Text

Proposed Tech Specs Eliminating Typos,Providing Addl Clarification,Improving Consistency & Deleting Administrative Stipulations/Allowances No Longer in Effect at Plant
	ML17305B113
Person / Time
Site:	Palo Verde
Issue date:	10/11/1990
From:	; ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	;
Shared Package
ML17305B111	List: ML17305B110; ML17305B113;
References
	NUDOCS 9010170227
	Download: ML17305B113 (147)
	v • d • e

INDEX DEFINITIONS SECTION

1. 0 DEFINITIONS

1. 1 ACTION.

PAGE 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9

1. 10

l. 12

l. 13 l.14

1. 15

1. 16

l. 17

1. 18

1. 19 AXIAL SHAPE INDEX AZIMUTHAL POMER TILT - Tq.

CHANNEL. CALIBRATION.

CHANHEL CHECK...

CHANNEL FUHCTIONAL TEST.............

CONTAINMENT INTEGRITY...

CONTROLLED LEAKAGE..................

CORE ALTERATION.................

DOSE EQUIVALENT I-131......................

E-AVERAGE DISINTEGRATION ENERGY............

EHGIHEERED SAFETY FEATURES

RESPONSE

TIME FREQUENCY NOTATION,.................

GASEOUS RADMASTE SYSTEM.

IDEHTIFIEO LEAKAGE........

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MEMBER(S) OF THE PUBLIC...........

OFFSITE DOSE CALCULATION MANUAL (

)..

OPERABLE " OPERABILITY..

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1-2 1-3 1"3 1-3 1-3 1-4 1-4 1-4 1.20

l. 21

1. 22

l. 23 1.24 OPERATIONAL MODE MODE.........

PHYSICS TESTS...........

PLANAR RADIAL PEAKING FACTOR " FXP PRESSURE BOUNDARY LEAKAGE..........

PROCESS CONTROL PROGRAM (PCP)......

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1-4 1-5 1-5

l. 25

l. 26

1. 27 PURGE - PURGING..............

RATED THERMAL POMER..

~.

~........

~..

REACTC:~ TRIP SYSTEM RESPONSE TIME.

~

1"5 1" 5

1. 28 REPORT

'LE EVENT.......

1. 29

1. 30 SHUTDGi'N MARGIN..

SITE BOUNDARY,...

9010170227 901011 P13R ADOCK 05000528 P

PDC 1-5 1" 6 1-6 PALO VERDE - UNIT 1 AMEHDMEHT HO 23

P

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INDEX DEFINITIONS SECTION 1.0 DEFINITIONS ACTION ~

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PAGE 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 1.10 1.11 1.12 1.13 1.14

1. 15 l.a6 1.17 1.18 1.19 1.20 1.21 1.22 1.23 AXIAL SHAPE INDEX..............:....

AZIMUTHAL POWER TILT - T q'HANNEL CALiBRATION.......................

CHANNEL CHECK.

CHANNEL FUNCTIONAL TEST......

CONTAINMENT INTEGRITY.

CONTROLLED LEAKAGE................

CORE ALTERATION DOSE E(UIVALENT I-131...............................

K " AVERAGE DISINTEGRATION ENERGY..

ENGINEERED SAFETY FEATURES RESPONSE TIME.............

FRE(UENCY NOTATION........................

GASEOUS RADWASTE SYSTEM...........-...............-..

IDENTIFIED LEAKAGE..

N 1 e

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K" MEMBER(S) QF THE PUBLIC.........

OFFSITE DOSE CALCULATION MANUAL (0

)

OPERABLE - OPERABILITY...............................

OPERATIONAL MODE - MODE.....................................

PHYSICS TESTSe ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~

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PLANAR RADIAL PEAKING FACTOR-PRESSURE BOUNDARY LEAKAGE..........................,.

1-2 1"2 1"2 lee3 1-3 1"3 1"3 1-3 1-3 1-4 lee4 1-4 1-4 1-4 1-4 1-5 1.24 1.25 1.26 1.27

'1.28 1.29 PROCESS CONTROL PROGRAM (PCP),....

PURGE " PURGING.................

RATED THERMAL POWER....

REACTOR TRIP SYSTEM RESPONSE TIME.

REPORTABLE EVENT.....

SHUTDOWN MARGIN.........

~

1"5 1-5 1-5 a-5 1-6 1.30 SITE BOUNDARY PALO V~~DE - UNIT 2 AMENDMENT NO.

13

>h Wt 0

FOR )NFORRlATION GlilLY TABLE 2.2-1 (Continued)

REACTOR PROTECTIVE" IHSTRUMEHTATIOH TRIP SETPOINT LIMITS TABLE NOTATIONS (Continued)

(S)

RATE is the maximum rate. of decrease of the trip setpoint.

There are no restrictions on the rate at which the setpoint can increase.

FLOOR is the minimum value of the..trip setpoint.

BAND is the amount,by which the trip setpoint is below the input signal unless limited by Rate or Floor.'etpoints are based on steam generator differential pressure.

(7)

The setpoint may be altered to disable trip function during testing pursuant to Specification 3e10.3.

I (8)

RATE is the maximum rate of increase of the trip setpoint.

(The rate at

.wn>ch the setpoint can decrease is no slower than five percent per second.)

CElLIHG is the maximum value of the trip setpoint.

BAND >s the amount by which.the trip satpoint is above ihii steady. state

, input signal unless, limited by the rate or the'ceilinge (9) I of the distance between steam generator upper and lo~er level narrow range instrument nozzles.

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INOEX LIRITIHG"CONBITIGHS-+OR-OPERATION-AHD-SURVEI-I LANCE RE UIR'EMENTS SECTION 3/4.10.4 CEA POSITION, REGULATIHG CEA INSERTION LIMITS AND REACTOR COOLANT COLD LEG TEMPERATURE........

3/4. 10. 5 3/4. 10.6 3/4. 10. 7 MINIMUM TEMPERATURE AND PRESSURE FOR CRITICALITY........

SAFETY INJECTION TANKS SPENT FUEL POOL LEVEL.....

3/4. 10.8 SAFETY INJECTION TANK PRESSURE 3/4.10.9 SHUTDOWN MARGIN AND K

" CEDMS TESTING................

PAGE 3/4 10-4 3/4 10-5 3/4 10-6 3/4 10-7 3/4 10-8 3/4 10-9 3 4.10.10 NATURAL CIRCULATION TESTING PROGRAM..............

3/4 10-10 3/4. 11 RADIOACTIVE EF FLUENTS 3/4.11.1, SECONDARY 'SYSTEM LIQUID WASTE DISCHARGES TO OHSITE EVAPORATION PONOS CONCENTRATION...

DOSE 3/4 ll-l 3/4 11-5 LIQUID HOLDUP TANKS. ~..

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3/4 11-6

.3/4.11.2 GASEOUS EFFLUEHTS DOSE RATE ~

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3/4 u,-7 DOSE " NOBLE GASES...-..-..--......-..--...-..-...-

3/4 ll"ll DOSE " IODINE-131, IODINE-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM.........

3/4 ll"12 GASEOUS RADWASTE TREATMENT..

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3/4 11-13 EXPLOSIVE GAS MIXTURE...........

3/4 11" 14 GAS STORAGE TANKS.......,..... -..--.....-.................

3/4 11-15 3/4. 11. 3 SOLID RADIOACTIVE WASTE...............

3/4. 11. 4 TOTAL DOSE.

3/4. 12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4. 12. 1 MONITORING PROGRAM.

3/4.12.2 LAND USE CENSUS.....

3/4. 12. 3 INTERLABORATORY COMPARISOH PROGRAM.

3/4 11-16 3/4 3/4 12-1 12-11 3/4 12-12 3/4 11-18 PALO VERDE " UNIT 1 AMENDMEHT NO.

23

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REACTIVITY CONTROL'SYSTEMS MINIMUM TEMPERATURE FOR CRITICALITY

? ~

'IMITING CONDITION FOR OPERATION 3.1.1.4 The Reactor Coolant System lowest operating loop temperature (T

ld) shall be greater than or equal to 552 F.

APPLICAOILITY:

MOOES 1 and 2~n.

ACTION:

a

?

r With a Reactor 552'F, restore STANDBY within

?

Coolant System oper ating loop temper ature (T

1 d) less than col d T

ld to within its limit within 15 minutes or be in HOT cold the next 15 minutes.

SURVEILLANCE RE UIREMENTS 4.1.1.4 The Reacto'r Coolant 'Sys'em'emperature (T

d) shall be determined be greater than or equal to 552'F:

?

.a.

Within 15 minutes prior to achieving reactor criticality, and b.'t least once per 30 minutes when the reactor is critical and the Reactor Coolant System T

ld is les's than 557 F.

?

to t

r

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e

¹With K f greater than or equal to 1.0.

eff "See Special Test Exception 3. 10.5.

F PALO VERDE " UNIT 1 3/4 1-6

e u

Vl

CGINTRGLLED IBV USER MINIMUM TEMPERATURE FOR CRITICALITY LIMITING CONDITION FOR OPERATION 3.1.1.4 The Reactor Coolant System lowest operating loop temperature (T

)

shall be,: greater than or equal to 552'F.

APPLICABILITY:

MODES 1 and 2

ACTION:

With a Reactor Coolant System operating loop temperature (T

ld) less than cold 552'F, restore T

ld to within its limit within 15 minutes or be in HOT STANDBY within the next 15 minutes.

SURVEILLANCE RE UIREHENTS 4.1.1.4 The Reactor Coolant System temper ature (T

ld) shall be determined to be greater than or equal to 552'F:

a.

b..

Within 15 minutes prior to achieving reactor criticality, and At, least.;-once per 30 minutes'hen the reacto'r is critical and the Reactor Coolant System T

ld is less than 557'F.

cold yWjth K f greater than or equal to 1.0 "See Special Test Exception 3. 10.5.

CGIMTIRGLLEDO'It'SER.

Vi'

MINIMUM TEMPERATURE FOR CRITICALITY LIMITING CONDITION FOR OPERATION

3. 1.1.4 The Reactor Coolant System lowest operating loop temperature (T

ld) shall be greater than or equal to 552 F.

APPLICABILI7Y:

NIDES 1 and 2i6I.

ACTION:

Mith a Reactor Coolant System operating loop temperature (T

ld) less than cold 552 F, restore T

ld to within its liliitwithin 15 ainutes or be in HOT STANOBY within the next 15 ninutes.

'URVEILLANCE RE VIREMEHTS 4.1.1.4 The Reactor Coolant. System temperature

{T ld) shall be determined to be greater than or equal to 552'F:

a.

Within 15 minutes prior to achieving reactor criticality, and b.

At least once per 30 minutes when the reactor is critical and the Reactor Coolant System T ld is less than 557'F.

With K greater than or equal to 1.0.

eff

See Special Test Exception 3.10.5.

PALO YEROE - UNIT 3 3/4 1-6 EHOHcNT Bg

"4 E

n

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GOP4 fRGiL,LFD BV USFR JAN 13 '89 14:46 APSiUHET 3 s

I IVI OHTAO EHS THI INC C NOIT ON FOR dPERAT ON Contin d

ACTI N:

(Ccnctnusd) b}

The SHBMMH ARGON requirement of Specfffcatkon 3,1.1,2

$ s determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , OtheMIe, bi

$ n at least HOT 3TAN08Y with)n 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

d.

Mich nne ful'l-length CEA Inoperable due to causes other than

.addressed by ACTION a,,

above but Hthln <ts above speclfled align-ment requirements, cpa@at<on n

NOOES 1 and 2 may continue pursuant, tc the requirements of Speclflcatkon S. 1.S.S.

e.

81th one part-length CEA inoperable and Inserted 4n the core, operation may continua prov]dad the alignment of the fnoparabla pait length CGA

$ s ma$ nta$ nad within 8.6 ]neiges

($ nd$ cated pos$ t$ on) of all other part-length CEAs

$ n its group and the CEA

$ s maintained pursuant to the requirements of Spacfffcat(on 3,1,3.7.

P.6 SURVE LUN RE IR NTS 4.1.3'l,l The pos)tlon of oach full-length and part length CEA shall be detem$ nad to 'pe w$ th$ n 5. 6 Inches (fndtcated pcs)tlon) of all other CKAs

$ n its group at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months excapt during t$ me )ntervals when one CEAC

$ s )noperable or when both CEACs ara

$ noperabla, than verify tha Individual CEA pos)Mons at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , 4.1,3ll.2 Each full-length CEA not fully Inserted and each part~length CEA which fs inserted tn the core shall ba determined to be DPERABLE by ovament.

of at least 5

$ nchos 3n any one d3rect<on at least once per 31 days,

%3th the exception that CEA N4 ts exempt from th$ s sur'valllance requirement for the ratttafnder of Cyc)a 2 operations (h.ess unttl restart from the second ref ling outaee).

PALO leE SlIT l 3It'4 1"22 NENNENT N. 42

P4 LC j',1 0

FOR lNFQRMATIONONLY

~

REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

II CTION:

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

d.

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

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

A

(

~

}

b)

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

e.

With one part-length CEA inoperable and inserted in the core, operation may continue provided the alignment of the inoperable part length CEA is maintained within 6.6 inches {indicated position) of all other part-length CEAs in its group and the CEA is maintained pursuant to the requirements of Specification 3.1.3.7.

SURVEILLANCE RE UIREMENTS 4.1.3.1. 1 The position of e'a'ch full-length and part-length CEA shall be deter-mined to be within 6.6 inches (indicated position) of all other CEAs in its group at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when one CEAC is inoperable or when both CEACs are inoperable, then verify the individual CEA positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.1.3.1.2 Each full-length CEA not fully inserted and each part-length CEA which is inserted in the core shall be determined to be OPERABLE by ovement of at least 5 inches in any one direction at least once.per 31 days."

"W) t e exception that CEAs 27 and 41 are exempt from this surveillance requirement until restart from the second refueling outage.

PALO VERDE - UNIT 2 3/4 1-22 AMENDMENT NO.

32

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CUR ) RULLEU 6V USBH POWER DISTRIBUTION LIMITS 3/4. 2. 8 PRESSURIZER PRESSURE LIMITING CONDITION FOR OPERATION 3.2.8 The pressurizer pressure shall be maintained between 2025 psia and 2300 psia.

APPLICABILITY:

MODES 1 and ACTION:

With the pressurizer pressure outside its above limits, restore the pressure to within its limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 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 .

SURVEILLANCE RE UIREMENTS 4.2.8 The pressurizer pressure shall be determined to be within its limit at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

" ee S ecial Test Exception 3.10.5 PALO VERDE - UNIT 1 3/4 2-12 AMENDMENT NO.

27

C

\\

I

CGR7RGI LED BV USER EMPOWER DISTRIBUTION LIMITS 3/4.2.8 PRESSURIZER, PRESSURE

. LIMITING,CONDITION FOR OPERATION 3.2.8 The pressurizer pressure shall be maintained between 2025 psia and 2300 psi a.

APPLICABILITY:

MODES 1 and ACTION:

'ith the pressurizer, pressure'utside its above limits, restore the pressure to within its limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT STANDBY within the next 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months s.

SURVEILLANCE RE UIREMENTS 4.2.8 The pressurizer pressure shall be determined to be within its limit at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

"See Special Test Exception 3. 10.5 PALO VERDE - UNIT 2 3/4 2-12 AMENDMENT NO.

19

'fC <

0

FOR lNFORMATjONONLY POWER OISTRIBUTION LIMITS 3/4.2.8 PRESSURIZER PRESSURE LIMITING CONQITION FOR OPERATION 3.2.8 The pressurizer pressure shall be maintained between 2025 psia and 2300 psia.

APPLICABILITY:

HOQES 1 and ACTION:

Mith the pressurizer pressure outside its above limits, restore the pressure to within its limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT STANQBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

/

SURVEILLANCE RE UIREMENTS 4.2.8 The pressurizer pressure shall be determined to be within its limit at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

C "See Special Test Exception 3.10.5 PALO VERQE - UNIT 3 3/4 2-12 AHENQHENT NO 18

'I p

t gC ill 4 P

CGWTRGLLED B'Il'SER

'RE'ACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE RE UIREMENTS (2)

(3)

(4)-

(5)-

(6)-

(7)-

(s)

(1O)-

TABLE NOTATIONS With reactor trip breakers in the closed position and the CEA drive system capable of CEA withdrawal, and fuel in the reactor vessel.

