Text

Amends 96,84 & 67 to Licenses NPF-41,NPF-51 & NPF-74, Respectively,Revising Degraded Voltage Relay Trip Setpoint & Enchancing Current Presentation of Info Re loss-of-voltage Relay Setpoint
	ML17311B089
Person / Time
Site:	Palo Verde
Issue date:	07/21/1995
From:	Brian Holian; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML17311B090	List: ML17311B089; ML17311B091;
References
	NUDOCS 9508070185
	Download: ML17311B089 (60)
	v • d • e

l

~ gy8'K0(

Cy O

II/I

~O

>>>>*++

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 0

A PUB IC SERVIC COMPANY AL DOCKET NO.

ST 50-528 PALO V RD NUCLEAR GEN RATI G

S AT 0 U

T ME TO FACIL OP I

G C

NS Amendment No. 96 License No. NPF-41 1.

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

A.

The applications 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 December 30,

1993, and July 12,

1994, as supplemented by letters dated November 30,

1994, May 24,

1995, and June 21, 1995, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the 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 comon defense and security or to the health and safety of the public; and E.

The-issuynce 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:

9S08070185 950721 PDR ADQCK 05000528, P

PDR

I ~

3.

(2) Tec ical S ecifications and Environme tal Protectio Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 96, 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 ful.ly implemented no later than 45 days from the date of issuance.

FOR THE 'NUCLEAR, REGULATORY COMMISSION

Attachment:

Brian E. Holian, Senior Project, Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Changes to the Technical Speci.fications Date of Issuance:

Ouly 21, 1995

Il 4 ~

I

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.

96 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.

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

35~0V XIX 3/4 3-22 3/4 3-23 3/4 3-26 3'/4 3-27*

3/4 3-28*

~IS~R'g XIX 3/4 3-22 3/4 3-23 3/4 3-24a 3/4 3-26.

3/4 3-27*

3/4 3-27a 3/4 3-28*

No changes were made to these pages; reissued as overleaf pages.

0 I

~ g

LIST OF FIGURES INDEX PAGE 3.1-1 3.2-1 MINIMUM BORATED WATER VOLUMES..........................

REACTOR COOLANT COLD LEG TEMPERATURE VS CORE POWER EVEL ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~

L 3/4 1-11 3/4 2-8 3.3-1 3.4-1 DOSE EQUIVALENT I-131 PRIMARY COOLANT SPECIFIC ACTIVITY LIMIT VERSUS PERCENT OF RATED THERMAL POWER WITH THE PRIMARY COOLANT SPECIFIC ACTIVITY

> 1.0 pCi/GRAM DOSE EQUIVALENT I-131....................

3/4 4-27 LOSS OF BUS VOLTAGE TRIP SETTING TIME VS.

VOLTS.......

3/4 3-27a 3.4-2a 3.4-2b 3.4-2c 3.4-2d REACTOR COOLANT SYSTEM PRESSURE TEMPERATURE LIMITATIONS FOR LESS THAN 8 EFPY OF. OPERATION..........

REACTOR COOLANT SYSTEM PRESSURE TEMPERATURE LIMITATIONS FOR 8 TO 32 EFPY OF OPERATION..............

REACTOR COOLANT SYSTEM MAXIMUMALLOWABLE HEATUP AND COOLDOWN RATES FOR LESS THAN 8 EFPY OF 0 PERATION ~

~ ~ ~

~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~

REACTOR COOLANT SYSTEM MAXIMUMALLOWABLE HEATUP AND COOLDOWN RATES FOR '8 TO 32 EFPY OF 0 PERATION ~

~

~ ~

~

~ ~

~

~ ~

~ ~ ~

~ ~ ~ ~

~

~ ~ ~

~ ~

~ ~ ~

~ ~ ~ ~

~

~ ~

~ o ~ ~

3/4 4-29 3/4 4-29a 3/4 4-29b 3/4 4-29c 4.7-1 5.1-1 5.1-2 5.1-3 5.6-1 SITE AND EXCLUSION BOUNDARIES..........................

LOW POPULATION ZONE.....................

GASEOUS RELEASE POINTS.................................

ASSEMBLY BURNUP VERSUS INITIALENRICHMENT..............

5-2 5-3 5-4 5-6a SAMPLING PLAN FOR SNUBBER FUNCTIONAL TEST..............

3/4 7-26 PALO VERDE UNIT 1 XIX Amendment No. 55-,69-,88, 96

IST OF TAB S

PME 1.2 2.2-1 3.3-1 4.3-1 3 ~ 3 3 3.3-4 4.3-2 3.3-6 4.3-3 3>>3 7

4.3-4 FREQUENCY NOTATION....,......,..................--.-...-.

OPERATIONAL I fODES>> ~ ~ o ~ ~ ~ o ~ o ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ o ~

REACTOR PROTECTIVE INS1I'RUMEhlTATION TRIP SETPOINT LIHITSo ~ ~ ~ ~ ~ o ~ ~ ~ ~ I>> ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ i ~ ~ ~ ~ ~ ~ ~ o

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o o ~ o REACTOR PROTECTIVE INSTRUMENTATION................>>..o..

REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMEN'TS>> ~ ~ oo ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ l>> ~ ol ~ ooo ~

~ o ~ ~ ~ oo ~ ~ ~ oo ENGINEERED SAFETY FEATLIRES ACTUA'tIOH SYSl'EH INSTRUMENTATION...,.............'... l...'.. I...'.............

ENGINEERED SAFETY FEATURES,ACTUAL!IOtlt SYSIt'EH INSTRUMENTATION'RIP VALUIES>> ~ ~ ~ ~ ~ ~ ~ >> ~ ~ ~ ~ w o ~

~

i's ~ ~ ~ ~ ~ ~ ~ ~ ~

~

ENGINEERED SAFETY FEATURES ACTUATION SYS1!'EH'NSTRUMENTATION SURVIEILLAl'tCE REQUIREMENTS.....,.....

RADIATION MONITORING INSTRUMENTATION..'...',.....,.....,

RADIATION MONITORING INISTRUMENTATIOtt SURVEILLANCE REQUIREMENTS.............>>..............................

SEISMIC MOINITORING INSTRUHENTATION..'...'...',.... o.'... o.....

SEISMIC MONITORINGl INSTRUMENTATION SURVEILLANCE REQUIREMENTS........>>....o.....,...................i.....

1-8 1-9 2!-3 3/4 3-3 3/4 3. 14 3/4 3 18 3/4 3 25 3/4 3-31 3/4'3-'38 3/4 3-40 3/4 3-43 3/4 3-44

,3.3-8 4.3-5 HETEOROLOG ICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...........,..........'........

