ML17311B177

Amends 99,87 & 70 to Licenses NPF-41,NPF-51 & NPF-74, Respectively,Revising Surveillance Requirements & Bases Section of TS 4.7.1.6 to Increase Min Nitrogen Accumulator Pressure for Atmospheric Dump Valves

ML17311B177
Person / Time
Site:	Palo Verde
Issue date:	09/06/1995
From:	Thomas C NRC (Affiliation Not Assigned)
To:
Shared Package
ML17311B178	List: ML17311B177 ML17311B180
References
NUDOCS 9509140196
Download: ML17311B177 (30)

Text

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UNITED STATES NUCLEAR REGULATORY COIVIMISSION WASHINGTON, D.C. 2055&0001 ARIZONA PUBLIC SERVICE COMPANY ET AL.

DOCKET NO.

STN 50-528 PA 0 VERDE NUCLEAR GENERAT G STATION U IT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 99 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 ImprovemeIIt 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 June 17,

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 endaneering the health anC 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 appli.cable 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:

9509140iqb, 95090b PDR ADOCK 05000528

... P, PDR I i 1

41 ii

(2)

Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised

,through Amendment No.

99, and the Environmental: Protection Plan contained in Appendix B, are.hereby incorporated into this l,icense.

APS shall-operate the fac'ility in,accordance with the Technical Specifications and the Environmental Protection

Plan, except where otherwi'se stated in specific l.icense conditions.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION

>Charles R. Thomas, Project,Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes,to the Technical Specifications Date of Issuance:

September 6,

1995

II@

4

AMENDMENT NO.

ATTACHMENT TO'ICENSE AMENDMENT 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 marginal lines indicating the areas of change.

The corresponding overleaf pages are also provided to,maintain document completeness.

REMOVE 3/4 7-10 B 3/4 7-3 INSERT 3/4 7-10 8 '3/4 7-3

I

PLANT SYSTEMS MAIN STEAM LINE ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.7.1.5 Each main steam line isolation valve shall be OPERABLE.

APPLICABILITY:

MODES I, 2, 3, and 4.

ACTION:

MODE 1:

Ath one main steam line isolation valve inoperable but open, PNER OPERATION say continue provided the inoperable valve is restored to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; otherwise, be in at least MODE 2 within the next'6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

MODES 2, 3, and 4:

Pith one main steam line isolation valve inoperable, subsequent operation in MODE 2, 3, or 4 may proceed provided:

a.

The isolation valve is maintained closed.

b.

The provisions of Specification 3.0.4 are not applicable.

Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE RE UIREMENTS 4.7.1.5.1 Each main steam line isolation valve shall be demonstrated OPERABLE by verifying full closure within 4.6 seconds when tested pursuant to Specification 4.0.5.

4.7.1.5.2 The provisions of Specification 4.0.4 are not applicable for entry into. MODE 3 or MODE 4 to perform the surveillance testing of Specification 4.7.1.5.1 provided the testing is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after achieving normal operating steam pressure and normal operating temperature for the secondary side to perform the test.

PALO VERDE - UNIT 1 3/4 7-9

PLANT SYSTEMS 0

¹I 1

ATMOSPH RE DUMP VALVES LIMITING CONDITION FOR OPERATION 3.7.1.6 The atmospheric dump valves, shall be OPERABLE.,

~¹<<!

¹I>> ¹ I...

¹'.

~CT ION:

With less than one atmospheric dump valve per steam generator OPERABLE, restore the required atmospheric dump valve to OPEfgB(E Istatug Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

~¹L

¹

¹ ¹¹¹ 4.7.1.6 Each atmospheric dump valve shall be 'demonstrated'PERABLE:

a.

At least once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />...by verifying that the nitrogen accumulator tank is at a pressure

~, 615 PSIG.'.

Prior to startup following any refueling shutdown or cold shutdown of 30 days or longer, verify that', all val,'ves will open and-close fully.

• When steam generators are being used for dhc6y he6t removal.

SSee Special Test Exception 3. 10.9.

PALO VERDE UNIT 1

3/4 7-1O Amendrilent No. K~,99

YST MS BASES 3

..1.4 ACTIVITY The limitations on secondary system specific, activity ensure that the resultant offsite'adiation dose will be limited to a small fraction of 10 CFR Part 100 l.imits 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 electr ical power.

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

3...5 MAIN ST AM 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 wi.thin 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

~- 615 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 615 psig retains sufficient nitrogen volume. for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of operation at hot standby.

plus 9.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 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 RT>> 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 '1 B 3/4 7-3 Amendment No. 99

PLANT SYSTEMS BASES 3/4.7.4 ESSENTIAL SPRAY POND SYSTEM The OPERABILITY of the essential spray palnd system ensures that suffi~cient cooling capacity is available 1,or continued'perati'on of equipment during ~normal and accident conditipns.