Each STARTUP or when required with the reactor trip breakers closed and the CEA drive system.capable of rod.withdrawal, if not performed in the previous 7 days.

Heat balance only (CHANNEL FUNCTIONAL TEST not included),

above 15X-of RATED THERMAL POWER; adjust the linear power level, the CPC delta T

power and CPC nuclear power signals to agree with the calorimetric calculation if absolute difference is greater than 2X.

During PHYSICS

-TESTS, these daily calibrations may be suspended provided these calibrations are performed upon reaching each major test power plateau and prior to proceeding to the next major test power plateau.

Above 15K of.RATED THERMAL POWER, verify that the linear. power sub-channel gains of the excore detectors are consistent with the values used to establish the shape annealing matrix elements in the Core

.Protection Calculators.

Neutron detectors may be excluded fr'om CHANNEL CALIBRATION.

After each fuel loading and prior to exceeding 70K of RATED THERMAL POWER, the encore detectors shall be used to determine the shape annealing'atrix. elements and the Core Protection Calculators shall'9'e these" el ements.'-

This CHANNEL FUNCTIONAL TEST shall include the injection of simulated process signals into the channel as close to the sensors as-practicable to verify OPERABILITY including alarm arid/or trip functions.

Above 70K of RATED THERMAL POWER, verify that the total steady-state'CS flow rate as indicated by each CPC is less than or equal to the actual RCS total flow rate determined by either using the reactor coolant pump differential pressure instrumentation or by calorimetric calculations and if necessary, adjust the CPC addressable constant flow coefficients such that each CPC indicated flow is'less than or equal to the actual flow rate.

The flow measurement uncertainty may be included in the BERRl term in the CPC and is equal to or greater than 4X.

.. Above 70K of RATED THERMAL POWER, verify 'that the total steady-state RCS flow rate as indicated by each CPC is less than or equal to the actual RCS total flow rate determined by -either using the reactor coolant um differen r 1 pressure instrumentation and the ultrasonic ~

ow me er a gus e

pump curves or calorimetric calculations.

The monthly CHANNEL FUNCTIONAL TEST shall include verification that the correct (current) values of addressable constants are installed in each OPERABLE CPC.

At least once per 18 months and following maintenance or adjustment of the reactor trip breakers, the CHANNEL FUNCTIONAL TEST shall include independent verification of the undervoltage and shunt trips.

PALO VERDE - UNIT 2 3/4 3-16 CGMTRGLLED BY USER

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0 TABLE 4. 3-1 Continued REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE RE UIREMENTS TABLE NOTATIONS 0

(2)

(3)

(4)-

(5)

(6)

(7)

With reactor trip breakers in the closed position and the CEA drive system capable of CEA withdrawal; and fuel in the reactor vessel.

Each STARTUP or when required with the reactor trip breakers closed and the CEA drive system capable of rod withdrawal, if not performed in the previous 7 days.

Heat balance only (CHANNEL FUNCTIONAL TEST not included),

above 15K of RATED THERMAL POWER; adjust the linear power level, the CPC delta T

power and CPC nuclear power signals to agree with the calorimetric calculation if absolute difference is greater than 2X.

During PHYSICS TESTS, these daily calibrations may be suspended provided these calibrations are performed upon reaching each major test power plateau and prior to proceeding to the next major test power plateau.

Above 15K of RATED THERMAL POWER, verify that the linear power sub-channel gains of the excore detectors are consistent with the values used to establish the shape annealing matrix elements in the Core Protection Calculators.

Neutron detectors may be excluded from CHANNEL CALIBRATION.

After each fuel loading and prior to exceeding 70K of RATED THERMAL POWER, the incore detectors shall be used to determine the shape annealing matrix elements and the Core Protection Calculators shall.

use these elements.

This CHANNEL FUNCTIONAL TEST shall include the injection of simulated process signals into the channel as close to the sensors as practicable to verify OPERABILITY including alarm and/or trip functions.

Above 70K of RATED'THERMAL POWER, verify that the total steady-state RCS flow rate as indicated by each CPC is less than or equal to the actual RCS total flow rate determined by either using the reactor coolant pump differential pressure instrumentation or by calorimetric calculations and if necessary, adjust the CPC addressabl'e constant flow coefficients such that each CPC indicated flow is less than or equal to the actual flow rate.

The flow measurement uncertainty may be included in the BERRl term in the CPC and is equal to or greater than 4X.

Above 70K of RATED THERMAL POWER, verify that the total steady-state RCS flow rate as indicated by each CPC is less than or equal to the actual RCS total flow rate determined by either using the reactor coolant um differen 1 pressure instrumentation and the ultrasonic flow meter a crusted pump curves or calorimetric calculations.

The monthly CHANNEL FUNCTIONAL TEST shall include verification that the correct (current) values of addressable constants are installed in each OPERABLE CPC.

At least once per 18 months and following maintenance or adjustment of the reactor trip breakers, the CHANNEL FUNCTIONAL TEST shall include independent verification of the undervoltage and shunt trips.

PALO VERDE - UNIT 3 3/4 3-16

0

0 0

INSTRUMENT Area Monitors TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE OPERABLE MODES ALARM/TRIP MEASUREMEHT SETPOTNT RANGE ACTION A.

Fuel Pool Area RU-31 B.

New Fuel Area RU"19 C.

Containment RU-148 &

RU-149 D.

Containment Power Access Purge Exhaust RU-37 &

RU-38 1,2,3,4

<15mR/hr

<10R/hr 10-~ to 10~mR/hr 22 & 24 10-~ to 10~mR/hr 22 1R/hr to 107R/hr 27

<2.5mR/hr 10-~ to 1 - mR/hr 25 E.

Main Steam 1)

RU-139 A8B 2)

RU-140 A&B 1,2,3,4 1,2,3,4 10 to 10 mR/hr 27 10 to 10 mR/hr 27 2.

Process Monitors A.

Containment Building Atmosphere RU-1 1)

Par ticulate 2)

Gaseous.

1P2P3P4

<2.3xlO-pCi/cc 10-9 to 10-~pCi/cc Cs"137

<6.6x10- pCi/cc 10-to 10- pCi/cc Xe"133 23 8

27 B.

Noble Gas Monitors Control Room Ventilation Intake RU-29 & RU-30 1

ALL MODES

<2xlO-pCi/cc 10-to 10- pCi/cc 26 3.

Post Accident Sampling System 1¹¹¹ 1,2,3 N.A.

H.A.

28 "With fuel in the storage pool or building.

""Mith irradiated fuel in the storage pool.

¹Mhen purge is being used.

¹¹Three (3) times background in Rem/hour.

¹¹¹The Minimum Channels Operable will be defined in the Preplanned Alternate Sampling Program.

INSTRUMENT TABLE 3.3-6 RAOIATION MONITORING INSTRUMENTATION MINIMUM CMANNELS APPLICABLE ALARM/TRIP OPERABLE MODES SETPOINT MEASUREMENT RANGE ACTION Area A.

B.

C.

D.

Monitors Fuel Pool Area RU-31 New Fuel Area RU-19 Containment RU-14& 8 RU"149 Containment Power Access Purge Exhaust RU-37 8 RU-38 1,2,3,4

<15mB/hr

<15mR/hr

<10R/hr

<2 5mR/hr 10-~ to 10~mR/hr 22 8 24 10-~ to 10~mR/hr 22 1R/hr to lO~R/hr 27 10-i to 1 - mR/hr 25 E.

Hain Steam 1)

RU-139 A8B 2)

RU-140 ABB Process Monitors 1)

Particulate 2)

Gaseous 2.

A.

Containment Building Atmosphere RU-1 1,2,3,4 1,2,3,4 1,2,3,4 10 to 10 mR/hr 2?

10 to 10 mR/hr 27 23 4 27

<2.3xl0- pCi/cc 10-to 10-"pCi/cc Cs-137

<6.6xlO-pCi/cc 10-to 10- pCi/cc Xe-133 B.

Noble Gas Monitors Control Room Ventilation Intake RU-29 8 RU-30 1

ALL MODES

<2x10- pCi/cc 10-to 10-'pCi/cc 26 3.

Post Accident Sampling System 1%8 1,2,3 N. A.

N.A.

28

With fuel in the storage pool or building.

""With irradiated fuel in the storage pool.

O'When purge is being used.

8PThree (3) times background in Rem/hour.

ONAThe Minimum Channels Operable will be defined in the Preplanned Alternate Sampling Program.

vt' 1

pC+

~,

CONTR0LLED BY USER E

INSTRUMENTATION REMOTE SHUTDOWN SYSTEM LIMITING CONDITION FOR OPERATION

'I 3.3.3.5 The remote shutdown system disconnect

switches, power, controls and monitoring instrumentation channels shown in Table 3.3-9 A-C shall be OPERABLE.

APPLICABILITY:

MODES 1 and 2.

9 ACTION:

b.

With the number of OPERABLE remote shutdown monitoring channels less than required by Table 3.3-9 A

C restore the inoperable channel(s) to OPERABLE status within 7 days, or be in HOT STANDBY

(/;,y~rn keble.S 3.'3 18 O<-~-H~~<) <

With one or more remote...shutdown system disconnect switches or power or control circuits-inoperable, restore the inoperable switch(s)/

circuit(s) to OPERABLE status or issue procedure changes per Speci-fication 6.8.3 that identifies alternate disconnect methods or power or control circuits for remote shutdown within 7 days, or be in HOT STANDBY within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c ~

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.3.3.5 The Remote Shutdown System shall be demonstrated operable:

a.

b.

By performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-6 for each remote shutdown monitoring instrumentation channel.

By operation of each remote shutdown system disconnect switch and power and control circuit including the actuated components at least once per 18 months.

PALO VERDE - UNIT 1 3/4 3-48 AMENDMENT NO. 27

.fI

'IN kn

~E'

INSTRUMENTATION REMOTE SHUTDOWN SYSTEM LIMITING CONDITION FOR OPERATION 3.3.3.5 The remote shutdown system disconnect

switches, power, controls and monitoring instrumentation channels shown in Table 3.3-9A-C shall be OPERABLE.

l APPLICABILITY:

MODES 1 and 2.

ACTION:

a, With the number of OPERABLE remote shutdown monitoring channels less than required by Table 3.3-9 -C restore the inoperable channel(s) to OPERABLE status within 7 days, or be in HOT STANDBY within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

(IS~e4in 7gked 3.e-egdZX>

b.

With one or more remote shutdown system disconnect switches or power or control circuits inoperable, restore the inoperable switch(s)/

circuit(s). to OPERABLE status or issue procedure changes per Speci-fic'ation 6,8.3"that identifies alternate disconnect methods or power or control circuits for remote shutdown within 7 days, or be in'HOT STANDBY within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c.'he provisions of Specification -33.9.%care hot applicable.'-".-.-=

~

I SURVEILLANCE RE UIREMENTS 4.3.3.5 The Remote Shutdown System shall be demonstrated operable:

a.

By performance of'the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table.4.3-6 for each remote shutdown monitoring instrumentation channel.

b.

By operation of each remote shutdown system disconnect switch and power and control circuit including the actuated components at least once per 18 months.

PALO VERDE - UNIT 2 3/4 3-48 gogTRGLLED BY USER

4 l

lp

CONTROLLED BY USER TABLE 3.3-98 DISCONNECT SWITCHES REMOTE SHUTDOWN DISCONNECT SWITCHES SWITCH LOCATION 2.

3.

5.

e.

7.

8.

9.

10.

12.

13.

14.

15.

16.

17.

18.

19.

20.

21.

22.

23.

24.

SG 1'line 2 Atmospheric Dump Valve Solenoid Air Isolation Valves SGB-HY-178A and SGB-HY-178R SG 2 line 1 Atmospheric Dump Valve Solenoid Air Isolation Valves SGB-HY-185A and SGB-HY-185R Auxiliary Spray Valve CHB-HV"203 Letdown to Regenerative Heat Exchanger Isolation, CHB-UV-515 Reactor Coolant Pump Controlled Bleedoff, CHB-UV-505 Auxiliary Feedwater Pump B to SG 1 Control Valve',

AFB-HV-.30 Auxiliary Feedwater Pump B to SG 2 Control Valve, AFB-HV-31 Auxiliary Feedwater Pump B to SG 1 Block Valve, AFB-UV-34 Auxiliary Feedwate!

Pump B to SG 2 Block Valve, AFB-UV-35 Pressurizet Backup Heaters Banks

B10, B18, A05 Control Safety Injection Tank 2A Vent Control SIB-HV-613 Safety Injection Tank 2B Vent Control SIB-HV-623 Safety Injection Tank 1A Vent Control SIB-HV-633 Safety Injection Tank 1B Vent Control SIB-HV-643 C

Safety Injection Tank Vent Val ves Power Supply SIB-HS-1 SG 1 line 2 Atmospheric Dump al ve Solenoid Air Isolation Valves SGD-HY-178B and SGD-HY-178S SG 2 line 1 Atmospheric Dump Valve Solenoid Air Isolation Valves SGD-HY-185B and SGD-HY-185S Control BLDG Battery Room D

Essential Exhaust Fan

'HJB-J01A'ontrol BLDG Battery Room B

Es senti al Exhaus t Fan 'JB-J01B

'attery Charger D Control Room Circuits PKD-H14 ESF Switchgear Room Essential AHU HJB-Z03 LPSI Pump SIB-POl Breaker Control Diesel Generator B Breaker Control Essential Spray Pond Pump SPB-POl Breake.

Control RSP RSP RSP RSP RSP RSP RSP RSP RSP RSP RSP RSP RSP RSP RSP RSP PHB"M3205 PHB-M3205 PHB-M3209 AND PKD-H14 PHB"M3205 PBB-S04F PBB-S04B PBB-504C PALO VERDE " UNIT 1 3/4 3-50 AMENDMENT NO. 27

P 4*

4d C,

Cl C+

OIS 2.

3.

4.

5.

6.

7.

9.

10.

. 12 13.

14.

15.

16 17.

18 19.

20.

21.

22.

23.

24

~O~TRCLbFP, PX U~<<

. REMOTE SHUTDOWN DISCONNECT SWITCHES CONNECT SMITCHES SG 1 line 2 Atmospheric Dump Valve Solenoid Air Isolation Valves SGB-HY-178A and SGB-HY-178R SG 2-line 1 Atmospheric Dump Valve Solenoid Air Isolation Valves SGB-HY;185A and SGB-HY-185R Auxiliary Spray Valve CHB-HV-203 Letdown to Regenerative Heat Exchanger Isolation, CHB-UV-515 Reactor Coolant. Pump Controlled Bleedoff,: CHB-.UV-505 Auxiliary Feedwater Pump B to SG 1 Control Valve, AFB-HV-30 Auxiliary Feedwater Pump B to SG 2 Control Valve, AFB-HV-31'uxiliary Feedwater Pump B to SG "1 Block. Valve, AFB-UV-34 Auxiliary Feedwater Pump B to SG 2 Block Valve, AFB-UV-35 Pressurizer Backup Heaters Banks 83,0,

B18, A05 Control, Safety Injection Tank'2A Vent Control SIB-HV-613 Safety Injection Tank 2B-Vent Control SIB-HV-623 Safety Injection Tank 1A Vent Control SIB-HV-633 Safety Injection Tank 1B Vent Control SIB-HV-643 Safety Injection Tank Vent Valves Power Supply SIB-HS-. 1 A SG 1 line 2 Atmospheric.

Dump Valve Solenoid Air Isolation Valves SGD-HY-178B and SGO-HY-178S SG 2 line 1 Atmospheric Dump Valve Solenoid Air Isolation Valves SGO-HY-185B and SGO-HY-185S Control BLDG Battery Room D

Essential Exhaust Fan

'HJB-J01A'ontrol BLDG Battery Room B

Essential Exhaust Fan

'HJB-JOZB'attery Charger 0 Control Room Circuits PKO-H14 ESF Switchgear Room Essential AHU HJB-Z03

,LPSI Pump SIB-P01 Breaker Control Diesel Generator B Breaker Control Essential Spray Pond Pump SPB-POl Breaker Control SMITCH LOCATION RSP RSP RSP RSP RSP RSP RSP RSP

'SP RSP RSP

'RSP RSP RSP RSP RSP RSP PHB-M3205 PHB-M3205 PHB-M3209 AND PKD-H14 PHB-M3205 PBB-504F PBB-S04B PBB-S04C PALO VERDE - UNIT 2 3/4 3-50

0 l'

j 2

0 u'Q

DISCONNECT SWITCHES TABLE 3.3-98 REMOTE SHUTDOWN DISCONNECT SWITCHES SWITCH LOCATION l.