3/4 3 47 HETEOROLOG ICAL MONIITORING INSTRUMENTATION...............

3/4 I 3~46

'i 3.3-9A REMOTE SHUTDOMN INSTRUMEN'll'ATION....o...............

3/4 3 49 PALO.VERDE UNIT 1

'XX, AMENDMENT NO. $~,~69-,&3; 88

TABI.E 3. 3-3 (Continued)

ENGINEEREO SAFETY I'EATURI;S ACTUATION SYSTf:H INSTRUHENTAfION ESFA SYSTEH FUNCTIONAL'UNIT V.

RECIRCULATION (RAS)

A.

Sensor/Tr ip Units Refueling Mater Storage Tank - Low B.

ESFA System Logic 1.

Hatrix Logic TOTAI NO.

Of CIIANNELS CIIANNrfS IO IRII'IN IHIIH CHANNf LS APPLICABLE OPL'RAIILE HODES 1, 2, 3

1, 2, 3

ACTION 13*, 14" 17 2.

Initiation Logic 3.

Hanual RAS C;

Automatic Actuation Logic VI.

AUXILIARY FEEBMATER (SG-1) (AFAS-1)

A.

Sensor/Trip Units 1;

Steam Generator Nl Level-Low 2.

Steam Generator h Pressure - SG2 )

SG1 4(c) 4(c) 2(d) 2(d) 2 1, 2, 3, 4

1, 2, 3, 4

1.2.3 1,2,3 12 12 16 13*

144 13*

]4*

TABLE 3 3-3 (Continued)

ENGINEERED SAFETY FEATUR S ACTUA ON SYS EH NSTRU ESFA SYSTEH FUNC ONAL UNIT H IN I HUH TOTAL NO ~

CHANNELS CHANNELS OF CHANNELS TO TRIP

~OP R~B APPLICABLE

~00 S

m C)m C

VI.

AUXILIARY FEEOWATER (SG-1) (AFAS-1) (Continued)

B.

ESFA System Logic 1.

Hatrix Logi'c 6

'2.

Initiation Logic MdnIIal AFAS r

Ace+Ash'h4 4h Ant ss~+4nh I nnir 4 ~

hu4VIIIRlrI4 pl% \\ ulsl lvss s vg sv hhPhI

~Jt t h thh h'l IJPJh h'l Vil. AUAlLJAKT I tkUWAItK (44 4) (Hl >> <)

A.

Sensor/Trip Units 1.

Steam Generator t2 Level Low 2.

Steam Generator h.

Pressure SG1

> SG2 1

2 (d) 2 fd) 1, 2, 3

1, 2, 3, 4

1 9

'3 4

~

h LS LI J 1, 2, 3

17 12 15 16 13* 14*

O B.

ESFA System Logic 1.

Hatrix Logic 2 ~

Initiation Logic 3

Hanual AFAS r

Asstn~~t4C.ACt <m Number of Channels, restore'he

'indpeirable channel to OPERABI.E status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or b'- in at least HOT STANDBY within the'ext 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SH'UTGOWN Within'he. following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

With the number:of OPERABLE ckanlne1s one less than the Hiriim!'~m

'umber of Ci!annels, operati'on'may continue.for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,.

After 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months operation may c!I!nt3n0e provided at least 1 t'rain

'f esse!ntial filtration is in opieraition, otherwise, be in HOT

,SlANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months andi in COLD SHUTDOWN withi'n the'olliowing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

PALO VERDE - UNIT 1 3/4 3-24 AHENDMENT NO. 2'7

TABLE 3.3-3 (Continued)

ACTI N

TATE T

(C tl di ACTION 19 -

With three of the degraded voltage relays per bus INOPERABLE or not energized:

a.

Restore one degraded voltage relay to OPERABLE and comply with the provisions of ACTION 14 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ,. or b.

Restore two degraded voltage relays to OPERABLE and comply with the provisions of ACTION 13 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or c.

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

With four of the degraded voltage relays per bus INOPERABLE or not energized:

a.

Restore two degraded voltage relay to OPERABLE and comply with the provisions of ACTION 14 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or b.

Restore three degraded voltage relays to OPERABLE and comply with the provisions of ACTION 13 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or c.

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 .

PALO VERDE UNIT 1

3/4 3-24a Amendment No.

96

0

~ ~

'I

TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES ESFA SYST M FUNCTIONAL UNIT I.

SAFETY INJECTION (SIAS)

A.

Sensor/Trip Units 1.

Containment Pressure High 2.

Pressurizer Pressure - Low B.

ESFA System Logic C.

Actuation Systems II.

CONTAINMENT ISOLATION (C IAS)

A.

Sensor/Trip Units 1.

Containment Pressure - High 2.

Pressurizer Pressure - Low B.

ESFA System Logic C.

Actuation Systems III.

CONTAINMENT SPRAY (CSAS)

A.

Sensor/Trip Units Containment Pressure High High B.

ESFA System Logic C.

Actuation Systems IV.

MAIN STEAM LINE ISOLATION (MSIS)

A.

Sensor/Trip Units 1.

Steam Generator Pressure

- Low 2.

Steam Generator Level - High 3.

Containment Pressure - High B.

ESFA System Logic C.

Actuation Systems TRIP SETPOINT

< 3.0 psig

> 1837 psia' Not Applicable Not Applicable

< 3.0 psig

> 1837 psia"'ot Applicable Not Applicable

< 8.5 psig Not Applicable Not Applicable

> 919 psia'

< 9I.OX NR'"

~ 3.0 psig Not Applicable Not Applicable ORB VA UES

< 3.2 psig

> 1821 psia"'ot Applicable Not Applicable

< 3.2 psig

> 1821 psia"'ot Applicable Not Applicable g 8.9 psig Not Applicable Not Applicable

> 911 psia'

< 91.5X NR' g 3.2 psig Not Applicable Not Applicable

TABLE 3.3-4 (Continued)

ENGINEEREO SAFETY FEATURES ACTUATION SYSTEH.INSTRUHENTATIO U S ESFA SYSTEH UNCTIONAL UN V.

RECIRCULATION (RAS)

A.

Sensor/Trip Units Refueling Water, Storage Tank - Low C'

~

1.

B ESFA Systelll Lop IC C.

Actuation System VI.

AUXILIARY FEEOWATER (SG-1) (AFAS-1)

A.

Sensor/Trip. Units 1,

Steam Generator 81 Level Low C+n~%%%

I andr~+nr A Driaccllrn C

~

%I 4CQIII

%1%

% 4ltVI ak

~

~ \\ 44'4 ~

SG2

> SG1 B.

ESFA System Logic C.