The redundant coolin'g capacity of this system~

assuming a single failure, is cons'istent with tlhe assumptions used in the safety. analyses.

3/4.7.5 ULTIMATE HEAT SINK The limitations on the ultimate heat sink level and temperature ensure that sufficient cooling capacity is available to either (1) provide normal cooldown of the facility, or (2) to mitiga'te the effect's of accident conditions within acceptable 1 imits.

The limitations on minimum water 'level and max'imum temperature are based an providing a 27-day cooling watcher supply to safety-related equipment without exceeding their design, basis temperature and is consistent with the intent of the recommendations iaaf Regulatory Guide 1.27, "Ultimate Heat Sink for Nuclear Plants,"

March 1974.

3/4.7. 6 ESSENTIAL CHILLED WATER SYSTEM The OPERABILITY of the iessential chilled water sp~stiem ensures that'su'ffi-cient cooling capacity is available for continueai operation of equipment and control room habitability during accident conditions.

Tlhe redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the safety analyses.

The Essential Chilledl Mater.5ystem (ECMS), i'n conjunction wi h respective emergency HVAC units, i,s required in accordance witih Specification Definition

1. 18 to provide heat removal in maintaining the various Engineered Safety Features (ESFs) room space design temperatures below the associated equ',ipment qualification limits for the'ange of Design Basis Accidient conditions.

The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> ACTION requiremient for a single ECMS train out-of-service is consistent with the operability requirements of the Emergency Core Cooling.System, Essen-tial Cooling Mater System, Auxiliary.Feedwater System, and Containment

.spray System Limiting Conditions for Operation.

The normal HVAC system is used in maintaining the space design conditions of required safety systems during normal operating conditions.

The, normal HVAC system is also usied in maintaining the space design conditions in tlhe vital power distriibution irooms during normal operating conditions.

Action requirements are provided to ensure operability of the vital bus invertiers and emergency battery chargers, by ver ifying within, one hour that the normal ilVAC system is providing space coailing to the vital power distribution rooms.

Tlhe Action requirement is provided tai establish within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> operability o'f the safe shutdown systems which do not depend on the inoperable ECMS.

The 8 Ihour period provides a reasonable time in which to establish operability of thi,s c:omplement of key ! afety systems.

This require-ment ensures that a functional train of safe shutdown equipment is available tai put the plant in a safe, stable condition for the most probable abnorma'1 aipera-tional occurences.

An Action requirement of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is provided '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 NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ARIZONA Pl/BLIC SERVICE COMPANY ET AL.

DOCKET NO.

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

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

87 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 June 17,

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 Facil'ity Operating License No.

NPF-51 is hereby amended to read as follows:

(2)

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

87, 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,speci'fic license conditions.

3.

This license.

amendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

, Charles R. Thomas, Project Hanager Project Directorate IV-2 Division. of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

September 6,

1995

0

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.

87 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 marginal l,ines indicating the areas. of change.

The corresponding overleaf pages are also provided. to maintain document completeness.

REMOVE 3/4 7-10 B 3/4 7-3 INSERT 3'/4 7-10 B 3/4 7-3

4i

~

1

,PLANT SYSTEMS HAIN STEAM LINE ISOLATION VALVES

'LIMITING CONDITION FOR OPERATION

3. 7. l. 5 Each main steam line isolation valve sha').l be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

MODE 1:

With one main steam line isolation valve inoperable but open, POWER OPERATION'ay continue provided the inoperable val.ve is restored to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; otherwise, be in at least MODE, 2 within, the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

MODES 2, 3, and 4:

With one mai'n steam line isolation valve inoperable, subsequent operation in

,MODE 2, 3, or 4 may proceed provided:

a.

The isolation valve is maintained closed.

b.

The provisions of Specitication 3.0.4 are not applicable.

Otherwise, be in at least,HOT STANDBY within the"next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and,in COLO SHUTDOWN within the fol.lowing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE RE UIREHENTS 4.7.1.5.1 Each main steam line isolation valve shall be demonstTated OPERABL'E by veri'fying full closure within 4.6 seconds when tested pursuant to.

Specification 4.0.5.

4. 7. 1.5.2 The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or MODE 4 to perform the surveillance testing of Specification 4.7.1.5. 1 provided the testing is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after achieving normal operating steam pressure and normal operating temperature for the secondary side to.perform the test.

PALO VERDE - UNIT 2

3/4 7-9

PLANT SYSTEMS ATMOSPHERIC DUMP VALVES 0

LIMITING CONDITION FOR OPERATION 3.7.1.6 The atmo. pheric dump valves shall be OPERABLE.,

APPLICABILITY:

MODES 1, 2, 3, and 4*.

