the assumptions used in the safety analyses.

3/4.7.1.5 MAIN STEAM LINE ISOLATION VALVES The OPERABILITY of the main.steam line isolation valves ensures that no more than one steam generator will blow down in.the event of a steam line rupture.

This restriction is required to (1) minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and (2) limit the pressure rise within containment in the event the steam line rupture occurs within containment.

The OPERABILITY of the main steam isolation valves within the closure times of the survei'llance requirements are consistent with the assumptions used in the safety analyses.

3/4.7. 1.6 ATMOSPHERIC DUMP VALVES The limitation on maintaining the nitrogen accumulator at a pressure

> 400 psig is to ensure that a sufficient volume of nitrogen is in the accumulator to operate the associated ADV which holds the plant at hot standby while dissipating core decay heat or which allows a flow of sufficient steam to maintain a controlled reactor cooldown rate.

A pressure of 400 psig retains sufficient nitrogen volume for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of operation at hot standby plus 6.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months of operation to reach cold shutdown under natural circulation conditions in the event of failure of the normal control air system.

3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness

'stress limits.

The limitations to 120 F and 230 psig are based on a steam generator RTNDT of 40'F and are sufficient to prevent brittle fracture.

3/4.7.3 ESSENTIAL'OOLING WATER SYSTEM The OPERABILITY of the essential cooling water system ensures that sufficient cooling capacity is available for continued operation of safety-related equipment during normal and accident conditions.

The redundant cooling capacity of this

system, assuming a single failure, is consistent with the assumptions used in the safety analyses.

PALO VERDE - UNIT 1 B 3/4 7-3

41 PLANT SYSTEMS BASES 3/4.7.4 ESSENTIAL SPRAY'OND SYSTEM The OPERABILITY of the essential spray Pond <ystem ensures that suff'icient cooling capacity is available for continued pperaf;ion of equipment during normal and accident conditions.

The redundant cooling c5pacity of this system, assuming a single failure, is consi!itent wi'th the assi'!mp'tions'sed'n the safety analyses.

3/4.7. 5 ULTIMATE HIEAT SINK The limitations on the ultimate heat 'sink level'nd temperature ensure -that sufficient cooling capacity is aivailable to either'1) provide normal cooldown of the facility, or (L) to mitigate the effects of'ccident conditions with'in acceptable limits.

The -limitations on minimum water level And maximum temperature are based on providing a 27-day cooli'ng waiter supply to slafdty related equipment without exceeding their design basiis 'temperature and is cons'istent with the intent of'he recommendations of Regula'tory Guide 1.27,, "Ultimate Heat Siink for Nudlekr Plants,"

March 1974.

3/4.7.6 ESSENTIAL CHILLED MATER SYSTEM The OPERABILITY of 'the. essent'ial chilled water !'ysterii! ensures that suffi-cient cooling capacity is aivailable for continued operation of equipment and control room habitability during accident conditions.',

The redundant cool'inq capacity of this system, assuming a single failure, 'is consistent with tHe assumptions used in the saf'ety analyses.

The Essential Chi llied Water System (ECMS), in conjunction with respective emergency HVAC units, is required in accordance with Specification Definition

1. 18 to provide heat removal in maintaining the various Engineered Safety Features (ESFs) room space design temper'atures bellow~the associated equip'mer')t

'ualification limits for the range of Design Basis Accident conditions.

'Thd.

72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ACTION requirement for a single ECMS train out-of-service is consistent with the operability requirements of the Emergency Core Cooling System, E'ss6n-'ial Cooling Water System, Auxiliary Feedwater

system, and Containment Sp'ray System Limiting Conditions for Operation.

The normal. HVAC system is used'ri maintaining the space design conditions of required

! afety systems during'ormal

'perating conditions.

The normal HVAC systemi is also used in maintaining'he

'pace design conditions

'in the vital ]power distribution rooms dlur'ing normeil operating conditions.

Action requirements are provided to ensure oper6bi'lit'y

'f the vital bus inver'ters and emergency battery chargers,,

by ver'ifying wiithinl one hour that the normal HVAC system is providing space ccioling to the vital

.power distribution rooms,.

The Actiion requirement is provided.to establish

.within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months operability of the ! afe shutdown systems which dlo not depend on the inoperable ECWS.

The 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provides a reasonable time in which to establish operability of this -comp1lement of key safety systems.

This require-ment ensures that a functiona'I train iof safe shutdown equipmient, is available to put the plant in a safe, stab;le condi'tion for the most iprobable abnormal ope,ra-tional occurences.