Actuation Systems VII. AUXILIARY FEEOWATER (SG-2) (AFAS-2)

Sensor/Trin Units C4 nn%%% nnnn%%ntnr B I nnnl I nld

~

%1 4eQIII %1CIICI 4leVI

%%1

~ Cv C

=

% 4%%

2.

.Steam Generator 6 Pressure SG1. > SG2 B.

ESFA System Logic C.

Actuation Systems V"I L<<c OF PnWI-8

'A.

4.16 kV Eimiergenicy Bus Undervoltage

.iILncc.nf Voltaae)

TRIP VA UES 7.4X of Span Ling A

11 ll Ilvi nIIIII I'4dv I c Not Applicable

> 25.8X WR'4'85 ncid Not Applicable Not Applicable 25 8$ WR<<I

< 185 ps id Not Applicable Not-Applicable 395O,'vnltc LLOW B V

U S 7.9 > X of Span p 6.9 Not App I I cable Noi Applicable

>>5.3X WR~41 192 ncid Not Applicable Not Applicable 9R

%g IJD(4)

< '192 psid Not Applicable Not Applicable h 3250 volts B.

4.16 kV Emergency Bus Undervoltage (Oegraded Voltage) 3697 to 3786 volts 3697 to 3786 volts IX CONTROL ROOH ESSENTIAL FILTRATION

< 2 x 10 pCi/cc

TABLE'.3-4 (Continued)

TABLE STATIONS (1)

In MODES 3-6, value may be decreased manually, to a minimum of 100 psia, as pressurizer pressure is reduced, provided the margin between the pres-surizer pressure and this value is maintained at less than or equal to 400 psi; the setpoint shall be increased automatically as pressurizer pressure is increased until the trip setpoint is reached.

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

(2)

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

(3)

In MODES 3-6, value may be decreased manually as steam generator pressure is reduced, provided the margin between the steam generator pressure and this value is maintained at less than or equal to 200 psi; the setpoint shall be increased automatically as. steam generator pressure is increased until the trip setpoint is reached.

(4)

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

PALO VERDE - UNIT 1 3/4 3-27

0

~

13 12 10 S 11.4 sec

@ 29293 volts 8

7 6

5 2.4 sec

@0 volts 1000 2000 3000 VOLTS LOSS OF BUS VOLTAGE TRIP SETTING TIME VS.

VOLTS See Table 3.3-4 item VIII A.

PALO. VERDE UNIT 1

,3/4 3-27a Amendment No. 96

THIS PAGE.INTENTIONALLYLEFT BlANIK PALO VERDE - UNIT 1 3/4 3-2S (Next page is 3/4 3-31)

AMENDMENT NO. BB

g ~

~R AE00

~ p~

.'o Op nO IIh0 Vg

/p

~O

++*++

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHlNGTON, D.C. 20555-0001 R

0 PUB IC S RVICE COMPAN T AL.

DOCKET NO.

STN 50-529 0

ERDE NUCLEAR GE T

G ST ON UN T 0.

DME T TO FACILITY OP RAT G L CE S

Amendment No.

84 License No. NPF-51 1.

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

A.

The applications 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 Cal.ifornia Edison

Company, Public Service Company of New Mexico, Los Angeles Department of Water and Power, and Southern California Public Power Authority dated December 30,

1993, and July 12,

1994, as supplemented by letters dated November 30,

1994, May 24,

1995, and June 21,

1995, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the 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

'I 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:

Cl

~ p I

3.

(2) Technical S ecifications and Environmental Protection Pla The Technical Specifications contained in Appendix A, as.revised through Amendment No. 84, 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 Brian E. Hol;ian, Senior Project Manager Project Directorate IV;2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Speci'fications Date of Issuance:

duly 21, 1995

'0

~ ~

1

NO.

ATTACHMENT TO LICENSE AMENDMENT TO FACILITY OP RATING LICENSE NO.

N

-5 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.

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

XIX 3/4 3-22 3/4 3-23 3/4 3-26 3/4 3-27*

3/4 3-28*

XIX 3/4 3-22 3/4 3-23 3/4 3-24a

" 3/4 3-26 3/4 3-27*

3/4 3-27a 3/4 3-28*

No changes were made to these pages; reissued as overleaf pages.

i~

ib T

~,

I

LIST OF FIGURES INDE PAG 3.1-1 3.2-1 MINIMUM BORATED WATER VOLUMES..........................

REACTOR COOLANT COLO LEG TEMPERATURE VS CORE POWER EVEL ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~

~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ o ~ ~

L 3/4 1-11.

3/4 2-8 3.3.1 3.4-1 3.4-2a DOSE E(UIVALENT I-131 PRIMARY COOLANT SPECIFIC ACTIVITY LIMIT VERSUS PERCENT OF RATED THERMAL POWER WITH THE PRIMARY COOLANT SPECIFIC ACTIVITY

> 1.0 pC)/GRAM DOSE E(UIVALENT I-131...................

REACTOR COOLANT SYSTEM PRESSURE TEMPERATURE LIMITATIONS FOR LESS THAN 8 EFPY OF OPERATION..........

3/4 4-27 3/4 4-29 LOSS OF BUS VOLTAGE TRIP SETTING TIME VS.

VOLTS.......

3/4 3-27a 3.4-2b 3.4-2c 3.4-2d 4.7-1 5.1-1 5.1-2 5.1-3 5.6-1 REACTOR COOL'ANT SYSTEM PRESSURE TEMPERATURE LIMITATIONS FOR 8 TO 32 EFPY OF OPERATION..............

REACTOR COOLANT SYSTEM MAXIMUMALLOWABLE HEATUP AND COOLDOWN RATES FOR LESS THAN 8 EFPY OF PERATION..............................................

0 REACTOR COOLANT SYSTEM MAXIMUMALLOWABLE HEATUP AND COOLDOWN RATES FOR 8 TO 32 EFPY OF P ERATI0N ~ ~

~

~ ~

~

~ t

~

~ ~

~

. ~

~

~ ~

~

~ ~

'0 SAMPLING PLAN FOR SNUBBER FUNCTIONAL TEST....;.........

SITE AND EXCLUSION BOUNDARIES..........................

LOW POPULATION ZONE....................................

GASEOUS RELEASE POINTS..................................

ASSEMBLY BURNUP VERSUS INITIALENRICHMENT..............

3/4 4-29a 3/4 4-29b 3/4 4-29c 3/4 7-26 5-2 5-3 5-6a PALO VERDE UNIT 2 XIX Amendment No. 42-,55-,69, 84

IST OF TABLES'HKS

~ s 1.2 2.2-1 3.3-1 4.3-'1 3 ~ 3 3 3.3-4 4.3-2

.3.3-6 4.3-3

3. 3-.7 4.3-4 FREQUENCY INTATION.. e.... e....

