ML17312A673

Amends 105,97 & 77 to Licenses NPF-41,NPF-51 & NPF-74, Respectively,Changing Instrument Setpoint for RT & MSIS Actuation on Low SG Pressure

ML17312A673
Person / Time
Site:	Palo Verde
Issue date:	04/05/1996
From:	Thomas C NRC (Affiliation Not Assigned)
To:
Shared Package
ML17312A674	List: ML17312A673 ML17312A675
References
NUDOCS 9604120268
Download: ML17312A673 (32)

Text

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UNITED,STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 A PUBL C

S RV C 0

PA T

CKET NO.

T 50-5 8 G

T T

Amendment No. 105.

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 Ri.ver Project Agricultural Improvement and Power District, El Paso Electric Company, Southern California Edison

Company, Public Service Company of New Mexico, Los Angeles, Department of Mater and

Power, and Southern California Public Power Authority dated December 20,

1995, complies with the standards and requirements of the Atomic Energy Act of 1954,. as amended (the Act) and the Comoission'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 Facili.ty Operating License No. NPF-41 is hereby'mended to read as follows:

9604f20268 960405 PDR ADOCK 05000528 P

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3.

(2)

T chnical S ecificatio s and Environmental Protection lan The Technical Specifications contained, in Appendix A, as revised through Amendment No. 105, and the Environmental Protection Pl'an 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 Pl'an, except where otherwise. stated in specific license conditions.

This license amendment is effective as of its date of issuance to be implemented within 45 days of issuance..

FOR THE NUCLEAR'EGULATORY 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:

April 5, 1996

Ii I

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TTACHH N C

NS 105 TO C

T OP T NG C

S NO, PF-4 CKET 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.

@fan'~0 2-3 3/4 3-25 3/4 3-27 2LBI 2-.3 3/4 3-25 3/4 3-27

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TABLE 2.2-1 a

S lUUNCT NA UN T 1.

TRIP GENERATION C

TRIP SETPOINT AUS A.

Process 1.

Pressurizer Pressure - High g 2383 psia g 2388 psia REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT M

S O

2.

Pressurizer Pressure Low 3.

Steam Generator Level Low 4.

Steam Generator Level High 5.

Steam Generator Pressure Low 6.

Containment Pressure '- High 7.

Reactor Coolant Flow Low a.

Rate b.

Floor c.

Band 8.

Local Power Density - High 9.

DNBR Low B.

Excore Neutron Flux 1.

Variable Overpower Trip a.

Rate b.

Ceiling c.

Band Z 1837 psia (2)

> 44.2X (4) g 91.0X (9)

~ 895 psia (3) g 3.0 psig g 0.115 psi/sec (6)(7)

~ 11.9 psid (6)(7) g 10.0 psid (6)(7) g 21.0 kW/ft (5)

Z 1.30 (5)

F10.6X/min of RATED THERMAL POWER (8) gllO.OX of RATED THERMAL POWER (8)

~9.7X of RATED THERMAL POWER (8) h 1821 psia (2)

Z 43.7X (4)

C 91.5X (9)

~ 890 psia (3) g 3.2 psig g 0.118 psi/sec (6)(7)

Z 11.7 psid (6)(7) g 10.2 psid (6)(7) 5 21.0 kW/ft (5)

Z 1.30 (5)

F11.0X/min of RATED THERMAL POWER (8) gill.OX of RATED THERMAL POWER (8) g9.9X of RATED THERMAL POWER (8)

m Kl CD FUNCT ONA --UNI TABLE 2:2-1 (Continued)

R ACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT'HITS

~TRIP EETP iNF AB VA U C.

.2.

L'ogiiithmic Power Level - High (I) a.

Startup and Operating

.b.

Shutdown Core-"Protection CalcIIlator'vstem 1.

CEA Calculators 2-

-Core Protection Calculators

< 0.010X of RATED vnrnuas nns urn I IICnrIHI I VIICIC

< 0.010X of RATED THERMAL POWER'ot Applicable Ro'"pl'c"b'e g- 0.011K oF 'RATED THERMAL. POWER C. 0.011%, of. RATED THERNL'OWER Not Applicable, Not ApplIcabl'e

'D.

Supplementary Protection System Pressur!zer---Pressure---

High-II.