An:Action requirement of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is providled to establish operability of the remaining required safety systems which do not depend on the inoperable ECWS.

PALO VERDE " UNIT 1 B 3/4 7-4 AMENDMENT NO. 65

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UNITED STATES NUCL'EAR REGULATORY COMMISSION WASHINGTON,D. C. 20555 RIZONA PUBLIC SERVICE COMPANY T AL.

OCKET NO.

STN 50-529 PALO VERDE NUCLEAR GENERATING STAT ON UNIT NO.

2 MENDM NT TO FACILITY OP RATING ICENSE Amendment No.

51 License No.

NPF-51 1.

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 April 27,

1992, 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; 2.

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.

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:

Il

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'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 Date of Issuance:

October 1,

1992 Theodore R. quay, Director Project Directorate V

Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.

5 TO FACILITY OPERATING LICENSE NO. NPF-51 OCKET 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 7-15 B 3/4'-4 Insert 3/4 7-15 B 3/4 7-4

4l

PLANT'YSTEMS 3/4.7.'6 ESSENTIAL CHILLED WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.6 At least two independent essential chilled water loops shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With only one essential chilled water loop OPERABLE, restore at least two loops 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With only one essential chilled water system OPERABLE:

1.

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months verify that the normal HVAC system is providing space cooling to the vital power distribution rooms that depend on the inoperable essential chilled water system for space

cooling, and 2.

Within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months establish OPERABILITY of the: safe shutdown systems which do not depend on the inoperable essential chilled water system (one train each of boration, pressurizer heaters and auxil,iary feedwater),

and 3.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months establish OPERABILITY of all required systems, subsystems,

trains, components, and devices. that depend

.on the remaining OPERABLE essential chilled water system for space cooling.

If these conditions are not satisfied within,the specified time, 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 .

SURVEILLANCE RE UIREMENTS 4.7.6.1 At least two essential chilled water loops shall be demonstrated OPERABLE at least once per 31 days by verifying that each valve (manual, power-operated, or automatic) servicing safety-related equipment that is not locked, sealed, or otherwise secured in position, is in 'its correct position.

4.7.6.2 Once per 18 months during shutdown, verify that each valve (manual, power-operated, or automatic) servicing safety-related equipment that is locked, sealed, or otherwise secured in position, is in its correct position.

PALO VERDE - UNIT 2 3/4 7-15 AMENDMENT NO. 6i

0 PLANT,SYSTEMS 3/4. 7. 7 CONTROL ROOM ESSENTIAL FII TRATION, S!IjSTSM

'IMITING CONDITION FOR OPERATION 3.7.7 Two independent; control room essent'ial filt'ratio'n systems shall be OPERABLE.

APPLICABILITY: Al 1 MODES.

ACTION:

MODES 1, 2, 3, and 4:

With one control room essential filtration'sy'st6m inoperable, restore t;he inoperable system to OPERABLE status within 7 days 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 SHU1DOWN within the followi'ng 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

MODES 5 and 6:

With one control room essential filtration system inoperable, reston the inoperable system to OPERABLF. status within 7 days or initiate and maintain operati'on of the remai'nihg OPERABLE control room essential filtration system.

b.

With both c'ontrol room essential filtration systems inoperable, or

.with the OPERABLE control room essential'iltrat'ion

system, required to be OPERABLE by ACTION a., not'ca'parle'f being powered by an OPERABLE emergency power source, suspend all operations involving CORE ALTERATIONS or positive reactivity ichanges.

4.7.7 Each control room essential filtration~ system shall be demonstrated OPERABLE:

At least 'once per 31 days on a STAGGERED TEST BASIS by initidtihg, from the control room, flow through'he HEPA filters and charcoal adsorbers and verifying that. the'system ope'rates'or at least 15 minute..

At least once per 18 months or (1) after any structural maint'enanc'e on the HEPA filter or charcoal adsokb6r housings',

or (2) following painting, fire, or c;hemical release in any,ventilation zone communicating with the system by:

PALO VERDE " UNIT 2 3/4 7-16

PLANT SYSTEMS BASES 3/4.7. 1. 4 ACTIVITY The limitations on secondary system specific activity ensure that the resultant offsite radiation dose will be limited to a small fraction of 10 CFR Part 100 limits in the event of a steam line rupture.

This dose also includes the effects of a coincident I gpm primary"to-secondary tube leak in the steam generator of the affected steam line and a concurrent loss-of-offsite electrical power.

These values are consistent with the assumptions used in the safety analyses.