~ ~ ~ 4 ~ - ~ ~

I - - - ~ ~ ~, ~ - ~ ~ ~ ~ ~ ~ ~ ~,

OPERATIONAIL htlODI:S e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ eI e ~ o e ~, ~. ~ e ~ ~ ~ ~ e e ~, ~ ~ e ~ ~,.

REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT IMITS ~ ~ ~ e ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~

~ ~ ~

~ ~ ~ e ~ e ~ ~ o ~ e, ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ oe ~

L REACTOR PROTECTIVE INSTRUHENTAYION..'..'....e. e...". -"--

REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS........e.... e.......,.....,..............,.....

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM, INSTRUMENTATION.....,;..-.............

~.;..................

ENGINEERED.SAFETY FEATUiRES ACTUATION SYSTEM, INSTRUMENTATION TRIP VALUES........>>.............-.

ENGINEERED SAFETY FEATURES ACTUAT'ION SYSTEM INSTRUMENTATION SURVIEILLANCE REQUIREMENTS.... ~..... ~.....

RADIATION tNNITORING INSTRUHENTATION....o.... ~...

RADIATION MONITORING INSTRUHENTATION SURVEILLANCE REQUIREMENTS.............e..............,......---..-.--

SEISMIC MONI1'ORING IINSTRUHENTATION.>>....................

SEISMIC MONITORING IINSYRVIRENTAYION SURVEILLANCE REQUIREMENTSe ~ e ~ ~ ~ ~ e'

~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ i ~ ~ e ~ ~

, ~ ~ j ~ ~ ~ ~ o ~ ~ ~ ee

~ ~ ~ ~ e 1-8 1-9 2-3 3/4 3-3 3/4,3-14, 3,/4,3-,18, 3,/4,3-25, 3/4,3-SI, 3/4i3-38'/4,3-,40, 3/4, 3-,43, 3/4, 3-,44, 3.3-8

4. 3-5 3.3-9A METEOROLOGICAL IHONITORING INSTRUMENTATION SURVEILLANCE REQUIREHENTS..........i.... o'...............

REMOTE SHUTIXNN INSTRUMENTATION...................,.....

3/4 3-47 3/4, 3;49, METEOROLOGICAL MOhlITORING INSTRUMENTATION....e.......;.

3/4I 3-l46 PALO VERDE - UNIT.2 AHENt3HENT NO. 49,Wg -'R-, 75

TABLE 3.3-3 (Continued)

ENGINEEREO SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION ESFA SYSTEM FUNCTIONAL UNIT V.

RECIRCULATION (RA'S)'.

Sensor/Trip Units Refueling Water Storage Tank - Low B.

ESFA System Logic 1.

Hatrix Logic HINIHUH TOTAL NO.

CHANNELS CHANNELS APPLICABLE OF CHANNELS TO TRIP OPERABLE HOOES 25 3

~ 1 2

3 ACTION 13", 14" 17 2.

Initiation Logic 3.

Manual RAS C.

Automatic Actuation Logic VI.

AUXILIARYFEEDWATER (SG-1)(AFAS-1)

A.

Sensor/Trip Units 1.

Steam Generator ¹1 Level-Low 2.

Steam Generator h Pressure - SG2 > SGl 4(c) 4(c) 2(d) 2(d) 2',

2, 3, 4 25 35 4 25 35 4 1, 2, 3

1, 2, 3

12 12 13", 14" 13*, 14"

TABLE 3.3-3 (Continued)

NG N

ER SAFETY FEATUR S CTUAT ON S STEH INSTRUH ESFA SYSTEH UNCTIONA UNI

, HINIHUH TOTAL NO.

CHANNELS CHANNELS OF CHANNELS

~TO TRI

~OP RA~B APPLICABLE

~OS'~0 VI.

AUXILIARYFEEOWATER (SG-1)(AFAS-1) (Continued)

B.

-ESFA System Logic 1

Mat.rix Inn1r n

r

'AB C ~

IIII 4 I CL I Ull LUAJ Il 3.

Hanual AFAS C.

Automatic Actuation Logic'I I. AUXILIARY FEEOWATER (SG-2) (AFAS-2)

A.

Sensor/Trio Units 1

CtAAsm L'annrstnr 89 IABUa1-J ~

VVV Ill~I 'Ql

~ ~l

~ 4VV ~

VV I

% V\\

~

Low 2.

Steam Generator h Pressure SU1 P Svc 4(c) 2 C'L4) 2(d) 1 1JP 1

B eJ 1

n n

LP CP JP

'1, 2, 3, 4

1,2,'3,4 1, 2, 3

1 n

LB CB 12 15 16

$3* $4*

B.

ESFA System Logic 1

Matrix l naic In'I+'I 14'4nn I n/I4n C ~

JIIAA Aaa AVU aVgAV 3.

Hanual AFAS Afr 1 TKvl 4(c) 2Id TI 2{dj 1

2 R

R 1JB

~

A LP CP A

~lP 3P 4

17 15 C.

Automati'c Actuation Logic VIII.

LOSS OF POWER (LOV)

A.

4.16 kV Emergency Bus Under-voltage (Loss of Voltage) 4/Bus(e) 2/Bus 3/Bus 1, 2, 3, 4

1, 2, 3

16 13*,14*

n 1I I

A ~

C

~ ~

DI ~

IlaJJaa 9

0 LO KV CIIILI'/tillf P4>

UIIUVI Un1tanIB (l1IBnrarlerl Vnltaaeh vv ~,vMJ Q

a a I 4/Bus(e)

IX.

'CONTROL ROOH ESSENTIAL FILTRATION 2

2/Bus 3/Rus 1 I 7

All Hodes 13* 14*,19*

I 18*

TABLE 3.3-3 Continued NGINEERED SAFETY FEATURES ACTUA ION SYSTEM INSTRUM NTATION TAB NOTAT ONS (a)

In MODES 3-4, the value may be decreased manually, to a minimum of 100

psia, as pressurizer pressure is reduced, provided the margin between th' pressurizer pressure and this value is maintained at less than or equal to 400 psi; the setpoint shall be increased automatically as pressurizer pressure is increased until the trip setpoint is reached.

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

(b)

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

(c)

Four channels

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

(d)

The proper two-out-of-four combination.

(e)

Input to channels.

The provisions.of Specification 3.0.4 are not applicable.

ACTION 12-ACTION 13 A Tl N NTATEIIENTE With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in. COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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

bypassed, the desirability of maintaining this channel in the bypassed condition shall be reviewed in accordance with Specification 6.5. 1.6.g.

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

With a channel, process measurement circuit that affects multiple

---furgtional units inoperable or in test, bypass or trip all associated functional units as listed below.

,Process Measurement Circuit 1.