2.

3.

4.

SG 1 line 2 Atmospheric Dump Valve Solenoid Air Isolation Valves SGB-HY-178A and SGB-HY-178R SG 2 line 1 Atmospheric Dump Valve Solenoid Air Isolation Valves SGB-HY-185A and SGB-HY-185R Auxiliary Spray Valve CHB-HV-203 Letdown to Regenerative RSP RSP RSP RSP

'Heat Exchanger Isolation, CHB-UV-515

5. Reactor Coolant Pump Controlled Bleedoff, CHB-UV-505 RSP e

6.

7.

8.

9.

10.

11.

12.

13.

14.

15.

16.

17.

Auxiliary Feedwater Pump B to SG 1 Control Valve, AFB-HV-30 Auxiliary Feedwater Pump 8 to SG 2 Control Valve, AFB-HV"31 Auxiliary Feedwater Pump B to SG 1 Block Valve, AFB-UV-34 Auxiliary Feedwater Pump B to SG 2 Block Valve, AFB-UV-35 Pressurizer Backup Heaters Banks

B10, B18, A05 Control Safety Injection Tank 2A Vent Control SIB-HV-613 Safety Injection Tank 2B Vent Control SIB-HV-623 Safety Injection Tank lA Vent Cont'rol SIB-HV-633 Safety Injection Tank 1B Vent Control SIB-HV-643 Safety Injection Tank Vent Valves Power Supply SIB-HS-1 A

SG 1 line 2 Atmospheric Dump Valve Solenoid Air Isolation Valves SGD-HY-178B and SGD-HY-178S SG 2 line 1 Atmospheric Dump Valve Solenoid Air Isolation Valves SGD-HY"185B and SGD-HY-185S RSP RSP

'SP RSP RSP RSP RSP RSP RSP RSP RSP RSP 19.

20.

21.

22.

23.

Control BLDG Battery Room B

Essential Exhaust Fan

'HJB-J01B'attery Charger D Control Room Circui ts PKD-H14 ESF Switchgear Room Essential AHU HJB-Z03 LPSI Pump SIB-P01 Breaker Control Diesel Generator B Breaker Control Essential Spray Pond Pump SPB-P01 Breaker Control

18. Control BLDG Battery Room D

Essential Exhaust Fan 'HJB-J01A'HB-M3205 PHB"M3205 PHB-M3209 AND PKD"H14 PHB-M3205 PBB"504F PBB-5048 PBB"504C PALO VERDE - UNIT 3 3/4 3"50

0 19

CGNTRGLLED BY USER DISCONNECT SWITCHES TABLE 3.3-9B (continued)

REMOTE SHUTDOWN DISCONNECT SWITCHES SWITCH LOCATION 50.

51.

52.

53.

54.

55.

56.

5?.

58.

59.

60.

LPSI-SD HX "B" Bypass S IB"HY-307 LPSI Pump "B" Recirc SIB-UY"668 LPSI Pump "B" Suction from RWT SIB-HV-692 SD Cooling LPSI Pump "B" Suction SIB-UV-652 SD Cooling LPSI Pump "B" Suction SIB-UV-654 LPSI Header "B" to RC Loop 2A SIB-UV-615 LPSI Header "8" to RC Loop 28 SIB-UY"625 VCT Outlet Isolation CHN-UV"501 RWT Gravity Feed g Y CHN-HV-536 Shutdown Coo g Temperature Control SIB UY 658 Shutdown Coo

>ng Heat Exchanger Bypass Valve SIB-HV-693

61. '4.16 KV Bus PBB-504 62.

63.

64.

65.

66.

67.

68.

69.

Feeder from XFMR NBN"X04

4. 16 KV Bus PBB"S04 Feeder from XFMR NBN-X03 Electrical Penetration Room B

ACU HAB"Z06 Control Room HVAC Isolation Dampers HJ B-M01/H J 8 "M55 O.S.A.

Supply Damper HJB-M02 O.S.A.

Supply Damper HJB-M03 R.C.S.

Sample Isolation Valve SSA-UV-203 R.C.S.

Sample Isolation Valve SSB-UV-200 125 VDC Battery A Breaker Control Room Circuits PHB-M3803 PHB-M3611 PHB"M3805 PHB-M3611 PKD-B44 F

PHB-M3611 PHB-M3640 NHN-M7208 NHN-M7209 PHB-M3416 P HB"M3416 PBB-S04K PBB-S04L PHB"M3640 RSP RSP RSP SSA"J04 RSP P KA"M4101 PALO VERDE - UNIT 1 3/4 3"52 AMENDMENT NO.

27

t

\\ ~I+

% t 4

DISCONNECT SWITCHES 49.'0.

51.

52.

'3.

54.

55.

56.

57.

58.

~ 59.

60.

61.

62 63.

64.

65.

'6.

67.

68.

69

~

SD HX "8".to RC Loops 2A/28.SIB-HV-696 LPSI'-SD HX "8" Bypass SIB-HV-307 LPSI Pump "8" Recirc SIB-UY-668 LPSI Pump "8" Suction from RMT SIB-HY-692 SD Cooling LPSI= Pump "8" Suction SIB-UV-652 SD Cooling LPSI Pump "8" Suction SID-UV-654 LPSI Header "8" to RC Loop 2A SIB-UV-615 LPSI Header "8" to RC Loop 28 SIB-UV-625 VCT Outlet Isolation

'HN-UV-501 RWT Gravity Feed CHE-HY-536 Shutdown Cool g Temperature Control SIB V 658.

Shutdown Coo ing Heat Exchanger Bypass Valve SIB-HV-693 4.16 KV Bus PBB-S04'eeder from XFMR NBN-X04 4'.16 KY Bus PBB-S04 Feeder from XFMR NBN-X03 Electrical Penetration Room 8

ACU HAB-106 Control Room HVAC Isolation Dampers HJB-M01/HJB-M55 O.S.A.

Supply Damper HJB-M02 O.S.A.

Supply Damper HJB-M03 R. C. S.

Sample Isolation Val ve SSA-UV-203 R.C.S.

Sample Isolation Yalve SSB-UV-200 125. VDC Battery A Breaker Control Room Circuits CGMTRQI.LED BY USER a

REMOTE SHUTDOWN DISCONNECT SWITCHES SMITCH LOCATION PHB"M3416 PHB"M3803 PHB"M3611 PHB-M3805 PHB-M3611 PKD-844 PHB-M3611-PHB"M3640 NHN"M7208 NHN-M7209 PHB"M3416 PHB-M3416 PBB-S04K e

PBB-S04L PHB-M3640 RSP RSP RSP SSA-J04 RSP PKA-M4101 PALO VERDE - UNIT 2 3/4 3-52 CO~TROLLED BY USER

g~

N 0

DISCONNECT SWITCHES TABLE 3.3-98 (Continued)

REMOTE SHUTDOWN DISCONNECT SWITCHES SWITCH LOCATION 49.

50.

51.

52.

53.

54.

55 ~

56.

57.

58.

59.

60.

61.

62.

63.

64.

65.

66.

67.

68.

69.

SD HX "B" to RC Loops 2A/2B SIB-HV-696 LPSI-SD HX "B" Bypass SIB-HV"307 LPSI Pump "B" Recirc SIB-UV-668 LPSI Pump "B" Suction from RWT SIB-HV-692 SD Cooling LPSI Pump "B" Suction SIB-UV-652 SD Cooling LPSI Pump "B".

Suction SID-UV-654 LPSI Header "B" to RC Loop 2A SIB"UV"615 LPSI Header "B" to RC Loop 2B SIB"UV"625 YCT Outlet Isolation CHN-UV-501 RWT Gravity Feed CHE-HV-536 Shutdown Coo '. Temperature Control SIB UV 658 Shutdown Coo ing Heat Exchanger Bypass Valve SIB-HV-693

4. 16 KV Bus PBB-S04 Feeder from XFMR NBN-X04 4.16 KV Bus PBB-S04 Feeder from XFMR NBN-X03 Electrical Penetration Room B

ACU HAB-Z06 Control Room HVAC Isolation Dampers HJB."M01/HJB-M55 O.S.A.

Supply Damper HJB-M02 0 ~ S.A.

Supply Damper HJB-M03 R. C. S.

Sample Isol ation Val ve SSA-UV-203 R.C.S.

Sample Isolation Valve SSB-UV-200 125 VDC Battery A Breaker Control Room Circuits PHB-M3416 PHB"M3803 PHB-M3611 PHB-M3805 PHB "M3611 PKD-B44 PHB-M3611 PHB-M3640 NHN-M7208 NHN-M7209 PHB-M3416 PHB-M3416 PBB-S04K PBB-S04L PHB-M3640 RSP RSP RSP SSA-J04 RSP PKA-M4101 PALO VERDE - UNIT 3 3/4 3-52

n

CONTROLLED BY USER CONTROL CIRCUITS TABLE 3.3-9C (continued)

REMOTE SHUTDOWN CONTROL CIRCUITS SMITCH LOCATION 29.

33.

35.

37.

43.

27.

28.

30.

31.

32 ~

34.

36.

38.

39.

40.

41.

42.

44.

45.

46.

47.

48.

E"PGB"L36 480Y Supply Breaker to Load Center PGB-L36 Battery Charger PKB-H12 Supply Breaker Battery Charger PKD-H14 Supply Breaker Backup Battery Charger PKB-H16 Supply Breaker Essential Spray Pond Pump SPB-P01 Essential Cooling Mater Pump EMB-POl Essential Chilled Mater Chiller ECB-E01 Battery Room D Essential Exhaust Fan HJB-J01A Battery Room 8 Essential Exhaust Fan HJB-J018 ESF Switchgear Room 8 Essential AHU HJB"E03 Electrical Penetration Room 8

ACU Fan HAB-E06 SIT Vent Valves Power Supply SIB-HS-1 A

SIT 2A Vent Valve 5I8"HV-613 SIT 28 Yent Valve SIB-HY"623 SIT 1A Vent Valve SIB"HV-633 SIT 18 Yent Yalve S I8-HV-643 LPSI Pump 8

SIB-POl Containment Spray Pump 8

Discharger to SD HX "8" Valve SIB-HV-689 LPSI Containment Spray from SD HX "8" X-tie Yalve SIB-HY-695 Shutdown Cooling LPSI Suction Yalve SIB-HV-656 Shutdown Cooling Marmup Bypass Valve SIB-UV-690 LPSI Containment Spray to SD HX "8" X-tie Valve SIB-HV-694 PGB"L3681 PHB"M3627 PHB-M3209 PHB"M3425 PBB-S04C PBB-S04M PBB-S04G PHB"M3206 PHB-M3207 PHB-M3203 PHB-M3631 RSP RSP RSP RSP RSP PBB"504F PHB"M3804 PHB-M3810 PHB"M3605, PHB"M3806 PHB-M3414 PALO YERDE - UNIT 1 3/4 3"54 AMENDMENT NO 27

-d 41

CQMTRQLLEP BY USER REMOTE SHUTDOWN CONTROL CIRCUITS CONTROL CIRCUITS SWITCH LOCATION 25.

26.

27.

28.

29.

30.

31 32.

33.

34.

35.

36 37.

38.

39.

40.

41.

42

~

43 44.

45.

46.

47.

48.

E-PGB L32B2 480V Main Supply Breaker To Load'enter PGB-L32 E-PGB-L34B2 480V Main Supply Breaker To Load Center PGB-L34 E-PGB-L36 480V Supply Breaker To Load Center PGB-L36 Battery Charger PKB-H12 Supply Breaker Battery Charger PKD-H14 Supply Breaker.

Backup Battery Charger PKB-H16 Supply Breaker Essential Spray Pond Pump SPB-P01 Essential Cooling Water Pump EWB-P01 Essential Chilled Water Chiller ECB-E01 Battery Room D Essential Exhaust Fan HJB-JOlA Battery Room B Essential Exhaust Fan HJB-J01B ESF Switchgear Room B

Essential AHU HJB-Z03 Electrical Penetration Room B

ACU Fan HAB-Z06 SIT Vent Valves ower Supply SIB-HS-1 A

8 SIT 2A Vent Valve SIB-HV-613 SIT 2B Vent'alve SIB-HV-623 SIT 1A Vent Valve SIB-HV-633 SIT 1B Vent Valve SIB-HV-643 LPSI Pump B

SIB-P01 Containment Spray Pump B

Discharger to SD HX "B" Valve SIB-HV-689 LPSI Containment Spray from SD HX "B" X-tie Valve SIB-HV-695 Shutdown Cooling LPSI Suction Valve SIB-UV-656 Shutdown Cooling Warmup Bypass Valve SIB-HV-'690 LPSI Containment Spray to SD HX "B" X-tie Valve SIB-HV-694 PGB-L32B1 PGB-L34B1 PGB-L36B1 PHB-M3627 PHB-M3209 PHB-M3425 PBB-S04C PBB-S04M PBB-S04G

'HB-M3206 PHB-M3207 PHB-M3203 PHB-M3631 RSP RSP RSP RSP RSP PBB-S04F PHB-M3804 PHB-M3810 PHB-M3605 PHB-M3806 PHB-M3414 PALO VERDE - UNIT 2 3/4 3-54 CC WT@GLLEB BY USE~

0 I

CONTROLLED BY USER CONTROL CIRCUITS TABLE 3.3-9C (Continued)

'. REMOTE SHUTDOWN CONTROL CIRCUITS SWITCH LOCATION 25 ~

26.

27.

28.

29.

30.

31.

32.

33.

34.

35.

36.

37.

E-PGB L32B2 480V Main Supply Breaker To Load Center PGB-L32 E-PGB-L34B2 480V Main Supply Breaker To Load Center PGB-L34 E-PGB-L36 480V Supply Breaker To Load Center PGB-L36 Battery Charger PKB-H12

,Supply Breaker Battery Charger PKD-H14 Supply Breaker Backup Battery Charger PKB-H16.Supply Breaker Essential Spray Pond Pump SPB-Pol Essential Cooling Mater Pump EWB"P01 Essential Chilled Mater Chiller ECB-EOl Battery Room D Essential Exhaust Fan HJB-JOlA Battery Room B Essential Exhaust Fan HJB-J01B ESF Switchgear Room B

Essential AHU HJB-Z03 Electrical Penetration Room B

ACU Fan HAB-Z06 PGB-L32B1 PGB" L3481 PGB-L36B1 PHB-M3627 PHB-M3209 PHB-M3425 PBB-S04C PBB-S04M PBB-S04G PHB-M3206 PHB"M3207 PHB"M3203 PHB-M3631 48.

Val ve SIB-HV-690 LPSI Containment Spray to SD HX "B" X-tie Valve SIB-HV-694 39.

SIT Vent Valves Power Supply SIB-HS-I A

39.

SIT 2A Vent Valve SIB-HV-613 40.

SIT 2B Vent Valve SIB-HV"623 41.

SIT 1A Vent Valve SIB-HV-633 42.

SIT 1B Vent Valve 5IB-HV-643 43.

LPSI Pump 8

S IB-P01 44.

Containment Spray Pump B

Discharger to SD HX "B" Valve SIB-HV-689 45.

LPSI Containment Spray from SD HX "8" X-tie Valve SIB-HV-695 46.

Shutdown Cooling LPSI Suction Valve SIB-UV-656 47.

Shutdown Cooling Warmup Bypass RSP RSP RSP RSP RSP PBB-504F PHB-M3804 PHB-M3810 PHB-M3605 PHB-M3806 PHB-M3414 PALO VERDE - UNIT 3 3/4 3-54

4I>>-

tF l4

CONTROL CIRCUITS TABLE 3.3-9C (continued)

REMOTE SHUTDOWN CONTROL CIRCUITS SWITCH LOCATION 34.

35.

Chiller ECB-E01 Battery Room D Essential Exhaust Fan HJB-J01A Battery Room B Essential Exhaust Fan HJB-J01B 36.

ESF Switchgear Room B

Essential AHU HJB-Z03 37.

Electrical Penetration Room B

27.