RPS LOGIC M~I ~ ix I 'og'i'c B.

Initiation Logic 2469-psia------

Not Applicable Not Applicable Not Applicable Not Applicable v r v,nnc isa.

'nrem A.

ACTUATION DEVICES Reactor Trip Breakers Hanual Trip Not Applicable Not Applicable Not Applicable Not Applicable CD

TABLE 3.3-4 NG NEERED SAFETY FEATURES ACTUAT ON SYSTEM INSTRUMENTAT ON TR P VA U S SFA SYST U CT ONA UN T 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 (CIAS)

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 g 3.0 psig

> 1837 psia"'ot Applicable Not Applicable 5 3.2 psig p 1821 psia"'ot Applicable Not Applicable g 3.0 psig Z 1837 psia' Not Applicable Not Applicable g 3.2 psig

>'1821 psia"'ot Applicable Not Applicable

< 8.5 psig Not Applicable Not Applicable g 8.9 psig Not Applicable Not Applicable h 895 psia' 5 91.0X NR"'

3.0 psig Not Applicable Not Applicable

~ 890 psia'

~ 91.5X NR<>>

g 3.2 psig Not Applicable Not Applicable TJUP EETPOINT

~tlilAB E VA U I

NG N

SAF SF SYS UNCT ON U

~3-(C tl d)

ATUR C

U S

H U

NT 0

V.

RECIRCULATION (RAS)

A.

Sensor/Trip Units Refueling Hater, Storage Tank - Low B.

ESFA System.'Logic C.

Actuation'System VI; AUXILIARYFEEDHATER (SG-1) (AFAS-1)

A.

Sensor/Trip Units 1

%foam nonoratnr 81' ovol -

I nw 2o Steam Generatol Ll Pressulc SG2 > SG1 B.

ESFA System Logic C.

Actuation Systems VII AUXILIARYFEEDHATER (SG-2)(AFAS-2)

A; Senser/Trip Units Steam Gene1'ator f2 Level - Low 2.

Steam Generator h Pressure-SG1 > SG2 B.

ESFA System Logic C.

Actuation Systems VIII.

LOSS OF POHER A.

4.16 kV, Emergency Bus Undervoltage

- --- -----(toss of-Vol-tage) 7.4X of Span Not Applicable.

Not Applicable Av MR(C) 10r lOil P5 IU-Not Applicabl'e Not Applicable

> 25-.8X-HR"'

185 psid Not Applicable Not Applicable

~ 3i50 volts 7.9 p '5 of Span p 6.9 Not Appl1cable Not Applicable

~ v ovsv nil 192 ps Id Not Applicable Not Applicable

> -25;3X-HR"'

< 192 psid Not Applicable Not Applicable z 3250 volts B.

4.16 kV Emergency Bus Undervoltage (Degraded Voltage)

IX; CONTROL ROON ESSENTIAL FILTRATION

< 2 x 10 aCi/cc

< 2 x 10 S uCi/cc 3697 to 3786 volts 3697 to 3786 volts

13330 3.3-4 (0

44 0).

3333JLADAT 0 3 (I)

In NODES,3-6, 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.

(2)

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

(3)

In NODES 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'si; 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 I 3/4 3-27 Amendment No.

105

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 205554001 OA UB C

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NU R

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D ENT TO FAC Y 0 T

G ENSE Amendment No. >>

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 Mater and

Power, and Souther n California Public:Power Authority dated December 20, 1995, 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'h'is 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 th'is 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:

I

2.

3.

(2) ec nic ecifications and v ro e tal Prote t P

The Technical Specifications contained in Appendix A, as revised through Amendment No.

97, 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 its date of issuance to be implemented within 45 days 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 Speci'fications Date of Issuance:

April 5, 1996

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TN 50-5 9

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.

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2-3 3/4 3-25

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TAB

2. 2-1 REACTOR PROTECT VE NSTRUM NTATION TRIP SETPOINT TS UNC N

UN 1.

TRIP GENERATION A.

Process 1.

Pressurizer Pressure High 2.

Pressurizer Pressure Low 3.

Steam Generator Level - Low 4.

Steam Generator Level - High 5.

Steam Generator Pressure Low 6.

Containment Pressure - High 7.

Reactor Coolant Flow Low a.