Steam Generator Pressure-Low 2.

Steam Generator Level (Wide Range)

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

Steam Generator Level 2-Low (ESF)

Steam Generator Level Low (RPS)

Steam Generator Level 1-Low (ESF)

Steam Generator Level 2-Low- (ESF)

PALO VERDE - UNIT 2 3/4 3-23 Amendment No. 84

1ABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION,SYSTEM INSTRUMENTATION ACTION STATEMEN1IS ACTION 14-ACTION 15'-

ACTION 16-ACTION 17-ACTION 18-With the nuimber iof channel OPEfNBLE one lesis t,han the Minimum Channels

OPERABLE, STARTUP anid/or POWER OPERATION may continue provided the following conditions are satisfied:

a.

Verify that one of the inoper able channiels has been bypassed and place tlhe otlher inoperable channel in the tripped

.condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

b.

All functional units affected by the bylpassed/tripped channel shall also be placed in the bypassed/tripped condition as listedl below:

Process Measurement.

Circuit, i

i i FunctionaI Unit Bypassed/Tripped 1.

Steam Generator Pressure Steam Gleherator Pressure

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

Steaim Glenierator Level 2 - Low (ESF i

2.

Steam Generator Level - Low Steaim Generator Level - Low (RPS)

(Wide Range)

Steaim Generator L.evel 1 - Low (ESF)

Steam Generator Level 2 - Low (ESF)

STAfLTUP and/or POWE:R OPERATION may continue until the performance of the next required CHANNEL FUNC'PIONAL'TEST'.

Sulbsequent.

STAf(TUP and/or POWER OPERATION may'.continue if one channel iis restored to OPERABLE status and the provisions of ACTION 13 are satisfied.

With the number iof OPERABLF channels one less than the Tota'1 Number of Channels, riestor e the inoperable channel to OPERAIBLE status within 48 hciurs or be iiniat 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 .

With the number of OPERABLE channels one less than, the Total Number of Channels, be in at leasti HOT,STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at lea.t HOl SHUTDOWN within the following 6 hour0;

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

With the number of OPERABLE channels one 'less than the Minimum Number o1F Channels restore the inoperable channel to OPERABLE:.

status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or'be ini 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 SIHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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

Aftier -6 Ihours operation may continue provided at least 1 train of essential filtration is in operation, iothieri~ise, be in HOT STANDBY wit,hin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the followinig 30 Ihours,.

PALO VERDE " UNIT 2 3/4 3-24

TABLE 3.3-3 (Continued) 6 Tl N

7 TENE S

(C i

d)

ACTION 19 With three of the degraded voltage relays per bus INOPERABLE or not energized:

a.

Restore one degraded voltage relay to OPERABLE and comply with the provisions of ACTION, 14 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ,. or b.

Restore two, degraded voltage relays to OPERABLE and comply with the provisions of ACTION 13 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or c.

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

With four of the degraded voltage relays per bus INOPERABLE or not energized:

'a.

Restore two degraded voltage relay to OPERABLE and comply with the provisions of ACTION 14 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ,,or b.

c ~

Restore three degraded voltage relays to OPERABLE and comply with the provisions of ACTION 13 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 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 .

PALO VERDE UNIT 2 3/4 3-24a Amendment No. 84

0 I

C

a ICl ESFA SYSTEM FUNCTIONAL UNIT TRIP SETPOINT ALLOMABLE VALUES TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES m

C7m I.

SAFETY-. INJECTION (SIAS)

A.

Sensor/Trip Units 1.

Containmeht Pressure 2.

Pressurizer Pressure B.

ESFA System Logic C.

Actuation Systems II.

CONTAINMENT ISOLATION (C IAS)

A.

Sensor/Trip Units 1.

Containment Pressure 2.

Pressurizer Pressure B.

ESFA System Logic C.

Actuation Systems III. CONTAINMENT SPRAY (CSAS)

A.

Sensor/Trip Units Containment Pressure B.

ESFA System Logic C.

Actuation Systems High Low High Low High High

- 3.0 psig 183> psian~

Not Applicable Not Applicable

~ 3.0 psig

~ 1837 psia"'ot Applicable Not Applicable

~ 8.5 psig Not Applicable Not Applicable 3+2 psig

~

1821 psia"'ot Applicable Not Applicable 3.2 psig

~ 1821 psia"'ot Applicable Not Applicable s 8.9 psig Not Applicable Not Applicable IV.

MAIN STEAM LINE ISOLATION (MSIS)

A.

Sensor/Trip Units 1.

Steam Generator Pressure Low 2.

Steam Generator Level High 3.

Containment Pressure - High B.

ESFA System Logic C.

Actuation Systems 919 psia'"

91.0< NR'"

~ 3.0 psig Not Applicable Not Applicable 911 psi a@

91.5'R'"

s 3.2 psig Not Applicable Not Applicable

TABLE 3.3-4 (Continued)

ENGINEERED SAFETY EATURES ACTUATION SYSTEM INSTRUMENT ON TRIP VA U S

ESFA SYS EM"FUNC IONAL UNIT TRIP VALUES

~IOII B VAIU 8

(

m C7m C

V.

RECIRCULATION (RAS)

A.

Sensor/Trip Units Refueling-Water Storage Tank - Low B.

ESFA System Logic C.

Actuation System 7.4X of Span Not Applicable Not Applicable "7.9 > X of Span > 6.9 Not Applicable Not Applicable VI..

AUXILIARY FEEOWATER (SG-1) (AFAS-1)

A.

Sensor/Trip Units 1.

Steam Generator fl Level - Low 2.

Steam Generator 8, Pressure-SG2

> SG1 B.

ESFA System Logic Artllati'nn SUStemS VII. AUXILIARY FEEOWATER (SG-2)(AFAS-2)

A.- - -Sensor/Ti'-ip Uni-ts ---

.l.

Steam.enerator 82 Level - Low 2.

Steam Generator

h. Pressure-SG1

> SG2 B.

ESFA

.System Logic C.

Actuation Systems VIII; LOSS OF-'POWER Bo 4o 16 kV Emergency, Bus Unvel voltage (Degraded Voltage) et A.

4.16 kV Emergency Bus Undervoltage R

(Loss of:Voltage)

IX.