E"PGB-L36 480V Supply Breaker to Load Center PGB-L36 28.

Battery Charger PKB-H12 Supply Breaker 29.

Battery Charger PKO-H14 Supply Breaker 30.

Backup Battery Charger PKB-H16 Supply Breaker

, 31., Essential Spray Pond -Pump SPB-Pol 32.

Essential Cooling Mater Pump

'WB-P01 33.

Essential Chilled Mater PGB-L36B1 PHB-M3627 PHB"M3209 PHB"M3425 PBB"'504C PBB"S04M PBB"S04G PHB"M3206 PHB-M3207 PHB-M3203 PHB"M3631 38.

39.

40.

41.

42.

43.

44.

45

~

46.

47.

48.

ACU Fan HAB-Z06 SIT Yent Yalves Power Supply SIB-HS-18A SIT 2A Yent Yalve SIB-HV-613 SIT 2B Vent Valve SIB "HV"623 SIT lA Vent Valve S IB-HY-633 SIT 1B Vent Valve SIB"HV"643 LPSI Pump B

SIB-P01 Containment Spray Pump 8

Discharger to SD HX "B" Yalve SIB-HY-689 LPSI Containment Spray from SO HX "B" X-tie Valve SIB-HV-695 Shutdown Co lin PSI Suction Valve SIB HV 656 Shutdown C

ling Warmup Bypass Valve SIB 90 LPSI Containment Spray to SD HX "B" X-tie Valve SIB-HV-694 RSP RSP RSP RSP RSP PBB"S04F PHB"M3804 PHB"M3810 PHB"M3605 PHB-M3806 PHB-M3414 PALO VERDE - UNIT 1 3/4 3-54 AMENDMENT NO.

27

'k k

~

0 l

,I

CONTROLLED BY USER CONTROL CIRCUITS 49.

50.

51.

52.

53.

54.

55.

56.

57.

58.

59.

60.

61.

62.

63.

64.

65.

66.

67.

68.

69.

70.

TABLE 3.3-9C continued)

REMOTE SHUTOOWN CONTROL CIRCUITS SD HX "8" to RC Loops 2A/28 Yalve SIB-HV-696 LPSI SD HX "8" Bypass Valve SIB-HY-307 LPSI Pump 8 Recirc.

Yalve SIB-UY 88 LPSI Pump 8 Suc ion From RWT SIB-HY-692 RC Loop to Shutdown Cooling Valve SIB-UV-652 RC Loop to Shutdown Cooling Yalve SIB-UV-654 LPSI Header 8 to RC Loop 2A Valve SIB-UV-61S LPSI Header 8 to RC Loop 28 Valve SIB-UV-625 SDC "8" Temperature Control Valve SIB-HV"658 Control Room Ventilation Isolation Dampers HJB-M01/HJB-MS5 O.S.A.

Supply Damper HJB-M02 O.S.A.

Supply Damper HJB-M03 Diesel Generator "8" Emergency Start Normal Offsite Power Supply Breaker Alternate Offsite Power Supply Breaker Battery "8" Breaker Battery "D" Breaker RCS Sample Isolation Valve SSA-UV"203 RCS Sample Isolation Valve SSB-UV-200 Train "8" Pumps Combined Recirc to RWT Valve SI 8-UV-659 Shutdown Cooling Heat Exchanger Bypass Val ve SIB-HV-693 Battery "A" Breaker SWITCH LOCATION PHB-M3415 PHB-M3803 PHB-M3609 PHB-.M3805 PHB"M3604 PKD-844 PHB-M3606 PHB-M3621 PHB"M3412 RSP RSP RSP DGB-801 PBB"S04K PBB"S04L PKB"M4201 PKD-M4401 SSA-J04 SSB"J04 RSP PHB"M3413 P KA"M4101 PALO VERDE " UNIT 1 3/4 3-55 AMENDMENT NO. 27

~ E h

4t

~ 44 gV,

FOR INFORMATIONONLY REACTOR COOLANT SYSTEM 3/4.4.3 PRESSURIZER PRESSURIZER LIMITING CONDITION FOR OPERATION 3.4.3.1 The pressurizershall be OPERABLE with a minimum steady-state water level of greater than or equal to 27K indicated level (425 cubic feet) and a

maximum steady-state water level of less than or equal to 56'/ indicated level (948 cubic feet) and at least two groups of pressurizer heaters capable of being powered from Class lE buses each having a minimum capacity of 125 kW.

APPLICABIL.'TY:

MODES 1, 2, and 3.

ACTION:

b.

With only one group of the above required pressurizer heaters OPERABLE, restore at leas.t two groups to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

With the pressurizer otherwise inoperable, restore the pressurizer to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , or be in at least HOT STANDBY with the reactor trip breakers open 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 .

SURVEILLANCE REQUIREMENTS 4.4.3.1.1 The pressurizer water volume shall be determined to be within its limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.4.3. 1.2 The capacity of the above required groups of pressurizer heaters shall be verified to be at least 125 kW at least once per 92 days.

4.4.3. 1.3 The emergency power supply for the pressurizer heaters shall be demonstrated OPERABLE at least once per 18 months by verifying that on an Engineered Safety Features Actuation test signal concurrent with a loss-of-offsite power:

a ~

b.

The pressurizer heaters are automatically shed from the emergency power sources, an~~

The pressurizer heaters can be reconnected to their respective buses manually from the control roomQ~

Deferred until cycle 3 refueling outage.

PALO VERDE - UNIT 2 3/4 4

9 AtlENDMENT NO.

30

I ll'

'<r

'I

'4

~

CONTROLLED BY USER REACTOR COOLANT SYSTEM OPERATIOHAL LEAKAGE LIMITIHG CONDITION FOR OPERATIOH 3.4. 5. 2 a 0 b.

C.

d.

e.

s Reactor Coolant System leakage shall be limited to:

Ho PRESSURE BOUNDARY LEAKAGE, 1 gpm UNIDENTIFIED LEAKAGE, 1 gpm total primary-to-secondary leakage through all steam generators, and 720 gallons per day through any one steam generator, 10 gpm IDENTIFIED LEAKAGE from the Reactor Coolant System, and 1 gpm leakage at a Reactor Coolant System pressure of 2250 f 20 psia from any Reactor Coolant System pressure isolation valve specified in Table 3.4-1.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:.

a.

With any PRESSURE BOUROARY LEAKAGE, be in at least HOT STAHOBY

~

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

b."

With any Reactor Coolant System leakage greater than any one of the limits, excluding PRESSURE BOUNDARY LEAKAGE and leakage from Reactor Coolant System pressure isolation valves, reduce the leakage rate to within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-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 .

c.

With any Reactor Coolant System pressure isolation valve leakage greater than the above limit, isolate the high pressure portion of

-. the affected system from the low pressure portion within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one closed manual or deactivated automatic valve, 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 withi'n the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

d.

'With RCS leakage alarmed and confirmed in a flow path with no flow rate indicators,'commence an RCS water inventory balance within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to determine the leak rate.

SURVEILLANCE RE UIREMEHTS n

4.4.5.2.1 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits,by:

a.

Monitoring the containment atmosphere gaseous and particulate radioactivity monitor. at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

s only extension during the power ascension

prograra, an additional 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months is granted to cold shutdown.

During this 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months if the unidentified leakage exceeds 2.0.gpm, an iaeediate cooldown will be initiated.. The RCS leakage (Surveillance Requirement 4.4. 5.2.1. c) will be calculated at least, once per ej ht hours during this 72-hour extension.

PALO VERDE - UNIT 1 3/4'4"19 AHEHOMENT HO. 27

I'

~f !

heal ll

CONTROLLED BY USER REACTOR COOLANT SYSTEM 3l4.4. 10 REACTOR COOLANT SYSTEM VENTS LIHITING CONDITION FOR OPERATION 3.4. 10 Both reactor coolant system vent paths shall be operable and closed at each of the following locations:

a.

Reactor vessel

head, and b.

Pressurizer steam space.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

a 0 With only one of the above required reactor coolant system vent paths OPERABLE, from either location restore both paths at, that location to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With none of the above required reactor coolant system vent paths OPERABLE, from either location restore at least one path at that location to OPERABLE. status within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE RE UIREHENTS 4.4. 10 Each Reactor Coolant System vent path shall be demonstrated OPERABLE at least once per 18 months, when in MODES 5 or 6, by:

a.

C.

Verifying all manual isolation valves in each vent path are locked in the open position.

r VB V8.

Cycling each vent<through at least one complete cycle from the control room.

Verifying flow through the r eactor coolant system vent paths during venting.

PALO VERDE - UNIT 1 3/4 4-35 AMENDMENT NO.

27

t$

REACTOR COOLANT SYSTEM 3/4.4. 10 REACTOR COOLANT SYSTEM VENTS LIMITING CONDITION FOR OPERATION 3.4. 10 Both reactor coolant system vent paths shall be OPERABLE and closed at each of the following locations:

a.

Reactor vessel

head, and b.

Pressurizer steam space.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

a.

With on'ly one of the above required reactor coolant system vent paths

OPERABLE, from either location restore both paths at that location to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With none of the above required reactor coolant system vent paths OPERABL:-, from either location restore at least one path at that location to OPERABLE status within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-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 HOT SHUTDOWN within the

- " - -"-.following. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.4. 10 Each reactor coolant system vent path shall be demonstrated OPERABLE at least once per 18 months, when in MODES 5 or 6, by:

a.

Verifying all manual isolation valves in each vent path are locked in the open position.

yaiVe b..

Cycling each vent~through at least one complete cycle from the control room.

c.

Verifying flow through the reactor coolant system vent paths during venting.

. v

CONTROLLED BY USER REACTOR COOLANT SYSTEM 3/4.4. 10 REACTOR COOLANT SYSTEM VENTS LIMITING CONDITION FOR OPERATION 3.4. 10 Both reactor coolant system vent paths shall be OPERABLE and closed, at each of the following locations:

a.

Reactor vessel

head, and b.

Pressurizer steam space.

APPLICABILITY:

MODES 1, 2,

3. and 4.

ACTION:

'I a.

With only one of the above required reactor coolant system vent paths INOPERABLE, from either location restore both paths at that location to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the-next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . and in HOT.SHUTDOWN.within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With none of the above required reactor coolant system vent paths

. OPERABLE, from either location restore at least one path at that location to OPERABLE status within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE RE UIREMENTS 4.4.10 Each reactor coolant system vent path shall be demonstrated OPERABLE at least once per 18 months, when in MODES 5 or 6, by:

/

a.

Verifying all manual isolation valves in each vent path are locked in the open position.

~VaIve b.

Cycling each vent'through at least one complete cycle from the control room.

c.

Verifying flow through the reactor coolant system vent paths during venting.

PALO VERDE - UNIT 3 3/4 4-35

~t

~r J

gl

FOR INFORMATIONONLY EHERGEHCY CORE COOLING SYSTEt'IS t.

SURVEILLANCE REQUIREMENTS 4.5.1 Each safety injection tank shall be demonstrated OPERABLE:

a.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by:

1.

Verifying the contained borated water volume and nitrogen cover-pressure in the tanks is within the above limits, and 2.

Verifying that each safety injection tank isolation valve is open and the nitrogen vent valves are closed.

b.

At least once per 31 days and whenever the tank is drained to maintain the contained borated water level within the limits of Specifica-tion 3.5.1b, by verifying the boron concentration of the safety in-jection tank solution is between 2300 and 4400 ppm.

c.

At least-once per 31 days when the pressurizer pressure is above 430 psia, by verifying that power to the isolation valve operator is removed.

d.

At least once per 18 months by verifying that each safety injection tank isolation valve opens automatically under each of the following conditions:

~

1.

When an actual or simulated RCS pressure signal exceeds 515 psia, and 2.

Upon receipt of a safety injection actuation (SIAS) test signal.*

)

e.

At least once per 18 months by verifying OPERABILITY of RCS-SIT differential pressure alarm by simulating RCS pressure

> 715 psia with SIT pressure ( 600 psig.

f.

At least once per 18 months, when SITs are isolated, by verifying the SIT nitrogen vent valves can be opened.

g.

At least once per 31 days, by verifying that power is removed from the nitrogen vent valves.

Oeferred until cycle 3 refuelin outa e.

PALO VERDE - UNIT 2 3/4 5-2 At'lEttGHEttT ttp.

30

0 J'g!

0

FOR INFORMATIONONLY EMERGENCY CORE COOLING SYSTEHS SURVEILLANCE RE UIREHENTS (Continued 2.

3.

A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks,

screens, etc.)

show no evidence of structural distress or corrosion.

Verifying that a minimum total of 464 cubic feet of solid granular trisodium phosphate dodecahydrate (TSP) is contained within the TSP storage baskets.

Verifying that when a representative sample of 0.055 0.001 lb of TSP from a TSP storage basket is submerged, without agitation, in 1.0

~ 0.05 gallons of ?7

+ 9 F borated water from the RWT, the pH of the mixed solution is raised to greater than or equal to 7 within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

e.

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

2.

Verifying that each-automatic valve in the flow path actuates to its correct position on (SIAS and RAS) test signal(s).*

I Verifying that each of the following pumps start automatically upon receipt of a safety injection actuation test signal:

a.

High pressure safety injection pump.*

b.

Low pressure safety injection pump.*

3.

Verifying that on a recirculation actuation test signal, the containment sump isolation valves

open, the HPSI, LPSI and CS pump minimum bypass recirculation flow line isolation valves

.and combined SI mini-flow valve close, and the LPSI pumps stop.

4.

Conducting an inspection of all ECCS piping outside of contain-ment, which is in contact with recirculation sump inventory during LOCA conditions, and verifying that the total measured leakage from piping and components is less than 1

gpm when pressurized to at least 40 psig.

By verifying that each of the following pumps develops the indicated differential pressure at or greater than their respective minimum allowable recirculation flow when tested pursuant to Specifica-tion 4.0.5:

I I

1.

High pressure safety injection pump greater than or equal to 1761 psid.

2.

Low pressure safety injection pump greater than or equal to 165 psid.

"De d unt>

cyc e

3 refueling outage.

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

30

0

'b ~ L pt'Qt

~ 1 1

0

FOR INFORMATlONONLY COHTAINMEHT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND.COOLING SYSTEMS COHTAINMEHT SPRAY SYSTEM LIMIT IHG CONDITION FOR OPERATION 3.6.2.1 Two independent. containment spray systems shall be OPERABLE with each spray system capable of taking suction from the RWT on a containment spray actuation signal and automatically transferring suction to the containment sump on a recirculation actuation signal.,

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

APPLICABILITY: MODES 1, 2, 3, and 4*.

ACTION:

With one containment spray system inoperable, restore the inoperable spray system to OPERABLE.status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or. be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore the inoperable spray system to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.6.2,1 a

~

b.

Co d.

Each containment spray system shall be demonstrated OPERABLE:

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

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

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

()115 foot level).

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

2.

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

l Verifying that upon a recirculation actuation test signal, the containment sump isolation valves open and that a

recirculation mode flow path via an OPERABLE shutdown cooling heat exchanger is established.C3* ~

. *Onl when shutdown cooling is not in operation.

- Deferred unt>

cyc e

re ue ing outage.

PALO VERDE - UflIT 2 3/4 6-15 At1Efl0f1EffT ff0.

30

0,

FOR INFORMATIONONLY t

CONTA[NtlENT SYSTEMS SURVE1LLANCE REQU1REHENTS Continued)

'e.

3.

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

At least once per 5 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.

De erred until cycle 3 refueling outage.

m PALO VERDE - UNIT 2 3/4 6-16 AHENDHENT NO.

30

0 it,

~ J

FOR INFORMATIONONLY CONTAINHENT SYSTEHS SURVEILLANCE REQUIREHENTS (Continued) d.

At least once per 18 months, during shutdown, by 2.

Verifying 'that each automatic valve in the flow path actuates to its correct position on a containment spray actuation (CSAS) test signal,* and Verifying that each spray chemical addition pump starts auto-matically on a

CSAS test signal.O" e.

At least once per 5 years by verifying each solution flow rate from the following drain connections in the iodine removal system:

1.

SIA-V253 pump discharge line 0.63

+ 0.02 gpm.

2.

SIB-V254 pump discharge line 0.63 0.02 gpm.

3/4 6-18 PALO VERDE - UNI T 2

Deferred until c cle 3 refuelin a

AHENDHENT NO.