3/4.7.1.5 MAIN STEAM LINE ISOLATION VALVES The OPERABILITY of the main steam line isolation valves ensures that no more than one steam generator will blow down in the event of a steam line rupture.

This restriction is required to (1) minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and (2) limit the pressure rise within containment in the event the steam line rupture occurs within containment.

The OPERABILITY of the main steam isolation valves within the closure times of the surveillance requirements are consistent with the assumptions used in the safety analyses.

3/4.7. 1.6 ATMOSPHERIC DUMP VALVES The limitation on maintaining the nitrogen accumulator at a pressure

> 400 psig is to ensure that a sufficient volume of nitrogen is in the accumulator to operate the associated ADV which holds the plant at hot standby while dissipating core decay heat or which allows a flow of sufficient steam to maintain a controlled reactor cooldown rate.

A pressure of 400 psig retains sufficient nitrogen volume for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of operation at hot standby plus 6.'5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months of operati'on to reach cold shutdown under natural circulation conditions in the event of failure of the normal control air. system.

3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits.

The limitations to 120 F and 230 psig are based on a steam generator RTNDT of 40 F and are sufficient to prevent brittle fracture.

3/4. 7. 3 ESSENTIAL COOLING WATER SYSTEM The 'OPERABILITY of the essential cooling water system ensures that sufficient cooling capacity is available for continued operation of safety-related equipment during normal and accident conditions.

The redundant cooling capacity of this

system, assuming a single failure, is consistent with the assumptions used in the safety analyses.

PALO VERDE - UNIT 2 8 3/4 7=3

PLANT SYSTEMS BASES 3/4.7.4 ESSENTIAL SPRAY POND SYSTEM The OPERABILITY of the. essential spray pond system ensures that suff'icient cooling capacity is avai'lable for continued operation of equipment during nOrmal and accident conditions.

The redundant cooling capacity of this system, assuming a single failure, is consistent with the, assumptions used in the safety ainalys&s.

3/4. 7. 5 ULTIMATE HEAT SINK, The limitations on the ultimate lheat sink level and temperature ensuire that sufficient cooling capacity i! availlalble to either (1) lprovide normal coolddwn of the facility, or (2) to mitigate the effects of accident conditions within acceptable limits.

The limitations on minimum water level and maximum temperature are based on providing a 27-day cooling water supply to'afe'ty-related equipment withdut'xceeding their design basis temperature and 'is'consistent with the intent of the recommendations of Regulatory Guide 1.27,'Ult'imate Heat Sink for Nuclear Plants,"

March 1974,.

3/4.7.6 ESSENTIAL CHILLED WATER SYSTI.:M The OPERABILITY of the e.sential chilled water system ensures that suffi-'ient cooling capacity is availalble for continu6d bpe!ration of equipment and control room habitability during accident conditions.

The r!.dundant cool'ing capacity of this sy. tern, assuming a, single fa'ilure', is consi! tent with the assumptions used in the safety analyses.

The Essential Chilled Hat.er System (ECWS), in conj)snction with respective emergency HVAC unit., is required in accordance with Specification Definition

1. 18 to provide heat removal in maintaining the various Engineered Safety Features (ESFs) room space design temperatures below the associated equipment qualification limit.; for the ran!ge of Design IBasis Accident conditions.

The 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ACTION requirement for a sing'ale ECMS train o0t-of-'service is consistent with the operability requirements of the Emergency Core Cooling System, ESsen-tial Cooling Water.system, Auxil'iary Feedwater

System, and Containment Spray System Limiting Conditions for Operation.

'Thee nor!nal HVAC syistem is used in maintaining the space design conditions of required safety systems during normal operating condition..

The norea'I HVAC system is also used in maintaining the space design conditions in,'the vital power di0tributi'on rooms during normal

'perating condition.'.

Action requirements are provided to ensure operability of the vital bus inverters and emergency battery char'gers, by verifying with'in'ne hour that the normal HVAC system

)is providing space cooling to the vital power distribution rooms.

The Action requirement is 'provided to establish within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months operability of the safe shutdown systems which do not depend on the inoperable ECWS.

'The 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provides a reasonable time in which to establish operability of this complement of key safety systems.

This require-ment ensures that a funct;ional train of safe hhultd6wn equipment is availalhle t6 put the plant in a. afe, stable condition for'he mos't probable abnormal opera+

tional occurences.

An Action requirement of 24 'ho!'~rs'. provided to establish operability of the remaining required safety Systems Which do not depend on the inoperable ECWS.