CONTROL ROOM ESSENTIAL FILTRATION

> 25.8X WR'4' 185 psid Not Applicable Not Applirable 7 25+8k wR

< 185 psid Not Applicable Not Applicable h 3250 volts 7tn7 4a 57OC

~ ~ 1I r VVVI lV VIVV YUI I >

< 2 x 10'Ci/cc

> 25,3X, WR~4i

< 192 psid Not Abnlicable Not Apnlicable

>. 25.3X wR

< 192 psid

.Not.Applicable Not Applicable h 3250 volts

'SLh7 4

77nt

~ I 14 VVVI lU +VIVV IVIES>

< 2 x 10'Ci/cc

TABLE 3.3-4 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRWENTATION TABLE NOTATIONS (1)

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

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

(2)

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

(3)

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

(4)

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

PALO YERDE - UNIT 2 3/4 3-27

0 I-

FIGURE 3.3-1 12 10 5 118 sec N 2929.5 volts 8

6 52 4 sec

@0 volts 1000 2000 3000 VOLTS LOSS.OF BUS VOLTAGE TRIP 'SETTING TIME VS.

VOLTS See Table 3.3-4 item VIII A.

PALO VERDE UNIT 2 3/4 3-27a Amendment No. 84

THIS PAGE INTENTIONALLY LEFT BLANK PALO VERDE UNIT 2 3/4 3-28 (Next page is 3/4 3-3l)

AMENDMENT NO. 75

~R RE0II.

Cy

~c n

C O

IVl0 Yr+~

~O

++*++

UNITED STATES NUCLEAR REGULATORY COMMtSS(ON WASHINGTON, D.C. 2055&4001 UB ICS C

C PA TA.

DOCK T NO.

STN 50-530 C

G I

G MENDMNTTO FAC YO TI G

C S

Amendment No. 67 License No. NPF-74 1.

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

A.

The applications 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 December 30,

1993, and July 12,

1994, as supplemented by letters dated November 30,

1994, May 24,

1995, and June 21,

1995, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the 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:

~ ~

(2) Tec nical 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 specific license conditions.

3.

This license amendment is effective as of the date of issuance and must be fully implemented no 1'ater than 45 days from the date of issuance.

FOR'THE NUCLEAR REGULATORY COMMISSION Brian E.

Hol ian, Seni or 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:

~ I j

, ~

~

I

M D

NT NO ATTACHMENT TO LICENSE AMENDMENT TO FACILITY OPENAT NG CENS N~O.

N

-74 DOCKET NO.

ST 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.

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

QEF~OVl',

XIX 3/4 3-22 3/4 3-23 3/4 3-26, 3/4 3-27*

3/4 3-28*

NSE T XIX 3/4 3-22 3/4 3-23 3/4 3-24a

'3/4 3-26 3/4 3-27*

3/4'-27a 3/4 3-28*

No changes were made to these pages; reissued as overleaf pages.

il p \\

~,

LIST OF FIGURES INDE PAGE 3.1-1 3.2-1 3.3-1 3.4-1 3.4-2a 3.4-2b 3.4-2c 3.4-2d MINIMUM BORATED WATER VOLUMES..........................

REACTOR COOLANT COLD LEG TEMPERATURE VS CORE POWER EVEL ~

~

~ ~

~

~ ~ ~ ~ ~

~

~ ~

~

~ ~

~

~ ~

~

~ ~ ~ ~ ~ ~

~

~ ~ ~ ~

~

~ ~

~ ~ ~ ~ ~ ~

L LOSS OF BUS VOLTAGE TRIP SETTING TIME VS.

VOLTS.......

DOSE EQUIVALENT I-131 PRIMARY COOLANT SPECIFIC ACTIVITY LIMIT VERSUS PERCENT OF RATED THERMAL POWER WITH THE PRIMARY COOLANT SPECIFIC ACTIVITY

> 1.0 pCi/GRAN DOSE EQUIVALENT I-131...................

REACTOR COOLANT SYSTEM PRESSURE TEMPERATURE LIMITATIONS FOR LESS THAN 8 EFPY OF OPERATION..........

REACTOR 'COOLANT SYSTEM PRESSURE TEMPERATURE LIMITATIONS FOR 8 TO 32 EFPY OF OPERATI'ON...............

REACTOR COOLANT SYSTEM MAXIMUMALLOWABLE HEATUP AND COOLDOWN RATES FOR LESS THAN 8 EFPY OF 0 PERATION'i ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ a ~ ~

~

~ ~ ~ ~

~

~ ~ ~

~ ~ ~ ~

~ ~ ~

~ ~

REACTOR COOLANT SYSTEM MAXIMUMALLOWABLE HEATUP AND COOLDOWN RATES FOR 8 TO 32 EFPY OF PERAT ION ~

~

~ ~

~

~ ~ ~

~

~ ~ ~ ~

~ ~

0 3/4 1-11 3/4 2-8 3/4 3-27a 3/4 4-27 3/4 4-29 3/4 4-29a 3/4 4-29b 3/4 4-29c 4.7-1 5.1-1 5.1-2 5.1-3 5.6-1 SITE AND EXCLUSION-BOUNDARIES..........................

LOW POPULATION ZONE.....;..............................

GASEOUS RELEASE POINTS...................,.............

~

ASSEMBLY BURNUP VERSUS INITIALENRICHMENT..............

5-2 5-3 5-4 5-6a SAMPLING PLAN FOR SNUBBER FUNCTIONAL TEST..............

3/4 7-26 PALO VERDE UNIT 3 XIX Amendment No. M-,4.2-',S4, 67

ST F TABLES IIHKK k

~

f e 1.2 2.2-1 3.3-1 4.3-1 3 ~ 3 3 3.3-4 4.3-2 3.3-6

'FREQUENCY NOTATION..o.............'.'..

J..'...'...'...,.......

OPERATIONAL MODES o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

i~ ~ ~

I ~ ~ J ~ ~ o ~ e o ~ o ~ e ~ ~ ~ ~ e o ~

REACTOR PROTECTIVE INSTRUMENTATION TRIP S'ETPOINT LIHITSe o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ o ~ ~ ~ ~ o ~ ~ ~ ~ 'o ~ ~ ~ ~ e ~ ~

REACTOR PROTECTIVE INSTRUMENTATION....o ~.'...', ~.'"'. "~ --

REACTOR PROTECTIVE IhlSTIRUMENTATION S'URVEI'LLANCE REQUIREMENTS... o.....,.............'.,'...'..........,........

ENGINEERED SAFETY FEATU'RES ACTUATION SYSTEM

)UMENTATIPNo ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ o ~ ~ ~ ~ ~ I, ~ ~ I ~ ~ J ~ ~ ~ ~ o ~ ~ ~ ~ e ~ ~ ~ ~ oo ~

'NGINEERED SAFETY FEATUIRES ACTUATION SYSTEM INSTRUMENTATION TRIP VAILUES......i..... J....'............,.

ENGINEERED SAFETY FBLTUIRES ACTUATION SYSTEM INSTRUMENTATION SURVEILILANCE REQUIREMENTS...'.'...'....

RADIATION MONITORIING IN,'STRUMIENTATION.. J....