30

CQINITIRQILILEDBY USEIR TABLE 3. 6-1 (Continued)

CONTAINMENT ISOLATION VALVES VALVE "NUMBER PENETRATIOH NUMBER FUNCTION MAXIMUM ACTUATION TIME (SECONDS)

CHE-V M70 41 ora IAE-V 072 59 SIB-V 533 67 CHE-V 835 72 AFE-V 079¹ 75 AFE-V 080¹ 76 SIA-V 523 77 D.

CHECK VALVES (Continued)

Regenerative heat exchanger to RC loop 2A Containment service air utility station Long term recirculation loop 2 RC pump seal injection water to RCP 1A, 1B, 2A, 2B Steam generator 1 auxiliary feedwater Steam generator 2 auxi 1 iary feedwater Long term recirculation loop 1 N. A.

N. A.

¹Not Type C tested.

CC WmOLILED BY USER

S

,Q1'4 C

CGMTRGLLED BY USER TABLE 3. 6-1 (Continued)

CONTAINMENT ISOLATION VALVES VALVE NUMBER PENETRATION NuntBER FUNCTION MAXIMUM ACTUATION TIME (SECONDS)

SIB-HV 690 SIC-UV 653 SIA-UY 655 SIA-HV 691'CC-HV 076~

.HPA-.HV.J307A HPB-HV OOSA 26 2/

2/

328 SID-UY 654 26 SIB-UV 656 26 From shutdown cooling RC loop 1

From shuiaown cooling RC loop 1

Containment pressure monitor

. -Containment to -hydrogen,monitoJ Containment to hydrogen monitor H.A.

G.

REQUIRED OPEN DURING ACCIDENT CONDITIONS From shutdown cooling RC loop 2 H.A.

From shutdown cooling RC.loop 2

N.A.

From shutdow'n coolina RC loop 2

N.A.

From shutdown cooling RC loop 1 H.A.

HPA-HV 007B HPB-HY 008B CHA-HV 524 38 3c 41 Hydrogen monitor to containment Hydrogen monitor to containment Regenerative heat exchanger to RC loop 2A t

H.A.

HCA-HV 074~

5~4 HCB-HY 075" 55A HCD-HV 0778 62A SID-HV 331 67 CHB-HV 255 72 SIC-HV 321 77 SGA-UY 1344 2

Containment pressure monitor Containment pressure monitor CB pressure monitor Long-term recirculation. loop 2

RC pump seal injection water to RCP lA, 1B 2A>

ZB

~i..

Long-term recalculation loop 1

N.A.

N.A..

N.A.

Main steam to auxiliary feedwater N.A."

turbine PNot Type C tested.

CGINIYRGLLkI5Y USER

r A

COHTAIHMcNT SYSTEMS ElECTRIC HYDROGEN RECOMBINERS LIMITING CONDITION'OR OPERATIOH 3.6.4.2 Two portable independent containment hydrogen recombiner systems shared among the three units shall be OPERABLE.

~

APPLICABILITY:

MODES 1 and 2.

(

ACTION:

With one hydrogen recombiner system inoperable, restore the inoperable system to OPERABLE status within 30 days or meet the requirements of Specif a-tion 3.6.4.3, or be in at least HOT STANDBY wfthfn the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months "

SURVEILLANCE RE UIREMEHTS 4.6.4.2

-Each hydrogen recombiner system shill be:demonstrated OPERABLE:

At least once per 6 months by:

1.

'erifyirig through a visual examination that there is no evi" dence of abnormal conditions within the recombiner enclosure and control console.

- b.

2.

Operating the recombiner to fnclude the afr blast heat exchanger fan motor and enclosed blower motor continuously for at least 30 minutes at a temperature of approximately

'800'F reaction chamber temperature.

At.least once per year by performing a CHAHHEL CAL!BRATIOH of recombfner instrumentation to include a functional test of the recombfner at 1200'F (f 50'F) for at least four hours.

"Prfor to March 30, 1986 or until the cohplotfon of thi envfronmental qualifi-cation modifications to the hydrogen rocoabfner

system, whichever occurs first, the provisions of Specification 3.0.4 are not applfcnble during implementation of the environmental qualification modifications to the hydrogen recombfner system, when the containment hydrogen purge cleanup system described.fn

$pqcfff-.

cation 3. 6.4.3 fs OPERABLE.

I r IP 0

FOR INFORMATIONONLY PLANT SYSTEHS SURVEILLANCE RE UIREHENTS Continued b.

At least once per 18 months during shutdown by:

1.

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

2.

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

c.

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

STAGGERED TEST BASIS (by means of -a flow test) that the normal flow path from the condensate storage tank to each of the steam generators through one of the essential auxiliary feedwater pumps delivers at least 750 gpm at 1270 psia or equivalent.

d.

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

"Deferred until cycle 3 refueling outage.

PALO VERDE - UNIT 2 3/4 7-5 AHEtlDHENT NO.

30

I t

'll'l

FOR INFORMATIONONLY

'LANT SYSTEtlS 3/4. 7.3 ESSENTIAL COOLING IIATER S'YSTEtl L INITING CONDITION FOR OPERATION 3.7.3-At least two independent essential cooling water loops shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

Vith only one essential cooling water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the-following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.7.3 At least two essential cooling water loops shall be demonstrated OPERABLE:

a.

'At least once per 31 days by verifyino that each valve (manual, power-operated, or automatic) servicing safety-related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.

b.

At least once per 18 months during shutdown, by verifyinq that each automatic valve servicing safety-related e uipment actuates to its correct position on an SIAS test signal.*

c.

At least once per 18 months during shutdown, by verifying that the essential cooling water pumps start on an SIAS test signal.*

d.

At least once per 18 months during shutdown, by verifying that each valve (manual, power-operated, or automatic) servicing safety-related equipment that is locked, sealed, or otherwise secured in position, is in its correct position.

'Deferred until cycle 3 refueling outage.

PALO YERDE - Ut<IT 2 3/4 7-12 AHEftDI<EttT ttO.

30

~a

,1

FOR lNFORMATION ONLY PLANT SYSTEHS SURVEILLANCE RE UIREHENTS (Continued) 1'.

Verifying that the cleanup system satisfies the in-place testing acceptance criteria and uses the test procedures of Regulatory Positions C.5.a, C.5.c and C.5.d of Regulatory Guide 1.52, Revision 2, Harch

1978, and the system flow rate is 28,600 cfm

+ 10K.

2.

Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, Harch 1978*, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, Harch 1978*.

3.

Verifying a system flow rate of 28,600 cfm

= 10~ during system operation when tested in accordance with ANSI N510-1980.

c.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, Harch 1978*,

meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, Harch 1978*.

d.

At least once per 18 months by:

1.

Verifying that the pressure drop across the combined HEPA filters, pre-filters, and charcoal adsorber banks is less than 8.4 inches Water Gauge while operating the system at a flow rate of 28,600 cfm

+ lOX.

2.

3.

Verifying that on a Control Room Essential Filtration Actuation Signal and on a SIAS, the system is automatically placed into a filtration mode of operation with flow through the HEPA filters and charcoal adsorber banks ~~

Verifying that the system maintains the control room at a

positive pressure of greater than or equal to 1/8-inch Water Gauge relative to adjacent areas during system operation at a makeup flow rate to the control room of less than or equal to 1000 cfm.

4.

Verifying that the emergency chilled water system will mainta'in the control room environment at a temperature less than or equal to 80'F for a period of 30 minutes.

'*ANSI N509-1980 is appl.icable for this s ecification.

- Oe erre unti cyc e

re ue ing outage.

0 VER

- UNIT

-17 AHENOHENT NO.

4r

,lyr 4'

l1 V

C Ll 0

FOR INFORMATIONONLY PLANT SYSTEMS SURVEILLANCE RE UIPEMENTS (Conti'nued l.

Verifying that the cleanup system satisfies the in-place test-ing acceptance criteria and uses the test procedures of Regula-tory Positions C.5.a, C.S.c and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 6000 cfm

+ 10K.

2.

Verifying within 31 days after removal that a laboratory analy-sis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revi-sion 2, March 1978,* meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.*

3.

Verifying a system flow rate of 6000 cfm + 10K during system operation when tested in accordance with ANSI N510-1980.

c.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of.charcoal,adsorber operation by verifying within 31 days zfter removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978,*

,meets the laboratory testing criteria of Regulatory Position C.6.a

,of Regulatory Guide 1.52, Revision 2, March 1978.*

d.

At least once per 18 months by:

2.

Verifying that the pressure drop across the combined HEPA fil-ters, pre-filters, and charcoal adsorber banks is less than 8.4 inches Water Gauge while operating the system at a flow rate of 6000 cfm + 10'i.

Verifying that the system starts on an SIAS test signal.**

e.

After each complete or partial replacement of an HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99" of the DOP when they are tested in-place in accordance with ANSI N510-1980 while operating the system at a flow rate of 6000 cfm +

IOX.

f.

After each comp'lete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99.05 of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1980 while operating the system at a flow rate of 6000 cfm +

10"'.

ANSI N509-1980 is a

licab f

ecification.

- Deferred unt>

cycle 3 refuelin outa e.

PALO VEROE - UNIT 2 3/4 7-20 Ar~ErrOrrENT tr0.

l S'q

'V 0

i CONTROLLED BV USER PLANT SYSTEMS 3/4.?. 9 SHU."BERS:

LIMITING CONDITION cOR OPERATION 3.7.9 All hydraulic and mechanical snubbers shall be OPERABLE.

The only snubbers excluded from this requirement are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed, would have no adverse effect on any safet'y-related system.

APPLICABILITY:

MODES 1, 2, 3, and 4.

MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.

ACTION:

..Mith one or move snubbers inoperable on any system, within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months replace ov restore the inoperable snubber(s} to OPERABLE status and perform an engineering evaluation per Specification 4.?.9g.

on the attached component or declare the attached system inoperable and follow the appropriate ACTION statement for that system.

SURVEILLANCE RE UIREMEHTS

~ ~ g

, 4.7.9 Each snubber shall be demonstrated OPERABLE by performance of the following 'augmented inservice inspection program and the requirements of Specification 4.0.5.

~Kbb i As used in this specification, type of snubber shall mean snubbers of the same design and, manufacturer, irrespective of capacity.

b.

Visual Ins ections Snubbers are categorized as inaccessible or accessible during reactor operation.

Each of these groups (inaccessible and accessible) may be inspected independently according to the schedule below.

The first inservice visual inspection of each type of snubber shall be performed after 4 months but within 10 months of commencing POMER OPERATION and shall include all hydraulic and mechanical snubbers."

If all snubbers of each type are found OPERABLE during the first inservice visual, inspection, the second inservice visual inspection of that type shall be performed at the first refuel.ing outage.

Otherwise, subsequent visual inspections of a given type shall be performed in accordance with the following schedule:

~Mith the exception that the first inservice visual inspection for all snubbers that are inaccessible during reactor operation shall be conducted no later than the first refueling outage.

PALO VERDE - UNIT 3 3/4 7-21 AMEHDMEHT HO.

Ji 0

~ff

~ ~

a CONTROLLED BY USER

~

PLANT SYSTP~S 3/4.7. 11 SHUTDOWN COOLING SYSTEt>

LIMITING CONDITION FOR OPERATION 3.7.11 Two independent shutdown coolino subsystems shall be OPERABLE, with each subsystem comprised of:

a.

One OPERABLE low pressure safety injection pump, and b.

An independent OPERABLE flow path capable of taking suction from the RCS hot leg and discharging coolant through the shutdown cooling heat exchanger and back to the RCS through the cold Ieg injection lines.

APPLICABILITY:

BODES 1, 2, and 3.

ACTION:

a.

With one shutdown cooling subsystem inoperable, restore the inoperable

,subsystem to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , be in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and be in COLD SHUTDOWN within,the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months and continue action to restore the required subsystem to OPERABLE status.

b.

With both shutdown cooling subsystems inoperable, restore one subsystem to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and continue action to restore the required subsystems to OPERABLE status.

c.

With both scftdown cooling svbsysteafs inoperabie and both reactor

. coolant loops inoperable, initiate action to restore the reauired subsystems to OPERABLE status.

SURVEILLANCE REQUIREMENTS 4.7.11 If a.

b.

Each shutdown cooling subsystem shall be demonstrated OPERABLE:

At least once per 18 months, during shutdown, by establishing shutdown cooling flow from the RCS hot legs, through the shutdown cooling heat exchangers, and returning to the RCS cold leos.

At least once per 18 months, during shutdown, by testing the automatic

~

and interlock action of the shutdown cooling system connections from the RCS.

The shutdown cooling system suction valves shall not open when RCS pressure is greater than 410 psia.

The shutdown cooling system suction valves located outside containment shall close auto-matically when RCS pressure is greater than 500 psia.

The shutdown cooling system suction valve located inside containment shall close automatically when RCS pressure is greater than 700 psia.-

PALO VERDE - UNIT 1

3/4 7-29 APENDHENT NO.

14

I r

a(1 jh T'!

'l U

4,

~w l

(

h I

0

CONTROLLED BY USER e

~

PLANT SYSTEMS 3/4.7. 11 SHUTDOWN COOLING SYSTEM LIMITING CONDITION FOR OPERATION 3.7. 11 Two independent shutdown cooling subsystems shall be OPERABLE, with each subsystem comprised of:

a.

One OPERABLE low pressure safety injection pump, and b.

An independent OPERABLE flow path capable of taking suction from the RCS hot leg and discharging coolant through the shutdown cooling heat exchanger and back to the RCS through the cold leg injection lines.

APPLICABILITY:

MODES 1, 2, and 3.

ACTION:

,0 C.

With both shutdown cooling subsystems inoperable, restore one subsystem to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and continue action to restore the required subsystems to OPERABLE status.

h Nith.both letdown cooIing subsystems inoperable and both reactor coolant loops inoperable, initiate action to restore the required subsystems to OPERABLE status.

a.

With one shutdown cooling subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , be in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months and continue action to restore the required subsystem to OPERABLE status.

SURVEILLANCE REQUIREMENTS 4.7. 11 Each shutdown cooling subsystem shall be demonstrated OPERABLE:

a.

At least once per 18 months, during shutdown, by establishing shutdown cooling flow from the RCS hot legs, through the shutdown cooling heat exchangers, and returning to the RCS cold legs.

b.

At least once per 18 months, during shutdown, by testing the automatic end interlock action of the shutdown'ooling system connections from the RCS.

The shutdown cooling system suction valves shall not open when RCS pressure is greater than 410 psia.

The shutdown cooling system suction valves located outside containment shall close auto-matically when RCS pressure is greater than 500 psia.

The shutdown cooling system suction valve located inside containment shall'close

".automatically when RCS pressure is greater than 700 psia.

PALO VERDE - UNIT 2 3/4 7-29 AMENDMENT NO, 8

C l

J'g

~~

h C

0 M

'I ll

CONTROLLED BV USHER PLANT SYSTEMS 3/4.7. 11 SHUTDOWN COOLING SYSTEM LIMITING CONDITION FOR OPERATION 3.7.11 Two independent shutdown cooling subsystems shall be OPERABLE, with each subsystem comprised of:

a.

One OPERABLE low pressure safety injection pump, and b.

An independent OPERABLE flow path capable of taking suction from the RCS hot leg and discharging coolant through the shutdown cooling heat exchanger and back to the RCS through the cold leg injection lines.

APPLICABILITY:

MODES 1, 2, and 3.

ACTION:

a.

With one shutdown cooling subsystem inoperable, restore the inoperable subsystem 'to OPERABl E status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , be in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and be in COLO SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months and continue action to restore the required subsystem to OPERABLE status.

b.

With both shutdown. cooling subsystems inoperable, restore one subsystem to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and continue action to restore the required subsystems to OPERABLE status.

c.

Nith both shutdown cooling subsystems inoperable and both reactor

,coolant. loops,.inoperable, initiate action to restore the required subsystems to OPERABLE status.

SURVEILLANCE RE UIREMENTS 4.7. 11 Each shutdown cooling subsystem shall be demonstrated OPERABLE:

a.

At least once per 18 months, during shutdown, by establishing shutdown cooling flow from the RCS hot legs, through the shutdown cooling heat exchangers,.and returning to the RCS cold legs.

b.