Rate b.

Floor c.

Band 8.

Local Power Density High 9.

DNBR - Low B.

Excore Neutron Flux 1.

Variable Overpower Trip a.

Rate b.

Ceiling c.

Band TRIP SETPOINT

~ 2383 psia

~ 1837 psia (2)

Z 44.2X (4)

< 91.0X (9)

~ 895 psia (3) g 3.0 psig g 0.115 psi/sec (6)(7) h 11.9 psid (6)(7) g 10.0 psid (6)(7) 5 21.0 kW/ft (5)

Z 1.30 (5) gl0.6X/min of RATED THERMAL POWER (8) 5110.0X of RATED THERMAL POWER (8) 69.7X of RATED THERMAL POWER (8)

OWA g 2388 psia h 1821 psia (2)

Z 43.7X (4) g 91.5X (9)

Z 890 psia (3) g 3.2 psig S 0.118 psi/sec (6)(7)

~ 11.7 psid (6)(7) g 10.2 psid (6)(7)

~ 21.0 kW/ft (5)

Z 1.30 (5)

Nil.OX/min of RATED THERMAL POWER (8)

~111.0X of RATED THERMAL POWER (8) 69.9X of RATED THERMAL POWER (8)

TABLE 2.2-1 (Continued)

REACTOR PROTECTIVE INSTRUM NTATION TR P

SETPO NT

~FUMC 0

A UN 2.

Logarithmic Power Level - High (1) a.

Startup and Operating b.

Sh'utdown I nre PrOter tihn CalCiilatOr SUStein 1.

.CEA Calculators n

~ s'r 4 ~

'OUI L t I 4 LLL4 I VII 'Ud I '44 I d LUI 0 D.

Supplementary Protection System rressurlZer rreSSure lllgn II.

RPS LOGIC TRIP S

TPO NT g 0.010X of RATED TutnIIAI nni.itn IIIChiinL rUIICn 6.0.010X of RATED THERNL POWER Not Applicable A

1~L1 11UL HPP I II dLII5 2409 psia 5 0.011X of RATED TIJl hUAi hhl lth I llCIMHL I'Uhcn 5 0.011X of'RATED THERNL POWER Not Applicable Not Applicable 2414 psla A.

R Hatrix Logic Initiatinn Lnnir Not Applicable Nnt Annlirahle Not Applicable Nnt Annlicahle III.

RPS ACTUATION DEVICES Rea"to" r " Bw"ke"s B.

Manual Trip Not Applicable Not Applicable iNot Applicable Not Applicable

TABLE 3.3-4 NGINE RED SAF TY EATURES ACTUATION SYST M

NSTRUMENTA ON TR P VA U SFA SYST FUNCT ONA UN T

~TRIP ETPO NT A~LMAB E.ll UEE 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 (CIAS)

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 Actuation Systems

< 3.0 psig

> 1837 psia"'ot Applicable Not Applicable

< 3.0 psig 2 1837 psia"'ot Applicable Not Applicable

< 8.5 psig Not Applicable Not Applicable

> 895 psia"'

91.0X NR~

< 3.0 psig Not Applicable Not Applicable g 3.2 psig

~ 1821 psia"'ot Applicable Not Applicable g 3.2 psig

> 1821 psia"'ot Applicable Not Applicable g 8.9 psig Not Applicable Not Applicable Z 890 psia"'

91.5X NR g 3.2 psig Not Applicable Not Applicable

IABBL3-4 lc t

d)

R TU S'

V.

RECIRCUL'ATION (RAS)

A.

Sensor/Trip Units

=Refueling Water Storage Tank - Low B.

ESFA System Logic C.

Actuation System VT AIIXTITARV PPCnlJdTFR (Cr. >>id'~ >>

~

~ ssaoe 1 ~

~ hI vl~ ~ ~ ~ bI1 1o'w 11 $ ~ I ~ IIv Jl A.

Sensor/Trip UnltS 1.

Steam Generator fl Level - Low IstozIII I:onorAfnr A Processr o

~ '8

~

- 04

~

~

VV'4 ~

SG2 > SG1 B.

ESFA System Logic C.

Actuation Systems UT T AIIYTITADV CCCAUATCD ICO s1'i IACAC O'I 1aa

~ nvna4anns

~

s 4vssns4n gvsa=cp gns na=c]

A.