J..'...'.......

1-8 1-9 21\\3 3/4 3-3

.3/4 3-14 3/4 3-18 3/4 3-25 3/4 3-31 3/4 3-38 4.3-3 3 ~ 3 7 4.3-4 3.3-8 4.3-5 RADIATION MONITORING IN'STRUMIENT'ATION SERVE IL'LANCE REQUIREMENTS...o......................o....o............

SEISMIC IMONITORING INSTIRUMENTATION....l.................

SEISMIC IMONITORING INSTRUMENTATIOl'i SURVEILLANCE' MliC EQUIREHENTS...o............o....o....o....o....o....o..

METEOROLOGICAL MONITORING INSTRUMENT~ATION.......,.......

METEOROLOGICAL l'lONITORING INSTRUMENTiATION SURVEILLANCE REQUIIREHENrs...........................;...

3.3-9A REMOTE SHUTDOMN INSTRUMIENTATION.....,.....,...............

3/4 3-40 3/4 3-43 3/4 3-44 3/4 3-46 3/4 3-47 3/4 3-49 PALO VERDE - UNIT 3 XX I

I I

AMENDMENT Np. ~ 4'S9 59

TABLE 3.3-3 (Continued)

ENGINEEREO SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION ESFA SYSTEM FUNCTIONAL UNIT V.

RECIRCULATION (RAS)

A.

Sensor/Trip Units Refueling Water Storage Tank - Low B.

ESFA System Logic TOTAL NO.

CHANNELS OF CHANNELS TO TRIP MINIMUM CHANNELS APPLICABLE OPERABLE MODES 1, 2, 3

ACTION 13", 14*

1.

Matrix Logic 2.

Initiation Logic 3.

Manual RAS C.

Automatic Actuation Logic VI.

AUXILIARYFEEDWATER (SG-1) (AFAS-1)

A.

Sensor/Trip Units 1.

Steam Generator tl Level-Low 2.

Steam Generator 6 Pressure - SG2

> SGl 4(c) 4(c) 2(d) 2(d)

.4 1,2,3 1, 2, 3, 4

1, 2, 3, 4 1, 2, 3, 4

1, 2, 3

1,2,3 17 12 12 16 13", 14+

13" 14*

ENGINEEREO SAFETY F ATURES AC UA ON SYSTEH INSTRUH 0

ESFA SYSTEH FUNC IONA UNIT TOTAL NO.

'OF CHANNELS HINIHUH CHANNELS CHANNELS

~TO RIP OPERABLE APPLICABLE

~00 S

BELCH VI.

AUXILIARYFEEDNTEA (SG-1) (AFAS-1) (Continued) ll CCCh Cite tnIII I nnie V ~

I VI el VJDIAI III LVQ ~ L i.

Hatrix Logic'.

Initiati on Logic 3.

Hanual AFAS C.

Automatic Actuation Logic VTT AUXTI TARY FEEnWATER (SG-2)(AFAS-2l A

C~<<r <<<< IT<<4<< ll<<44 i IS ~

4LIIAIUII I I III vll I Ln i.

Steam Generator d2 Level-I n LVW 2.

Steam GeneT'ator 6 Pressullrn SG1 s

SG2 B.

ESFA System Logic l.

Hatrix.Logic 2.

Initiation Logic 3.

Hanual AFAS C

AIltOmatiC Artuatinn I nair VIII.

LOSS OF POitER (iOV)

A.

4.16 kV Emergency Bus Under-voltage (Loss of Voltage)

B.

4.i6 kV Emergency Bus Under-33~1+ age (Degas ze1ed UO1+agnb IX.

CONTROL ROOH ESSENTIAL FILTRATION 6

4(c) 4(c) 2 4(c) 4(c).

2 4/Bus(e) 4/Bus /eh 1

2(d) 2(d) 1 1

2(d) 2(d) 1 2 IBue 2/vus 3

3/Bus 3/vus 1, 2, 3

1, 2, 3, 4

1. 2. 3.

4 JP cP 3

1 1

9I P

%I 1, 2, 3

1, 2, 3, 4

1,2,3,,4 1

0

'\\

h 1

<<1 1, 2, 3

1, 2, 3

All Hodes 17 12 15 16 13*ll4*

1 9+

1'A+

JAAI IJT 17 12 15 13* 14* 19+

t 18"

TABLE 3.3-3 Continued G

R S

F URES ACTU T 0 SYS TABLE NOTATIONS T

U (a)

In MODES 3-4, the value may be decreased manually, to a minimum of 100

psia, as, pressurizer pressure is reduced, provided the margin between the pressurizer pressure and this value is maintained at less than or equal to 400 psi; the setpoint shall be increased automatically as pressurizer pressure is increased until the trip setpoint is reached.

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

(b)

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

(c)

Four channels

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

(d)

The proper two-out-of-four combination.

(e)

Input to channels.

The provisions of Specification 3.0.4 are not applicable.

~TT N

T ENENTN.

ACTION 12 With the number of OPERABLE channel's one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 13 With the number of channels OPERABL'E one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may continue provided the inoperable channel is placed in the bypassed or tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . If the inoperable channel is

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

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

--4i'th a channel process measurement circuit that affects multiple

-functional units inoperabl'e or in test, bypass or trip all associated functional units as listed below.

Process Measurement Circuit 1.

Steam Generator Pressure

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

Steam Generator Level 2-Low (ESF) 2.

Steam Generator Level (Wide Range)

Steam Generator Level Low (RPS)

Steam Generator Level 1-Low (ESF)

Steam Generator Level 2-Low (ESF)

PALO VERDE UNIT 3 3/4 3-23 Amendment'o.

67

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION S'YS1EH INSTIRUMIENTATION ACTION STATEHENTS ACTION 14 "

Functional Unit Bypassedl/Tripped Steam Generator Pressure - Low Steam Generator Level 1 -

ILow (ESF)

Steam Generator Level 2 -

ILow (ESF) 1.

Steam Generator Pressure-Low With the number of clhanne'Is OPERABLE'ne less than the Hinimuk Channel.;

OPERABLE, STARTUP and/or POWER OPERATION may continue

.provided the follciwing conditidns aHe satisfied:

a.

Verify that aine of the indipe&ablle'hannels has been bypassed i

and place the other inoperable channel in, the tripped condition within 1, hour.

b.

Alll functionail units affected by the bypassed/tripped channel shall a'iso be placed in the bypassed/tripped condition as listed below:

Process Heasurement Circu'it 2.

Steam Generator (Wide Rainge)

STARTIUP and/or POWER of the next required STARTIUP and/or POWER restoredl to OPEIRABLE satisfied.