At least once per 18 months, during shutdown, by testing the automatic and inter lock action of the shutdown cooling system connections from the RCS.

The shutdown cooling system suction valves shall not open when RCS pressure is greater than 410 psia.

The shutdown cooling system suction valves located outside containment shall close auto-matically when RCS pressure is greater than 500 psia.

The shutdown cooling system suction valve located inside containment shall close automatically when RCS pressure is greater than 700 psia.

PALO VERDE - UNIT 3 3/4 7-29

C 1

<<'flf1

~ 4 P

g<

O.

'h I

CoiMRQLKEQ ISY USiER ELECTRICAL POWER SYSTEMS SURVEILLANCE RE UIREMENTS,.

. 4.8.1.1.1 Each of the above required, physically independent circuits between the offsite transmission network and the onsite Class 1E distribution system shall be:

a ~

b.

Determined OPERABLE at least once per 7 days by verifying correct

'reaker alignment indicating power availability Demonstrated OPERABLE at least once per 18 months during shutdown by manually transferring the onsite Class lE power supply from the normal circuit to the alternate circuit.

4.8. 1.1.2 Each diesel generator shall be demonstrated OPERABLE:

a.

In accordance with the frequency specified in Table 4.8-1 on a

STAGGERED TEST BASIS by:

l.

Verifying the fuel level in the day tank.

2.

Verifying the fuel level in the fuel storage tank.

3.

Verifying the fuel transfer pump can be started and, transfers fuel from'the storage system to the day tank.

4.

Verifying the diesel generator. can start~

and accelerate to generator voltage and frequency at 4160 + 420 volts and 60.+

1.2 Hz in less than or equal to 10 seconds.

Subsequently, the generator shall be manually synchronized to its appropriate bus and gradually loaded"" to an indicated 5200-5400 kW""" and operates for at least 60 minutes.

The diesel generator shall be started for this tes

""" using one of the following signals on a

STAGGERED TEST BASIS:

a) b)

c) d)

Manual Simulated loss of offsite power by itself.

Simulated loss of offsite power in conjunction with an ESF actuation test signal.

An ESF actuation test signal by itself.

5.

Verifying the diesel generator is aligned to provide standby power to the associated emergency busses.

""This test shall be conducted in accordance with the manufacturer's recommen-dations regarding engine prelube and warmup procedures, and as applicable regarding loading recommendations.

"""This band is meant as guidance to avoid routine overloading of the engine.

Loads in excess of this band for special testing under'irect monitoring of the manufacturer or momentary variations due to changing bus loads shall not invalidate the test.

""""Until the first refueling outage, the diesel generator shall be test starte onl manual

'0 PALO VERDE - UNIT 1 3/4 8"3 AMENDMENT No-

I

~l I

0

FOR INFORMATiONONLY ELECTRICAL POWER SYSTEMS SURVEILLANCE RE UIREMENTS 4.8. 1. l. 1 Each of the above required physically independent circuits between the offsite transmission network and the onsite Class 1E distribution system shall be:

a.

b.

Determined OPERABLE at least once per 7 days by verifying correct breaker alignment indicating power availability Demonstrated OPERABLE at least once per 18 months during shutdown by manually transferring the onsite Class lE power supply from the normal circuit to the alternate circuit.

4. 8. l. 1.2 Each diesel generator shall be demonstrated OPERABLE:

r a.

In accordance with the frequency specified in Table 4.8-1 on a

STAGGERED TEST BASIS by:

1.

Verifying the fuel level in the day tank.

2.

Verifying the fuel level in the fuel storage tank.

3.

Verifying.the fuel transfer pump can be started andtransfers fuel from the storage system to the day tank.

4.

Verifying the diesel generator can start*" and accelerate to generator voltage and frequency at 4160

+ 420 volts and 60

+

1.2 Hz in less than or equal to 10 seconds.

Subsequently, the generator shall be manually synchronized to its appropriate bus and gradually loaded*~ to an" indicated 5200-5400 kW~*" and operates for at least 60 minutes.

The diesel generator shall be star ted for this tes using one of the following signals on a

STAGGERED TEST BASIS:

a) b)

c) d)

Manual Simulated loss of offsite power by itself.

Simulated loss of offsite power in conjunction with an ESF actuation test signal.

An ESF actuation test signal by itself.

5.

Verifying the diesel generator is aligned to provide standby power to the associated emergency busses.

This test shall be conducted in accordance with the manufacturer's recommen-dations regarding engine prelube and warmup procedures, and as applicable regarding loading recommendations.

~~*This band is meant as guidance to avoid routine over loading of the engine.

Loads in excess of this band for special testing under direct monitoring of the manufacturer or momentary variations due to changing bus loads shall not invalidate the test.

~""~Unti] the first re ueling outage, the diesel generator shall be test stai ted nl manu a l ly.

0 PALO VERDE - UNIT 2 3/4 8-3

AlA r

CONTROLLED BY USER ELECTRICAL POWER SYSTEMS SURVEILLANCE RE UIREMENTS 4.8. 1. l. 1 Each of the above required physically independent circuits between the offsite transmission network and the onsite Class 1E distribution system shall be:

a.

Determined OPERABLE at least once per 7 days by verifying correct breaker alignment indicating power availability b.

Demonstrated OPERABLE at"least once per 18 months 'during shutdown by

'anually transferring the onsite Class lE power supply from the normal circuit to the alternate circuit.

4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE:

a ~

In accordance with the frequency specified in Table 4.8-1 on a

'TAGGERED TEST BASIS by:

1.

Verifying the fuel level in the 'day tank.

2.

Verifying the fuel level in the fuel storage tank.

3.

Verifying the fuel transfer pump can be started and transfers fuel from the storage system to the day tank.

4.

Verifying the diesel generator can start"" and accelerate to generator voltage and frequency at 4160

+ 420 volts.and 60 +

1.2 Hz in less than or equal to 10 seconds.

Subsequently, the generator shall be manually synchronized to its appropriate bus and gradually loaded"" to an indicated 5200-5400 kW*"" and operates for at least 6

minutes.

The diesel generator shall be started for this tes

""" using one of the following signals on a

'TAGGERED TEST BASIS:

a)

Hanual b)

Simulated loss of offsite power by itself.

c)

Simulated loss of offsite power in conjunction with an ESF actuation test signal.

d)

An ESF actuation test signal by itself.

5.

Verifying the diesel generator is aligned to provide standby power to the associated emergency busses.

h lid d

d l d

"l h

h dations regarding engine prelube and warmup procedures, and as applicable regarding loading recommendations.

""This band is meant as guidance to avoid routine overloading of the engine.

Loads in excess of this band for special testing under direct monitoring of the manufacturer or momentary variations due to changing bus loads shall not

'nvalidate the test.

""""Until t e

) rst refueling outage, the diesel generator shall be test started only manually.

PALO VERDE - UNIT 3 3/4 8-3

A(

~

FOR 1NFORMATlON ONLY ELECTRICAL POWER SYSTEIi SURVEILLANCE RE UIREYiEHTS (Conti.nued 4.8. 1. 1. 2 (Cont inued) b.

C.

d.

At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tank obtained in accordance with ASTI1-04176-82, is within the acceptable limits specified in Table 1 of ASTIl 0975-81 when checked for viscosity, water and sediment.

At least once per 184 days the diesel generator shall be started**

and accelerated to generator voltage and frequency at 4160 420 volts and 60

~ 1.2 Hz in less than or equal to 10 seconds.

The generator voltage

~nd frequency shall be 4160 420 volts and 60 1'.2 Hz within 10 seconds after the start signal.

The generator shall be manually synchronized to its appropriate emergency

bus, loaded to an indicated 5200-5400**"

kW in less than or equal to 60 seconds, and operate for at least 60 minutes.

This test, if it is performed so it coincides with the testing required by Surveillance Requirement 4.8. 1. 1.2.a.4, may also serve to concurrently meet those requirements as well.

At least once per 18 months during shutdown by:

2.

3.

4, Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for this class of standby service.

'Verifying the generator capability to reject a single largest load of greater than or equal to 839 kW (Train B AFW pump) for emergency diesel generator B or 696 kW for emergency diesel generatcr A (Train A HPSI pump) while maintainin voltage at 4160

+ 420 volts and frequency at 60

+ 1.2 Hz.**"*

Verifying that the automatic load sequencers are OPERABLE with the interval between each load block within +

1 second of its design interval.~**~

Simulating a loss of offsite power by itself, and:

a) b)

Verifying deenergization of the emer ency busses and load shedding from the emergency busses.****

Verifying the diesel starts*" on the auto-start signal, energizes the emergency busses with permanently connected loads within 10 seconds, energizes the auto-connected shut-down loads through the load sequencer and operates for greater than or equal to 5 minutes while its generator is

""This test shall be conducted in accordance with the manufacturer's recommen-dations regarding engine prelube and warmup procedures, and as applicable regarding loading recommendations.

- - This band is meant as guidance to avoid routine overloading of the engine.

Loads in excess. of this band for special testing under direct monitoring of the manufacturer or momentary variations due to changing bus loads shall not invalidate the test.

- "'Deferre unti cyc e

re ue in outage.

PALO VERDE - Ut)IT 2 3/4 8-4 AI'1EIIDHEilT se0, 30

I II 0

ry 0

COINI'll'IRGLILEDBV USEIR ELECTRICAL POWER SYSTEM SURVEILLANCE..RE ULREl1ENTS

. Continued).

4.8. 1. 1. 2 (Continued) loaded with the shutdown loads.

After energization of these

loads, the steady state voltage and frequency shall be maintained at 4160 + 420 volts 'and 60 + 1.2/-0.3 Hz.

5.

Verifying that on an ESF actuation test. signal (without.loss of power) the diesel generator starts" on the auto-start signal and operates on standby for greater than or equal to 5 minutes.

6.

Simulating a loss-of-offsite power in conjunction with an ESF actuation test signal, and a)

Verifying de-energization of the emergency busses and load shedding from the emergency busses.

b)

Verifying the diesel starts" on the auto"start signal, energizes the emergency busses with permanently connected loads within 10'econds, energizes the auto-connected emergency (accident) loads through the load sequencer, and operates for greater than or equal to 5 minutes and maintains the steady-state voltage and frequency at 4160 ~

420 volts and 60 + 1.2/-0;3 Hz.

c)

Verifying that all automatic diesel generator trips, except engine overspeed, generator differential, and low lube oil

pressure, are automatically bypassed upon loss of voltage on the emergency

bus, upon a safety injection actuation signal or upon AFAS.

7.

Verifying the diesel generator operates" for at least 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

During the first 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of this test, the diesel generator shall be loaded to an indicated 5800-6000 kW"" and during the remaining 22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months of this test, the diesel generator shall be loaded to an indicated 5200-5400 kW. Within 5 minutes after completing this 24-hour test, perform Surveillance Require-mentt

4. 8. 1. 1. 2. d. 6. b). """

"This test shall be conducted in accordance with the manufacturer's recommen-dations regarding engine prelube and warmup procedures, and as applicable regarding loading recommendations.

""This band is meant as guidance to avoid routine overloading of the engine.

Loads in excess of this band for special testing under di rect monitoring of the manufacturer or momentary variations due to changing bus loads shall not invalidate the test~8

"""IfSpecification 4.$. 1. 1.2.d.6.b) is not satisfactorily completed, it is not necessary to repeat the preceding 24-hour test.

Instead, the diesel generator may be operated at 5200-5400 kW"" for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or until operating te~oerature has stabilized.

PALO VERDE " UNIT 1 3/4 8-5 AMENDMENT NO. 9

e

'a

0~1>

j I

~a*

FOR! NFORMATION ONLY ELECTRICAL POWER SYSTEH SURVEILLANCE RE UIREHENTS (Conti.nued) 4.8.1.1.2 (Continued) loaded with the shutdown loads.

After energization of these

loads, the steady state voltage and frequercy shall be maintained at 4160

~ 420 volts and 60

+ 1.2/-0.3 Hz ***"

}

5.

Verifying that on an ESF actuation test signal (without loss of power) the diesel generator starts*

on the auto-start signal and operates on standby for greater than or equal to 5 minutes C"***~

6.

Simulating a loss-of-offsite power in conjunction with an ESF actuation test signal, and a)

Verifying de-energization of the emer ency busses and load shedding from the emergency busses.

b) c)

Verifying the diesel starts*

on the auto-start

signal, energizes the emergency busses with -permanently connected loads within 10 seconds, energizes the auto-connected emergency (accident) loads through the load sequencer, arid operates for greater than or equal to 5 minutes and maintains the steady-state volta and frequency at 4160

+

420 volts and 60 + 1.2/-0.3 Ilz.****

Verifying that all automatic diesel generator trips, except engine overspeed, generator differential, and low lube oil

pressure, are automatically bypassed upon loss of voltage on the emergency

bus, u on a safety injection actuation signal or upon AFAS. *"*

7.

Verifying the diesel generator operates* for at least 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

During the first 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of this test, the diesel generator shall be loaded to an indicated 5800-6000 kW** and during the remaining 22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months of this test, the diesel generator shall be loaded to an indicated 5200-5400 kW*".

Within 5 minutes after completing this 24-hour test erform Surveillance Require-ment 4 8 1

1 2 d 6 b) *******

AHENDHENT NO.

30

+This test shall be conducted in accordance with the manufacturer's recommen-dations regarding engine prelube and warmup procedures, and as applicable regarding loading recommendations.

- This band is meant as guidance to avoid routine overloading of the engine.

Loads in excess of this band for special testing under direct monitoring of the manufacturer or momentary variations due to changing bus loads shall not invalidate the test~9

- "IfSpecification 4.&4 I. I 2 d.6.b) is not satisfactorily completed, it is not necessary to repeat the preceding 24-hour test.

Instead, the diesel generator may be-operated at 5200-5400 kW** for I hour or until operating temperature has stabilized.

- - - Deerred until cyc e

re ueling outa e.

ERDE - UNIT 2

/4 8-5

t P

P 0

FOR INFORMATlONONLY

. ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued 8.

9.

Verifying that the auto-connected loads to each diesel generator do not exceed the continuous rating of 5500 kM.****

Verifying the diesel generator's capability to:

a) b)

c)

Synchronize with the offsite power source while the generator is loaded with its emergency l

ds upon a

simulated restoration of offsite power **".*

Transfer its loads to the offsite power

urce, and ***

Proceed through its shutdown sequence.****

e.

10.

Verifying that the following diesel generator lockout features prevent diesel generator starting only when required:

a) turning gear en a ed~**

b) emergency sto ***

At least once per 10 years or after any modifications which could affect diesel. generator interdependence by starting** both diesel

~ generators simultaneously, during shutdown, and verifying that both diesel generators accelerate to generator voltage and frequency at 4160

+ 420 volts and 60 1.2 Hz in less than or equal to 10 seconds.

4.8.1.1.3

~ge orts - A11 diesel generator failures, valid or nonvalid, shall be reported to the Commission within 30 days in a Special Report pursuant to Specification 6.9.2.

Reports of diesel generator failures shall include the information recommended in Regulatory Position C.3.b of Regulatory Guide 1.108, Revision 1, August 1977.

If the number of failures in the last 100 valid tests (on a per nuclear unit basis) is greater than or equal to 7, the report shall be supplemented to include the additional information recommended in Regulatory Position C.3.b of Regulatory Guide

1. 108, Revision 1, August 1977.

- This test shall be conducted in. accordance with the manufacturer's recommen-dations regarding engine prelube and warmup procedures, and as applicable re ardin loading recommendations.

- - ~Deferred unt>

cyc e

refueling outage.

PALO VERDE - UNIT 2 3/4 8-6 ANENDtlENT NO.

30

0 E"

n, a.+

FOR INFORMATIONONLY ELECTRICAL POWER SYSTEHS SURVEILLAHCE REQUIREHEI'ITS (Continued b.

At least once per 92 days and within 7 days after a battery discharge with battery terminal voltage below 105 volts, or battery overcharge with, battery terminal voltage above 145 volts, by verifying that:

1.

The parameters in Table 4.8-2 meet the Category B limits, 2.

There is no visible corrosion at either terminals or connectors, or the connection resistance of these items is less than 150 x 10-6 ohms, and 3.

The average electrolyte temperature of six connected cells is above 60'F.

c.

At least once per 18 months by verifying that:

1.

The cells, cell plates, and battery racks show no visual indication of physical damage or abnormal deterioration, 2.