Sensor/Trip Units 1.

Steam Generator 82 Level - Low C4nssss I nssnrn4 Ar A'rneessrn c ~

&It% sslls U%

~ ~\\

~ ssUvs aa s I s ddsl ~

SG1 > SG2 R

CCCd Cvc.tnsss Inn4r

~ vs sl vJvv%

~I~

s vg ~ %t C.

Actuation Systems VIII.

LOSS OF POWER 7.4X of Span Not Applicable Not Applicable Z.25.8X WR"'R5 ns4d Not Applicable Not Applicable 25.8%

MR<4) r 1DC Ae4l a VV Is4 I'l Hot Applicable 7.9 p X of Span p 6.9 Not Applicable Not Applicable Z 25.3X WR"'

1OO Ar 4i adC IIO IU Not Applicable Hot Applicable 25 M MR(C) 1OO ave IIB Isa llA4 AAA14Aslsln sssss nlsls s ss sssis4 Hot Applicable A.

4.16 kV Emergency Bus Undervoltage (Loss 0 I Vo I idge) nACA

~ ~

1 a

+7CQU YUI I 5 3250 volts B.

4.16 kV Emergency Bus Undervoltage (Degraded Voltage) 3697 to 3786 volts 3697 to 3786 volts Tv r nIIvonl onnu eCCtilTTAI eTI TDATThLI ahs 4VIII AV4 ISVVI1 I +7alE I1I an4 I a4 I ISnS aVS1 r 5 u 1n S

asr4 la~

c h av Iav II44

~ A~

2 x ~10 pCI/CC

~ A ~ s z

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++*++

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ONA PUB C SERVIC 0

P TA.

.S 5-0 AO R

C A

GN T

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NT ENDM NT TO FACILITY OPERAT NG ENSE Amendment No. 77 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 Servi'ce Company of New Mexico, Los Angeles Department of Mater and

Power, and Southern California Public Power Authority dated December 20,

1995, compl.ies wi,th 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.

C.

The facil,ity will operate in conformity with the application, the provisions of the Act, and-the rules and regulations of the COIImIission; 4

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:

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3.

The Technical Specifications contained in Appendix A, as revised through Amendment No.

77, 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 its date of issuance to be implemented within 45 days of issuance.

FOR'HE NUCLEAR REGULATORY COMMISSION Charles R. Thomas, Project Manager

'roject Directorate IV-2

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

Attachment:

Changes to the Technical, Specifications Date of Issuance:

April 5, 1996

~l

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C NT TO C

NS N

T O.

77 I

TY C

O.

-74 CKET NO.

ST

0 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.

REHOV INSERT 2-3 3/4 3-25 2-3 3/4 3-25

~

~,

a I

Lt l1

FUNC ON 1.

TRIP GENERATION A.

Process TABLE 2.2-1 REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS TRIP SETPOINT 1.

Pressurizer Pressure - High 2.

Pressurizer Pressure - Low 3.

Steam Generator Level - Low 4.

Steam Generator Level - High 5.

Steam Generator Pressure - Low 6.

Containment Pressure - High 7.

Reactor Coolant Flow - Low a.

Rate b.

Floor c.

Band 8.

Local Power Density - High 9.

DNBR Low 4

B.

Excore Neutron Flux 1.

Variable Overpower Trip a.

Rate b.

Ceiling c.

Band

< 2383 psia

~ 1837 psia (2)

> 44.2X (4) g 91.0X (9)

~ 895 psia (3) g 3.0 psig g 0.115 psi/sec (6)(7)

~ 11.9 psid (6)(7) g 10.0 psid (6)(7) 5 21.0 kW/ft (5)

Z 1.30 (5) 610.6X/min of RATED THERMAL POWER (8) gllO.OX of RATED THERMAL POWER (8) 69.7X of RATED THERMAL POWER (8)

~ 2388 psia

~ 1821 psia (2)

Z 43.7X (4) g 91.5X (9) h 890 psia (3)

~ 3.2 psig g 0.118 psi/sec (6)(7) h 11.7 psid (6)(7) g 10.2 psid (6)(7) 5 21.0 kW/ft (5)

Z 1.30 (5)

Nil.OX/min of RATED THERMAL POWER (8) 6111.0X of RATED THERMAL.POWER (8) 69.9X of RATED THERMAL POWER (8)

FUNCT ONAL UN 2.-

Logarithmic Power Level - High (1) a.