PALO VERDE - UNIT 2 B 3/4 7-4 AMENDMENT NO. 51

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/g 4y*y4 UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ARIZONA PUBLIC SERVICE COMPANY ET OCKET NO.

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

3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 38 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 April 27,

1992, 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:

Il II

(2)

Technical S ecifications and Environmental Protection Pl'an The Technical Specifications contained in Appendix A, as revised through Amendment No.38 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.

3.

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 COHMISSION Theodore R. quay, Director Project Directorate

'V Division of Reactor Projects III/IV/V Office of Nuclear Reactor..Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

October 1,

1992'

il

AMENDMENT NO.

ATTACHMENT TO LICENSE AMENDMENT TO F CI ITY OPERATING ICENS NO.

PF-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 7-15 B 3/4 7-4 nsert 3/4 7-15 B 3/4 7-4

II Il

PLANT'.SYSTEMS 3/4.7..6 ESSENTIAL'HILLED'WATER SYSTEM LIMITING CONDITION.'FOR OPERATION 3.7.6 At least two independent essential chilled water loops shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

a ~'ith only one essential chilled water loop OPERABLE, restore at least two loops 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 NOT 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 .

b.

With only one essential chilled water system OPERABLE:

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months verify that the normal HVAC system is: providing space cooling to the vital power distribution rooms that depend on the inoperable essential chilled water system for.space

cooling, and 2.

Within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months establish OPERABILITY of the safe shutdown systems which do not depend on the inoperable essential chilled water system (one 'train each of boration, pressurizer heaters and auxil,iary feedwater),

and 3.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months establish OPERABILITY of all required systems, subsystems,

trains, components, and devices that depend on the remaining OPERABLE essential chilled water system for. space cool,ing.

If these conditions are not satisfied within the specified time, 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'ours.

SURVEILLANCE -RE UIREMENTS 4.7.6. 1 At least two essential chilled water loops shall be demonstrated OPERABLE at least once per 31 days by verifying that each valve:(manual, power-operated, or automatic) servicing safety-related equipment that is not locked, sealed, or otherwise secured in position, is in.its correct position.

4.7.6.2 Once,per 18 months during shutdown, verify that each valve, (manual, power-operated, or automatic) servicing safety-related equipment that is

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

PALO VERDE - UNIT 3 3/4 7-15 AMENDMENT 'NO'. 38

PLANT SYSTEMS 3/4 7 7 CONTROL,ROOM ESSENTIA FIL'TRATION SYSTEM LIMITING CONDITION FOR OPERATION Il 3.7.7 Two independent control room essential filtration systems shall be OPERABLE.

APPLICABILITY:

A 1 1,MODES.

ACTION:

MODES 1, 2, 3, and 4:

With one control room essential filtration 'sy<te5 inoper'able, restore the inoperable system to OPERABLE,status within 7 days 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 SflUTIDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

MODES 5 and 6:

With one con'trol room essential filtration system inoperable, re store the inoperable system to OPERABLE status'ithin 7 days br 'ini-

'iate and mai ntain operat'ion of the reizaining OPFRABLF. control room essential filtration system.

b.

With both control room essential filtration systems inoperable, or with the OPERABLE control room es.sential filtration system, rtquirkd to be OPERABLE by ACTION a.,

not capable of being powered by hn OPERABLE emergency power source,,suspend all operations involving CORE ALlERATIONS or positive reactivity chahges.

III!

E>>

4.7.7 Each control room essential filtration system ~hall be demonstrated OPERABLE:

a.

b.

At least once per 31 days on a STAGGERED TEST BASIS by, initiating,'rom the contro'I room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 15 minutes,.

At least, once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber

housings, or (2) followi,ng painting, fire, or chemical release in any ventilat'ion zone commuriicating with the, system by:

PALO VERDE - UNIT 3 3/4 j~j6 i

PLANT SYSTEMS BASES 3/4. 7. 1. 4 ACTIVITY The limitations on secondary system specific activity ensure that the resultant offsite radiation dose will be limited to a small fraction of 10 CFR Part 100 limits in the event of a steam line rupture.

This dose also includes the effects of a coincident 1 gpm primary-to-secondary tube leak in the steam generator of the affected steam line and a concurrent loss-of-offsite electrical power.

These values.are consistent with the assumptions used in the safety analyses.

3/4. 7. l. 5 MAIN STEAM LINE 'ISOLATION

'VALVES'he OPERABILITY of the main steam line isolation valves ensures that no more than one steam generator will blow down in the event of a steam line rupture.