ACTION:

With less than one atmospheric dump valve per steam generator OPERABLE, restore the required atmo. pheric dump valve to OPERABti.E status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />;,

or, be in at least HOT STANDBY within the next 6 hbuds.

~RVEILLRRCE RE I RE ERE 4-.7.1.6 Each atmospheric dump valve shall be ',demonstrat'ed OPERABLE:

a.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying that the nitrogen accumulator tank is at a,pressure

), 615 psig.'.

Prior to startup following any refueling shutdown or cold shutdown,

'of,'0 days or longer, verify that al'1 valves will open and close~ fully.

~

• When steam generators

-are being used for decay heat removal.

PALO VERDE UNIT 2 3/4 7-10 Amendment No.

87

P ANT 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 1'imi'ts 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 HAIN STEAM LINE ISOLATION V L'VES 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 limi.tation on maintaining the nitrogen accumulator at a pressure h 615 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 615 psig retains sufficient nitrogen volume for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of operation at 'hot standby plus 9.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 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 Ropy of 40'F and are sufficient to prevent brittle fracture.

3 4.7.3 ESSENTIAL COOLING WATER SYSTE 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 cool'ing capacity of this system, assuming a single failure, is consistent with the assumptions used in the safety analyses.

PALO VERDE UNIT 2 B 3/4 7-3 Amendment No.

87

PLANT SYSTEMS BASES 3/4.7.4 ESSENTIAI'PRAY POND SYSTEM The OPERABILITY.of the esisential spray'6nd'ystem ensures that su'fficient cooling capacity is avail,able for continued'operation, of, equipment during,'normal and accident condition..

The redlundant coo'ling capacity of this system',

assuming a single failure, is consistent with the as'sumptions used in the safety'nalyses.

3/4.7. 5 ULTIMATE HEAT SINK The limitations on the ultimate heat sink level and temperature ensure that sufficient cooling capacity is avai'lable to ei'thier (1) pirovide normal c'ooldown

'f the facility, rir (2)i tio mitigate the effects of iaccident conditions within acceptable limits.

The limitations on minimum water level'nd maximum temperature are'ased on providing a 27-day coo'1ing water supply to,'safety-related equipment without exceeding their design basis temperature and is consistent with the intent of the recommendations iof Regulatory Guide 1.27,,"Ultimate Heat Sink for Nuclea'r Plants,"

March 19l4.

3/4.7. 6 ESSENTIAL CHILLED WiATER SYSTEM The 'OPERABILITY of the essential chillled water system ensures that suffi-cient cooling cap'acity is avai'Iable for continued operation of equipment and control room habitability during accident conditions.

The redundant coblilng capacity of this system, assuming a single ',failure is consistent with 'the; assumptions.

used i'n 'the safety analyses.

The Essential Chilled Water System (ECWS),

in conjunction with respective emergency HVAC uni'ts, is required in accordlande With Specification Definition 1.18 to provide heat removal in maintaining the various Engineered Safety Features (ESFs) room spiace d'es ign temperatures below the a sociated equipment qualification limits fair the. range of Desigh Basis Accident con~itions.

The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> ACTION requiretrient for a single ECWS tra'in out-of-service is consistent with the operability requirements of the Emlergendy Core 'Cooling System, ESsep-i tial Cooling Water System, Auxiliary Feedwater

System, and Containment Spray'ystem Limiting Conditions for Operation.

'The normal HVAC system is used in maintaining the space dlesign conditiions of required safety systems duripg nolrmal operating conditions.

The normal HVAC system is also used in maintaining the space design conditions in the vita>

AMENDMEN1 NO.'->i

1P,R AE00 po Cy A.0 0 Q

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++*++

'UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 ARIZONA'UBLIC SERVICE COMPANY ET AL.

DOCKET NO.

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

3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 70 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 June 17,

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.

The". e is reasonable assurance (i) tliat the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activitieswill be conducted in compliance with the Comission'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:

(2)

Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment.No.

70',

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'he Environmental Protection

Plan, except where otherwise stated, in specific license conditions.

'3.

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

FOR THE NUCLEAR REGUL'ATORY COMMISSION,

/'z Charles R. Thomas, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

September 6,

1995

II

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.

"0 TO FACILITY OPERATING LICENSE NO. NPF-74 DOCKET NO.

STN 50-530 Replace the fol;lowing pages of the:'Appendix A Technical Specifications with the enclosed, pages..

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

The corresponding overleaf pages are also provided to maintain document completeness.

REMOVE 3/4 7-10 8 3/4 7-3 INSERT 3/4 7-'10 B 3/4 7-3

41

, ~

PLANT SYSTEMS MAIN STEAM LINE ISOLATION. VALVES LIMITING CONDITION FOR OPERATION 3.7.1.5 Each main steam line isolation valve shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

MODE 1:

With one main steam line isolation valve inoperable but open, POWER OPERATION may continue provided the inoperable valve is restored to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; otherwise, be in.at least MODE 2 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

MODES 2, 3, and 4:

With one main steam line isolation valve inoperable, subsequent operati'on in MODE 2, 3, or 4 may proceed provided:

a.