Startup and Operating 5 0.01IX of RAIED THERMd1 POuED 0 010'K of DhTED THERMAL POWER

< 0;OIOX of RATED TUCDMAt hnurn I I II IIIllll I IIIIQQ g 0.011'f RATED THERMAL POWER' Chil 4 Alluvia w e Vd ~llldVVIII I J

Core Protection Calculator System

~dddd:

-I (d

dd dd REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT L HITS A

TRIP SETPOINT AL ORB VA UES 1 ~

CEA Cal oui >>ters Core Protection Calculators D.

Supplementary prntection ~ cust Pressurizer Pressure - High II.

RPS LOGIC A.- Natrix.L'o'gic

, B.

Initiat ion I og ic III. RPS ACTUATION DEVICES A-Ractor Trip

=Breakers'.

Manual Trip Not Applicable Not Applicable g 2409 psia Not'onli cable Not Applicable Not Applicable Nnt Annlic>>bio Not Applicable Not Applicable

< 2414 nck>>

Not,Annlicable Not Applicable Not Applicable gilt All"ea1 4 a+Ll ~

~IVld nyy I II ClLIIC C7.

TABLE 3.3-4 NGIN E

D SAFETY-F ATURES ACTUAT ON SYSTEM INSTRUMENT T T

VA U S

SFA SYST FUNC ON UN IP EETPEIAT

~AA EEE.

I.

SAFETY INJECTION (SIAS)

A.

Sensor/Trip Units 1.,

Containmeht 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-B.

ESFA System Logic C.

Actuation Systems S 3.0 psig

> 1837 psja-Not Applicable Not Applicable

.g 3.0 psig 1837 psia"'ot Appl.icable Not Applicable High g 8.5 psig Not Applicable Not Applicable g 3.2 psig

~ 1821 psia"'ot Applicable Not Applicable g 3.2 psig Z 1821 psia"'ot Applicable Not Applicable g 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

> 895 psia'-'

gI.OX NR"'g 3.0 psig Not Applicable Not Applicable

~ 890 psia~-~

< g1.5~

NR~>>

g 3.2 psig Not Applicable Not Applicable

S A SYS UH ON U

'SAF A U U

ON S S

NS RU ltd t

IIIttlRUM V.

VI.

RECIRCULATION (RAS),

A.

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

ESFA System logic.

C t Actuat IOII SysteJII AUX1LlANT I ttVWAIER (SG-1) (AFAS-1)

A.

Sensor/Trip Units 1.

Steam Generator fl Level -- Low 2.

Steam Generator h Pressure-SG2 > SG1 7..4X of Span Not Applicable U i I 1t L1 I1U L tlIIIII I4IIVI L

> 25.8X WR

< 185 bsid 7.9 p X of Span p 6.9 Not Applicable 1I l.

S 1 l L1 IIOL HPPI ICaUIe

~ 25.3X WR~'>

( 192 psid tl PP PA P

J.

~

1 9 ~

GO I H Qgb lL'III LU'g II C.

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

A.

Sensor/Trip Units 1%

Steam. Generator f2 Level - Low C+ast%%

I atlattsl ntt A Dttaeenpa L ~

%t it&%%%%%

U%

~ l%

~ %%%t'll ~ ~

~

~ \\ MMU%

SG1 > SG2 B.

ESFA System-Logic C.

Actuation,,Systems VIII.

LOSS OF POWER A.

4.16 kV Emergency Bus Undervoltage (Loss of Voltage)

R 4 16 kV Emeraency Bus Undervoltage (Oegraded Voltage)

~tea

~

aalu% ~

Pt%%%P%%S' t ~

~ t l S'ASS tall LX.

lUNIKUL NUOPI tS>tNIIAI. I-aL,IIMIlivll LI J:

S 14 L1 IIV L t HIIIII I\\ %IU I L Noi Applicabl'e

> 25.eX WR<>5.3X WR<<i i'92 psid Hot -Applicable Hot Applicable 3697 to 3786 volts t.

2 x 10-5 pC1/cc 4