Level - Low Steam Generator LeVel - 'Low (RPS)

Steam Generator Level 1 -

ILowi (I=SF)

Steam Generator Level 2 -

ILowi (I=SF)

OPERATION may continue unti11 the performance CHANNEL FUNCTIONAL TEST.

Subsequent OPERATION may continue if one channel, is, status andi the provisions of ACTION 13 at.e ACTION 15-ACTION 16 "

ACTION 17-ACTION 18-With the number of OPERABLE chainnels one less than the Total Number oif Channels, restore the. inopei able channel to OPERABLE status witlhin 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY withiA 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following-6 hours.

With 'the number of OPERABLE chainnels one less than the Total Number of IChannels, be in at least HOT STANDBY within 6 hocirs'nd in ait least HOT SHUTDOWN within the fol'lowing 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ;

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

With the number of OPERABLE chainnels one less than the Hiniimum Number-of Channels, restore the. inopierable channel to OPERABLE status writhini 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in a't least HOT STANDBY within the

'ext i6 hours and in COLD SHUTDCIWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

With the numbier of OPERABLE channiels one less than the Hinimum Number of iChainnels, operation may continue 'for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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

PALO VERDE - UNIT 3 3/4 3-24

TABLE 3.3-3 (Continued)

S Ti N

T TfMINT (C

i dl ACTION'19 -

With three of the degraded voltage relays per bus INOPERABLE or,not energized:

a.

Restore one degraded voltage relay to OPERABLE and comply with the provisions of ACTION 14 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or b.

Restore two degraded voltage relays to OPERABLE and comply with the provisions of ACTION 13 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or.

c.

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

With four of the degraded voltage relays per bus INOPERABLE or not energized:

a.

Restore two degraded voltage relay to OPERABLE and comply with the provisions of ACTION 14 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or b.

Restore three degraded voltage relays to OPERABLE and comply with the provisions of ACTION 13 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or c.

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 .

PALO VERDE UNIT 3 3/4 3-24a Amendment No. 67

ik

\\,

I

~

J 4>

TABLE 3.3-4 ENGIN R 0 SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALU S ESFA SYSTEM FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES I.

SAFETY INJECTION (SIAS)

A.

Sensor/Trip Units 1.

Containmant< Pressure

- High 2.

Pressuriier Pressure

- Low B.

ESFA System i.ogic C.

Actuation Systems II.

CONTAINMENT ISOLATION (C IAS)

A.

Sensor/Trip Units 1.

Containment Pressure

- High 2.

Pressurizer Pressure

- Low B.

ESFA System Logic C.

Actuation Systems 111.

CONTAINMENT SPRAY (CSAS)

A.

Sensor/Trip Units Containment Pressure High High B.

ESFA System Logic C.

Actuation Systems IV.

MAIN STEAM LINE ISOLATION (MSIS)

A.

Sensor/Trip Units 1.

Steam Generator Pressure

- Low 2.

Steam Generator Level - High 3.

Containment Pressure

- High B.

ESFA System Logic C.

Actuati.on Systems

< 3.0 psig

> 1837 psia"'ot Applicable Not Applicable

. ~ 3.0 psig

> 1837 psia"'ot Applicable Not Applicable s 8.5 psig Not Applicable Not Applicable

> 919 psia."'

91.0X NR"'

3.0 psig Not Applicable Not Applicable

~ 3.2 psig

~ 1821 psia"'ot Applicable Not Applicable

~ 3.2 pssg

> 1821 psia'"

Not Applicable Not Applicable s 8.9 psig Not Applicable Not Applicable s 91,5X NR" s 3.2 psig Not Applicable Not Applicable

.IABIE 3

-4 ti ti d)

E GIN ERED SAF TY FEATURES CTU ION S ST H NS RUH N

ON TRI V

U S ESFA SYSTEH UNCTIONAL UN T V.

RECIRCULATION (RAS)

A.

Sensor/Trip Units Refueling Water Storage Tank - Low B.

ESFA System l,ogIC I

A+4

~ ~ ~4 4 aa CIt ~ '4 AM

'4 ~

I14 4 u a lr I UlI 4J 0 LrtJII VI.

AUxILIARY'FEEUwAIER (SG-1) (AFAS-1)

A.

Sensor/Trip Units 1.

Steam Generator

¹1 Level - Low 2.

Steam:Generator b, Pressure

SG2

> SG1 B.

ESFA SysteImI Logic C.

Actuation Systems VII. AUXILIARYFEEDWATER (SG-2)(AFAS-2)

A.

Sensor/Trip Units 1

Steam Generator ¹2 Level - Low SGl

> SG2 TR VALU S 7.4X of Span..

Not Applicable Llh4 AM1 4 t1 IL1 h nut nyyI II avIt

> 25.8X WR

< 185 psid

LI 4

A <<14 Il llUI ftpp I II aV It Not Applicable

> 2S.BX WR'4'85 psid lllLoi~lll 7.9 > X of Span

> 6.9 Not Applicable LI~4 A~~1 4~~I 1'~

Ilu4 flpp I I \\ aV It

> 2S.3X WRl4>

< 192 Dsid LI 4

A 14 Il I1Ul ttpp I I \\ a V It Not Applicable

> 2S.3X WR"'92 psid B.

ESFA System Logic C.

Actuation Systems VIII.

LOSS OF POWER A.

4.16 kV Emergency Bus Undervoltage (Loss of Voltage) 8 4

16 kV Fmeraency Bus Undervoltage (Degraded Voltage)

Not Applicaole Not Applicable Not Applicable Not Applicable

~ 3250 volts

~ 3250 volts 3697 to 3786 volts 3697 to 3786 volts W ~

IX.

CONIROL ROOH ESSENTIAL FILTRATION u

1A C

~Iil C

A JU U P'VIII Iv c x 10 5 PC I/cc

TABLE 3.3-4 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TABLE NOTATIONS (1)

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

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

(2)

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

(3)

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

(4)

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

PALO VERDE - UNIT 3 3/4 3-27

0

~ -

~ g'

13 12 10 5.11.4 sec

.N.29293 volts 8

6 5 2.4 sec 0 volts 1000 2000 3000 VOLTS LOSS OF BUS VOLTAGE TRIP SETTING TIME VS.

VOLTS See Table 3.3-4 item VIII A.

PALO VERDE UNIT 3 3/4 3-27a Amendment No.

67

THIS PAGIE INTENTIONALLY BLANK'.

'PALO VERDE - UNIT 3 3/4 3-28

,,'MENDMENT NO,.

(Next page is 3/4 3-31)

ML17311B089

Contents

Text

Attachment:

Attachment:

Attachment:

Navigation menu

ML17311B089

Text

Attachment:

Attachment:

Attachment:

Navigation menu

Search