The isolation valve is maintained closed.

b.

The, provisions of Specification 3.0.4 are not applicable.

Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE RE UIREMENTS 4.7.1.5.,1 Each main steam line isolation valve shall be demonstrated OPERABLE by verifying full closure within 4.6 seconds when tested pursuant to Speci ficati on 4. 0. 5.

4.7.1.5.2 The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or MODE 4 to perform the surveillance testing of Specification 4.7.1.5.1 provided the testing is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after achieving normal operating steam pressure and normal operating temperature for the secondary side to perform the test.

PALO VERDE UNIT 3 3/4 7-9

T SYST MS 0

MOS HERIC DUMP VALVES LIMITING CONDITION FOR OPERATION 3.7.1.6 The atmospheric dump valves-shall be OPERABLE.

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With less than one atmospheric dump valve per steam generator OPERABLE, restor'e the required atmospheric dump valve to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

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'MUT 4.7. 1.6 Each atmospheric dump valve shall be demonstrated OPERABLE:

a.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying that the nitrogen accumulator tank is at a pres ure

): 615 psig.

b.

Prior to startup following any refueli:ng shutd'owh or cold shutdown of 30 days or longer,, verify that alii valves will open,and close full.'y.

• When steam generators are being used for decay heat removal.

PALO VERDE UNIT 3 3/4 7-10 Amendment No.

70

P ANT SYSTEMS BASES 3 4.7.1.4 ACTIVITY The limitations on secondary system specific activity ensure that the resultant offsite radiation dose will'e limited to a small fraction of 10 CFR Part 100 limits in the event of a steam line rupture.

This dose al'so 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 1'oss-of-offsite electrical power.

These values are consistent wi,th the assumptions used in the safety analyses.

3 1.5 MAIN STEAM IN 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 cool'down 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

~ 615 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 615 psig retains sufficient nitrogen volume for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of operation at hot standby plus 9.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 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 Ropy 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 3 B 3/4 7-3 Amendment No. 70

PLANT SYSTEMS BASES 3/4.7.4 ESSENTIAL SPRAY PON'D SYSTEM The OPERABILITY of the es'. entia1 spray pdnd system 'ensures that sufficient cooling capacity is available ifor continued operation of equipment during normal and accident conditions.

The redundart coolirig capacity of this system, assuming a single failure, is consistent with the asisumptIions used in the safety'analyses.

3/4.7. 5 ULTIMATE HEAT SINK The limitations on the ultimate heat sink level and temperature ensure that sufficient coolingl capacity is available to either (1) provide normal cooldown 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 safety-rel'ated equipment without exceeding their design basis temperature and is consistent with the intient of the recommendations t)f Regulatory Guide 1.27, "Ultimate Heat Sink for Nuclear Plants,"

March 1974.

3/4. 7. 6 ESSENTIAL CHILLED WATER,SYSTEM The OPERABILITY of the essential chilli'ed 'water system ensures that suff'i-cient cooling capacity is available for continued operation of equipment and~

control room habitability during accident, conditions.

The redundant cobling capacity of this system, assuming a single fai'lure,'s consistent with 'the assumptions used in the safety analyses.

The Essential Chilled Water System (ECWS), 'in conjunction witlh respective emergency HVAC units is required in accordance with Specification Definition 1.18 to provide heat removal in maintaining the various Engineered Safe'ty Features (ESFs) room space design temperatures~

below the associated equipment qualification limits for the rangie of Design Bas'is Accident conditions.

The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> ACTION requirement for a,single ECWS tlrain 'out-of-service is consistent with the operability requiirements of the Emergency Core Cooli,ng System, Essen-tial Cooling Water System Auxili,ary Feedwater System and Containment Spray System Limiting Condition. for Opieration.

The normal HVAC system is used in maintaining the space design conditions of required safety systems during norm~1 operating conditions.

'The normal HVAC system is al~so used in maintaining thee space design conditions in the vital power distribution rooms during normal operating conditions.,

Action requirements are provided to ensure operability of the vital bus inverter.

and emergency battery chargers, by verifying within one hour that the nodal HVAC system is providing space cooling to the lvital power distribution rooms.

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

The 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />;period provides'

'reasonable time in whidh to establish operability of this complement of key.safety systems.

This require-

.ment ensures that a functional train of safe shutdown, equipment is avai'labia to put the plant in a safe, stable condition for thee most probable abnormal opera-tional occurences.

An Action requirement of 24 Ihours is provided to establi',sh, operability of the remaining required safety systems which do not depend on the inoperable ECWS.

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