The cell-to-cell and terminal connections are clean, tight, and coated with anticorrosion material, 3 ~ ~

The-resistance of each cell-to-cell and terminal connection is less than or equal to 150 x 10-6 ohms, and 4.

The battery charger will supply at least 400 amperes for batteries A and B and 300 amperes for batteries C and D at 125 volts for at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

d.

At least once per 18 months, during shutdown, by verifying that the battery capacity is adequate to supply and maintain in OPERABLE status all of the actual or simulated emergency loads for the design duty cycle when the battery is subjected to a battery service test.cw W e.

At least once per 60 months, during shutdown, by verifying that the battery capacity is at least 80K of the manufacturer's rating when subjected to a performance discharge test.

This performance discharge test may be performed in lieu of the battery service test required by Surveillance Requirement 4.8.2. 1d.

E

f. 'nnual performance discharge tests of battery capacity shall be given to any battery that shows signs of degradation or has reached 85 of the service life expected for the application.

Degradation is indicated when the battery capacity drops more than 10".: of rated capacity from its average on previous performance

tests, or is below 90" of the manufacturer's rating.

"Deferred until cycle 3 refueling outage.

PALO VERDE - UNIT 2 3/4 8-10 AHEtlDHEI'lT tj0.

30

VN v't.

m aa FOB INFORMATIONONLY ELECTRICAL POWER SYSTEMS MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION AHD BYPASS DEVICES LIMITING CONDITION FOR OPERATION 3.8.4.2 The thermal overload protection of each valve shown in Table 3.8-3 shall be bypassed continuously or under accident conditions, as applicable, by an OPERABLE device integral with the motor starter.

APPLICABILITY'.

Whenever the motor-operated valve is required to be OPERABLE.

ACTION:

With the thermal overload protection for one or more of the above required valves not bypassed continuously or under accident conditions, as applicable, by an OPERABLE integral bypass

device, take administrative action to continuously bypass the thermal overload within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or declare the affected valve(s) inoperable and apply the appropriate ACTION Statement(s) for the affected valve(s).

SURVEILLANCE REQUIREMENTS

'I 4.8.4.2.1 The thermal overload protection for the above required valves shall be verified to be bypassed continuously or under accident conditions, as applicable, by an OPERABLE integral bypass device by the performance of a CHANNEL FUNCTIONAL TEST of the bypass circuitry for those thermal overloads which are normally in force during plant operation and bypassed under accident conditions and by verifying that the thermal overload protection is bypassed for those thermal overloads which are continuously bypassed and temporarily placed in force only when the valve motors are undergoing periodic or maintenance testing:

a.

At 1east once per 18 months, an~a b.

Following maintenance on the motor starter.

4.8.4.2.2 The thermal overload protection for the above required valves which are continuously bypassed shall be verified to be bypassed following testing during which the thermal overload protection was temporarily placed in force.

Deferred until cycle 3 refueling outage.

PALO VERDE - UNIT 2 3/4 8-40 AMEs'DMEflT NO.

30

~ 1 0

>4 I

I v~

V $

~%>>

0

3/4. 9 REFUELING OPERATIONS 3/4.9. 1 BORON CONCENTRATION LIMITING CONDITION FOR OPERATION ov 3.9.1 Wit/ the reactor vessel head closure bolts less than fully tensioned or with the head

removed, the boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions is met:

a.

Either a

K ff of 0.95 or less, or eff b.

A boron concentration of greater than or equal to 2150 ppm.

APPLICABILITY:

MODE 6".

ACTIDN:

With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes and in'itiaie and continue boration at greater than or equal to 26 gpm of a solution containing

> 4000 ppm boron or its equivalent until K ff i s reduced to 1 ess than or equal to 0. 95 or the boron concentration is eff restored to g. eater than or equal to 2150 ppm, whichever is the more restri ctive.

SURVEILLANCE RE UIREHENTS 4.9.1.1 The more restrictive of the above two reactivity conditions shall be determined prior to:

a.

Removing or unbolting the reactor vessel

head, and b.

Withdrawal of any full-length CEA in excess of 3 feet from its fully inserteQ position within the reactor pressure vessel.

4.9. 1.2 The boron concentration of the Reactor Coolant System and the refueling canal shall be determined by chemical analysis at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

The reactor shall be maintained in MODE 6 whenever fuel is in the reactor vessel with the reactor vessel head closure bolts less than fully tensioned or with the head removed.

PALO VERDF. - UNIT L

~,II 4/+

REFUELING OPERATPZNQIMTRQLLED IBY USER 3/4. 9. 6 REFUELING MACHINE P

LIMITING CONDITION FOR OPERATION 3.9.6 The refueling machine shall be used for movement of fuel assemblies and shall be OPERABLE with:

a.

A minimum capacity of 3590 pounds and an overload cut off limit of less than or equal to 1556, (1727)" pounds for the refueling machine.

APPLICABILITY:

During movement of fuel assemblies within the refueling cavity.

ACTION:

Mith the above requirements for the refueling machine not satisfied, suspend use

, of the refueling, machine from operations involving the movement of fuel assemblies.

SURVEILLANCE RE UIREMENTS 4.9.6.1 The refueling machine used for movement of fuel assemblies shall be demonstrated OPERABLE within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months prior to the start of such operations by performing a load test of at least 3590 pounds and demonstr t'n automatic load cut off when the refueling machine load exceeds 1556 (1727)".pounds-

"For initial fuel load only.

PALO VERDE - UNIT 1 3/4 9-6 CC)+J]TRQILLtFD IBY uSER

l gg

r REFUELING OPERATIONS 3/4. 9. 6 'EFUELING MACHINE LIMITI'NG CONDITION FOR OPERATION r

3.9.6 The'efueling machine shall be used for movement of fuel assemblies and shall be OPERABLE with:

a.

A minimum capacity of 3590 pound nd an overload cut off limit of less than or equal to 1556 (1727)" pounds for the refueling machine.

APPLICABILITY: During movement of fuel assemblies within the refueling cavity.

ACTION:

'ith the 'above requirements for. the refueling 'machine'not satisfied, suspend use of the refueling machine. from operations. involving the movement of fuel assemblies.

SURVEILLANCE REQUIREMENTS t

4.9.6. 1 The refueling machine used for movement of fuel assemblies shall be demonstrated OPERABLE within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months prior to the start of such'perations by

. performing a load test of at least 3590 pounds and demonstrat an automatic load cut off when the refueling machine load exceeds 1556 (1727)" pounds.

~For initial fuel load only.

<<4

~p@

P

)>>

CONTROLLED BV USER REFUELING OPERATIONS 3/4. 9. 6 REFUELING MACHINE LIMITING CONDITION FOR OPERATION 3.9.6 The refueling machine shall be used for movement of fuel assemblies and shall be OPERABLE with:

a.

A minimum capacity of 3590 pound and an overload cut off limit of less than or equal to 1556 (1727) pounds for the refueling machine.

'APPLICABILITY: During movement of fuel assemblies within the refueling cavity.

ACTION:

With the above requirements for the refueling machine not satisfied, suspend use of the refueling machine from,.operations involving the movement of fuel assemblies.

SURVEILLANCE RE UIREMENTS I

4.9.6.1 The refueling machine used for movement of fuel assemblies shall be demonstrated OPERABLE within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months prior to the start of such operations by performing a load test of at least 3590 pounds and demonstrat'n an automatic load cut off when the refueling machine load exceeds 1556 1727)" pounds.

"For initial fuel load only.

PALO VERDE - UNIT 3 3/4 9-6

A'

'I o ~

CONTROLLED BY USER 3/4. 10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTOOMN MARGIN AND KH 1 - CEA MORTH TESTS LIMITING CONDITION FOR OPERATION 3.10.1 The SHUTDOMN MARGIN and K

requirements of Specification 3.1.1.2 may be suspended for measurement of CIA%orth and shutdown margin provided re-activity equivalent to at least the highest estimated CEA worth is available for trip insertion from OPERABLE CEA(s), or the reactor is subcritical by at least the reactivity equivalent of the highest CEA worth.

APPLICABILITY:

MODES 2, 3" and 4 ACTION:

a ~

b.

Mith any full-length CEA not fully inserted and with less than the above reactivity equivalent available for trip insertion, immedi-ately initiate and continue boration at greater than or equal to 26 gpm of a solution containing greater than or equal to 4000 ppm boron or its equivalent until the SHUTDOMN MARGIN and KN 1 required

'by Specification 3.1.1.2 are restored.

Mith all full-length CEAs fully inserted and the reactor subcritical by less than the above reactivity equivalent, immediately initiate and continue boration at greater than or equal to 26 gpm of a solution containing greater than or equal to 4000 ppm boron or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

(

SURVEILLANCE RE UIREHEHTS 4.10.1.1 The position of each full-length and part-length CEA required either partially or fully withdrawn shall be determined at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

4.10.1.2 Each CEA not fully inserted shall be demonstrated capable of full insertion when tripped from at least the 50K withdrawn position within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to reducing the SHUTDOWN HARGIN to less than the limits of Specification

3. 1. 1.@

2.

4.10.1.3 Mhen in MODE 3 or MODE 4, the reactor shall be determined to be subcritical by at least, the reactivity equivalent of the highest estimated CEA worth or the reactivity equivalent of the highest estimated CEA ~orth is 'avail-able for trip insertion from OPERABLE CEAs at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months by con-sideration of at least the following factors:

a.

Reactor Coolant System boron concentration, b.

CEA position, c.

Reactor Coolant System average temperature, d.

Fuel burnup based on gross therm'al energy generation, e.

Xenon concentration, and f.

Sa'mar'um concentration.

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

y4~'imited to low power. PHYSICS TESTING at the 320'F plateau.

PALO VERDE - UNIT 1 3/4 10-1 AMEHDMEHT NO.

23

0 4

4

COiMTROLLFD BV USFR 3/4. 10 SPECIAL,TEST EXCEPTIOHS 3/4.10.1 SHUTDOWN MARGIN ANO KN 1 -

CEA WORTH TESTS..

LIMITING CONDITION FOR OPERATION 3.10.1 The SHUTDOWN MARGIN and K

1 requirements of Specification 3.1.1.2 may be suspended for measurement of CIA worth and shutdown margin provided reac-tivity equivalent to at least the highest estimated CEA worth is available for trip insertion from OPERABLE CEA(s),,or the reactor is subcritical by 'at least the reactivity equivalent of the highest CEA worth.

APPLICABILITY:

MODES 2, 3~ and 4 ACTION:

'a ~

With any full-length CEA not fully inserted and with less than the above reactivity equivalent available for trip insertion, immediately initiate and continue boration at greater than or equal to 26 gpm of a solution containing greater than'r=equal to 4000 ppm boron or its equivalent until the SHUTDOWN MARGIN and KH required by Specifica-tion 3.1.1.2 are restored.

b.

With all full-length CEAs fully inserted and the reactor subcritical by less than the above reactivity equivalent; immediately initiate and continue boration at greater than or equal to 26 gpm of a solution containing greater than or equal to 4000 ppm boron or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

SURYEILLANCE RE UIREMEHTS 4.10.1.1 The position of each full-length and part-length CEA required either partially or fully withdrawn shall be determined at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

4.10.1.2 Each CEA not fully inserted shall be demonstrated capable of full insertion 'when tripped from at least the 50Ã withdrawn position within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to reducing the SHUTDOWN MARGIN to,less than the limits of Specification S. I..X.Q 4.10. 1.3 hen in MODE 3 or MODE 4, the reactor shall be determined to be subcritical by at least the reactivity equivalent of the highest estimated CEA worth or the reactivity equivalent of the highest estimated CEA ~orth is avai l-able for trip insertion from OPERABLE CEAs at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months by con-sideration of at least the following factors:

a.

Reactor Coolant System boron concentration, b.

d.

e.

CEA position, Reactor Coolant System average temperature, Fuel burnup based on gross thermal energy generation, Xenon concentration, and f.

Samarium concentration.

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

Limited to low power PHYSICS TESTING et the SEG P pleteeo PALO VERDE - UNIT 2 3/4 10-1 AMEHOMEHT NO.

13

C

Ã 0

(

FGB 1NFQRMATlON ONLY 3/4.10 SPECIAL TEST EXCEPTIONS TDON MARGIN ANO KN EA CNORTH TESTS LIMITIHG CONDITION FOR OPERATION 3.10.1 The SHUTDOW MARGIN and KN 1 requirements of Specification 3.1.1.2 may be suspended for measurement of CEA worth and shutdown margin provided reac-tivity equivalent to at least the highest estimated CEA worth is available for trip insertion from OPERABLE CEA(s), or the reactor is subcritical by at least the reactivity equivalent of the highest CEA worth.

APPLICABILITY:

MODES 2, 3" and 4 ACTION:

a.

Mith any full-length CEA not fully inserted and with less than the above reactivity equivalent available for trip insertion, immedi-

, ately initiate and continue boration at greater than or equal to 26 gpm of a solution containing greater than or equal to 4000 ppm

,boron or its equivalent until the SHUTDOMH MARGIN and KH 1 required by 'Specification

3. 1.1.2 are restored.

b.

With all full-length CEAs fully inserted and the reactor subcritical'y less than the above re'activity equival'ent, immediately initiate and continue boration at greater than or equal'to 26 gpm of a solution containing greater than or equal to 4000 ppm boron or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

'URVEILLANCE RE UIREMEHTS 4.10.1.1 The position of each full-length and part-length CEA required either partially or fully withdrawn shall be determined at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

4.10.1.2 Each CEA not fully inserted shall be demonstrated capable of full insertion when tripped from at least the 50K withdrawn position within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to reducing the SHUTDOWN MARGIH to less than the limits of Specification s.z.z.l.

4.10.1.3 When in MODE 3 or MODE 4, the reactor shall be determined to be subcritical by at least the reactivity equivalent of the highest estimated CEA worth or the reactivity equivalent of the highest estimated CEA worth is avail-able for;trip insertion froa OPERABLE CEAs at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months by con-sideration of 4t least the following factors:

a.

Reactor Coolant System boron concentration, b.

CEA position, c.

Reactor Coolant System average temperature, d.

Fuel burnbp based on gross thermal energy generation, e.

Xenon concentration, and

. f.

Samarium concentration.

AMEHDMEHT HO.

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

Limited to low power a

p a eau.

PALO YERDE - UNIT 3 3/4 10-1

togs I

. Pp

J P

SPECIAL TEST EXCEPTIONS 3/4.10.5 MINIMUM TEMPERATURE AND PRESSURE FOR CRITICALITY l

J 3.10.

The mi mum temp rature pressure or critic lity li 'ts of S

ci-fic ions 3.

. 1.4 and

.2.8 may e suspend d during 1

temp ature PH ICS T

S to a inimum t peratur of 300'F d a minim press re of 50 psia

'ov)ded:

The TH MAL POW does no exceed 5" of RAT THERM POWER.

b'.

The eactor t ip setpo's on t OPERAB Vari e Over ower tr ch nels ar set at 20% of R

ED THE AL PO R, and C.

he React r Coola System empera re an pressu relat nship is maintain d withi the acc ptable egion f oper ion re ired by Specifi ation

.4.8 exc t that he c

e crit'cal lin shown on Figur 3.4-2 oes not pply.

e APP ABI TY NOBE-+.

Qfl's +pc ~1 ~~cR~~ 0)i l nfegkio~a y de e7 a.

Wi h t e THER AL POW R grea er than 5% of RATED T ERMAL P HER,

'ed'ately pen t react trip bre kers.

b.

Wi 0 the eactor oolant ystem te erature a

d pressu e

r atio hip wi hin the region of unacceptab e opera on on igur 3.4-2, mmedia ly open t e reactor rip bre ers and r store the empera re-pres re relat'ship to thin it limit wit in 30 inutes perform the engin ering eval ation r

uired by S ecific ion 3.4

. 1 prior o the nex reactor criticalit.

SURV LLAN RE UIREMENT 4

0.5.

The R actor Co lant Syst m temperatu e and pr ssure relat'onship all verif'ed to b within th acceptable region f r operation of Figur

3. 4-2 t least nce per ur.

4. 1.5.2 T e THERM

'POWER s ll be deter ined to e

5% of TED THERMAL PO ER at 1 ast onc per hour

~ 10.5.3 The Re ctor Cool nt System t mperatur shall be v rified to be greater than or equal to 00'F at le t once r hour.