This restriction is required to (1) minimize the positive reactivity effects of the Reactor-Coolant System cooldown associated with the blowdown, and (2) limit the pressure rise within containment in the event the steam line rupture occurs within containment.

The OPERABILITY of the main steam isolation valves within the closure times of the surveillance requirements are consistent with the assumptions used in the safety analyses.

3/4.7. 1.6 ATMOSPHERIC DUMP VALVES The limitation on maintaining the nitrogen accumulator at a pressure

> 400 psig is to ensure that a sufficient volume of nitrogen is in the accumulator to operate the associated ADV which holds the plant at hot standby while dissipating core decay heat or which allows a flow of sufficient steam to maintain a controlled reactor cooldown rate.

A pressure of 400 psig retains sufficient nitrogen volume for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of operation at hot standby plus 6.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months of operation to reach cold shutdown under natural circulation conditions in the event of fai,lure of the normal control air system.

3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress 'limits.

The limitations to 120 F and 230 psig are based on a steam generator RTNDT of 40'F and are sufficient to prevent brittle fracture.

3/4.7. 3 ESSENTIAL COOLING WATER-SYSTEM The OPERABILITY of the essential cooling water system ensures that sufficient cooling capacity is available for continued operation of safety-related equipment during normal and accident conditions.

The r'edundant cooling capacity of this

system, assuming a single failure, is consistent with the assumptions used in the safety analyses.

PALO 'VERDE - UNIT 3 8 3/4 7-3

0 PLANT SYSTEMS BASES 3/4.7.4 ESSENTIAL SPRAY POND SY'TEM The OPERABILITY of the essential spray pionid system ensures that sufficien!t cooling capacity is available for continued ope!ration of equipment dluring n6rmlal and accident conditions.

The redundant cooling capacity of 'this system, assuming a single failure, is consistent with the assumptions used in the safety analyshs~

3/4.7. 5 ULTIMATE HEAT SINK The limitations on the. ultimate heat sink 'level and temperature ensure that sufficient cooling capac'ity is avaiilable to either (1) provide normal coo'ldown'.

of the facility, or (2) to mitigate the effects of accident conditions within acceptable limits.

The limitations on minimum water leve"I and maximum temperature ar'e based on providing a 27-day cooling water supply ta safety; related equipment without exceeding their design basis temperature and is consilstent with the intent of the recommendations of Regulatory Guiide 1.27, "Ult'imate Heat Sink for Nuclear Plants,"

March 1974.

3/4.7.6 ESSENTIAL CHILLI-D WATER SYSTEM The OPERABILITY of the e.sential chilled water system ensure.

that suffi-cient cooling capac'ity i. available for continu&d opera'tion of equipment and control room. habitability during ac:cident conditions.

The redundant cool'ing capacity of this system, assuming a single failUre, is consistent with the assumptions used in the safety analyses.

The Essential Chilled Water System (ECWS), in cdnjunc!tion with respective emergency HVAC units, is requireid in accordance with Specification Defini'tion

1. 18 to provide heat, removal i!n maintaining the various Engineered Safety Features (ESFs) room space design temperatures below the associated equipment

'ualification limit. for the ran!ge of Design Basis Accident conditions.

The 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ACTION requirement for a single ECWS !train oUt-of-service is cons!istlent with the operability requirements of the Emergency Core Cool'ing System, ECse'n-'ial Cooling Water.system, Auxiliary Feedwater

System, and Containment Spray System Limiting Conditions for Operation.

Th'e normal'VAC system is used'in maintaining the space design c:onditions of required safety systems during normal operating condition..

The normal HlVAC system is a'iso used in maintaining the space design condit'ions in the v'ital power distribution rooms during normal

'perating condition..

Action requirements are provided to ensure operabilitJy of the vital bus inverters anci emergency battery chargers, by verifying with'in one hour that the normal HVAC system

',is provilding space'co'oling to tlhe vital power distribution rooms.

'The, Action requirement hs 'provided to establish within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months operability of the safe shutdown syhte!ms'which do not depend on the inoperable ECWS.,

The 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provides a reasonable time in whith to establish operability of this complement of key safet~y systems.

This require-ment ensures that a functional train of safe ShutdOwn equipment is a'vailable to put the plant in a safe, stable condition for'he most probable abnormal opera<

tional occurences.

An Action requirement of 2I 4 ho0rs is p'roiiided to establish operability of the remainin!g required safety systems

~which do not depend on the.

inoperable ECWS.

PALO VERDE - UNIT 3 B 3/4 7-4 AMENDMENT NO. 38

ML17306B030

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