4. 10.

.4 Eac Logarig mic Power L vel and ariable Ov power channel shall be subj cted to a

CHANN t. FUNCTIONA TEST wi in 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to initiating low tern erature PHYSICS TESTS.

V

<R~cor~nh~pr i.o~~H~t~x~edm~~EDWHfRN~GWER.

CGMTRGILLElh B'f USER

J f.lt P. '4 1 1-0 0

CGMTIRGILILEBBY USEIR SPECIAL TEST EXCEPTIONS 3/4.10.5 MINIMUM TEMPERATURE AND PRESSURE FOR CRITICALITY 3.10.5 The inimum te gerature a d pressure for riticalitp'imits of Speci-fications

.'1.1.4 an 3.2.8 may e suspended du ng low t mperature PH EPICS TESTS to minimum emperature f 300 F and a

inimum pr ssure of 50 psia provide:

a.

The ERMAL POW does not exc ed 5X of ED THERMA OWER.

b.

T e reactor ip setpoints on the OPE BLE Variab Overpower rip annels ar set at

< 2. of RATED ERMAL POWE and C.

The Rea or Coolant ystem temp ature and p essure rel sonship s

maint ned within he acceptab e region of operation y quired b

Spec ication 3..8 except t at the core ritical li,re shown Fi ure.3.4-2 d es not appl APPLICAB ITY:

MODE

"<)))): +Q) g 5'p8'C) 4C2 ILOln. )6+8'Yl+)d))B p 6'P4P:6 a.

With th THERMAL P WER grea er tha 5X of R TED THERMA

POWER, immed tely open he rea'ct r trip-reakers b.

Wit the React r Coolan System tempera re and pr sure re ationship ithin t'egion of unac ptable op ation on F gure 3.4-immedi ely op the re tor trip eakers and estore he temper ture-pre sure re tionshi to withi its limit w thin 30 minut

perfor the en sneerin evaluatio required by Specifi tion 3.

.8. 1 pri r to th next reac or critical iy.

SNQAHV4H UTREMENTS

4. 10 5. 1 The Reactor oolant stem tern rature an pressure r

ationship sha 1

be ver fied to e withi the acce able regi n for opera on oi Fi ure 3.4-at lea once p r hour.

. 10,5.2 The THE AL POW shall b

determine to be SX of RATED THERE L

POWER a

least o ce per ur.

4. 10.

.3 The eactor oolant S

tern temper ture shall e verified to be grea r than r equal to 300~F at least o

e per hour.

4.

.5.4 ach Log rithmic P wer Level nd Variabl Overpowe'r ch nel shall be s

jecte to a

CH NNEL FUN IONAL TEST within 12 ours prior to initiating low empera ure PHY CS TESTS.

e~ ~~ATES-FHERM~~OWGM "F-i PALO VER E -

BI 1

i Alp A

g) g f W 1 f/1(

f fA f

f

SPECIAL TEST EXCEPTIONS 3/4. 10. 5 MINIMUM TEMPERATURE AND PRESSURE FOR CRITICALITY 3.10.5 e minim temperat e and presg, re for cd icality l'ts of Sp i-ficati s 3.1.1.

and 3.2.

may be suspended during low temp rature PHY CS TEST to a mi

'mum tempe ture of 30 5 and a m'rfimum pres re of 500 sia pro ided:

a.

The THER POWER doe not exce 5X of RA D THERMAL OWER.

c ~

The r ctor trip tpoints o

the OPER@

LE Variabl Overpower ip cha els are se at

< 20K df RATED T fRMAL POWER and e Reactor oolant Sy tern tempe ature and p

ssure relati nship is maintaine ithin t 6 acceptab e region of peration re red by Specific ion 3.4 except t t the core ritical line hown on Figure

.4-2 do s not apply AP LICABILIT.

MODE Pi g. speci iCBW)QB iH4e'N AQY)dl QC'l a.

With e THERMAL PO ER greater t an 5X of RATE THERMAL POW R, imme ately open t e reactor tr p breakers.

b.

W h the Reacto Coolant Sys em temperatur and pressur elationship thin the re on of unacce able operati n on Figure 3.4-2 immediately open the rea or trip brea rs and estore the temper ure-pressur relationship o within its imit w hin 30 minut

perform th engineering valuation re ired by Specifi ation 3.4.8.

prior to the next reactor ritical'.

SURVEILLANCE R UIREMENTS

4. 10.5. 1 he Reactor Co lant System emperature an pressure elationshi shall be erified to b within the ceptable regi n for ope tion of Figure 3.4-2 at least nce per hou

4. 10.

.2 The THERM L POWER sha be determin to be of RATED HERMAL POWE at least onc per hour.

4.

.5.3 The R

ctor Coola System temp rature sh 1

be verif 'ed to be g eater than o

equal to 3

'F at least nce per h

4. 10.5.4 E ch Logarith c Power Leve and Vari le Overpo r channe shall be subjected o

a CHANNEL UNCTIONAL T T within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months pr or to ini iating low temperatu e

PHYSICS T STS, ERM OWN".

PALO VERDE - UNIT 3 3/4 10"5

L

,$g)'gQg ",~,)ij'g

~ym f:K Ik Er 0

CONTROLLED BY USER SPECIA TEST EXCEP IONS 3

. 10. 10 H

URAL CIRCULAT H TESTING OGRAM LIMITIN CONOITION FOR PERATION 3

0.10 The li tations of ecifications 3.4..2, 3.4.1.3 and 3.7.1.6 ay be uspended duri g the perfor ance of the Start Natural Ci culation Tes ing Program" pro ided:

a.

b.

Operations i volving a reducti n in boron c centration f the Reacto Coolant Sy em are suspended Core ou et temperature i

maintained least 10 F below Satura on temper ture.

C.

A r actor coolant pu shall not b star ted w

h one or mor of R actor Coolant Sy em cold leg mperature less than or qual to 55'F during cool own, or 295'F during he up, unless th secondary water temperatu e (saturation emperatur correspondin to steam generator pre ure) of each team gene tor is less an 100~F abo each of the eactor Coolan System c

d leg temper ores.

AP LICABILITY:

MO S

3 and 4 dur ng Natur Circulation sting.

ACTION:

Mith the Re tor Coolant stem satu tion margin ess than 10 F, place at least one eactor coola loop in eration, wit at least on reactor co ant pump.

S VEILLAHCE R UIREMEHTS

4. 10. 10 The sat ation marg shall be d

ermined to b within the above limit by contin us monitor '

with the turation mar in monitors equired by T le 3.3-1 or, by cal lating the turation mar in at least nce per 30 minutes.

tartup Na ral Circula on Testing P ogram:

Hat al Circula on Cooldown est at 80K wer.

PALO VEROE - UNIT 1 3/4 10-10 AMEHDMEHT NO.

23

h

4

+

I ~

h e

~

CONTROI LED BY USER 3/4. 11 RADIOACTIVE EFFLUENTS 3 4.11.1 SECONDARY SYSTEM LI UID WASTE DYSCHARGES TO ONSITE EVAPORATION PONDS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11. 1.1 The concentration of radioactive material discharged from secondary system liquid waste to the onsite evaporation ponds shall be limited to the lower limit of detectability (LLD) defined as 5 x 0-7 pCi/ml,for the prin-cipal gamma emitters or 1 x 10-6 pCi/ml for I-131.~

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

When any secondary system liquid waste discharge pathway concentration determined in accordance with the surveillance requirements given below exceeds the specified LLD, divert that discharge pathway to the liquid radwaste system without delay or process the liquid-wastes to meet the specified limits prior to release to the onsite evaporation ponds.

t SURVEILLANCE RE UIREMENTS 4.11.1.1.1 Radioactive liquid wastes collected in the chemical waste neutralizer tank shall be sampled and analyzed prior to their batchwise discharge to the onsite evaporation pond in accordance with the.sampling and analysis program specified in Table 4..11-1.

4.11.1.1.2 With the concentration of radioactive material in the chemical waste neutralizer tank exceeding the specified LLD, sample and analyze other secondary system discharge pathways in accordance with the sampling and analysis program specified in Table 4. 11-1.

~ For one time only, effective March 24, 1987, releases of principal gamma emitters with half lives less than 75 days may be allowed to exceed 5 x 10-7 pCi/ml but shall be limited to 10 CFR 20, Appendix B, Table II, Col.

2 con-centrations for a period not to exceed 60 days.

Furthermore, effective June 3,

1987, releases of Antimony-124 (Sb-124) may be allowed to exceed 5 x 10-7 pCi/ml, but shall be limited to 10 CFR 20, Appendix B, Table II, Column 2, concentrations until 2400 MST on March 31, 1988.

PALO VERDE - UNIT 1 3/4 11-1 AMENDMENT HO. l8

II t

(W

3/4. 10 SPECIAL TEST EXCEPTIONS BASES 3/4. 10. 1 SHUTDOWN MARGIN This special test exception provides that a minimum amount of CEA worth is immediately available for reactivity control when tests are performed for CEAs worth measurement.

This special test exception is required to permit the periodic verification of the actual versus predicted core reactivity condition occurring as a result of fuel burnup or fuel cycling operations.

Although testing will be initiated from MODE 2, temporary entry into MODE 3 is necessary during some CEA worth measurements.

A reasonable recovery time is available for return to MODE 2 in order to continue PHYSICS TESTING.

3/4. 10. 2 MODERATOR TEMPERATURE COEFFICIENT GROUP HEIGHT INSERTION, AND POWER DISTRIBUTION LIMITS This special test exception permits individual CEAs to be positioned outside of their.normal group heights and insertion limits during the perform-ance of such PHYSICS TESTS as those required to (j.) measure CEA worth, (2) determine the reactor stability index and damping factor under xenon oscillation conditions, (3) determine power distributions for non-normal CEA configurations, (4) measure rod shadowing factors, and (5) measure temperature and power coefficients.

Special test exception permits MTC to exceed limits in Specification

3. 1. 1.3 during performance of PHYSICS TESTS.

3/4. 10.3 REACTOR COOLANT LOOPS This special test exception permits reactor criticality with less than four reactor coolant pumps in operation and is required to perform certain STARTUP and PHYSICS TESTS while at low THERMAL POWER levels.

3/4.10.4 CEA POSITION, REGULATING CEA INSERTION LIMITS AND REACTOR COOLANT COLD LEG TEMPERATURE This special test exception permits the CEAs to be positioned beyond the insertion limits and reactor coolant cold leg temperature to be outside limits during PHYSICS TESTS required to determine the isothermal temperature coefficient and power coefficient.

3/4.10.5 MINIMUM TEMPERATURE AND PRESSURE FOR CRITICALITY This special test exception (inkendton~ll cue(eked.

OWER leve s

w>

T 1

be ow the m~nsmum crs

>ca empera ure an pressure during PHYSICS TEST( Mich are required to verify the low temperature physics predictions and to ensure the adequacy of design codes for reduced temperature conditions.

The Low Power Physics Testing Program at low temperature (300'F) and a pressure of 500 psia is used to perform the following tests:

1.

Biological shielding survey test 2.

Isothermal temperature coefficient tests 3.

CEA group tests 4.

Boron worth tests 5.

Critical configuration boron concentration

t'I Ig I

~ 1'.g

3/4. 10 SPECIAL TEST EXCEPTIONS BASES 3/4. 10. 1 SHUTOOMN MARGIN This special test exception provides that a minimum amount of CEA worth is immediately ayailab1e for reactivity control when tests are performed for CEAs worth measurement.

This special, test exception is required to permit the periodic verification of the actual versus predicted core reactivity condition occurring as a result of fuel burnup or fuel cycling operations.

Although testing will be initiated from MODE 2, temporary entry into MODE 3 is necessary during some CEA worth measurements.

A reasonable recovery time is available for return to MODE 2 in order to continue PHYSICS TESTING.

3/4. 10. 2 MODERATOR TEMPERATURE COEFFICIENT GROUP HEIGHT INSERTION AND POHER DISTRIBUTION LIMITS This special test exception permits individual CEAs to be positioned outside of their normal group heights and insertion limits during the perform-ance of such PHYSICS TESTS as those required to (1) measure CEA worth, (2) determine the reactor'tability index and damping facto~ under xenon oscillation conditions, (3) determine power distributions for non-normal CEA configurations, (4) measure rod shadowing factors, and (5) measure temperature and power coefficients.

Special test exception permits MTC to exceed limits in Specification 3..1.1.3 during performance of PHYSICS TESTS.

3/4. 10. 3 REACTOR COOLANT LOOPS This special test exception permits reactor criticality with less than four reactor coolant pumps in operation and is required to perform certain STARTUP and PHYSICS TESTS while at low THERMAL POMER levels.

3/4.10.4 CEA POSITION REGULATING CEA INSERTION LIMITS AND REACTOR COOLANT COLO LEG TEMPERATURE This special test exception permits the CEAs to be positioned beyond the insertion limits and reactor coolant cold leg temperature to be outside limits during PHYSICS TESTS required to determine the isothermal temperature coefficient and power coefficient.

3/4.10. 5 MINIMUM TEMPERATURE ANO PRESSURE FOR CRITICALITY This s ecial test exce tion/ig4en+ionaNy dele4ed-POMER leve s wit 1

e ow t e m)nimum cri )ca tempera ure an pre sure during PHYSICS TESTF which are required to verify the low temperature physics predictions and to ensure the adequacy of 8esign codes for reduced temperature conditions.

The Low Power Physics Testing Program at low temperature (300 F) and a pressure of 500 psia is used to perform the following tests:

1.

2.

3.

4 5.

Biological shielding survey test Isothermal temperature coefficient tests CEA group tests Boron worth tests Critical configuration'oron concentration PALO. VERDE - UNIT 2 B 3/4 10-1

-4 l

CGPj i RGKi FD BV USFR ah 3/4.10 SPECIAL TEST EXCEPTIONS BASES 3/4. 10. 1 SHUTDOWN MARGIN This special test exception provides that a minimum amount of CEA worth is immediately available for reactivity control when tests are performed for CEAs worth measurement.

This special test exception is required to permit the periodic verification of the actual versus predicted core reactivity condition occurring as a result of fuel burnup or fuel cycling operations.

Although testing will be initiated from MODE 2, temporary entry into MODE 3 is necessary during some CEA worth measurements.

A reasonable recovery time is available for return to MODE 2 in order to continue PHYSICS TESTING.

3/4. 10. 2 MODERATOR TEMPERATURE COEFFICIENT GROUP HEIGHT INSERTION AND POWER DISTRIBUTION LIMITS This special test exception permits individual CEAs to be positioned outside of their normal group heights and insertion limits during the perform-ance of such PHYSICS TESTS as those required to (1) measure CEA worth, (2) determine the reactor stability index and damping factor under xenon oscillation conditions, (3) determine power distributions for non-normal CEA configurations, (4) measure rod shadowing factors, and (5) measure temperature and power coefficients.

Special test exception permits MTC to exceed limits in Specification 3.1.1.3 during performance of PHYSICS TESTS.

3/4. 10.3 REACTOR COOLANT LOOPS This special test exception permits reactor criticality with less than four reactor coolant pumps in operation and is required to perform certain STARTUP and PHYSICS TESTS while at low THERMAL POWER levels.

3/4.10.4 CEA POSITOH REGULATING CEA IHSERTION l.IMITS AND REACTOR COOLANT CQLQ LEG TEMPERATURE This special test exception permits the CEAs to be positioned beyond the insertion limits and reactor coolant cold leg temperature to be outside limits during PHYSICS TESTS required to determine the isothermal temperature coefficient and power coe fficient.

3/4.10. 5 MINIMUM TEMPERATURE AND PRESSURE FOR CRITICALITY This special test exce tiontin&nflogalt elela+eJ.

OW eve s

ws 1

elow e msnsmum crs seal temperature and pressure during PHYSICS TEST( wIIich are required to verify the low temperature physics predictions and'o ensure the adequacy of design codes for reduced temperature conditions.

The Low.Power Physics Testing Program at low temperature (300'F) and a pressure of 500 psia is used to perform the following tests:

l.

2.

3.

5.

Biological shielding survey test Isothermal temperature coefficient tests CEA group tests Boron worth tests Critical configuration boron concentration PALO YEROE - UNIT 3 8 3/4 10-1

ML17305B113

Text

RESPONSE

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